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BARC/1994/P/001

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Rf-.I'ORT ON R & D ACTIVITIES Ol"IIIiALTH PHYSICS DIVISION

1990- 1993

( otnpilcJ by

A. K;iju, K. K. Narayanan and R. C. Sharnia

1994

BARC/1994/P/001

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GOVERNMENT OF INDIAATOMIC ENERGY COMMISSION

REPORT ON R & D ACTIVITIES OF

HEALTH PHYSICS DIVISION

1990 - 1993

Compiled by

A. Raju, K.K. Narayanan and R.C. Sharma

r BHABHA ATOMIC RESEARCH CENTREBOMBAY, INDIA

10

BARC/1994/P/0O1

BIBLIOGRAPHY DESCRIPTION SHEET FOR TECHNICAL REPORT

(as per IS : 9400 - 198O)

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Progress Report

BARC/1994/P/001

Title and subtitle : Report on R & D activities of HealthPhysics Division 199O-1993

11 Collation :

13 Project No. :

20 Personal author (s)

244 p., appendix

A. Raju; K.K. Narayanan;R.C. Sharma (comps.)

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Affiliation of author (s) :

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Originating unit :

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Type :

Date of submission :

Pub 1ication/Issue date

Health Physics Division, Bhabha AtomicResearch Centre, Bombay

Bhabha Atomic Research Centre,Bombay-400 085

Health Physics Division, BARC, Bombay

Department of Atomic Energy

Government

February 1994

March 1994

r on t d . - . Hi)

40 Publisher/Distributor Head, Library and Information Division,Bhabha Atomic Research Centre, Bombay

42 Form of distribution

50 Language of text :

51 Language of summary :

52 No. of references :

53 Gives data on s *

Hard Copy

English

English

60 Abstract :This report is a compilation of various R&D programmesundertaken, continued and/or completed by Health Physics Division ofBARC during the period 199O-1993. The findings and results of severaltypes of investigations on<ftopics ranging from environmental studies,radiation dosimetry — internal and external, operational healthphysics, site evaluation studies, micrometeorology, instrumentationand techniques and industrial hygiene and safety are presented in theform of abstracts. The abstracts have been arranged subject wise.References to the scientific papers and technical reports publishedor presented have been included. Also included are extracts from IAEAResearch Agreements and theses submitted for the award of M.Sc./Ph.D.degrees by research by the staff members of the Division.

70 Keywords/Descriptors : RADIATION PROTECTION;. PROGRESS REPORT;BARC; RESEARCH PROGRAMS; ENVIRONMENTAL IMPACTS; DOSIMETRY;METEOROLOGY; SAFETY; NUCLEAR FACILITIES; TRAINING; MATHEMATICALMODELS; RADIATION MONITORING

71 Class No. s INIS Subject Category : C54OO

99 Supplementary elements :

FOREWORD

Protection of workers and members of the public from unduerisks from exposure to ionising radiation in and around thenuclear facilities in the country through a comprehensive systemof radiation monitoring and surveillance has remained the princi-pal aim of Health Physics Division, BARC. In pursuance of thisobjective, R & D programmes in related subjects have been under-taken and pursued primarily with a view to improving the qualityof service. The Division also conducts Health Physics StipendiaryTraining Course annually and thus generates a trained manpowerbase to ensure comprehensive safety in the nuclear facilities.

This report provides a brief account of R&D activities car-ried out in Health Physics Division during the period. 1990-93.Taken together with similar biennial reports brought out earlier,it essentially ensures continuity. It contains abstracts ofscientific papers and technical reports published or presented aswell, as extracts from IAEA Co-ordinated Research Programmes andtheses submitted for the award of M.Sc./Ph.D. degrees by researchby the staff members of the Division.

I am sure that this consolidated report, although in acondensed form, will be a useful source of reference for allthose working in these and related areas.

(S . Krishnamony)Head, Health Physics Division

Trombay,February 9, 1994

ABSTRACT

This report is a compilation of various R&D programmes

undertaken, continued and / or completed by Health Physics Divi-

sion of BARC during the period 1990-1993. The findings and re-

sults of several types of investigations on topics ranging from

environmental studies, radiation dosimetry - internal and exter-

nal, operational health physics, site evaluation studies, micro-

meteorology, instrumentation and techniques and industrial hy-

giene and safety are presented in the form of abstracts. The

abstracts have been arranged subject wise. References to the

scientific papers and technical reports published or presented

have been included. Also included are extracts from IAEA Research

Agreements and the theses submitted for the award of M.Sc./ Ph.D.

degrees by research by the staff members of the Division.

ACKNOWLEDGEMENT

Thanks are due to Shri S.Krishnamony, Head, Health Physics

Division, for his keen interest in preparing this Report and for

the valuable suggestions made and guidance provided throughout.

Thanks are also due to Shri A Ramamurthy, Dr. T.M.Krishnamoorthy,

DrtSmt) Kamala Rudran and Shri M.Sundaram - Heads of Sections,

for furnishing the entire data on the R & D work carried out in

their respective Sections.

Many staff members of Health Physics Division have co-oper-

ated in a number of ways in bringing out this Report in the

present form and their services are highly acknowledged. The

following persons need a special mention .-

Shri S.D.Bharambe

Shri K.Chandran

Shri M.P.George

Shri S.Narayan

Shri K.D.Singh

Shri R.K.Singhal

Shri S.Soundararajan

Shri V.D.Vashi

CONTENTS

SUBJECT PAGE NO.

1. ENVIRONMENTAL STUDIES 1 - 7 3

2. RADIATION DOSIMETRY (INTERNAL & EXTERNAL) 74 - 115

3. OPERATIONAL HEALTH PHYSICS AND NUCLEAR SAFETY 116 - 137

4. SITE EVALUATION STUDIES 138 - 144

5. MICROMETEOROLOGY 145 - 153

6. INSTRUMENTS & TECHNIQUES 154 - 163

7. RADIATION PHYSICS 164 - 174

8. MATHEMATICAL MODELLING & SOFTWARE 175 - 197DEVELOPMENT

9. INDUSTRIAL HYGIENE 198 - 207

10. TRAINING 208 - 210

11. APPENDIX

- IAEA RESEARCH PROJECT 211

- THESES TITLES 212 - 219

- AUTHOR INDEX 2 20 - 22 7

1. ENVIRONMENTAL STUDIES

1. TITLE :

Radon and Uranium Mine Ventilation

3. AUTHOR/S AND ADDRESS :

A.H. Khan and M. RaghavayyaHealth Physics Unit, Jaduguda,Health Physics Division, BARC

2. CATEGORY

1 - 1

4. ABSTRACT :

An extensive survey of radon, its progeny and ventilation wascarried out in(370 ML) tocompute freshfor control ofsection alonesection was 50,

the largest ore producing section of the mineevaluate the quantity of radon generation,air requirement and its distribution patterninhalation hazard. The radon emanation in thisworked out to 7.7 KBq/s. The air flow in this5 mJ/s with initial radon content of 1 KBq/mJ.

Considering the mine or a section thereof as a discreteenclosure with constant rates of ventilation and radonemanation, an equation was developed as under to describe thesteady state radon concentration (EER) at a given rate ofvent ilat ion,

i- R e R i -iFsRs = ( ) . Aw + (p.Fi + Aw) / (Aw + p)

L Q Fi -I

where Ri and Rs are initial and study state EER concentra-tions (Bq/m^), Fi and Fs are equilibrium factors for incomingand steady state air. Re is radon emanation rate (Bq/s), Q isair flow rate (m-Vs), Aw is a hypothetical value of radonprogeny decay constant (3.5 x 10~4 s~*) and p is ventilationrate. With a 5 mSv/y target of per capute effective dosefrom radon progeny, the radon concentration works out to be0.155 KBq/m^ (EER). This can be achieved by adopting splitventilation with 20 m-Vs of fresh air to each haulage levelin a one pass system. Based on similar computations, Jadugu-da mine ventilation is being improved.

5. REMARKS : 6. STATUS :

Completed

7. KEYWORDS :

RadonMine ventilationSpli t systemOne pass system

8. REFERENCES

RadonKhan.,

andBull

Uranium Mine Ventilation, M. Raghavayya and, of Rad. Prot. Vol. 12, No. 1 & 2, 1989

A.H.

1. TITLE : 2. CATEGORY :

Radioactivity in the Off Shore 1 - 2Marine Environment at Tarapur


S. Chandramouli, R.S. Iyer, A.G. Hegde and I.S. Bhat*Environmental Survey LaboratoryTARAPUR - 401 504E & PA, Nuclear Power Corporation,World Trade Centre, Bombay

4. ABSTRACT :

A comprehensive off shore marine survey was conducted duringJanuary 1989 at Tarapur. A total of 55 samples consisting ofsurface sea water, bottom grab sediment, marine algae, fishand plankton were collected and analysed for fission andactivation products. Temperature and pH of surface sea waterwere also noted at different locations. The results indicat-ed that after 18 years of Tarapur Atomic Power Station and12 years of fuel reprocessing plant operation, there was nosignificant increase in environmental radioactivity overnatural fallout background.

REMARKS : 6. STATUS : 7. KEYWORDS :

Completed Off shoreRadioactivi tyMarine matrices

REFERENCES :

i) Radioactivity in the off-shore marine environment atTarapur, S. Chandramouli, R.S. Iyer, A.G. Hegde and I.S.Bhat, Bulletin of Radiation Protection, Vol. 13, No.2, pp12-15, April-June 1990

ii) Off Shore Survey of Tarapur Marine Environment, A.G.Hegde, R.S. Iyer, S. Chandramouli, D.D. Rao, M.C. Balani,I.S. Bhat, Health Physics Division, BARC (BARC/I-1077-1990)

1. TITLE : 2. CATEGORY:

Dose Commitment to the Public 1 - 3due to the Use of Uranium BearingNH4NO3 as Fertiliser from NFC Effluents


A.R. Lakshmanan and S. RajagopalanHealth Physics UnitNuclear Fuel ComplexHYDERABAD - 500 762

4. ABSTRACT :

Uranium Oxide Plant of Nuclear Fuel Complex, which processesmagnesium diuranate, generates in a month about 300 m^effluent containing NaNO3 and NH4NO3. These effluents aftertreatment to bring down uranium concentration, are sold tosmall scale industries for recovery salts. A limit foruranium in the effluent has been fixed on the basis thatwhen these salts are used as fertiliser for crops, the soiluranium is not raised to more than l/50th of the backgroundlevel.

The implication of this limit on the dose equivalent ratesfor the general public through critical path way via foodhas been studied. It was observed that the application ofNH4NO3 effluent containing uranium at the prescribed limitof 50 mg/1 as fertiliser to paddy gives rise to dose equiva-lent rates of 0.036 mSv and 0.546 mSv for red bone marrowand endosteal surfaces respectively which are less than 8%of the permitted dose to the public.

5. REMARKS : 6. STATUS : 7. KEYWORDS :

Completed UraniumDose commitmentEffluent

8. REFERENCES :

Dose Commitment to Public Due to the Use of Uranium BearingNH4NO3 as Fertiliser from NFC Effluents, A.R.Lakshmanan andA.S.Rajagopalan, 17th IARP Conference, 1990


Subseabed Disposal of High Level 1 - 4Radioactive Waste.

3. AUTHORXS AND ADDRESS :

T.M.Krishnamoorthy, R.N.Nair and T.P.SarmaHealth Physics Division, BARCBOMBAY -400 085

4. ABSTRACT :

Diffusion and advection controlled migration of radionu-clides through sub sea-bed sediments is analysed to deter-mine the flux at the sediment water boundary which is subse-quently translated into radionuclide concentration in oceanwaters.


Completed Rad waste managementDispersion in seawater

8. FERENCES :

Subseabed Disposal of High Level Radioactive Wastes,T.M.Krishanmoorthy, R.N.Nair and T.P.Sarma, Ind. J. Mar.Sci., 19, 1, 1990


G e o c h e m i c a l A s s o c i a t i o n o f A m - 2 4 1 1 - 5in T r o m b a y C o a s t a l S e d i m e n t


V.M. Matkar, Usha Narayanan, I.S. Bhat* and K.C. PillaiEnvironmental Studies SectionHealth Physics Division, BARCBombay 400 085E & PA, Nuclear Power Corporation,World Trade Center, India

4. ABSTRACT :

The binding characteristics of Americium in Trombay sedimentwas studied by applying a sequential chemical leachingmethod. The extracted species were analysed for Am-241following preconcentration, coprecipitation, ionexchange,electroplating and alpha spectrometry. The results show that94 + 14 % of the Am-241 was extracted by different leachingagents out of which 59 ± 10 % was associated with organicmatter and hydrous oxide and 38 + 10 % with residualfraction.


Completed SedimentAm-241Chemical bindings.

8. REFERENCES :

Geochemical Association of Am-241 in Trombay Coastal Sedi-ment, V.M. Matkar, Usha Narayanan, I.S. Bhat and K.C. Pillai,International Conference on 50 years of Plutonium,Bombay,Feb.4-6, 1990


Distribution of Tritium in the 1 - 6Environment of Rajasthan Atomic PowerStation and its impact on CriticalGroup (1981-1988)

— — — — — — — — — — — — • — . — — — — — — * - — . — — — * — — — _ , — — — . — — — . — — — — — _ _ _ — — — — _ _ _ . — ,-.__-»._—,•„.•..•_.„«


R.P. Gurg, P.V. Vyas, K.G. Varughese,B. Dube, T.A. Sebastin & B.M.L. SanEnviromental Survey Laboratory (RAPS),Health Physics Division, BARC,Bhabha Nagar -323 307Via Kota

4. ABSTRACT :

Monitoring the levels of tritium in the environment ofPressurised Heavy Water (PHWR) system is an essentialparameter as tritium release and inventory is the highest inthis system in comparison to all other types of reactorsystems. Rajasthan Atomic Power Station comprises of two PHWRtype units of 210 MWe each. An on going comprehensiveprogramme monitors tritium contents in aquatic andatmospheric matrices of this environment to assess the impactof tritium on the members of the critical group. The paperdescribes the levels of tritium observed during 1981-88 andits impact on critical group.


Work in Tritiumprogress RAPS

Environment

8. REFERENCES :

Distribution of Tritium in the Environment of RajasthanAtomic Power Station and its Impact on Critical Group (1981-1988), R.P. Gurg, P.V. Vyas, K.G. Varughese, B. Dube. T.A.Sebastian and B.M.L. Sah, Symposium on Tritium Measurementand its Application, Feb. 22-23, 1990


Environmental Impact of Tritium 1 - 7Discharged from Indian PHWRs


K.K. Narayanan, B.M.L. Shah, K.C. PillaiHealth Physics Division, BARCBombay 400085

4. ABSTRACT:

The radiological significance of tritium discharged into theenvironment is discussed. The revaluation of the DerivedLimits (DL) based on ICRP's latest recommendation onpopulation exposure has been carried out and bases forestablishing the revised DLs for tritium are explained. Pastexperience with respect to environmental releases of tritiumfrom operating PHWRs in the country indicates that actualreleases of tritium results in a small fraction of dose limitto public (4.3 uSv/year for RAPS and 2.4 uSv/year for MAPS)and the annual regional collective doses are 2.7 person-Svand 0.5 person-Sv for RAPS and MAPS, respectively. Projectedpopulation collective dose for the year 2000 AD from tritiumreleases from PHWRs of installed capacity 10 GWe, indicates afigure of 60 person-Sv/year which is only 0.003 percent ofthe estimated collective dose to the Indian population fromnatural sources.

5. REMARKS: 6. STATUS: 7. KEYWORDS:

Completed TritiumDerived limitsDose limitCollective dose

8. REFERENCES:

Environmental Impact of Tritium Discharged from Indian PHWRs,K.K. Narayanan, B.M.L. Shah, K.C. Pillai, Symposium on Triti-um - Measurements and Applications, BARC, Feb. 22-23, 1990


Chemical Methods in Environmental 1 - 8Radioactivity Measurements

3. AOTHOR/S AND ADDRESS :

M.A.R. Iyengar, S. Ganapathy, V. Kannan.M.P. Rajan and S.RajaramEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam - 603 102

4. ABSTRACT :

Normal environmental monitoring programmes around nuclearcomplex generally involves collection and processing ofenvironmental materials of considerable diversity, complex-ity and size, wherein the radionuclides present at traceconcentration levels, can only be measured by employingsensitive radiochemical procedures combined with the lowlevel counting techniques. Also, growing public concern forradiation safety in the environment in recent times and theneed for strict compliance with regulatory requirements bythe nuclear facilities, make it obligatory on the part ofthe monitoring agencies, to evolve sensitive and reliablechemical methods for environmental radioactivity surveil-lance purposes. Keeping these requirements in view, theEnvironmental Survey Laboratory has, over the years, de-veloped some sensitive radiochemical techniques, which arebeing regularly employed in nuclear power station environs,providing considerable assurance on the safe performance ofthe power station with regard to public exposure. Some ofthese radiochemical techniques covering both natural andman-made radionuclides i.e. Ra-226, Ra-228, Po-210, Pb-210,Cu-137, Sr-90, 1-131, H-3, etc. which are presently in useat ESL during pre-operational and operational phase ofreactor operations are discussed.


Completed EnvironmentalradioactivitymeasurementsChemical methods

8. REFERENCES :

Chemical Methods in Environmental Radioactivity Measure-ments, M.A.R. Iyengar, S. Ganapathy, V. Kannan, M.P. Rajanand S.Rajaram, Seminar on Environmental Radioactivity, KAPP,Kaiga, April 16-18, 1990.


Transfer Co-efficients of 1 - 9Plutonium-239+240in TarapurEnvironment, West Coast of India


R.S. Iyer, S.Chandramou1i, A.G. Hegde and I.S. Bhat*Environmental Survey LaboratoryTARAPUR - 401 504

* E & PA, Nuclear Power Corporation,World Trade Centre, Bombay

4. ABSTRACT :

Concentrations of Plutonium-239+240 in various sample ma-trices from the Tarapur Coastal Environment have been deter-mined for ten years. Plutonium concentration factors insediments, algae and marine organisms were evaluated fromannual average concentration. The measurements indicatedthat the levels of plutonium in the environmental matriceswere too low to present any radiation hazard to the public.


Completed Plutonium transferco-efficient

Marine matrices

8. REFERENCES :

Transfer Co-efficients of Plutonium-239+240 in TarapurEnvironment, West Coast of India, R.S. Iyer, S. Chandramou-li, A.G. Hegde and I.S. Bhat, Indian Journal of MarineSciences, Vol.19, pp 140-142, June 1990


Environmental Impact Evaluation 1 - 1 0of Proposed Uranium Recovery fromCopper Tailings by Acid Leaching


A.H. Khan and P.M. MarkoseHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

A proposal for recovery of uranium by acid leaching ofcopper tailings containing samll quantities of uranium hasbeen under consideration. Nearly 800000 tonnes of coppertailings would have to be treated with sulphuric acid,pyrolusite and lime. After recovery of uranium the finaltailings to be disposed would have radium-226 content ofabout 0.7 Bq/Tonne with nearly equivalent activities ofother radionuclides of 238 U series.

The gamma radiation field 1 m above the tailings surface isestimated to be below 50 uR/hr compared to the regionalbackground of the order of 10-15 uR/hr. The radon emanationrate is expected to be around 0.15 Bq m"2 S"1 compared tothe 0.02 Bq m"2 S"1 from the local soil.

The tailings would, however, need to be moistened or vege-tated to avoid dust dispersal.


Completed Copper TailingsU RecoveryEnvironmentRadon

8. REFERENCE :

Possible environmental impact of proposed recovery of urani-um from copper tailings by acid leaching, by A.H. Khan, P.M.Markose and K.C. Pillai, Report submitted to DAE on 19.06.90


Pathways of Internal Exposure at 1 - 1 1the High Background Area


A.C. Paul, T. Velayudhan, P.M.B. Pillai and K.C. Pillai*Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, Kerala

* Consultant AERB, Bombay

4. ABSTRACT :

Pathways of internal exposure at the high background area atManavalakurichi have been identified. As a part of this workmobilisation of activity from the monazite ore was studied.It was observed that about 0.3% of the Ra-228 in monazite wasleachable with simulated digestive fluid. The leach out ofPo-210 was high due to alpha recoil. The per capita dose dueto indoor and outdoor thoron and daughters has been estimatedto be in the range of 0.1 to 0.4 mSv per year per capita.The individual committed dose equivalent due to inhalation ofTh-232 was estimated to be 0.8 mSv per year. An unspecifiedroute of internal exposure was the direct ingestion of thesand containing monazite.


Work in Natural highprogress background

Internalexposure.

8. REFERENCES :

Pathways of Internal Exposure at the High Background Area,Paul A.C., Velayudhan T., Pillai P.M.B. and Pillai K.C.,International Conference on High Levels of NaturalRadiation, Ramsur, Iran, November 1990.

1. TITLE : 2. CATEGORY s

Distribution of Natural 1 - 1 2Radionuclides in Marine Organisms


Vasanthi S. Bangera and B. PatelHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Distribution of natural radionuclides, uranium-238, radium-226, lead-210 and poljonium-210 in marine organisms wereevaluated. The work was carried out as a part of the re-search and development programme of Health Physics Division,BARC/IAEA research agreement No. 5405/CF, "Sources of radio-activity in the marine environment and their relative con-tributions to over all dose assessment from marine radioac-tivity". Samples of fish and shell fish of commercial impor-tance from the Indian ocean and coastal waters of India werecollected. Tissues were separated and measured for U-238,Ra-226, Pb-210, Fo-210 and expressed in terms of BqKg"1 drytissue. Datas obtained in this study are compared withsimilar data obtained by other workers in different loca-tions of the world.

Accumulation of Po-210 from sea water to marine biota washigh (CF 103 to 10s). Among the internal organs relativelyhigh accumulations are observed in hepatopancreas and vis-cera (105). Accumulations and distributions of Po-210 insubcellular fractions in the liver of crab, scylla serratawere studied.

Bone of fish accumulated significant quantities of Ra-226 CF(7.6xl03 to 1.8x10*). Pb-210 (l.OxlO3 to 2xlO«) Po-210U.3xlO3 to 1.0x10*) and U-238 (101). In fish muscle distri-butions, CFs observed were U-238 (1.5-4X101), Ra-226 (4-lOxlO2) Pb-210 (102) and Po-210 (l-5xlO3) respectively.


Completing Distribution ofnatural radionuclidesMarine environment

8. REFERENCES :

Progress report submitted at Riso National Laboratory,Roskilde, Denmark, 1990.


A Critical Evaluation of Low Level ' 1 - 1 3Radioactivity in Rana Pratap Sagar (RPS)


T.A.Sebastian, P.V. Vyas, K.G. Varughese, L. Sebastian, G.Chaurasiya and R.P. GurgEnviromental Survey Laboratory (RAPS),Health Physics Division, BARC,Bhabha Nagar -323 307Via Kota

4. ABSTRACT :

Protection of environment from the harmful effects ofradiation is the primary concern of the Indian Atomic EnergyProgrammes. Environmental surveillance around nuclearfacilities provides vital information (i) for testing theadequacy and effectiveness of control of permissibleradioactive release limits at source (ii) for measuringradioactive concentrations in various matrices and (iii) toobserve gross trends in air, water and terrestrialenvironment for evaluating the exposure dose to the generalpopulation. At the Rajasthan Atomic Power Station (RAPS),where PHWR type reactors are in operation, tritium has beenidentified as the critical isotope of human exposure, andwater being the main source of the uptake. The maximum doseto the most vulnerable members of population via waterpathway has been only 0.4 % of the permissible 1 mSv/year.With mean renewal rate of 2 lake volume per year, the lakeretains its large receptive capacity.


Work in Low-Levelprogress Radioactivity,

Rana Pratap Sagar

8. REFERENCES :

A Critical Evaluation of Low Level Radioactivity in RanaPratap Sagar (RPS), T.A. Sebastian, P.V. Vyas, K.G.Varughese, L. Sebastian, G. Chaurasiya and R.P. Gurg,National Symposium on Protection of Environment of City WaterFronts, December 20-22, 1990, Organised by Central WaterCommission, New Delhi.


Studies on Speciation of Transuranics 1 - 1 4in the Environment


V.M. Matkar and K.C. Pillai- Environmental Studies SectionHealth Physics Division, BARCBombay 400 085

4. ABSTRACT :

The study of physico-chemical and biotic process in theenvironment is essential to understand the behaviour oftransuranic nuclides and to assess their environmentalimpact. Dialysis, ion exchange and co-precipitationtechniques have been used to study speciation. The dissolvedfraction of Pu-239, 240 in coastal waters of Bombay harbourbay and in interstitial water from bottom sediments of thebay were found to be associated with organic matter. Thedesorption of Pu from sediment in coastal waters isinfluenced by salinity and carbonate. Study indicates that,even from anoxic sediments, immobilisation and the potentialfor migration is not significant.


Completed SpeciationMarineEnvironmentTransuranics

8. REFERENCES :

Studies on Speciation of Transuranics in the Environment,V.M. Matkar and K.C. Pillai, J. of Radio. Analy. and Nucl.Chem., Articles, Vol. 138, No.l, pp 93-101,1990

1. TITLE 2. CATEGORY :

Offshore Survey of Tarapur Marine 1 - 1 5Environment 23-25 January, 1989


A.G. Hegde, R.S. Iyer, S. Chandramouli, D.D. Rao,K.G. Pimple, M.C. Balani and I.S. BhatHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A comprehensive offshore marine survey was conducted during23-25 Jan., 1989 at Tarapur. Samples of sea water, bottomgrab sediments, sea weeds and fish were processed and analy-sed for fission and activation products by gamma spectrome-try. Plankton samples collected were separated for identi-fication of various species, and processed for trace ele-ments and radionuclide analyses. Plankton population re-corded near the confluence of discharge canal with coastalwaters was comparable with the plankton population of Intakecanal indicating no perceptible impact of thermal dischargeson plankton. The detectable increase in radioactivity ob-served in the nearshore samples is far below the prescribedlimits. The survey showed that radiological impact of theTarapur Atomic Power Station on the marine environment isnegligible.

5. REMARKS : 6. STATUS 7. KEYWORDS :

Completed Tarapur environmentalimpact

Marine plankton

8. REFERENCES :

Offshore survey of Tarapur marine environment 23-25 January,1989, Hegde, A.G., Iyer, R.S., Chandramouli, S., Rao, D.D.,Pimple, K.G., Balani, M.C. and Bhat, I.S., B.A.R.C./I-1007,p. 1-27, 1990


Effect of Mercury, Selenium and 1 - 1 6 tGlutathione on Sulphydryl Levelsand Glutathione Reductase in Bloodclam Anadara Granosa (L).


B. Patel, J.P. Chandy, and S. PatelHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Effects of Hg, Se and glutathione (GSH) on sulphydryl levels(SH) and glutathione reductase (GSSG-R) in an arcid bloodclam A . granosa were evaluated. Exposure to Hg (0.1mgl~l, as HgCl2) alone and in the presence of Se (1 mgl~l,as SeO2) significantly increased SH levels in digestiveglands, blood and erythrocytes, but reduced them in gills inrelation to control .clams. GSH, on the otherhand, producedno significant changes in thiol content. Treatment withHg+GSH conversely restored SH levels to the control rangein these tissues, GSSG-R activity in the erythrocytes wassignificantly reduced on exposure to Hg alone and in thepresence of Se. Complete ante!, ioration of the enzyme activi-ty was recorded after treatment with Hg+GSH. The resultsdemonstrate that at least in marine clams, GSH plays animportant role in offering protection against toxic effectsof inorganic Hg at cellular levels, whereas Se does not.


Completed MercuryEnzymeC1 ams

8. REFERENCES :

Effect of Mercury, Selenium and Glutathione on SulphydrylLevels and Glutathione Reductase in Blood Clam AnadaraGranosa (L), Patel B., Chandy J.P., and Patel S.t IndianJournal of Marine Sciences, Vol. 19, pp. 187-190, 1990

16


Impact of the Gulf Oil Well Fires 1 - 1 7over the Indian Subcontinent:An Environmental Assessment Study

3. AUTHORNS AND ADDKESS :

T.N.Mahadevan* , V.Sitaraman * etalHealth Physics Division, BARCBOMBAY - 400 085Environmental Asesment Divis ion,BARC

4. ABSTRACT :

The study attempts at a first approxiinat ionb evaluation ofthe environmental impact over India of the Gulf Oil WellFire. The impact data were taken from reported values. Theestimates were based on simple models of plume rise anddispersion in the atmosphere. The results indicate magrginalincrease in atmospheric turbidity at a distance 2000 km, tocause any major changes in the mean surface temperature orweather pattern over the Indian Subcontinent. The calculatedratio of Vanadium and Nickel, the elements of significancefor oil combustion in aerosol samples from BARC site atTrombay do not indicate any additional contribution from theoil well combustion sources. The sulphur levels were alsowithin the normal variations observed. Oil and Grease levelsin .sea water collected around Bombay coast do not show anyabnormal concentration typical of oil slick.


Completed Long range disper-sionOil well firesImpact assessment

8. REFERENCES : '

Impact of Gulf Oil Well Fires over the Indian Subcontinent:An Environmental Assessment Study, T.N.Mahadevan,V.Sitaramanet al Encology, Vol 6, No. 2, July.1991

17

1. TITLE t 2. CATEGORY :

Soil to Vegetation Transfer Factors 1 - 1 8for Cs-137 and Co-60 in TarapurEnvironment


S. T. Mehendarge, K.G. Pimpale, S. ChandramouliR-S. Iyer, A.G. Hegde and I.S. BhatEnvironmental Survey LaboratoryTARAPUR - 401 504

" - " - — • — • — — — — ' — — - • • — — ^ — — — — — — — — — — — • - . • — — — — • - . — — - • — — — — _ _ _ . » . — — — . — . • — • - • . « » _ » _ » — — . — — — » — « • —

4. ABSTRACT :

Leaves of commonly grown trees and corresponding surfacesoil were sampled during the monsoon seasons from TAPS andPREFRE premises. Estimation of Co-60 and Cs-137 in all thesamples were carried out by gamma spectrometry using HPGedetector and transfer factors were calculated. The transferfactor for Cs-137 in leaves of 6 trees (Casurina, Neem,Badam, Mango, Bannana, Ashok) were of the same order. Incase of Co-60 Casurina leaves showed highest transfer factorwhereas bannana leaves the lowest. The results indicate thatCasurina leaf sampling can be used for monitoring deep soilcontamination.


Completed LeavesSurface soilTransfer factorCo-60, Cs-137

8. REFERENCES :

Soil to Vegetation Transfer Factors for Cs-137 and Co-60 inTarapur Environment, S.Y. Mehendarge, K.G. Pimpale, S.Chandramouli, R.S. Iyer, A.G. Hegde and I.S. Bhat, Bulletinof Radiation Protection Vol. 14 Nos. 3&4, July-December,1991

18


Studies on the Po-210/Pb-210 1 - 19Equilibrium Ratios in a nearshoreMarine Ecosystem.

3. AUTHOR/S AMD ADDRESS :

M.A.R. IyengarEnvironmental Survey LaboratoryHealthPhysics Division, BARCKalpakkam-603 102

4. ABSTRACT :

Po-210, the terminal radioactive member of the naturallyoccurring U-238 series, in contrast to its 'parent' Pb-210is known to display an interesting movement and accumulationbehaviour in the marine environment. A study was thereforecarried out to investigate the status of Po-210/Pb-210activity ratios in the nearshore coastal waters at Kalpak-kam, in both dissolved and particulate phases and in certainmarine organism species. The results demonstrate that whiledissolved Po-210/Pb-210 ratios in seawaters are less thanunity, there is a gradual enhancement of these ratios inparticulates (1.4 to 2.4), and in plankton (1.2 to 6.8).Significantly higher ratios appear to be quite common amonghigher species like fish, mollusca and Crustacea, with atypical range observed from about 10 to 100 . The studyshows that Po-210 is able to maintain an active transportwithin the coastal marine ecosystem, which has considerableinternal exposure significance among seafood consumingpopulation.


Completed Po-210/Pb-210 ratiosMarine ecosystem

8. REFERENCES :

Studies on the Po-210/Pb-210 Equilibrium Ratios in a near-shore Marine Ecosystem, M.A.R. Iyengar, 9th NationalSymposium on Radiation Physics held at Hyderabad, November27-29, 1991.

19


Performance of System Integrated 1 - 2 0Inert Gas Monitor in EstimatingAr-41 Release through Stack at MAPS


S. Venkataraman, S. Venkataraman* and K. Chudalayandi*Environmental Survey LaboratoryHealth Physics Division, BARCKalpakkam-60 3 102

* Health Physics Unit, MAPS, Kalpakkam• • " " • — — — — — — — ••'••- — — — •» — — — — — — • — . — — . — — — — •-.«. — — _ . — — — — • • — . — — — . ™ — « « » _ _ ^ ^ » — — — — •»•—.«»«-.—.* —

4. ABSTRACT :

Performance of system integrated inert gas monitor in esti-mating Ar-41 release through stack at MAPS is checked on aroutine basis. For this purpose exhaust gas samples arecollected regularly and analysed by gamma spectrometry forcalculating Ar-41 release in a day. Results of daily re-lease of Ar-41 noted from system integrated inert gas moni-tor and that measured from actual grab sampling analysiswere compared. It is observed that the daily Ar-41 activityrelease monitored by system integrated inert gas monitorvaries within 20% with the results of Ar-41 activity releasecalculated by the actual gas analysis method. It is alsofurther demonstrated that the release of Ar-41 from stackwas always well within Technical Specification Limits forMAPS.


Completed Ar-41 releaseMAPS stack

._...-_.••_.-_„. _ — — — — — — — — — -» — — . . — — . • — — — — — . - - • . • — .•- — — * - — .•—•»-—— — — ^ — — — — •» — — — . — — — - • — — — — — . —

8. REFERENCES :

Performance of System Integrated Inert Gas Monitor in Esti-mating Ar-41 Release through Stack at MAPS, S. Venkatara-man, S. Venkataraman and K. Chudalaiyandi, 9th NationalSymposium on Radiation Physics, Hyderabad, November 27-29,1991.

20

1. TITLE : • 2. CATEGORY :

Determination of Mercury in 1 - 2 1Environmental Samples by NeutronActivation

3. AUTHOR\S AND ADDRESS :

G.R.Doshi,S.N.Joshi and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 08 5

4. ABSTRACT :

The procedure developed and standardised for estimation oftrace quantities of mercury in environmental samples in-volves preconcentration of the nuclide by coprecipitat ion oncopper sulphide, irradiation with a neutron flux of 1 E12 n/cm2/sec, ion exchange separation and quantitative determi-nation by gamma spectroscopy by counting Hg-197 isotope. Thetechnique has been applied for estimating mercury in freshwater, sea water and food stuff samples which had mercuryconcentration ranging from 65-70 ng/1, 85- 400 ng/1 and0.5-2.7 ng/g respectively.


Comp1e t ed

8. REFERENCE :

Determination of Mercury in Environmental Samples by NeutronActivation, G.R.Doshi, S.N.Joshi and K.C.Pillai, Indian J.Envi ron. Health, Vol. 33, No.4, pp 492-497, 1991

.21


Distribution of Cs-137 in Different 1 - 2 2Parts of Mango Plants


P. Hemalata, V.M. Matkar and I.S. BhatHealth Physics Division, BARCBomaby - 400 08 5

4. ABSTRACT :

A study of Cs-137 distribution in mango plant growing nearwaste burial ground was undertaken. Samples of mango plant,leave, edible portion of the fruits, hard shell wereprocessed and measured for Cs-137 content by gammaspectrometry using HPGe detector. It was observed that thetrend of Cs-137 distribution in mango plant was, leaves >shell > cotyledine > flesh, thus showing less Cs-137concentration in the edible portion of mango.


Completed MangoConcentration

8. REFERENCES :

Soil to Vegetation Transfer Factors Cs-137 and Co-60 inTarapur Environment, Mehandergi T-S. et.al., IARP XVIIIConference at Tarapur, 1991

Distribution of Pu-239, 240 and Am-241 in Different Parts ofMango Plants, P. Hemalata, V.M. Matkar and I.S. Bhat, Bulle-tin of Radiation Protection, Volume 15, No. 2, April- June,1992.

22


Natural Radionuclides in a Tropical 1 - 2 3River subjected to Pollution


A.C. Paul and K.C. Pillai*Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, Kerala

* Consultant, AERB, Bomaby

4. ABSTRACT :

The radionuclide concentration in Periyar river at the indus-trial zone showed significant reduction, by factors rangingfrom 3 to 5 during the post 1980 period as compared to pre1980 due to better effluent treatment practice. The studiesrevealed that nearly 90% of Po-210 in the river environmentwas unsupported, showing atmospheric pathway of deposition bydecay of Rn-222. The mass and activity (Ra-228) median diame-ters of sedimented particles of less than 63 urn were 15 ± 2.8urn and 18 t 2.5 urn respectively. The particle size • showedlog-normal distribution. Depth distribution of Ra-228 insediment was investigated for its concentration. Highestconcentration was observed at 10 to 30 cm depth. The studieshave helped to identify that particles of less than 63 um inthe sediment layer upto 30 cm were responsible for transportof radionucl ides in the river arid its estuary.


Completed Tropical riverParticle sizePollutionSediment transport

8. REFERENCES :

Natural Radionuclides in a Tropical River subjected toPollution, Paul A.C. and Pillai K.C., Water, Air and SoilPollution 55: 305-319, 1991

23


Migration of Radium and Calcium from 1 - 2 4Soil and Uranium Mill Tailingsto Plants

3. AOTHOR/S AND ADDRESS :

P.M. Markose, I.S.Bhat and K.C.PillaiHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

Accumulation of trace elements by plants from soil dependsupon many parameters such as soil composition, pH, moisture,fertility level and the concentration of the elements beingconsidered. Often the transfer characteristics are influ-enced by the concentration of essential elements havingsimilar chemistry. A study was carried out to determine themigration characteristics of calcium and radium by plants.

Experimental plots were prepared and plants were cultivatedin soil spiked with calcium salts and uranium tailings whichincreaased the radium content of the soil. The Ra/Ca ratioshowed consistency when available radium and calcium in theplants and the precursor were considered. The observedratio (OR Ra/Ca) in plants and soil was found to be of theorder of 10"^. Also the discrimination factor (DF Ra/Ca) wasfound to vary from 0.1 in roots to 0.03 in fruits and ob-served to be consistent in various experimental fieldsirrespective of the radium content. The high DF in fruitssuggests that the radiation dose to the population by con-sumption of fruits grown on tailings in not significant.


Completed Essential elementsObserved ratioDiscrimniation

factorRad i urn

8. REFERENCES :

Migration of radium and calcium from Soil and Uranium milltailings to plants, P.M. Markose, I.S. Bhat and K.C. Pillai,Symposium on Natural Radiation Environment NRE V Salsburg,Austria, 1991

24


Radioecology of Cobalt-60 under 1 - 2 5Tropical Environmental conditions


B. Patel, and S. PatelHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Cobalt-60 and Cesium-137 released into the nearshore envi-ronment of a BWR (400 MWe) nuclear power station at Tarapur,have been found to be readily sorbed by the sedimentaryparticles. Surveillance over last two decades showed thatbeyond 2 km distance north and south of the discharge point,levels were within background range despite continued re-lease of controlled low levels of radioactive wastes.Within 1 km of the effluent point levels of both the nu-clides dropped exponentially with time yielding effectivehalf-life of 1.5 and 2.0 y against their respective physicalhalf-life of 5.2 and 28 y. Under laboratory simulatedconditions sorption-desorption of Cesium could be explainedin terms of ambient salinity and other environmental parame-ters. It was however, not possible to demonstrate similarbehaviour of Cobalt-60 under laboratory studies. The possi-ble mechanisms governing sorption-desorption of both theradionuclides under field and laboratory conditions arediscussed.

5. REMARKS : 6. STATUS s 7. KEYWORDS :

Completed Cobalt-60Half lifeDesorption

8. REFERENCES :

Radioecology of Cobalt-60 under Tropical EnvironmentalConditions, Patel B. and Patel S.,In Radionuclides in theStudy of Marine Process Edited by P.J. Kershaw andD.S.Woodhead, Elsevier applied Science - London and NewYork, 1991

25


Uptake of Cadmium in Tropical Marine 1 - 2 6Lamel1ibranchs, and Effects onPhysiological behaviour.


B. Patel, and K. AnthonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The effect of Cadmium introduced as inorganic salts (Chlo-ride, nitrate, sulphate, carbonate, acetate and iodide) ororganic chelates (with EDTA, NTA and humic acid) on thephysiolo-gical behaviour of six species of Tropical lamelli-branchs-arcid blood clams Anadara granosa and Arhombea , venerid clams Meretrix casta and Kate-lysia opima , and mytilid mussels Perna viridisand P indica collected from various intertidal areasin Southern India from 1986 to 1989 has been evaluated.


Completed CadmiumLamel1ibranchs

behaviour

8. REFERENCES :

Uptake of Cadmium in Tropical Marine Lamel1ibranchs andEffects on Physiological behaviour, Patel B. and AnthonyK.,Marine Biology, 108, pp 457-470, 1991

26


Incorporation of C-14 in Chemical 1 - 2 7Constituents of Algal Cells


G.R.Doshi and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 08 5

4. ABSTRACT :

Two marine algal species Dunaliella premodecta, Chlamydemo-nas sp,. and one fresh water species, Scenedesmlus obliquuswere studied for C-14 incorporation under laboratory condi-tions. The uptake of C-14 in dry marine algal species wasfound to be more compared to that in fresh water species forthe same initial concentration in the respective media. Asequential extraction technique was employed to study thedistribution of C-14 in different organic constituents. C-14fixation was found to be more in fatty acid fraction fol-lowed by protein and nucleoprotein fraction.

5. REMARKS : 6. STATUS : 7. KEYWORD

Completed

8. REFERENCE :

Incorporation of C-14 in Chemical Constituents of AlgalCells, G.R.Doshi and K.C.Pillai, Ind. J. Exptl. Biology,Vol. 29, pp 1074-1076, 1991

27


Atmosphric Stability Evaluation 1 - 2 8based on net Radiation for Applic-tions in Dose Estimation


V.J.Daoo,Faby Sunny and V.N.BapatHealth Physics Division, BARCBOMBAY - 444 085

4. ABSTRACT :

For Atmospheric Stability Evaluation, Net radiation is alwayspreferred to convenientionaly used insolation/cloud cover,asone of the input parameters. Its use has certain advantagesand limitations which are highlighted in this paper. Twoapproaches, one based on net radiation, insolation/cloudcover are compared using concurrent data on net radiation,insolation and cloud cover collected at Trombay during Janu-ary to June 1987. It is shown that use of net radiation isadvantageous particularly in night time categorisation andconsiderably reduces the uncertainty associated with night-time categories. Finally some aspects on improvement inaccuracy of dose estiamtes due to reduction in the uncertain-ty normally associated with the stability estimation are alsodiscussed.

5. REMARKS: 6. STATUS 7. KEYWORD:

Completed Atmospheric stabilityNet Radiation

8. REFERENCE :

Atmospheric Stability Evaluation based on net Radiation forApplications in Dose Estimation, V.J.Daoo, Faby Sunny andV.N.Bapat, Bulletion of Radiation Protect. Vol. 14, Nos. 3& 4, pp 27-30,1991

28


1-129 in Soil and Grass Samples 1 - 2 9around a Nuclear ReprocessingPlant


G.R.Doshi,S.N.Joshi and K.C.PillaiHealth Physics Division, BARC' BOMBAY - 400 085

4. ABSTRACT :

Neutron activation analysis was used to determine I- 129 insoil and grass samples around a reprocessing plant. Themethod involved wet oxidation of samples, using chromicacid, followed by distillation, collection of Iodine inalkaline solution, loading on Dowex-1, irradiation and postirradiation purification steps. The factivity of 1-130isotope of the purified samples was measured for quantita-tive determination of 1-129. The experimental results showedthat 1-129 and the I-129/I-127 specific activity in soilsamples varied from 1.09 E-4 to 5.33 E-3 pCi/g and 0.10 E-6to 6.12 E-6 pci/g respectively. Further, the geometric meanof soil to plant transfer factor (Bv) for 1-129 was found tobe 0.16 which was comparable with other published valules.


Completed

8. REFERENCE :

1-129 in Soil and Grass Samples around a Nuclear Reprocess-ing plant, G.R.Doshi, S.N.Joshi and K.C.Pillai, J. Radioan-al. Nucl. Chem. Letters, 155 (2), pp 115-127, 1991

29


Environmental Impact Assessment 1 - 3 0Studies Around OSCOM Project of IRE


S.C. Saha and S. Suresh Kumar*Health Physics Unit OSCOM

* IRE Ltd, OSCOM, Orissa

4. ABSTRACT :

Assessment of air pollution impact due to OSCOM projectinvolves the following parameters (a) choice of an appropri-ate air pollution dispersion model, (b) compilation ofmeteorological data appropriate to the model, (c) determina-tion of the sources inventory, (d) computation of the impactusing the model, and comparison of the impact with respectto ambient air quality for the plant prescribed by theState Pollution Control Board. For the present work Pas-quill's disperson model together with Brigg's plume riseformula using double Gausian expressions were used. Inputparameters are so chosen taking into account their "Plausi-bility' of occurence such that the model gives the maximumimpact. Meteorological data for the input to dispersionmodel are wind speed & direction, cloudiness & inversion.Source inventory of 12 stacks with their release rate,height, heat release were taken into account for the calcu-lation of ground level concentration for 20 locations (100 mto 20 KM) with respect to SO2 and SPM which are the mainpollutants from all the units of OSCOM. Three permanentsampling stations in a grid of 120° sector within 3 Kmradius were chosen with the concurrence of State PollutionControl Board. Continuous 8 hrs monitoring for pollutantslike SO2» NOx, CO & SPM has been continued throughout theyear at the above locations. From these it has been conclud-ed that there has been no adverse effect on air qualityaround this region due to the operation of the OSCOM plants.

5. REMARKS : 6. STATUS : 7. KEYWORDS:

Completed Impact assessmentPasquill's dispersion

modelAir pollutionBrigg's plume riseDouble gausion

expression

8. REFERENCES :

Environmental Impact Assessment studies around OSCOM projectof IRE. S.C. Saha and S. Suresh Kumar, 1st NationalSymposium on Environment Bombay, Feb. 1992.

30


Ambient Air Quality Monitoring at 1 - 3 1Nuclear Fuel Complex, Hyderabad


N. Balachandran, B. Balaiah, A.R. Lakshmanan andS. ViswanathanHealth Physics UnitNuclear Fuel ComplexHYDERABAD - 500 762

4. ABSTRACT :

The various chemical, metallurgical and mechanical plants ofNuclear Fuel Complex produce sizeable quantities of liquid,solid and gaseous effluents in their operations.

Gaseous effluents are scrubbed through suitable absorbentsand air borne UO2 dusts generated in the powder handlingareas are passed through filters and vented out throughstacks at a height of 10-14m from ground.

To assess the ambient air quality, four monitoring stationshave been selected on the basis of wind direction, frequen-cies, stack height and the population of the residentialareas. Three 8 hourly samples for SPM, SO2t NO£, CL2» U andNH3 were collected on each monitoring day, twice a week forfour weeks in each season and for four seasons covering theyear 1990-91.

The monitoring data reveal that the levels of pollutants arewell within the CPCB and international norms for industrialand mixed areas indicating the emissions from NFC are undercontrol.

5. REMARKS : 6. STATUS: 7. KEYWORDS:

Completed Ambient airAir quality

8. REFERENCES :

Ambient Air Quality Monitoring at Nuclear Fuel Complex,Hyderabad, N. Balachandran, B. Balaiah, A.R. Lakshmanan andS. Viswanathan, National Symposium on Environment, BARC,Bombay, 1992

31


Biological Indicator based Approach 1 - 3 2in Environmental Pollution Studiesat Kalpakkam


S. GanapathyEnvironmental Survey LaboratoryHealth Physics Division,BARCKalpakkam-603 102

I. ABSTRACT :

Many marine organisms especially filter-feeding benthicspecies serve as excellent indicators of metallic/radioac-tive pollution in the marine environment. Thus in thesearch for ideal marine pollution indicators, detailedstudies on the distribution of trace elements Fe, Mn, Co,Zn, Cu, Pb & Cd - in the Kalpakkam coastal environment(seawater) marine organisms (bivalves, gastropods and crus-taceans) were carried out. The studies have shown- thatoysters are "ideal indicators", both quantitative and quali-tative, for detecting levels of Cu and Zn in the environ-ment. Similarly the operculate barnacles from Kalpakkamenvironment are ideal 'indicator species' for monitoring ofFe, Mn, Co, Pb & Cd irrespective of their habitat - whethermarine or estuarine. Also species specificity was noticedin oysters for Zn and Cu and in barnacles and crabs for Mnand Cu. Tissuewise distribution of trace elements in var-ious benthic species has also shown that the levels aremaximum in tissues involved in feeding processes and indigestive glands followed by other muscular tissues.


Biological indicatorsMarine organismsKalpakkam coastalenvironment

. _ , — . _ . _ . . _ - . _ _ _ _ _ - . _ . _ — . — — . — . — _ - - - - . . — , — . — _ — — — _ _ _ _ _ _ _ . - , _ _ _ _ _ . _ - _ _ _ — _ - _ _ - — _ — _ . • - _ _ _ - . _ . • — _ _ _ _ • — .

8. REFERENCES :

Biological Indicator based Approach in Environmental Pollu-tion Studies at Kalpakkam, S. Ganapathy, National Symposiumon Environment - Scientific Approach to Environment issues,BARC, Bombay, Feb. 3-5, 1992.

32


A Programme of Tritium (H-3) 1 - 3 3Surveillance in the Environmentof MAPS, Kalpakkam


M.P. Rajan and M.A.R. lyengarEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam-603 102

4. ABSTRACT :

Pressurised heavy water reactors (PHWR) use heavy water asmoderator and coolant which results in considerable produc-tion of tritium as an activation product. During normaloperations tritium is routinely released into the environ-ment from such reactors through atmospheric and liquiddischarges routes. Tritium concentrations have been inves-tigated in the atmospheric environment and aquatic environ-ment of MAPS ( 2 x 235 MWe) Kalpakkam, consisting of coastalsea waters, back waters and fresh waters. From the investi-gations carried out during 1989-90 in the atmospheric envi-ronment, it is evident that the site concentrations oftritium are significantly higher, compared to the levelsobserved in villages away from site. Similarly the resultsof tritium in the aquatic samples during the same periodshowed very low ambient levels of tritium except for thesamples collected from Jetty, near the low level liquideffluent discharge area. Doses to public due to tritiuminhalation and ingest ion were calculated using the mean (GM)concentrations of tritium in air and water. From thesefindings it was observed that tritium concentrations in theenvironment and consequently dose received by the public atKalpakkam due to tritium releases from MAPS is less than 1uSv/yr which is insignificant.


Completed TritiumEnvironmentKalpakkamDose to Public

8. REFERENCES :

A Programme of Tritium (H-3) Surveillance in the Environmentof MAPS, Kalpakkam, M.P. Rajan and M.A.R. Iyengar, Scientif-ic Approach to Environmental Issues, Bombay,Feb. 3-5, 1992..

33


An Approach to the Derivation of 1 - 3 4Authorised Limits for RadioactiveEffluents from Nuclear Facilities


K.K. Narayanan, S. Krishnamony, K.C. PillaiHealth Physics Division, BARC.Bombay 400 08 5

4- ABSTRACT :

The comparatively vigorous and systematic approach andmethodology used in India for establishing Authorised Limitsfor radioactive effluent discharges from nuclear facilitiesis described. The concept of dose apportionment amongfacilities, pathways and radionuclides at nuclear site inIndia is described. The important parameters like atmosphericdilution factor, concentration limit in air and water, dose -release rate relationship, etc. for nuclear sites are given,along with the calculated values of Authorised Limits forimportant radionuclides, As an example, Authorised Limitscalculated using the methodology, applicable to RAPS 1,2 aregiven. The three tier system of regulatory control andcompliance is explained.

5. REMARKS : 6. STATUS: 7. KEYWORDS:

Completed Authorised limitDose apportionmentAtmospheric dilutionfactor

8. REFERENCES:

An Approach to the Derivation of Authorised Limits forRadioactive Effluents from Nuclear Facilities, K.K. Naraya-nan, S. Krishnamony, K.C. Pillai, National Symposium onEnvironment Scientific Approach to Environmental Issues,BARC,Bombay,1992

34


Impact Assessment of Long Lived 1 - 3 5Particulate Air Activity in theVicinity of Nuclear Installations


A.G. Hegde, S. Chandramouli, R.S. Iyer and I.S. Bhat*Environmental Survey LaboratoryTARAPUR - 401 504E & PA, Nuclear Power Corporation,World Trade Centre, Bombay

4. ABSTRACT :

Monitoring of particulate radioactivity released throughstack near the Tarapur Nuclear Installations is routinelycarried out by Environmental Survey Laboratory (ESL). Esti-mation of long lived gross beta a/id alpha air particulateactivity and individual radionuclides of Co-60, Sr-90, Cs-134, Cs-137 has been done at two locations continuously.Twenty three years of data collected on air particulateactivity indicate that the impact due to stack release isnegligible.


Completed Air particulateactivity

Impact assessmentGross betaCo-60, Sr-90, Cs-137

8. REFERENCES :

Impact Assessment of Long Lived Particulate Activity in theVicinity of Nuclear Installations, R.S. Iyer, S. Chandramou-li, A.G. Hegde and I.S. Bhat, Proceedings of National Sympo-sium on Environment, Scientific Approach to EnvironmentalIssues, BARC, Bombay, pp 18-20 , Feb. 3-5, 1992

35


Environmental Impact of Heavy Water 1 - 3 6Plant (Kota)


R.P. Gurg, T.A. Sebastian, K.G. Varughese and K.C. PillaiEnviromental Survey Laboratory (RAPS),Health Physics Division, BARC,Bhabha Nagar -323 307Via Kota

4. ABSTRACT :

Heavy water plant at Anushakti is based on Gridler's sulphideand vacuum distillation processes. In the plant, for initialenrichment of deuterium H2O-H2S duel temperature exchangeprocess is used and further vacuum distillation to producereactor grade heavy water.

Environmental releases at ground level are mainly of H2S andtritium through liquid effluent and H2S gas through leaks inthe working environment of the plant. The paper gives thelevels of unionized sulphide and tritium observed in liquideffluent and sulphide in air at different places in publicdomain during 1983-1990.


Work in H2Sprogress Heavy water

Environment

8. REFERENCES :

Environmental Impact of Heavy Water Plant (Kota), R.P. Gurg,T.A. Sebastian, K.G. Varughese and K.C. Pillai., NationalSymposium on Commissioning and Operating Experiences in HeavyWater Plants and Associated Chemical Industries, Organised byHeavy Water Board, BombayFebruary 27- 28, 1992

36


A Ten Year Radiation Profile of the 1 - 3 7Environs of Rajasthan Atomic PowerStation •


A.S. Basu, R.P. Gurg* and K.S.V. NambiEnvironmental Assessment Division

* Health Physics Division, BARCBombay - 400 08 5

4. ABSTRACT .•

The environmental radiation levels in the region of about 20km radius around RAPS have been under constant surveillancesince its inception by the use of ThermoluminescentDosimeters (TLDs). The programme is to monitor any increasein the radiation levels from day to day functioning of theplant and in case of any incidental release. About 23locations are being monitored continuously on quarterlyintegrating cycle by TLDs mailed from Bombay. There are sixlocations within the exclusion zone and 17 locations betweenthe exclusion ring and 20 km radii almost radially around thestack.


Work in TLDsprogress RAPS

Environment

8. REFERENCES :

A Ten Year Radiation Profile of the Environs of RajasthanAtomic Power Station, A.S. Basu, R.P. Gurg and K.S.V.Nambi,Second National Symposium on Safety of Nuclear Power Plantsand other Facilities, Organised by Board of Research inNuclear Sciences.March 11-13, 1992

37


Gamma Spectrometric Studies of 1 - 3 8Beach Sands and Soils in theKalpakkam Environment


V. Kannan, M.P. Rajan and M.A.R. IyengarEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam-603 102

4. ABSTRACT :

To investigate the significance of monazite prevalence inthe Kalpakkam area on environmental exposures, detailedstudies consisting of scinti1lometric surveys of beach areasfollowed by gamma spectrometric analyses of beach sands andsoils (using HPGs detector) from interior villages werecarried out. Th-232, U-238 and K-40 contents in beach sandsand soils from different locations of substantially varyinggamma radiation backgrounds were measured. The observedranges of these nuclides in local beach sands and soils wereas follows:

Th-232 U-238 K-40(Bq/kg)

Beach sand 856 - 3872 72 - 258 300 - 404soils 17 - 171 5 - 31 124 - 632

The activity ratios of Th-232 / U-238 in beach sands aregenerally higher - in the range of 11 to 15 - attributableto monozite presence, while in soils the ratios are innormal range i.e. 5 to 10. These levels of activity, inparticular Th-232 appeared to be much higher compared tolevels at other NPP sites. Using UNSCEAR (1988) dose fac-tors an attempt has been made to compute the external doselikely to be received by public from the above range ofnuclide levels.


U-238, Th-232, K-40r-spectrometryMonazi teBeach sand, Soil

8. REFERENCES :

Gamma Spectrometric Studies of Beach Sands and Soils in theEnhanced Background Site at Kalpakkam, Kannan V., Rajan M.P.and Iyengar M.A.R., National Seminar on Radiation, Environ-ment and Man, Mysore, October 8 - 9 , 1992.

38


Distribution of Pu-239+240 and Am-241 1 - 3 9in Different parts of Mango Tree


V.M. Matkar, Usha Narayanan and I.S. BhatEnvironmental Studies SectionHealth Physics Division, BARCBombay 400 085

4. ABSTRACT :

Study of Plutonium and Americium in the mango leaves and thedistributions in different parts of the mango fruits weretaken up. The generally observed pattern is leaves >cotyledon > shell > flesh. It is seen that, if there iscontamination by Pu and Am, human intake of radioactivity islowest as the edible portion of the mango fruit has thelowest activity.


Completed TransuranicsMango treeDistributionRadiation exposure

8. REFERENCES :

Distribution of Pu-239+240 and Am-241 in Different Parts ofMango Tree, V.M. Matkar, Usha Narayanan and I.S. Bhat, TheFourth International Conference on Low Level Measurements ofActinides and Long lived Radionuclides in Biological andEnvironmental Samples held at Brazil, October 15-20, 1992.

39


A Study of the Nutritional Adequacy 1 - 4 0of Dietary Trace Element Intake ofUrban Indian Population


H.S.Dang, D.D.Jaiswal and M. ParameshwaranHealth Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT :

The d.aily dietary intakes of a few nutritionally important traceelements, Fe, Zn, Se, Cr, Mo and Co were estimated using instru-mental neutron activation analysis (INAA). The concentrations ofthese elements were determined in the aliquotes of processedduplicate diet samples obtained from sixteen volunteers residingin Bombay and representing the urban Indian population. Theintakes by the individual volunteers were obtained on the basisof the total diet consumed on a single day and the concentrationsof the trace element in their diet. The comparison of averageintake of these elements with the world averages obtained on thebasis of trace element analysis of the diet obtained from 11countries showed that out of the 6 trace elements included in thestudy, the intake of only Zn and Mo are lower than the worldaverages. The intake of Mo, when compared with recommended die-tary allowances (RDA) value appears to be adequate. The intake ofZn however is lower than both the world and also with the RDAvalue.


Completed NutritionTrace elementDietary intake

8. REFERENCES :

A Study of the Nutritional Adequacy of Dietary Trace ElementIntake ofUrban Indian Population. H.S.Dang, D.D.Jaiswal andM.Parameshwaran, Paper Presented in IAEA seminar on IsotopeTracer in Human Research, Hyderabad, November 15-20, 1992

40


Relative Stability Constants of 1 - 4 1Organic Matter from Sediments withZinc, Copper, Manganese and Iron


V.M. Matkar and K.C. PillaiEnvironmental Studies SectionHealth Physics Division, BARCBombay 400 085

4. ABSTRACT :

The mobilisation of metals in the environment are known totake place as organo-metal1ic complex compound. Thestability of these complexes will therefore be dominantfactor in the mobilisation. The stability of the complexesformed by the organic matter extracted from the sediment withmetals such as Zn, Cu, Mn and Fe were studied since thesemetals are stable counter parts of the activation products ofZn-65, Cu-64, Mn-54 and Fe-59 and also biologicallysignificant element. Relative values of formation constantobtained for the metals were 0.468 for Zn, 2.94 for Cu and.0137 for Mn. However stability constant for Fe could not becalculated since the reactivity measured was proportional tothe organic matter concentration.


Completed Stability constantOrganic matterZn, Cu, Mn & Fe.

8. REFERENCES :

Relative Stability Constants of Organic Matter from Sedimentwith Zinc, Copper, Manganese and Iron, V.M. Matkar and K.C.Pillai, Nuclear and Radiochemistry Symposium,Visakhapatnam,Dec. 21-24, 1992

41

1- TITLE : 2. CATEGORY :

Green House Effect and its Impact 1 - 4 2on Global Climate.

3. AUTHORNS AND ADDRESS :

T.N.Mahadevan* and V. SitaramanHealth Physics Division, BARCBOMBAY - 400 08 5Environmental Assessment Division,BARC

4. ABSTRACT :

The nature of Green House Effect and its impact on GlobalClimate is reviewed. The review gives a brief summary of theatmospheric inventary- present and projected of differentgreen house gases and their infra-red heating rates. Theeffect of increased heating rate on global climate is re-viewed. Various feed back effects in the atmosphere whichmodify green house warming are summarized and their relativecontributions are indicated. Recent studies which criticallyexamine various feed back processes are described. The reviewdiscusses the green house warming in the context of IndianScenerio.


Completed Green house effectsGlobal warmingClimateFeedback processesPlume depletion

8. REFERENCES :

Green House Effect and its Impact on Global Warming,T.N.Mahadevan and V.Sitaraman, Environmental Directory, 1992

42


Environmental Radiation Levels 1 -'43Around Jaduguda Complex


G.K. Srivastava and A.H. KhanHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

Regular environment radiation surveillance is carried outaround Jaduguda since 1984 using mailed TLDs in quarterlyintegrating cycles. Site for placing TLDs for exposure areselected with reference to the uranium mining and ore proc-essing facility in this area. For comparison some far awaylocation were also selected. Average background radiationaround plant area is observed as 2.2 mR/y. At locations outside the plant average radiation level is 90'mR/y. As com-pared to this the regional background radiation level aroundJaduguda works out to be 95 mR/y.


Completed Natural radiationTLDUranium industry

8. REFERENCES :

Environmental Rndiation Levels Around Uranium Corporation ofIndia Limited Jaduguda during 1984-1989 Navnit Mehta, G.K.Srivastava and K.S.V.Nambi Bulletin for Radiation Protec-tion, Vol 15, No. 2 ,1992

43


Environmental Radioactivity Survey 1 - 4 4around Kaiga Atomic Power Project


M.D. Borkar, B.M. Sankhesara, B.U. Kothari and I.S. BhatHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A preliminary survey to establish the baseline radiationlevels and radioactivity content in the environmental mate-rials in the neighbourhood of Kaiga Atomic Power Project wasconducted in Jan 1992, covering an area 16 Km radius aroundKaiga. Radiation levels were measured at various locationaand samples of soil, river water, bore well water, seawater, grass and areca-nut were collected from some of thelocations. Air sampling was done at the site. The environ-mental samples were analysed for gross alpha, gross beta,and Cs-137. The radiation levels were measured with gammaray scintillation meter, with sensitivity of 1 uR/hr. Theradiation levels ranged from 3.5 - 12 uR/hr. The gross alphaactivity was counted with ZnS scintillation counter withsensitivity of 0.14 mBq and efficiency of 25%, while grossbeta activity was counted with gas flow proportional counterwith sensitivity of 0.6 mBq and efficiency of 35%. Theaverage results are given.


Continued SurveyRadiationRadioactivi ty

8. REFERENCES :

Environmental radioactivity survey around Kaiga Atomic PowerProject - M.D. Borkar, B.M. Samkhasara, B.U. Kothari andI.S. Bhat, 1992-

44


Radiological Safety in Phosphate 1 - 4 5Processing


A.C. PaulHealth Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, Kerala

4. ABSTRACT :

Phosphoric acid contains uranium of about 100 ppm. Solventextraction, stripping and precipitation concentrates theuranium. The activity inventory at different process stagesin the pilot plant at FACT Ambalamedu, vary from 20 to 400MBq. Estimated radiation fields in the plant range from 0.3to 10 uGy hr~l. The estimated average air activity in theplant is 0.01 Bq m~3 which is 1% of the DAC. The averageindividual exposure for the operation works out to 1.5 mSvper year. The liquid effluent which amounts to 5 m^ per daycontains U at 10 ppm level. The effluent is diluted by afactor of 10^ at Effluent Treatment Plant at FACT and dis-charged into Chitrapuzha river. Operation of the pilot plantdoes not result in significant environmental impact.


Completed Uranium phosphateprocessingEnvironmentalimpact.

8. REFERENCES :

Radiological Safety in Phosphate Processing, Paul A.C.,Technical Meeting on Plant Operation for Uranium Recoveryfrom Phospheric Acid, FACT, CD 1992

45


Monitoring of a Tropical River for 1 - 4 6Pollution


A.C. Paul and K.C. Pillai*Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, Kerala* Consultant, AERB, Bomaby

4. ABSTRACT :

The study carried out in river Periyar showed that tracemetals have significant enhancement upto a factor of 10 atthe industrial zone during the late 1980 period as comparedto 1970s. The enhanced levels could be observed in the 20 Kmstretch of the river between the industrial outfall area andC6chin Harbour. The concentration gradient in the sedimentsbetween these points work out to 15. Solubi1isation increasesthe concentration of trace metals in water at the backwatersduring summer due to high salinity. Zinc and Cadmium levelsas high as 550 and 30 ug/1 respectively have been observed inwater at the estuarine area in summer. Such high concentra-tions along with high salinity have synergistic effects andmay be deleterious to aquatic life. Pollutants tend to con-centrate in the upper layer of the sediment at the respectiveside of discharge.


Work in Tropical riverprogress Pollution

Trace metals

8. REFERENCES :

Monitoring of a Tropical River for Pollution, Paul A.C. andPillai K.C., First National Symposium on Environment, BARC,Bombay 1992

46


Environmental Impact of Argon-41 1 - 4 7Release from Rajasthan Atomic PowerStation for the Period 1984 - 1991


R.P. Gurg, R.K. Gupta and M.B. SaxenaM.M. Lab, RAPS, Health Physics Division,BARC, Anushakti 32 3 30 3Via Kota

4. ABSTRACT :

The external gamma radiation dose due to release of Ar-41from RAPS was evaluated at fence post (1.6 km) in all thesectors and at different population centers upto 20 kms forthe period 1984-1991, The paper summarises and discusses thedata obtained.


Work inprogress

7. KEYWORDS

Ar-41RAPS

8. REFERENCES :

Environmental Impact of Ar-41 Release from Rajasthan AtomicPower Station for the Period 1984-1991, R.P. Gurg, R.K. Guptaand M.B. Saxena, Second National Symposium on Environment,Jan. 27-30, 1993, Jodhpur and Jaisalmer, Organised by Boardof Research in Nuclear Sciences.

47


Distribution of Ruthenium-106 in 1 - 4 8the Tarapur Marine Environment


.R.S. Iyer, S. Chandramouli, S. T. Mehendarge,A.G. Hegde and I.S. Bhat*Environmental Survey LaboratoryTARAPUR - 401 504E & PA, Nuclear Power Corporation,World Trade Centre, Bombay

4. ABSTRACT :

The marine environment of Tarapur receives controlled lowlevel liquid waste from nuclear facilities. Ruthenium-106 isone of the important fission product radionuclide found inthe liquid effluent of fuel reprocessing plant. Distributionand concentration of Ru- 106 in different marine matricesare studied and estimated. The bio-accumulation factors werecomputed and indicator species were identified. The internaldose due to the consumption of the marine food was estimatedand found to be insignificant compared to the annual doselimit.


Completed Marine environmentRuthenium - 106Reprocessing plant

distributionConcentrationBi oaccumu1a t i on

factorIndicator speciesInternal dose

8. REFERENCES :

Distribution of Ruthenium-106 in the Marine Environment,R.S. Iyer, S. Chandramouli, S. T. Mehendarge, A.G. Hegde andI.S. Bhat, Proc. 2nd National Symposium in Environment,Jodhpur, Board of Research in Nuclear Sciences, DAE, Govt.of India, pp 25-28, Jan.1993

_ _ • _ — • — . « . — — *• — — ••-•-• — — — — —. — — — — — — — — — — — — — — — — — — — — — . — _ _ _ _ _ _ — _ — • _ — _ . „ . . . _ _ — _ ~ _ _ _ —

48


Effect of Oil Pollution on 1 - 4 9Radionuclide Uptake byMarine Sediments.


A.K.More, S.R.Sachan and I.S.Bhat*Health Physics Division, BARCBOMBAY - 400 085Environmental Group, Directorate of E &, P A, NPCILWorld Trade Centre,BOMBAY - 400 005

4. ABSTRACT :

Effect of oil pollution on uptake of radionuclide on marinesedimenthas been studied using Cs-137 and Pu-(239+240)raditracers. The distribution factors (kd) have been evalu-ated under different conditions simulated in the laboratory.It is observed that for alkali metal radionuclides like Cs-137 there is comparatively less effect of oil pollution onsediment absorption.The kd value for Cs-137 is reduced onlyby about 25% due to presence of oil in the sea water. Incase of radionuclides which get hydrolysed at sea water pH,there is marked reduction in kd values due to oil pollution.The kd for Pu-(239+240) is reduced by about 83%. The studywill help in predication and interpretation of transport ofvarious radionuclides under polluted condition of marineenvironment.

5. REMARKS : 6. STATUS -• 7. KEYWORDS :

Completed Cs-137, Pu-(239+240)Marine sedimentsOil Uptake

8. REFERENCE :

Effect of Oil Pollution on Radionuclide Uptake by MarineSediments, A.K.More, S.R.Sachan and I.S.Bhat, Second Nation-al Symposium on Environment, Jodhpur, Jan 27 - 30, 1993

49


Contribution of Drinking Water to 1 - 5 0the Daily Intake of Trace Elements

3. AUTHOR/S AND ADQRESS :

H.S.Dang, D.D.Jaiswal, M.Parameswaran and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Trace elements are known to play a significant role inhealth and disease. The deficient intake of essential ele-ments (Cu,Zn, Fe etc.) and excessive intake of toxic ele-ments (As and Hg) can lead to human health problems. Drink-ing water is the second largest source of the daily intakeof trace elements by adult population.

This paper reports on the analyses of drinking water samplesobtained from 21 different cities of India spread over 11states. The analysis was carried out for 4 essential ele-ments Cu, Zn, Mn, Mo and one toxic element As, using thetechnique of neutron activation followed by radiochemicalseparation. Assuming the reported daily mean drinking waterconsumption of 4.5 L, the median daily intakes of As, Cu,Mn, Mo and Zn by adult population were obtained to be 1.3ug, 37.4 ug, 20.6 ug, 3.4 ug and 176 ug respectively.


Completed Trace ElementsDaily IntakeDrinking Water

8. REFERENCES :

Contribution of Drinking Water to the Daily Intake of TraceElements, H.S.Dang, D.D.Jaiswal, M.Parameswaran andR.C.Sharma, Journal of Indian Water Works Association, Jan -March, 1993

50


A Comparative Study of Annual 1 - 5 1Atmospheric Dispersion Factors atDifferent Reactor Sites in India


V.J. Daoo, B.B. Adiga, R.P. Gurg, E. Chandrasekharan, L.N.Sharma and T.M. KrishnamurthyHealth Physics Division, BARC,Bombay 400 085

4. ABSTRACT :

A three year (1987-89) average annual atmospheric dispersionfactors for five sites vi2. Trombay, Tarapur, Rawatbhata,Kalpakkam and Narora has been evaluated at 1.6 km and 16 kmdownwind distances from the source, using the sitemeteorological data and examined for its site specific natureand directional dependence. The sector weighted dispersionfactor at 1.6 km downwind distance averaged over 5 sites(site average) is found to be 4.0 x 10~& s/m^ with a standarderror of 35%. Individual sitewise sector weighted valuesvary by a factor of 1 to 1.3 on the site average value forall the site except in case of Narora for which the factor is0.5. The lower factor at Narora has been attributed tohigher height of release, considered for Narora compared toother sites. At 16 km downwind distance the dispersionfactors are smaller by about an order of magnitude for allthe sites. Range of the individual directionwise dispersionfactors at a particular site is within a factor of 2 to 3 ofthe sector weighted value of the respective site.Irrespective of the sites, the absolute maximum and minimumdispersion factors (direction values) observed in the studyvary within a factor of 3 to 5 of the site average value.The site average value with a standard error of 35% can beconveniently used for future site evaluation purposes forsites having topographic features comparable with the sitesconsidered in this study.


Work in Dispersionprogress factors,

Atmosphere,Reactor sites.

8. REFERENCES :

A Comparative Study of Annual Atmospheric Dispersion Factorsat Different Reactor Sites in India, V.J. Daoo, B.B. Adiga,R.P. Gurg, E. Chandrasekharan, L.N. Sharma and T.M. Krishna-murthy, Twentieth Annual IARP Conference, Feb.24-26, 1993

51

1. TITLE :

Marine Radioactivity Investigationsin the Coastal Ecosystem atKalpakkam following Low LevelEffluent Discharges from MAPS

2. CATEGORY :

1 - 52


M.P. Rajan and M.A.R. IyengarEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam-603 102

4. ABSTRACT :

A detailed programme of environmental radioactivitymonitoring is in practice at Kalpakkam ever since the twounits of 230 MWe each of MAPS went into operation in 1983and 1985 respectively. During the operation of the reactorlow level liquid effluent are released to the coastal waterof the Bay of Bengal, for which the discharge limits havebeen set by regulatory authorities based upon certain

. criteria, such as dilution and dispersion capacity of coastalwaters, migration of radioactivity along marine, food chainand possible build up in the critical marine matrices, seafood consumption pattern of local population, dosimetry ofthe radionuclides, etc. Detailed investigation wereconducted to get data on coastal characteristics,radionuclide composition of liquid effluents andradioactivity content in different environmental matrices ofmarine origin. The results obtained showed that the activitylevels were uniformly low and insignificant from the point ofview of public exposures.


Completed

7. KEYWORDS :

Marine radioactivityKalpakkam,Marine food chainLiquid effluent.

8. REFERENCES :

Marine Radioactivity Investigations in the Coastal Ecosystemat Kalpakkam following Law Level Effluent Discharges fromMAPS, M.P. Rajan and M.A.R. Iyengar, National Symposium onManagement of Radioactivity and Toxic Wastes, Kalpakkam,March 17 - 19, 1993.

52


Rn-222 fluctuations in thermal 1 - 5 3spring gases and possible

'• transport mechanism



4. ABSTRACT :

A study of radon concentration in hot springs in West Bengaland Bihar was taken up. Radon concentration in hot springwater, soil-gas and in atmosphere at Bakereshwar (W.B.) andTantaloi & Dumka (Bihar) were measured. Water temperature infive hot springs at Bakereshwar ranged from 52 to 72°C. At asmaller hot spring at Tantaloi, temperature recorded was68°C. Radon concentration in soil gas from Bakereshwar hotsprings ranged from 173 to 410 KBq m~3 and in Tantaloi itvaried from 553 to 557 KBq m~3. Dissolved radon concentra-tion in hot spring water at Bakereshwar was in the range of9.4 to 53.9 KBq m~3 and in Tantaloi hot spring water, radonconcentration was 26.2 KBq m~3. Tantaloi hot spring is on ariver bed itself. It was felt that there may be some otherhidden source of radon in the area not covered with water.With this in view radon emanation from soil in that area wasstudied. It was found to be 0.03 Bq m"2 against 0.02 Bq m~2

from soil in the region.


Completed RadonSoi1 gasHot spring

B. REFERENCES :'

Rn-222 fluctuations in thermal spring gases and possibletransport mechanism, N.K. Das, Debasish Ghosh, G.K. Srivas-tava and A.H. Khan, Tenth National Symposium on RadiationPhysics, held at Kalpakkam & Madras, August 17-20, 1993

53


Fresh Water Mussel Parreysia 1 - 5 4Favidens (Benson) as a BiologicalIndicator of Po-210 in a RiverineSystem


P. Shahul Hamid*, R. Asokan*, M.A.R. Iyengar** and V. Kannan**PG Department of ZoologyJamal Mohammed College, TiruchirapalliEnvironmental Survey LaboratoryHealth Physics Division, BARC, Kalpakkam

4. ABSTRACT :

The concentration of Po-210, an alpha emitter from thenatural uranium series was measured in the soft tissues(total), shell and different organs of the fresh watermussel, Parreysia Favidens (Benson), collected from the riverKaveri, at Tiruchirapalli in South India. The analysis weremade in three size groups based on shell length (Group 1: 2-4cm, Group 2t 4-5 cm. Group 3 : 5-6 cm). The soft tissue ofmussel accumulated higher concentrations of Po-210 (74.0125.5 Bq/kg fresh) than the shell (2.9 - 3.9 Bq/kg fresh).Further, younger mussel (I Group) showed higherconcentrations (125.5 ± 2.0 Bq/kg fresh) in total softtissues than older ones (III Group) (74.0 ± 1.6 Bq/kg fresh);concentration factors were 1.59 x 10-> in I group and 9.37 x10* in III Group. Po-210 was observed to be non-uniformlydistributed among the internal organs, which maintained thefollowing descending orders with reference to Po-210accumulation : digestive glands < gills < mantal < foot,ranging from 286.2 ± 3.5 Bq/kg fresh to 43 ± 1.3 Bq/kg fresh.The concentration of Po-210 in the mussels were distinctlyhigher than that in the grass, Echinochloa colonum(J.Koenig), and carp, Cirrhinus cirrhosa (Block), from thesame river. These data indicate that younger mussel could beused as an excellent biological indicator of PO-210 and amongsoft tissues, digestive glands are preferable to othertissues to monitor the distribution of Po-210 in the riverinesystem.


Fresh water musselBiological indicatorPo-210 reverinesystem.

8. REFERENCES :

Fresh Water Mussel Parreysia Favidens (Benson) as a Biologi-cal Indicator of Po-210 in a Riverine System, P. ShahulHamid, R. Asokan, M.A.R. Iyengar and V. Kannan, Chemistry andEchology, Vol. 8, pp 11-18, 1993

54


Some Characteristics of Ra-226 1 - 5 5Transfer from Soil and UraniumMill Tailings to Plants


P.M. MarkoseHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

A study on the migration characteristics of Ra-226 from soiland uranium mill tailings to plants was carried out. Concen-tration of Ra-226 in the plants and soil was measured. Thetransfer ratio (TR) showed wide variation (0.1 x 10~2 to 40x 10~2) in different species, while a few species of wildplants such as Echinops echinatus indicated preferentialuptake of radium.

Controlled experiments carried out by growing edible vegeta-ble plants on soil and uranium tailings also indicatedvariation in TR when calculated on the basis of total radi-um, while reasonably consistent TRs (1.6 x 10~2 to 4.2 x10"2) were obtained when calculated on the basis of avail-able radium in soil/tailings. Ra-226 accumulation in fruitwas two orders of magnitue less than that in root and leavesof edible plants.


Completed Transfer ratioEchinops echinatusAccumulationUranium tailings

8. REFERENCES :

Some characteristics of Ra-226 Transfer from soil and urani-um tailings to plants, P.M. Markose, I.S. Bhat and K.C.Pillai, Journal of Environmental Radioactivity, 21, pp 131-142, 1993

55


Radiation Exposure at the High Back- 1 - 5 6Ground Area - The Drinking Water Route

3. AUTHOK/S AND ADDRESS :

A.C. Paul, P.M.B. Pillai and T. Velayudhan*Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, KeralaIRE Ltd., Manavalakurichi

4. ABSTRACT :

Radiation exposure to the population residing at the highnatural background radiation zone at Manavalakurichi due tointake of radionuclides such as Th-232, U-238, Ra-228, Ra-226and Po-210 through drinking water amounts to 90uSv/person/yr. The exposure due to Ra-228 and Po-210accounts for about 90% of the total from all other sources.The study area extending 10 km distance from Manavalakurichihas been divided into 15 sampling grids depending on theradial distance from the monazite ore body. Thirty communitywells spread out evenly in the study area have been used forsampling the drinking water. The radionuclide showeddecreasing concentrations as one moved away from the main orebody. The drinking water accounted for 5% of the totalinternal dose at the high background area.


Completed Natural highbackgroundInternal doseGrids sampling

8. REFERENCES :

Radiation Exposure at the High Background Area, Paul A.C.,Pillai P.M.B. and Velayudhan T., Proc. Second National Sympo-sium on Environment, Jodhpur, pp 33-36, 1993.

56


Radionuclides Associated with 1 - 5 7Phosphate Processing


A.C. Paul and P.P HaridasanHealth Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 68 3 501, Kerala

4. ABSTRACT :

The concentration of Ra-226 in phophogypsum is about 1 Bq/g.Studies have shown that a substantial portion of Ra-226 inphosphogypsum is leachable. The leached activity is confinedto a few centimeters of the soil strata after a decade ofoperation. The Ra-226 activity in the leachate vary from 0.1to 0.3 Bq I"1, using a solution to sludge ratio of 10:1.Monitoring of river Chitrapuzha, by the side of FACT CochinDivision has shown enhanced levels of Ra-226 in water andsediment attributed to disposal of gypsum in the nearbylands. The Ra-226 activity in the river sediment varied from130 to 1437 Bq Kg~*. The higher activity was similar to thatof gypsum, showing that environmental contamination occursthrough physical dispersal of the waste sludge.


Work in Gypsum, Ra-226progress River pollution

8. REFERENCES :

Radionuclides Associated with Phosphate Processing andRadiological Safety in the Recovery of Uranium fromPhospheric Acid, Paul A.C., Technical Meeting, FACT, CD,1993

57


Occupational and Environmental 1 - 5 8Radiation Exposure in theBeach Mineral Mining


A.C. PaulHealth Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, Kerala

4. ABSTRACT :

Radiological surveillance at the IRE Mineral separation plantat Chavara has shown that the average dose to the worker wasabout 3 mSv per year. Persons who are closely associated withthe handling of monazite in the plant receive 5 to 10 mSv peryear. Being a physical separation plant, no significantliquid effluents are generated in the process. The solidwastes (tailings) consist essentially of silica devoid of themineral fraction. The tailings are disposed off in thedredged area as refill. Radiation fields at the tailingsdisposal area have come down to normal natural backgroundlevels. The results show nearly 10-fold reduction in thefields as compared to pre-mining status.


Completed Mineral processTailings disposalMining

8. REFERENCES :

Occupational and Environmental Radiation Exposures in theBeach Mineral Mining, Paul A.C., Seminar on Scope of MineralBased Industries in Kollam, 1993.

58

1. TITLE :

Deposition and Clearance of Pb-212in Humans

2. CATEGORY

1 - 59


P.M.B. Pillai, A.C. Paul, I.s. Bhat*,M.R. Iyer** and K.C. Pillai*Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, KeralaNuclear Power Corporation Ltd., Bombay

** Radiation Safety Systems Division,Consultant, AERB, Bombay

BARC, Bombay

4. ABSTRACT :

Radiation exposure due to inhalation of Pb-212 has beenidentified as one of the major hazards in the chemicalprocessing of monazite and thorium. Volunteers were exposedto Pb-212 in the thorium hydroxide storage facility.Personnel air samplers were used to determine theconcentration of Pb-212 in air. The Pb-212 in the chest wasmeasured using a shadow shield whole body counter and thedecay in the chest was followed. Half-life for the inhaledPb-212 was observed as 6.63 ± 0.23 h. Comparison of thechest burden with the intake has shown that 55% to 76% of theinhaled Pb-212 is deposited in the respiratory system. Thechest monitoring data have been related to the work.ing levelexposure due to thoron daughters.

5. REMARKS 6. STATUS :

Completed

7. KEYWORDS :

Clearance half lifeChest burden

8. REFERENCES :

Deposition and Clearance of Pb-212 in Humans, PillaiP.M.B., Paul A.C., Bhat I.S., Iyer M.R. and Pillai K.C.,Health Physics (in press)

59


Trace Metals and Lanthanides in a 1 - 6 0Tropical River Environment


A.C. Paul, M. Parameshwaran and K.C. Pillai*Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, KeralaConsultant, AERB, Bombay

4. ABSTRACT :

The river Periyar in the state of Kerala is subjected topollution front a number of industrial units such as Zinc-smelter, rare-earth plant, phosphatic fertilizer unit etc.The concentration of trace metals in water and sediment atthe background zone do not show any significant change overthe years. The mass median diameter of Zn and Cd in thesediment works out to 11 + 2.5 urn. In first ever studycarried out on the distribution of rare-earth elements in theriver Ce, La and Y were detected in the concentration rangesof 0.1 to 0.2 ppm in water. Significant levels of Ce, La, Y,Sm and Gd were also observed in the sediments at theindustrial 2one of the river. The concentration factor forrare-earth elements in sediment worked out to


Work in Pollutionprogress Rare earth elements

Trace metals

8. REFERENCES :

Trace Metals and Lanthanides in a Tropical RiverEnvironment, Paul A.C., Parameshwaran M. and Pillai K.C.,Water, Air and Soil Pollution, (in press)

60


Radiation Exposure at the High Back- 1 - 6 1Ground Area - The Changing Trends.


A.C. Paul, T. Velayudhan*, P.M.B. Pillai,C.G. Maniyan and K.C. Pillai**Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, Kerala

* IRE, Ltd., Manavalakurichi** Consultant, AERB, Bomaby

4. ABSTRACT :

Large scale surface mining and refilling of the mined areaswith monazite free tailings have reduced the external radia-tion fields by an order of magnitude at some locations at thenatural high background areas situated in the coastal regionsof penisular India. Significant reduction by a factor of 3has been observed in the airborne activity due to loweremanation of thoron (Rn-220) at the refilled areas. Thethatched huts in the area are giving way to brick and con-crete structures, radically altering the indoor exposureprofile. The total exposure due to gamma radiation was re-duced by a factor of 4 due to the shielding by the construc-tion materials. Rn-220 levels as high as 4 20 Bg m~3 have beenobserved > in some of the mud houses. Significant levels ofTh-232 and Ra-228 were found in the urine samples collectedfrom the adults residing in a village situated in the highbackground area.


Work in Natural highprogress background

Internal exposureIndoor radon

3. REFERENCES :

Radiation Exposure at the High Background Area at Mana-valakurichi - The changing trend, Paul A.C, Velayudhan,Pillai P.M.B., Maniyan C.G. and Pillai K.C., J. EnvironmentalRadioactivity 13, 1993

61

1. TITLE :

Sorption and Desorption of Caesiumin Coastal Sea Water Sediments

2. CATEGORY

1 - 62


M.V.M. Desai, Sathi S. Kumar, Hemalata Padmanabhan,I.S.Bhat and K.C. PillaiHealth Physics Division, BARCBombay - 400 085

— — — - • • — • — — • — — — — — — — — — . — — — — — — — - — — — . — — • — — — — . — — — — • — . — » — — — _ — — — — . — , . — — — « _ _ — — — _ — . _ — . _ • _ — _

4. ABSTRACT :

Experiments carried out with elevated concentrations ofCaesium carrier with Cs-137 as tracer to sediment aliquotindicated that sorption of Cs-137 by marine sedimentapproaches the base exchange capacity of the sediment.Experiments were carried out with carrier free Caesiumconcentration amounting to natural concentration showed theequilibrium constant K increasing with increase in specificactivity of Cs-137. The desorption of Cs-137 by sea waterindicated three components of desorption suggesting threebinding sites for Cs-137 in the sediment.

5. REMARKS : 6. STATUS :.

Completed

7. KEYWORDS :

SorptionDesorption

8. REFERENCES :

Sorption and Desorption of Caesium in Coastal Sea WaterSediments, M.V.M. Desai, Sathi S. Kumar, HemalataPadmanabhan, I.S.Bhat and K.C. Pillai, National Symposium onEnvironment, BARC, Bombay, 1992.

62


Estimation* of Sr-90 in Liquid 1 - 6 3Effluents (LEMP) at MAPS


S. Venkataraman and M.A.R. IyengarEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam - 603 102

4. ABSTRACT :

Liquid effluents from MAPS before disposal in the coastalwater are being regularly investigated at ESL forradionuclide composition and concentration levels by gammaspectrometry using HPGe detector. However the abovemeasurements exclude Sr-90, an important beta emittingfission product radionuclide which has exposure significancein the environment. Before dilution, these liquid effluentsgenerated in the reactor system were collected daily andcomposited for a whole month. Such monthly composite liquideffluent samples were collected regularly and analysed forSr-90 using a modified analytical approach. In this method,Y-90 is separated from equilibrated Sr-90/Y-90 activity byprecipitating Yttrium carrier as its hydroxide using KOH inpresence of magnesium sulphate at pH-10. The Mg(OH)2precipitate carrying Y-90 is dissolved in dilute HNO3 (1:1)followed by precipitation of Yttrium oxalate which is countedfor Y-90 activity in low background beta counting system.Using this method for analysis of Sr-90 in effluent samplesfrom MAPS during the period April 92 - March 93, it was foundthat Sr-90 activities varied from 4.1 to 275 Bq/1 with amedian value of 13.7 Bq/1.


Completed Strontium-90,Liquid effluents,MAPS.

8. REFERENCES :

Estimation of Sr-90 in liquid effluents (LEMP) at MAPS, S.Venkataraman and M.A.R. Iyengar.

63

•1. TITLE : 2. CATEGORY :

Tritium Distribution Studies in the 1 - 6 4Atmospheric Environment at MAPS,Kalpakkam

3. AUTHOR/S AND-ADDRESS :

M.P. Rajan, A.P. Thulasi Brinda and M.A.R. IyengarEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam-603 102

4. ABSTRACT :

Tritium in the form of HTO is one of the radionuclidesreleased through the stack during MAPS operation. Thetransfer of released tritium to other compartments such aswater, soil, vegetation, etc. is of considerable significancewith respect to environmental migration of tritiuni andpossible public exposures. Rain water is an important vectoras atmospheric tritium activity is transferred to the soiland further to the ground water system. Vegetation also,following tritium uptake can act as reservoir of tritiumwhose tritium levels could fluctuate with the ambient tritiumlevels in air. A study was therefore carried out toinvestigate these aspects. The tritium concentration in rainwater at micro-met lab. during 1990-92, varied from < 314709 Bq/1. The ratio of tritium in vegetation to tritium inair at site was found to be (0.53 - 0.8) which appeared toagree with those of others. Hourly variation of tritium attwo locations at MAPS site also showed substantial variationfrom hour to hour depending upon the release, meteorologicalfactors etc. Further studies are in progress.


Work in Tritium distributionprogress Environment

MAPS, Kalpakkam.

8. REFERENCES :

Tritium Distribution Studies in the Atmospheric Environmentat MAPS, Kalpakkam, M.P. Rajan, A.P. Thulasi Brinda andM.A.R. Iyengar.

64


Study of Natural Radioactivity in 1 - 6 5Damodar-Kedla-Garhi Aquatic Systemin Ranchi-Palamau Area of South Bihar


P.M. Markose and A.H. KhanHealth Physics Unit, JadugudaHealth Physics Division, BARC

4. ABSTRACT :

Natural radioactivity in the waters of Damodar-Kedla-Garhiaquatic system in Ranchi-Palamau area of South Bihar has beenevaluated. Four sets of 16 river water and 3 ground watersamples each were supplied by M/s. MECON (India) Ltd. tocover the different seasons of the year from the differentlocations of the aforesaid aquatic system. The gross alphaactivities were in the range of BDL - 150 Bq/m3 (Mean : 70Bq/m3) and gross beta activities were in the range of BDL -1500 Bq/m3 (Mean : 600 Bq/m3) respectively, in the riverwaters. The mean alpha and beta activity contents of theground waters were of the same order (80 Bq/m3 and 570 Bq/m3,respectively). Seasonal variations were discernible, thehighest activities being obtained during summer.

The area under study is in coalfield with no knownradioactive mineral deposits. Thus the values obtainedrepresent natural background radioactivity in this SouthBihar region.


Completed Natural radio-act ivi tyAaquaticSouth-Bihar.

8. REFERENCES :

Study of Natural Radioactivity in Damodar-Kedla-Garhi AquaticSystem in Ranchi-Palamau Area of South-Bihar, P.M. Markoseand A.H. Khan.

65


Study on Outdoor Atmospheric Concen- 1 - 6 6trations of Potential Alpha Energyof Radon and Thoron Progeny at Jaduguda


AiH. Khan, D. Vidyasagar and G.K. SrivastavaHealth Physics Unit, Jaduguda,Health Physics Division, BARC

4. ABSTRACT :

Potential alpha energy concentrations of radon and thorondaughters in the outdoor atmosphere at the ESL about 0.5 kmfrom . Jaduguda uranium mine and mill have been measured forabout one year period, mostly during forenoon. ModifiedKusnetz's method was used to evaluate these parameters. Thegeometric mean radon progeny concentration works out as 2.5mWL (GSD : 2.3) and that of thoron progeny as 0.0 9 mWL (GSD :2.5). A few samples collected in the afternoon showedslightly lower values but in the same order, i.e. 2.3 mWL forradon progeny and 0.05 mWL for thoron progeny.

An year long continuous measurement using SSNTD in a dwelling(indoor) in this region showed average radon progenyconcentration of 16 mWL.


Work in Rn progenyprogress Tn progeny

Outdoor concentra-tion.

8. REFERENCES :

Study on Outdoor Atmospheric Concentrations of PotentialAlpha Energy of Radon and Thoron Progeny at Jaduguda, A.H.Khan, D. Vidyasagar and G.K. Srivastava.

66


A Laboratory Evaluation Of 1 - 6 7Interception & Translocation of13*1 in Fenugreek ( TrigonellaFoenum Graecium ) & Okra (HibiscusEsculentus ) Plants

3. AUTHORS/S AND ADDRESS :

R.K.Singhal U.Narayanan and I.S.Bhat*Health Physics Division, BARCBOMBAY - 400 085

* Environmental Group, Directorate of E & P A, NPCILWorld Trade Centre,BOMBAY - 400 005

4. ABSTACT :

The work reported here deals with the laboratory study ofinterception and translocation factor of^lj j n fenugreek(Trigonella foenum graecum ) and Okra (Hibiscus esculentus )two very common vegetables in India. The Activity was in-jected as Iodide aerosols into an experimental chamber whenthe plants were grown in pots. Size distribution of aerosolswas 0.3-5.0 urn (AMAD). Samples of plants were collected overa period of few days at different time intervals . Inter-ception cum deposition & translocation of 131j w a s evaluatedfrom Che activity measured in air and plants parts. Thedeposition factors are 1.22 m3/kg for the fenugreek plantsleaves and 1.49 m^/kg for the plants as a whole. For okraplants DF are 0.02 and 0.06 m3/kg in edible okra and leavesrespectively. For the okra plant as a whole DF is 0.19m^/kg.The translocation factor vary from 0.62-0.86 and0.47-0.87 for leaves and stem respectively in case of fenu-greek plants. For okra plants the variations in transloca-tion factor are from 0,21-0.82, 0.53-0.93 and 0.42-0.81 inedible okra, leaves and stem respectively.


Completed InterceptionDepositionTranslocationIodine-131Vegetable plants

8. REFERENCE :

Laboratory Evaluation of Interception & Translocation of131l in Fenugreek (Trigonella foenum graecum) & Okra (Hibis-cus esculentus) Plants, R.K.Singhal, U.Narayanan andI.S.Bhat, Health Physics (in press)

67


Report on the participation by the 1-68Bhabha Atomic Research Centre inthe Tenth Indian Expedition toAntarctica.


T.V. Ramachandran* and M.C. BalaniHealth Physics Division, BARCBOMBAY - 400 085

* Environmental Assessment Division, BARC

4. ABSTRACT :

The Antarctic continent can be expected to provide referencelevel for all environmental and pollution studies due to itsremoteness and restricted human activities. BARC has partic-ipated in the Tenth Expedition primarily to collect back-ground baseline data an natural radioactivity, heavy metalconcentration in soil and water and biological specimens.While radioactivity data and some limited heavy metal con-centration data have already been collected on air, waterand soil samples from participation in 8th and 9th expedi-tions, this is the first time BARC made attempts to collectbiological samples as well. Fairly complete data base hasbeen built up on all these samples and these are presentedin this report.

5. REMARKS i 6. STATUS : 7. KEYWORDS :

Completed RadonRadioactivityBiology

8. REFERENCES :

Report on the participation by the Bhabha Atomic ResearchCentre in the Tenth Indian Expedition to Antarctica, Rama-chandran T.V. and Balani M.C., pp 1-24, 1993

68

1- TITLE : 2. CATEGORY :

Quality Assurance Analysis by BARC 1 - 6 9for the EIA base line study carriedout by M/s Vimta Laboratories Ltd.,Hyderabad for Bharat PetroleumCorporation Ltd., Bombay, Manmad Pipeline Project.


K.S.V. Nambi, R.N. Khandekar, A.M. Mohan Rao, T.N. MahadevanG.G. Pandit, R.M. Tripathi, A Vinod Kumar, A.P. Sathe*

T.M. Krishnamoorthy, V.N. Sastry, V.N. Bapat, S.J. Dao, M.C.Balani, V.V. Kulkarni**

K. Raghu, S.P. Kale***

* Environmental Assessment Division** Health Physics Division

*** Nuclear Agriculture DivisionBARC, BOMBAY - 400 085

4. ABSTRACT :

Quality assurance services were requisitioned for the as-sessment of air quality, meteorology, water quality and soilcharacteristics by M/s Bharat Petroleum Corporation Ltd.,(BPCL), Bombay in connection with the baseline data collec-tion for the Environmental Impact Assessment of their Bom-bay-Manmad pipeline project. Quality assurance servicescomprised of random sampling jointly with M/s Vimta Labs.Hyderabad and comparison of analytical results besidesascertaining the fact that the procedures followed by theVimata Labs were as per the prescribed standards.


Completed Baseline studyWater, soil &

air quali ty

B. REFERENCES :

Quality Assurance Analysis by BARC for the EIA BaselineStudy, carried out by M/s Vimta Laboratories Ltd., Hyderabadfor Bharat Petroleum Corporation Ltd., Bombay-Manmad Pipe-line Project. . Project Report by EAD, HPD and NAD,BARC/1993/R/008, pp 1-22, 1993.

69


Determination of 1-129 in Water 1 - 7 0and Air Samples near a ReprocessingPlant by Neutron Activation Analysis


G.R.Doshi, S.N.Joshi and K.C.Pi 1laiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The neutron activation analysis was used to determine 1-129in water and air samples collected in the vicinity of areprocessing plant. The method involved preconcentration of1-129 on Agl from water samples, separation of Agl followedby distillation, loading on Dowex 1, irradiation and postirradiation purification steps. Filter air samples were wetoxidized followed by distillation and other chemical proce-dure steps as descirbed for water samples. The concentrationof 1129 in rain water and air samples ranged from 0.155 E-3to 0.323 Bq/ml and 0.054 E -6 to 0.295 E-6 Bq/ml respective-ly. The average concentration of 1-129 in seawater sampleswas 0.157 E-3 Bg/1.


Completed Neutron Activation

8. REFERENCES :

Determination of 1-129 in Water and Air Samples near aReprocessing Plant by Neutron Activation, G.R.Doshi,S.N.Joshi and K.C.Pillai, Water, Air and Soil Pollution, 37,1993

70


Evaluation of Deposition & Migration 1 - 7 1of^Mn in Fenugreek (Trigonella foenum-graecum),Potato (Solanum tuberosum)& ""Co in Okra (Hibiscus esculentus)Plants in Tropical Condition

3. AUTHORS/S AND ADDRESS :

R.K.Singhal U.Narayanan and I.S.Bhat*Health Physics Division, BARCBOMBAY - 400 085


4. ABSTRACT :

Study was carried out on of the interception and transloca-tion of 54Mn in fenugreek (Triqonella foenum-graecum),potato (Soloanum tuberosum) and 60Co in okra (Hibiscusesculentus) plants following their release to the atmos-phere. Activity was injected into an experimental chamber inthe form of aerosols having a size distribution of 0.3-1.0urn (AMAD). Samples of plants were collected over a period of163 hrs (54Mn) and 98 hrs (60Co) at different time intervalsafter injection of aerosols. DEPOSITION (activity intercept-ed by different parts of plant) & MIGRATION (transfer ofactivity from different surfaces to internal parts) wereevaluated. For deposition factor (D.F.) the value is 0.27m3/kg for leaves and 0.03 m3/kg for stem in case of5*Mn for fenugreek (Trigonella foenum-graecum) plant. Forplant as a whole the DF is 0.13 m3/kg. For potato (Solanumtuberosum) plant the values of DF are 0.03 m-Vkg for leavesand 9.21 x 10~3 m3/kg for stem & for plant as a whole DF is0.03 m3/kg. For 60Co the okra plant showed DF 1.25xlO~3,0.11 and 1.68 x 10~3 m3/kg in the edible okra, leaves & stemrespectively & for plant as a whole the value is 0.11 m3/kg.In case of 54Mn the migration factor from varied from 0.63to 0.78 for fenugreek and 0.48 to 0.82 for potato plantrespectively. For ̂ C o the variation in migration factorsare from 0.56 to 0.92 in case of okra (Hibiscus esculentus)plant.


Completed 54MN, 60CoDeposition factorMigration factorFenugreek, Okra

8. REFERENCE :

Evaluation of Deposition & Migration of 54Mn in Fenugreek(Trigonella foenum-graecum), Potato (Solanum tuberosum) &60Co in Okra (Hibiscus esculentus) Plants in Tropical Condi-tion, R.K.Singhal, U.Narayanan and I.S.Bhat, Journal ofEnvironmental Radioactivity (in press)

71

1. TITLE : 2. CATEGORY : .

Estimation of Deposition Velocity 1 - 7 2for 85Sr & 1 3 1I on Spinach Leavesin Tropical Region Under SimulatedFallout Conditions


R.K.Singhal and I.S.Bhat*Health Physics Division, BARC 'BOMBAY - 400 085


4. ABSTRACT :

The work reported here deals with the determination ofdeposition velocity for 85Sr & 131j o n tropical spinachplant (Spinicia olericia). The experiment is carried out inspecially designed exposure chamber to simulate the exposureunder fallout condition. The activity is injected in theform of aerosols having a size distribution of 2.35 urn(AMAD) with a geometric standard deviation of 2.00. Thedeposition velocity in tropical region differs considerablyfrom those in temperate region ( for tropical region it isof the order of 10~5 m/s compared to a value for temperateregion 10~3 m/s ).

5. REMARKS : 6. STATUS : 7. KEYWORDS

Completed 85Sr131Spinach deposition

velocity

REFERENCE :

Estimation of Deposition Velocity for 85Sr & 131j o n spinachleaves in Tropical Region Under Simulated Fallout ConditionsR.K.Singhal and I.S.Bhat, IASTA, Bombay, Jan. 1994

72


A Laboratory Evaluation of 1 - 7 3Interception and TranslocationFactor of 59Fe & 60Co in IndianSpinach Plants


R.K.Singhal, U.Narayanan and I.S.BhatHealth Physics Division, BARCBOMBAY - 400 065


4. ABSTRACT :•

Interception and translocation factors for some of theimportant activation products like ^^Hn,^^Fe and ^ C o a r e ofuse in hazard evaluation of atmospheric contamination fromaccidental releases.Deposition on leafy vegetables which areconsumed fresh is one of the important pathway of radionu-clides reaching man. A program of study has been planned tostudy these factors for all the important radionuclides invarious types of leafy vegetables. Laboratory scale investi-gation on interception & translocation of *9Fe & 60QO b yspinach plants are carried out. The interception factorobtained for 59pe an(j 60co are respectively 0.51 and 0.06m^/kg. 6(iCo is found more mobile than ^9Fe even though thelatter translocates from surface quickly and to a greaterextent.

5. REMARKS : 6. STATUS : 7. KEWWORDS :

Completed 59Fe,60CoInterceptionTranslocationSpinach

8. REFERENCES :

A Laboratory Evaluation of Interception and TranslocationFactor of 59Fe & 60Co in Indian Spinach Plants, R.K.SinghalU. Narayanan and I.S.Bhat, Water Air & Soil Pollution, (inpress)

73

2. RADIATION DOSIMETRY (INTERNAL & EXTERNAL)


In-vivo Measurements Of Low-Energy 2 - 1Photon (LEP) Emitters


R.C.Sharma, T.Surendran, T.K.Haridasan and C.M.SuntaHealth Physics Division, BARCBOMBAY - 400 08 5

4. ABSTRACT :

This paper presents the considerations guiding the selectionof requisites for a laboratory dedicated to perform in-vivomeasurements of low-energy photon (LEP) emitters-namely theactinides (U, Pu and Am) important from the view -point ofnuclear industry. In this context, brief reviews of theshielding requirements, radiation detectors, associatedelectronic instrumentation, calibration problems, subject-detector geometries and data analysis and other computation-al techniques have been given. Finally, notable operationalexperiences of Trombay in-vivo monitoring laboratory fromthe recent past are succinctly summarised.

5. REMARKS : 6. STATUS : 7. KEYWORDS :Completed In-vivo measurements

ActinidesRadiation detectors

8. REFERENCES :

In-vivo Measurements Of Low-Energy Photon (LEP) Emitters,R.C.Sharma, T.Surendran, T.K.Haridasan and C.M.Sunta,Bull.Rad.Prot, IARP, Vol.12 No.4, pp 41-56, Oct-Dec, 198 9

74

1. TTITLE : 2. CATEGORY :

Experiences on Techniques for 2 - 2Evaluation of Ra Body Burdenin Indian Uranium Industry


G.K. SrivastavaHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

A shadow shield whole body counter was installed at Jadugudain 1968 for assessment internal contamination f radium-226among workers of uranium mining and ore processing facility.After a sustained efforts for increasing the sensitivity andreducing the counter background the minimum detectable bodyburden of 0.75 KBq could be achieved. An alternative methodwith radon measurement in axhaled breath was also consideredfor estimation of radium body burden. With the developmentof an electrostatic system called Low Level Radon DetectionSystem (LLRDS) in this unit it became possible to estimatethe radon concentration in exhaled breath, the conventionalbreath sampling was also modified for adoption for routinemeasurement in field areas. M.D.A. with the system is 0.15KBq of radium. It has replaced the shadow shield whole bodycounting facility here at HPU, UCIL.

Workers of uranium mine and the mill at Jaduguda have beenmonitored. The workers from Bhatin uranium mine and thosefrom uranium recovery plants at Surda, Mosabani and Rakhaare being now monitored with this technique.


On going Radium in bodyRadon in breathWhole body countingElectrostatic systemLLRDS

8. REFERENCES :

Experiences on techniques for evaluation of Ra body burdenin Indian uranium industry, G.K. Srivastava and A.H. Khan,Bulletin for radiation Protection, Vol 12, No. 4, 1989

75


Levels of Natural U in Normal and 2 - 3a Group of Occupationally ExposedSubjects


V.R.Pullat, H.S.Dang, C.M.Sunta and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The concentration of natural U were measured in the urine ofpersons from general population and some selected occupa-tional workers of Nuclear Fuel Complex (NFC). U analysis wascarried using preconcentration, followed by neutron activa-tion, chemical separation and gamma counting of 239jjp acti-vation product of 2 3 8U. The average U concentration in theurine of 20 normal background subjects was found to be 0.01ug L"1 (0.003 to 0.04 ug L""1). The NFC subjects were workingin 1) natural and enriched uranium oxide plants, 1} ceramicfuels fabrication plants and 3) enriched fuel fabricationplants. The uranium concentrations for 160 NFC workers werefound to be in the range 0.03-7.4 ug L~l. The results of theU concentration in the urine samples obtained from NFCworkers indicate that the U exposure is within the safetylimits (ALI).


UraniumUrine

8. REFERENCES :

Levels of Natural U in Normal and a Group of OccupationallyExposed Subjects, V.R.Pullat, H.S.Dang, C.M.Sunta andK.C.Pillai, Bulletin Radiation Protection, Vol. 13, No. 2,April- June, 1990

76

1. TITLE : .. 2. CATEGORY :

S t u d i e s on U p t a k e of T h o r i u m in 2 - 4Hum a n B o d y

3. A U T H O R / S A N D A D D R E S S :

H.S.Dang, D.D.Jaiswal and C.M.SuntaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

This paper reports the daily intake and organ burdens of Thfor Indian population. The Th analysis was carried out usingneutron activation technique. The results of analysis showedthat the uptake of Th in skeleton is much lower and that inmuscle is much higher as compared to that assumed by Inter-national Commission on Radiological Protection (ICRP). Thehair samples obtained from subjects living in low and highbackground areas and also from those working in Thoriumprocessing plant were also analysed. The results of analysisshowed distinctly different concentrations. However, therewas no linear correlation between the Th concentrations inair and those in hair samples of subjects living or workingthere.

5. REMARKS : 6. STATUS: 7. KEYWORDS :

Completed ThoriumUptake

8. REFERENCES :

Studies on Uptake of Thorium in Human Body, H.S.Dang,D.D.Jaiswal and C.M.Sunta, International Conference on HighLevels of Natural Radiation, Ramsar, Islamic Republic ofIran, November 3-7, 1990.

77

1. TITLE :

Daily Intake of Uranium by UrbanIndian Population

2. CATEGORY

2 - 5


H.S.Dang, V.R.Pullat, D.D.Jaiswal, M. Parameswaran andC.M.SuntaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The daily intake of uranium (238u) by an urban Indian popu-lation was estimated by the analysis of a duplicate diet,drinking water and air samples using neutron activation andradio-chemical separation. The uranium intake through foodis 0.55 ug which is much larger than that from drinkingwater and air, at 0.09 and 0.01 ug respectively. The totaldaily dietary intake of uranium, calculated from the concen-tration measured in the individual food ingradients andtheir daily consumption (based on the national survey), isfound to be 2.2 ug which is a factor of 3.5 higher than thatbased on a duplicate urban diet. The maximum contribution tothe daily intake is found to be from cereals. The lowerintake by the urban population is most likely due to theirlower food consumption.

REMARKS : 6. STATUS :

Comp 1 e t ed

7. KEYWORDS :

UraniumDaily intake

8. REFERENCES :

Daily Intake of Uranium by Urban Indian Population,H.S.Dang, V.R.Pullat, D.D.Jaiswal, M.Parameswaran and(J.M.Sunta, Journal of Radioanalytical and Nuclear Chemistry,Article, Vol. 138, No.l, pp 67-72, 1990

78


Thorium in Blood Serum, Clot 2 - 6and Urine: Comparison withICRP Excretion Model


C.M.Sunta, H.S.Dang, D.D.Jaiswal and S.D.SomanHealth Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT :

Neutron activation followed by a simple radiochemical sepa-ration procedure was employed to determine the concentrationof thorium (232^) in human blood serum, clot and urine ofnormal subjects and three groups of occupationally exposedpersons. The thorium concentration in the blood serum, clotand urine samples of the exposed groups were distinctlyhigher- than those of the other study groups and were fo.undto increase with increasing occupational length of thepersons. Daily urinary excretion is correlated with serumthorium burden and it is estimated that the daily excretedthorium is about 15% of the thorium in serum pool.


Completed ThoriumBlood SerumExcret ion

8. REFERENCES :

Thorium in Blood Serum, Clot and Urine: Comparison with ICRPExcretion Model, C.M.Sunta, H.S.Dang, D.D.Jaiswal andS.D.Soman, Journal of Radioanalytical and Nuclear Chemistry,Article, Vol. 138, No. 1, pp 139-144, 1990

79


Thorax Burdens of Thorium Using 2 - 7A Double Filter Device


D.J.Mehta, H.S.Dang, R.C.Sharma and C.M.SuntaHealth Physics Division, BARCBOMBAY - 400 08 5

4. ABSTRACT :

Assessment of thorax burdens of thorium in the occupationalworkers is needed as a part of health physics surveillance..It is shown in this paper that an alternative method for thethorax burden assessment of thorium is provided by themeasurement of Thoron (220Rn) gas in the exhaled breath. Adouble filter device is used for this purpose. A quantity aslow as ALI/30 of thorax burden of thorium is measurable withthis equipment. For 30 non-occupational laboratory personnelthorium burdens were indistinguishable from the systembackground. Twelve occupational persons were monitored. Tenwere from the IRE thorium plant and 2 from a gas mantlefactory. The former showed an average lung burden of 15.5Bq. The gas mantle workers showed significantly higherthorax burdens in comparison to those of IRE workers. As-sessments of thorium burdens have also been made in the samegroup of occupational workers by the direct in-vivo thoraxcounting procedure and the bioassay of blood serum samplesusing the neutron activation analysis (NAA) technique.Although there is no one-to-one correspondence between theburden estimates obtained from these methods, a trend ofsimilarity is clearly discernible. Thoron in breath measure-ment technique described in this paper is simple, free frominterference from external body contamination and inexpen-sive. It thus, forms an attractive alternative for routineinternal monitoring of lung contamination in thorium work-ers.


Completed . Double FilterThorium burden

8. REFERENCES :

Thorax Burdens of Thorium using a Double Filter Device,D.J.Mehta, H. S. Dang, R. C. Sharma and C. M. Sunta, Bull.Rad. Prot. Vol. 13, No'. 2, pp 31-33, 1990

80


Leachability of Radium from 2 - 8Fertilizer and Monazite ProcessWastes


A.C Paul and K.C. Pillai*Health Physics DivisionHealth Physics Unit, IRE Ltd.Udyogmandal - 683 501, Kerala

* Consultant, AERB, Bomaby

4. ABSTRACT :

Leaching studies on the fertilizer and monazite process wastesludge have indicated that a significant fraction of radiumis in a loosely bound state. A substantial reduction in theleaching of radium was observed when SO4 ions were present.The leaching was reduced by a factor of 103 when radium inmonazite sludge was immobilized in cement. There is signifi-cant potential for Ra-226 contamination of the environmentowing to processing of phosphate rock for production offertilizer and disposal of phosphogypsum. Further data arerequired on the Ra-226 content in phosphogypsum from differ-ent sources, leachability, physico- chemical forms, disposal,migration and biological uptake. Monazite waste sludge havinga much higher specific activity as compared with uranium milltailings or phosphogypsum has the potential for causing ahigher degree of localised environmental contamination ifadequate precautions are not taken during its disposal.


Work in Gypsum disposalprogress Monazite waste

Environmentalcontamination

8. REFERENCES :

Leachability of Radium from Fertilizer and Monazite ProcessWaste, Paul A.C. and Pillai K.C., IAEA Tech. Series Report.No. 310 on Environmental Migration of Radium, Vol.2, pp 83-95, 1990

81


A Steel Room Facility with a Mib 2 - 9Window Phoswich Detector forIn-Vivo Measurement of Pu/Am Lung Burden

3. AUTHOS/S AND ADDRESS :

S.P. Garg, D. Datta, R.L. Kshirsagar, G. Krishnamachari,D.N. Kelkar, M.R.Iyer and I.S. BhatHealth Physics Division, BARCBombay 400 08 5

4. ABSTRACT :

Assessment of internal dose to workers due to inhalation oftransuranic elements require in-vivo determination of verylow levels of these low energy ( < 100 Kev ) photon emittingradionuclides in human lungs. The measurements are carriedout in steel room using special MIB window phoswich detectorsystems. A steel room facility for assay of lung burden ofPu and other transuranic elements in personnel working in thevarious plants in the Tarapur area was recently commissioned.A PC based HPD 4K MCA is used for spectrum analysis whichalso enables the burdens to be compared on line.

Estimation of lung burdens of Pu-239 and Am-241 involves thedetection of 17 Kev UL X - rays and 60 Kev gamma raysrespectively. The phoswich detector consists of a (20 cm diax 1.5 mm) Nal(Tl) as primary and (20 cm dia x 51 mm) CsI(Tl)as secondary detector and incorporates 3 low-noisephotomultiplier tubes which can be used for additional signalcoincidences. In deriving the accurate calibration factorsfor Pu-239 individual subjects, estimation of Pu/Am lungburdens is carried out via 60 Kev gammas from Am-241 which issubjected to much less errors. The preliminary optimisationof the PSD circuitry has shown the background of about 7-8cpm each in both the energy region of (12 - 25) Kev and (43 -76) Kev used for 17 Kev and 60 Kev photons respectively.Using the appropriate calibration factors of 0.0027 cpm/Bqand 0.86 cpm/Bq the MDA figures obtained are 66 Bq and 4 Bqfor Pu and Am respectively for an individual subject ofaverage body build. With a loss of about 30% in the 17 Kevsignals, background recorded was as low as 1-2 cpm in 12-25Kev region. Incorporation of additional circuitry like PMTcoincidence and overload rejection is expected to give afurther reduction of about 50% in the background in (12-25)Kev region. This paper reports the details of this newsystem along with its performance characteristics.


Completed Phoswich detectorMIB window, Pu/Am

8. REFERENCES :

A Steel Room Facility with a MIB Window Phoswich Detector forIN-VIVO Measurement of Pu/Am Lung Burden, S.P. Garg, D.Datta, R.L. Kshirsagar, G. Krishnamachari, D.N. Kelkar,M.R.Iyer and I.S. Bhat., 1990

82


Comparison of Daily Intake Through 2 - 1 0Duplicate Diet, Total Diet and ModelDiet for a few Selected Elements


H.S.Dang, M.Parameswaran, D.D.Jaiswal and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4- ABSTRACT :

The duplicate diet and the model diet sample were analysedfor Na, K, Ca, Mg, Cu, Zn, Mn, Fe, Mo, Se, Co, Sb using bothinstrumental neutron activation analysis (INAA) and atomicabsorption spectrophotometry. The comparison of results withtotal dietary intake showed that the intake of most of thetrace elements in duplicate diet consumed by urban popula-tion is lower than that from total diet. The intake of mostof the elements was found to be lesser than that reportedfor ICRP Reference Man. This study indicated that the traceelement intake.for the diet of urban population may notbe representative of the total dietary intake.


Trace elementsDietary intake

8. REFERENCES :

Comparison of Daily Intake Through Duplicate Diet, TotalDiet and Model Diet for a few Selected Elements, H.S.Dang,M.Parameswaran, D.D.Jaiswal and K.C.Pillai, IAEA-RCA Meetingon Reference Asian Man, Bombay, April 8-12, 1991 (This workwas carried out under IAEA Research Contract No. 5583/ JN)

83

1. TITLE : 2. CATEGORY

Bioassay Monitoring for 2 - 11Thorium - A Sensitive Method


D.D.Jaiswal, H.S.Dang, M.G.Nair and C.M.SuntaHealth Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT :

ICRP-54 has reported the inability of the existing analyti-cal techniques, such as spectrophotometry and oC- spectrome-try, for the bio-assay monitoring of Th at derived investi-gation levels (DIL). There is, therefore, a need for a moresensitive method for bioassay monitoring purposes. Thispaper reports on the development of a sensitive analyticalprocedure for routine bio-assay monitoring. It involvespreconcentration of Th with calcium oxalate precipitate,neutron activation and gamma counting. Using this procedureit is possible to detect as low as 0.04 mBq of Th, which isthree times lower than the derived investigation levelrecommended by ICRP. The bioassay monitoring of Th proce-dure and the results showed that the exposure to thorium iswithin the safety limits of one ALI/Y.


Completed ThoriumBio-assay monitoringNAA

8. REFERENCES :

Bioassay Monitoring for Thorium - A Sensitive Method,D.D.Jaiswal, H.S.Dang, M.G.Nair and C.M.Sunta, Bulletin ofRadiation Protection, Vol. 14, Nos. 3 & 4, July-December,1991

84


Population Exposure to Ionising 2 - 1 2Radiation in India

3. AUTHOR/S AND ADDRESS:

K.K. Narayanan, Health Physics Div BARCD. Krishnan, Division of Radiological Protection, BARCM.C. Subha Ramu, Environmental Assessment Division, BARC

4. ABSTRACT:

Data on exposure to ionising radiation of the Indianpopulation from natural and man made sources are collected.The Per caput dose to average Indian is 2490 uSv per year.97.7% of the dose results from natural sources, 734 uSvexternal and 1699 uSv from internal. Medical exposureconstitutes 1.93% and nuclear activities (nuclear fuel cycle,nuclear weapons tests and Chernobyl accident) makes 0.3%.Industry, . Consumer products, research, air travels,etc.contribute 0.07%. Average per caput radiation dose in Indiais compared with average dose in UK, USA, Japan and theUNSCEAR - 1988 data for world average. Indian value of 24 90jiSv is comparable with UK values of 2522 uSv but lower thanUSA values of 3600 uSv and Japan value of 3275 uSv. UNSCEAR1988 values for world average is in the range of 2830-3430uSv. Contribution from nuclear fuel cycle is 0.08% , 0.56% ,0.01% and 0,005% in UK, USA, Japan and India respectively.


Completed Population exposureNatural backgroundPer caput doseCollective dose

8. REFERENCES:

Population Exposure to Ionising Radiation in India , K.K.Narayanan, D. Krishnan, M.C. Subha Ramu, ISRP(16J-BR-3,Indian Society for Radiation Physics, Kalpakkam Chapter 1991.

1. TITLE : • 2- CATEGORY :

Some Important Aspects of Thorium 2 - 1 3Metabolism and Their Effects onUrinary Excretion Levels


D.D.Jaiswal, H.S.Dang and K.C.PillaiHealth Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT :

The current bio-assay procedures employed to monitor the Thexposure in occupational subjects, are based on the ICRPmetabolic model of Th, which in turn is based on the animalexperiments and hence may not be valid for humans. With aview to study its metabolic behaviour in humans, the concen-trations of Th in human tissue and body fluids were deter-mined using radiochemical neutron activation analysis(RNAA). Some of the important observations of this studyare: 1) The Th concentration in human skeletal tissue in-creased with the age of the subjects, 2) The observed dailyurinary excretion of Th for the occupational subjects wasmuch lower than the expected on the basis of ICRP metabolicmodel and 3) The observed ratio of liver to skeletal burdenof Th was found to be much higher than that expected on thebasis of ICRP model. This study indicates that there is aneed to revise the ICRP metabolic model of Th and thatcaution should be exercised when using the derived excretionlimits recommended in ICRP-54 to interpret the Th exposureto the occupational subjects on the basis of the dailyurinary excretion of Th.


Completed ThoriumMetabolic model

8. REFERENCES :

Some Important Aspects of Thorium Metabolism and TheirEffects on Urinary Excretion Levels, D.D.Jaiswal, H.S.Dangand K.C.Pillai, Bulletin of Radiation Protection, Vol. 15,No. 1, IARP 19/J20, January-March, 1992

1. TITLE s 2. CATEGORY :

Dose Estimates due to Ar-41 in 2 - 1 4the Kalpakkatn Environment


E. Chandrasekharatn, V. Rajagopal*, M.A.R. Iyengar andS. VenkataramanEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam-603 102Health and Safety Lab., IGCAR, Kalpakkam

4. ABSTRACT :

In the two units of MAPS ( 2 x 235 MWe) Ar-41 gas (Tl/2 =110 tnin, gamma energy = 1.29 MeV) is produced as an activa-tion product due to irradiation of Ar-40 present in air(0.93% by vol.) in the calandria vault and thermal shield ofthe reactor system. On purging these systems Ar-41 is re-leased into exhaust ventilation duct and ultimately dis-charged to the environment can give rise to external radia-tion exposures to members of public in the vicinity. Toestimate the potential doses to public from Ar-41 releasesthe diffusion climatology data from micrometeorologicalstudies at site together with the Ar-41 release source termduring the year, were employed and annual doses in differentsectors at fence post (1.6 km) were computed. The maximumdose due to Ar-41 during 1984-90, varied from 17.4 uSv/yr(1984) to 188.5 uSv/yr (1988). The sector weighted averageAr-41 dose ranges from 9.2 uSv/yr (1984) to 87.05 uSv/yr(1987). From these data it is demonstrated that externalgamma dose to public at fence post due to Ar-41 is wellwithin TECHSPECS limits.


Completed Ar-41 dose estimates

8. REFERENCES :

Dose Estimates due to Ar-41 in the Kalpakkam Environment,E. Chandrasekharan, V. Rajagopal, M.A.R.Iyengar and S.Venkataraman, 19th Annual IARP Conference, Bombay, March 3-5, 1992.


Assessment of Intake and Radiation 2 - 1 5Doses Following Exposure toTritiated Water

3. AUTHOR/S AND AND ADDRESS :

Kamala Rudran, Jyoti V. Sawantr S. Thampan and V.S. BangeraHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Results of follow up of 75 cases of acute exposure totritiated water (HTO) were studied critically. It has beenexperimentally verified that HTO concentration in urine andin blood at the time of voiding are at equilibrium. Biologi-cal half- life of the fast component (Tb^) varied between2.5 and 16 days (6.5 to 7 days). Mathematical analysis ofthe Tbi with respect to prevailing weather conditions showedan increasing trend in Ibj with decreasing temperature andan inverse relationship for Tbj with relative humidity andabsolute moisture content in air. Within the age boundary of20 years to 60 years and body weight boundary of 40 kg to 90kg, the data showed only a marginal variation which can beassociated with age or body weight.

8 cases were studied for longer periods and showed a secondcomponent in elimination of HTO. The second component variedfrom 3.5% to 18% of the total intake with Tb2 of 30 days to226 days and gave rise to CD ranging from 1.5 times to 2.4times that due to the first component. This implied a needto revise ALI and DAC of tritium as HTO.


Ongoing Internal DosimetryH-3

8. REFERENCES :

Assessment of intakes and radiation dose following exposureto tritiated water - Rudran K., Sawant J.V., Thampan S., andBangera V.S., IRPA 8 Montreal, Canada, May 1992.

1, TITLE i 2. CATEGORY :

Internal Dosimetry of Thorium For 2 - 1 6Occupational Workers


D.D.Jaiswal, H.S.Dang and R.CSharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Natural thorium (232^) j s t n e parent of a long chain ofalpha, beta and gamma emitting radioactive nuclides and isconsidered to be radiologically more toxic than other acti-nides. Its applications in nuclear and other industries arelikely to cause exposure of the occupational workers. Thispaper describes and compares the three commonly employedtechniques for implementing internal dosimetry programme ofTh for occupationnal workers: namely 1) direct in-vivocounting, 2) thoron in breath measurement and 3) bio-assaymeasurement using neutron activation analysis (NAA). Al-though each of these techniques has its own advantages, yetwhen applied for measurements below derived investigationlevels (DILS), bioassasy measurement using NAA turn out tobe the most sensitive technique.


Completed ThoriumInternal dosimetry

8. REFERENCES :

D.D.Jaiswal, H.S.Dang and R.C.Sharma, Internal Dosimetry ofThorium For Occupational Workers, IARP Topical Meeting onInternal Dosimetry, Bombay, Sept. 16-18, 1992


internal Dosimetry For Occupational 2 - 1 7Workers Handling Natural And EnrichedUranium


R.C.Sharma, T.Suirendran and T.K.HaridasanHealth Physics Division, BARCBOMBAY - 4 00 08 5

4. ABSTRACT :

First ever direct measurements of thorax burdens of naturaland enriched uranium for occupational workers of four fuelfabrication plants of Nuclear Fuel Complex namely UOP(Uranium oxide), EUOP (Enriched uranium oxide), CFFP (Ceram-ic fuel fabrication) and EFFP (Enriched uranium fuel fabri-cation), were performed at the in-vivo monitoring laboratoryat Trombay. A total of 300 workers were monitored.Two typesof detectors-a 20 cm dia phoswich (3mm thick NaI(Tl)asprimary) in centrally over supine chest geometry and 12.7 cmdia x 1.27 cm thick Nal(Tl) in one over each lung configra-tion, housed inside a graded lined steel room shield wereemployed for measurements of low-energy (63, 93 and 185 keV)photons. The detection systems were calibrated with the aidof a REMCAL phantom by loading its lungs with the standardsources of uranium of four different enrichments- 0.7%,1.66%, 2.1% and 2.66% respectively.Although separate cali-bration factors were obtained for each uranium enrichment,in practice only those pertaining to an average enrichmentin the plant, were used. Analysis of the measurement resultsrevealed that: 1. About 2/3rd of the subjects had measurablethorax burdens in the 5-25 mg range. 2. The assessed thoraxburdens in the subjects of each of the four plants werelog-normally distributed and their estimated GMs correspond-ed to air activity concentrations of about 1/3 DACs. 3.Comparisons with lung model predictions identified threesubjects for whom exposure rates were in excess of 1ALI/year. 4.Follow-up measurements in one case showed anunusually long clearance half-life of about 2900 days and 5.Improvements in detection systems are needed if yearlyincrements arising from intakes of 1 ALI are to be measuredover and above the existing thorax burden levels.


Completed Natural uraniumEnriched uraniumThorax burdens

8. REFERENCES :

Internal Dosimetry For Occupational Workers Handling Naturaland Enriched Uranium, R.C.Sharma, T.Surendran and T.K.Hari-dasan, Topical Meeting on Internal Dosimetry, Sponsored byIARP and AERB, BARC, Bombay, Sept.16-18, 1992


Estimation Of Thoron Inhalation Dose 2 - 1 8Using A Sensitive Whole-Body Counter


Pushparaja*, T.K.Haridasan, C.O.Gohel*, T.Surendran,R.C.Sharma and M.R.Iyer*Health Physics Division, BARC^BOMBAY - 400 085*Radiation Safety System Division, BARC

4. ABSTRACT :

Exposure to thoron daughters is a potential inhalationhazard in thorium handling faci1ities.The internal exposureof individual workers is estimated using air sampling dataand occupancy factor. In order to corroborate the results ofthis indirect method, a study was carried out by plannedexposure of human volunteers to thoron daughters and in-vivoactivity measurements using a sensitive whole-body counter.The methodology and findings of such a procedure are pre-sented in this paper. The effective dose equivalents esti-mated from the air sampling data and whole-body countingshow agreement within +20 %.


Completed Air-samplingEffective dose-

equivalentIn-Vivo measurement

8. REFERENCES :

i) Estimation Of Thoron Inhalation Dose Using A SensitiveWhole Body Counter, Pushparaja, T.K.Haridasan, C.O.Gohel,T.Surendran, R.C.Sharma and M.R.Iyer, Rad.Prot.Dos.,Vol.42(4), pp 307-312, 1992ii) Internal Doses Arising Frum Inhalation Of Thoron Daugh-ter Products: Results Of Air Sampling And In-vivo CountingOf 212p]-,( Pushparaja, T.K.Haridasan, C.O.Gohel, T.Surendran,R.C.Sharma and M.R.Iyer, Topical Meeting on Internal Dosime-try, Sponsored by IARP and AERB, BARC, Bombay, Sept.16-18,1992iii) Internal Dosimetry Arising From Thoron (220gn) Daugh-ters Based On Air Samples And in-vivo Counting Of 212Pb OfExposed Persons, Pushparaja and R.C.Sharma, Bull. Rad.Prot., Vol.15, No.3&4, pp 1-3, 1992


Radiation Exposure to Dial 2 - 1 9Painters from H-3 in LuminousPaint Industry


Jyoti V. Sawant and Kamala RudranHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

To study in-vitro solubilisation of H-3 labelled paint,experiments were conducted using bovine serum and syntheticserum, changing parameters such as volume of serum, durationof solubi1isation and specific activity of luminous paint.The study showed a fast component solubilised in first daycomprising around 12% to 13% of total activity followed by aslow component. Solubilisation pattern is independent of thevolume used, duration of study (upto 16 days) and specificactivity of the paint used.

Urine samples of luminous paint workers and air samples fromtwo factories manufacturing alarm and wrist watch respec-tively were analysed for H-3. The CED values were observedto be within the prescribed limit. In wrist watch factory,air concentration in assembly hall where luminous paint isnot handled is of the some order of magnitude as in lumi-nous paint room. Complete segregation of assembly hall fromluminous paint room has been subsequently recommended.


Completed H-3 labelled paintSolubi1isation - fast

componentSlow component

dialysate

8. REFERENCES :

Radiation exposure to Dial painters from H-3 luminous paintindustry - Jyoti V. Sawant, Bulletin of Radiation Protec-tion, Vol.15, No. 3 and 4, July-Decemebr 1992

92


Direct Methods Of Internal Dosimetry 2 - 2 0Of Plutonium And Americium ForOccupational Workers


T.Surendran, T.K.Haridasan and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

This paper describes the requisites of direct methods ofinternal dosimetry of Plutonium and Americium at Trombay.Some notable operational experiences have been summarisedand the methodology for calculating intake and CEDE hasbeen illustrated. Notable observations described have in-cluded: lung clearance half-life of about 3.7 years for24lAmO2? a ca'se showing build-up instead of decline of 2 4 1 ^in lungs due to ingrowth from 241pU/ yet another case inwhich an erroneous indication of ^^^hn\/Pu lung contaminationwas finally traced to a deposition of activity in the later-al axillary lymph-nodes resulting from an old but forgottenwound contamination at the finger tip; and first case ofa successful excision of the contaminated wound. Though thecases of Pu/Am internal contamination have been too few,each one has been typically unique and rare. As a result,-special investigation techniques, use of a variety of detec-tor systems and novel methods for assessment of organburdens, intakes and dose calculations were required and hadto be applied.


Completed IntakeInternal DosimetryOrgan Burdens

8. REFERENCES :

Direct Methods of Internal Dosimetry Of Plutonium and Ameri-cium for Occupational Workers, T.Surendran, T.K.Haridasanand R.C.Sharma, Topical Meeting on Internal Dosimetry,Sponsored by IARP and AERB, Bombay, Sept.16-18, 1992

Direct Methods of Internal Dosimetry Of Plutonium and Ameri-cium for Occupational Workers, T.Surendrai., T.K.Haiidasanand R.C.Sharma, Bull. Rad. Prot., IARP, Vol.15, No. 3 & 4,July-Dec, pp 40-48, 1992

93


Internal Monitoring Using Partially 2 - 2 1Shielded In-Vivo Counting Systems andDetermination of Internal Dose

3. AUTHOR/S AND ADDRESS ;

K.B.S.Murthy, M.C.Abani1, R.C.Sharma and C.M.Sunta2

Health Physics Division, BARCBOMBAY - 400 085Radiation Safety Systems Division, BARC^Atomic Energy Regulatory Board, Bombay 400 094

4. ABSTRACT :

While monitoring radiation workers for their internal dose,types of monitoring programmes to be undertaken and perio-dicity of monitoring are important factors (ICRP, 1988).These aspects are given in this paper for measurementof fission and activation products. From the measured bodyburden values, estimation for committed dose and methodsadopted to maintain dose records are discussed.


Completed In-Vivo MonitoringFi ssion/Activat ionProducts

8. REFERENCES :

Internal Monitoring Using Partially Shielded In-Vivo Count-ing Systems and Determination of Internal Dose,K.B.S.Murthy, M.C.Abani, R.C.Sharma and C.M.Sunta, Bulletinof Radiation Protection, Vol. 15, No. 3 & 4, July-December,pp 18-25, 1992

94


Body Burden and Excretion of Uranium 2 - 2 2based on ICRP Models and ChemicalToxicity Criteria

3 . ACJTHOR/S AND ADDRESS :

M.C.Abani1 , K.B.S.Murthy and CM.Sunta 2

Health Physics Division, BARCBOMBAY - 400 085^Radiation Safety Systems Division, BARC^Atomic Energy Regulatory Board

4. ABSTRACT :

Internal monitoring of uranium gets a wide attention becauseof its chemical toxicity. In the internal monitoring pro-gramme, correlation between body burden, excretion and theintake has to be found out. Reference levels are introducedusing calculations based on ICRP models. These aspects arediscussed in this paper for uranium for an acute intake. Asper the earlier recommendations of the ICRP (ICRP, 1978),the intake of uranium compounds was governed solely by thecriterion of radiological toxicity. With more details avail-able, ICRP in its later recommendations took radiological aswell as chemical toxicity into consideration and the re-strictive value of tolerance was fixed. Thus (ICRP, 1988)has suggested that intake of D and W types of uranium com-pounds should be governed by the criterion of chemicaltoxicity and radiological toxicity applies only for Y classcompounds. The same reasoning holds good for kidney which isthe organ at risk in case of soluble uranium. Values ofkidney burden also are discussed in this paper taking radio-logical and chemical toxicities into account.


Completed UraniumChemical ToxicityICRP Models

8. REFERENCES :

Body Burden and Excretion of Uranium based on ICRP Modelsand Chemical Toxicity Criteria, M.C.Abani, K.B.S.Murty, andC.M.Sunta, Bulletin of Radiation Protection, Vol. 155, Nos.3 & 4, pp 26-34, Jul.- Dec. 1992

Body Burden and Excretion of Uranium based on ICRP Modelsand Chemical Toxicity Criteria, M.C.Abani, K.B.S.Murty, andC.M.Sunta, Report No. BARC-1435 1988

95


Internal Dosimetry Programmes For 2 - 2 3Uranium And Transuranics at Trombay


R.C.Sharma and S.KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

At Trombay, a well formulated internal dosimetry programmefor workers handling Uranium and Transuranics has been inoperation for a long time.Indirect (bioassay)and direct(in-vivo counting)methods for monitoring of intakes of theseradionuclides have been standardised and refined from timeto time.Bioassay techniques (urine-analysis) have beenvalidated by several inter-comparison experiments.Externalcountings of lung/liver/skull burdens are performed in alow-level counting laboratory using phoswich and HPGe (LO-AX) detectors.The phoswich is operated with electronicpulse-shape discrimination technique.Wound contamination isassessed by a miniature Cd-Te probe and / or with the abovementioned detectors. Utilising bioassay and in-vivo countingmethods routine, special / operational , confirmatory andfollow-up monitoring programmes have been extensively con-ducted. The intakes by occupational workers, in general areobserved to be below the detection limits of the techniquesemployed.Further, there are instances where the measurementdata are found to be at variance with the known ICRP meta-bolic models, e.g. unusually long retention half- times ofNatural Uranium in lungs.Some of these observations alongwith their implications for establishing a U/TRU registryare presented in this paper.

5. REMARKS : 6. STATUS : 7. KEYWORDS :Completed Internal Dosimetry

UraniumTransuranics

8. REFERENCES :

Internal Dosimetry Programmes For Uranium And Transuranicsat Trornbay, R.C.Sharma and S.Krishnamony, IAEA-TCM on Estab-lishment of Occupational Uranium and Transuranium ExposureRegistries, IAEA, Vienna, Nov 30 - Dec.4, 1992

96


Assessment of Internal Dose from 2 - 2 4Inhalation Exposure to Plutonium


Sharda Bhati, Kamala Rudran and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

ICRP implies dose allocation of 0.2 SV per year due to anintake of 1 ALL This practice does not err much for majori-ty of radionucl ides that have, short residence time (1 y'r) inbody, but for the case of Plutonium and other radionuclideswith long residence time in body, the actual dose deliveredin the year of intake may differ significantly from the 50years dose commitment, necessitating computation of annualdoses from exposures to Pu 239r for making individual doserecords. A study was carried out to determine annual doseequivalent to all reference organs and annual effective doseto whole body received in 50 successive years following anacute (lBq) and chronic (1 Bq/y) intakes of W and Y-classesof Pu-239 for inhaled particles of size distribution of 1 urnAMAD. The methodology is based on the lung model (ICRP-1979)metabolic model of Pu-239 (ICRP-1986) and the dosimetricmodel for bone (ICRP-1979a) and takes into account themodified weighting factors published by ICRP (1991). Theresults indicate that the dose delivered in the year ofintake is only 5.7% and 12.5% of the total 50 years commit-ment for W and Y classes of Pu compounds, respectively. The~ALI' values calculated for W and Y-class of Pu-239, corre-sponding to annual stochastic limit of 0.02 Sv were ob-tained as 300 Bq each. The results obtained from this studycan be used to assign annual doses to known Pu-239 exposurecases.

5. REMARKS : 6. STATUS : . 7 . KEYWORDS :

In progress Internal dosimetryPu 239, Annual Dose

8. REFERENCES :

.Assessment of Internal Dose from Inhalation Exposure toPlutonium, Sharda Bhati , Kamala Rudran and K.C.Pillai,Bull. Rad. Prot. Vol. 15(1), pp 33-34, 1992

97


A Review of Urinary Uranium 2 - 2 5Excretion Data of NFC Workmen


A.R. Lakshmanan, T. Krishna Rao, B. Balaiah andS. ViswanathanHealth Physics UnitNuclear Fuel ComplexHYDERABAD - 500 762

4. ABSTRACT :

Nuclear Fuel Complex, Hyderabad processes Uranium concen-trates (Magnesium diuranate) and uranium hexafluoride fornuclear energy programmes in the country. The personnelworking in the uranium plants are likely to be exposed toairborne Uranium.' Intake of uranium by the occupationalworkers through ingestion and inhalation is assessed bymeasuring the daily excretion rate of uranium in the urine.

Monitoring of the personnel, for the last 10 years indicatesthat more than 85% of them had shown Uranium excretion lessthan 5 ug/1. Further the data show that the annual intake ofsoluble uranium by NFC workmen is within the limit as perthe ICSP biokinetic model.


Completed UrineUranium

8. REFERENCES :

A Review of Urinary Uranium Excretion Data of NFC Workman,A.R. Lakshmanan, T. Krishna Rao, B. Balaia and S.Viswana-than, Bulletin of Radiation Protection, Vol. 15, No. 1, IARP19/33, 1992

98


Studies in Biological Excretion of 2 - 2 6Inhaled Plutonium in the Case of aFew Occupational Workers in a FuelReprocessing Plant


A.G. Hegde, S. Chandramouli, R.S. Iyer and I.S. Bhat*Environmental Survey LaboratoryTARAPUR - 401 504E & PA, Nuclear Power Corporation,World Trade Centre, Bombay

4. ABSTRACT :

Follow-up studies of plutonium elimination in four inhala-tion exposure cases of a fuel reprocessing plant have beencarried out by bioassay. Periodic excretion analysis weredone upto 100-500 days post exposure. Single and two compo-nent excretion were found with biological half lives rangingfrom 2 to 653 days. The results are in agreement with re-ported cases of exposure to different chemical forms ofPlutonium like Pu{NO3>4, PUCI3 and Pu-TBP complex.


Completed Plutonium inhalationexposure

Biological excretion

8. REFERENCES :

Studies in Biological Excretion of Inhaled Plutonium in thecase of a Few Occupational Workers in a Fuel ReprocessingPlant, Journal of Radioanalytica.' and Nuclear Chemistry,Articles, Vol. 156, No.l, pp 72-74, 1992

99

X. TITLE 2. CATEGORY :

Relevance of ICRP Metabolic Model of 2 - 2 7Th in Bio-assay Monitoring


H.S.Dang, D.D.Jaiswal,P.P.V.J.Nambiar, C.M.SuntaHealth Physics Division, BARC,BOMBAY - 400 085

K.B.S.Murthy, R.C.Sharma,

4. ABSTRACT :

This paper compares the urinary excretion levels of Thobtained in bio-assay monitoring using the neutron activa-tion technique with those predicted by applying the ICRPmetabolic model to the measured Th activity in chest andtotal body of a group of Thorium plant workers. The resultsindicated much lower urinary Th excretion as compared towhat was expected on the basis of the ICRP model. Lowerurinary excretion in occupational subjects is explained interms of negligible contribution of skeleton and soft tissueto the activity excreted in urine. It is suggested that theexisting model should be modified to enable it to be ap-plicable to the bio-assay monitoring of occupational work-ers .


Completed

7. KEYWORD :

ThoriumMetabolic Model

8. REFERENCES :

Relevance of ICRP Metabolic Model of Th in Bioassay Monitor-ing, H.S.Dang, D.D.Jaiswal, K.B.S.Murthy, R.C.Sharma,P.P.V.J.Nambiar, C M . Sunta, Journal of Radioanalytical andNuclear Chemistry, Article, Vol. 156, No. 1, pp 55-64, 1992.

100


Simultaneous Determination of 232^h 2 - 2 8and 238(j in Biological Samples:Application to the Estimation oftheir Daily Intake Through Diet


H.S>Dang, V.R.Pullat and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A simple method employing neutron activation and radiochemi-cal separation was developed for simultaneous determinationof 232xh and 238y j n biological materials. Using thismethod, it is possible to detect 0.05 and 0.2 ng of Th andU, respectively, in the samples. This method was applied todetermine the daily dietary intake of these two nuclides bythe population living in the high background areas of India(Monazite area), where the soil contains very high levels ofthese two nuclides. The comparison of the daily intakes bythe population living in high and normal background areasshowed significantly higher intake of these two nuclides bythe high background population.


Completed ThoriumUran i urnDietaryIntake

8. REFERENCES :

Simultaneous Determination of 2 3 2Th and 238y j n BiologicalSamples: Application to the Estimation of their Daily IntakeThrough Diet. H.S.Dang, V.R.Pullat and K.C.Pillai. Journalof Radioanalytical and Nuclear Chemistry, Articles, Vol.162,No.l, pp. 163-169, 1992.

101


Gastrointestinal Absorption Factor 2 - 2 9for Uranium Incorporated in Diet

3 . AUrilOR/S AND ADDRESS :

H.S.Dang, V.R.Pullat and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The gastrointestinal absorption factor (f].) for uraniumincorporated in diet was estimated for a group representingthe urban Indian population, by studying the average dailyingestion and urinary excretion of U. The technique ofneutron activation was employed to determine the concentra-tion of 238u in daily diet, drinking water-and urine .sam-ples. The gut absorption factor was found to be 0.016.


Completed UraniumGastrointestinalFactor (fi)

8. REFERENCES :

Gastrointestinal Absorption Factor for Uranium Incorporatedin Diet, H.S.Dang, V.R.Pullat and K.C.Pillai, RadiationProtection Dosimetry, Vol. 40, No. 3, pp 195-197 NuclearTechnology Publishing, 1992

102


Determination of Normal Concentration 2 - 3 0of Uranium in Urine and Applicationof the Data to its Biokinetics


H.S.Dang, V.R.Pullat and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A method involving preconcentration of U from urine with Caphosphate, neutron activation, followed by simple radiochem-ical separation was developed and applied for the determina-tion of the concentration of U (238U) in urine. Using thismethod, it is possible to detect 0.2 ng of 2 3 8U. The averageand geometric mean concentration of U found in urine ofsubjects from normal background environment was 12.8 and 9.4ng L"1 respectively. The concentration of U in the urine andthe daily intake of U by the same population was used toarrive at the gastrointestinal absorption factor(fj) for Uincorporated in the diet. The fi factor was obtained to bel'9%


Completed Uraniumfl factorBiokinetics

8. REFERENCES :

Determination of Normal Concentration of Uranium in Urineand Application of the Data to its Biokinetics, H.S.Dang,V.R.Pullat and K. C. Pillai, Health Physics, Vol. 62, No.6,pp 562-566, 1992

103

TITLE :

ICRP Recommendations of the DerivedThorium Excretion Levels forOccupational Workers - A View Point

2. CATEGORY :

2 - 3 1

AUTHOR/S AND ADDRESS :

H.S.Dang, D.D.Jaiswal and R.C.SharmaHealth Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT :

The reconunendations of the International Commission onRadiological Protection (ICRP) are followed in most coun-tries. In ICRP publication 54 (1988), the derived investiga-tion and recording levels (DIL & DRL) for daily urinaryexcretion for different time intervals have been reportedfor a number of actinides including thorium. The report alsogives the derived urinary excretion rate for continuousexposure at the rate of 1 ALI/365. All of these derivedlimits of excretion were based on the metabolic and dosimet-ric models adopted by ICRP 30 (1979) for different acti-nides.- Some of the data on metabolism of thorium obtained byus clearly indicate that the Tfc values for thorium depositedin different human compartments are likely to be much longerthan those utilized in ICRP 30 (1979). The results obtainedin our laboratory on the thorium analysis of human boneobtained at autospy of subjects in different age groups alsoshow a linear increase of thorium concentration in bone withage of the subjects. This implies that Tj, of 8000 d . forthorium deposited in human skeleton is indeed unrealisticand that use of a longer Tjj (>50 y) wouldappear to be moreappropriate. Measured urinary excretion of thorium in work-ers from a thorium plant was much lower than expected basedon application of the ICRP model (body burdens measured bywhole body counting).This observation supports the inferencethat biological retention of thorium in humans is muchhigher than assumed by ICRP 30. Summarizing, in our view,the availability of additional information suggests thatthere is an urgent need to modify the metabolic model forthorium. In tune with this, the proposed ICRP limits ofderived urinary excretion levels for thorium in occupationalworkers would need downward revision.


Completed

KEYWORDS ;

ThoriumMetabolic modelDIL, DRL

8. REFERENCES :

ICRP Recommendations of the Derived Thorium Excretion Levelsfor Occupational Workers - A View Point, H.S.Dang,D.D.Jaiswal and R.C.Sharma, Health Physics, Vol. 63, 1992

104


Whole Body Monitoring of Workers 2 - 3 2for their Internal Contaminationof Gamma Emitting Radionuclides

3. AUTHOR/S AND ADDRESS :•S.P.Garg and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Whole body monitoring of personnel handling radioactivity orworking in radioactive environment in various plants andlaboratories of BARC is an on-going program at Whole BodyCounting Laboratories located in the basement of ModularLaboratories. This ensures that the radiation doses to theoccupational workers do not exceed the recommended limits.Two different counting systems are employed for this purposeviz. (a) Shadow shield bed Counter (b) Shielded Chair. Boththese systems incorporate a (4" x 3") Nal detector. Twodifferent types of Monitorings were carried out in accord-ance with ICRP-54, (a) Special (b) Routine. In general allpersonnel are scanned for all gamma energies above about 200keV. A special attention is given to the gamma energiesrelevant to the workplace of the worker. To facilitate thistwo parallel recording systems are used. In one of thementire energy spectrum is recorded on a microprocesser basedHPD 4K MCA where as in the other, four SCAs have been ad-justed for the radionuclides encountered more frequently.For instance CIRUS and DHRUVA personnel are checked forfission and activation products like Cs-137, Ce-58, Co-60,1-131 etc.

Personnel from Divisions like Isotope, RPhD, Radiochemistry,Radiometallurgy are checked for the radionuclides which theparticular worker handles. CWS personnel going to TAPS formaintenance work fall under Operational Category while mostof others in the Routine Category. With reference to the DRLvalues calculations of CDE and CEDE are also carried out.Monthly Whole Body Counting reports are sent to the respec-tive Divisions regularly.


In progress Whole body countingGamma emittersShadow Shield

8. REFERENCES:

i) Internal Monitoring using Partially Shielded In-vivoCounting Systems and Determination of Internal Dose,K.B. S.Murthy, M.CAbani, R.C.Sharma and C.M.Sunta, Bull.Rad. 15, pp 18, 1992

105


Intercomparison of Whole-Body 2 - 3 3Monitors in India


D.J.Mehta, D.S.Katoch, R.Dhandayutham and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Internal Dosimetry Section initiated the in-vivo monitoringprogramme in 1961. .Till now, eighteen whole body countershave been installed for health physics surveillance atvarious nuclear facilities in the country. The monitors havebeen calibrated at different times, with different phantomsusing different sets of radioactive sources. The extent ofoverall errors, this could introduce in the estimation ofradioactivity contents of the human body, had been largelyunknown. Therefore, a programme for intercomparison ofshadow-shield whole body monitors currently in operation atvarious Health Physics Laboratories has been taken up.Delineation of aims and procedures to be followed for con-ducting the intercomparison are presented in this paper. Theprogress made so far is also reported.


In progress IntercomparisbnWhole-body monitors

8. REFERENCES :i

Intercomparison of Whole-Body Monitors in India, D.J. Mehta,D.S. Katoch, R. Dhandayutham and R. C. Sharma, Bull. Rad.Prot. Vol.15, No. 3&4, pp 35-39, 1992

106


Estimates of Internal Doses to 2 - 3 4DAE-Staff Due to Intake ofIodine-125 From RIA Procedures


Sharda Bhati and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 08 5

4. ABSTRACT :

Iodine -125 is commonly used as a tracer in the preparationof radio-immunoassay (RIA) kits, by a considerable number ofworkers of BRIT and BARC. Since activities handled per annumcorrespond to several hundred times its ALI and being vola-tile, 1-125 can get easily airborne and may lead to thyroidcontamination in workers,we have set up a personal monitor-ing system consisting of a thin (75mm dia x 2mm thick)Nal(Tl) scintillation detector coupled to a low-noise photo-multiplier tube. The detector is calibrated with a REMCALPHANTOM. It is capable of measuring as low as 6 Bq of 1-125activity (MDA) in thyroid for 10 min counting time. Theworkers are routinely monitored in a sitting position withthe detector positioned close to the neck at a known dis-tance. The detected activity is extrapolated back to the dayof iodination to compute intake per operation. The annualintake of 1-125 and corresponding committed dose equivalent(CDE) received by each individual are calculated in ac-cordance with ICRP-30 and ICRP-54 concepts. The computedintakes are generally found to be positive. Three cases ofexposure to 1-125 exceeding Recording Level have been en-tered in the doserecords. The whole data of the last sevenyears has been statistically analysed for log-normal distri-bution and an attempt is made to relate the doses received,with the nature of work and amount of activity used peroperation by a worker. Follow-up studies conducted on threesubjects suggested a value of mean effective half-life of1-125 in the thyroid as 45.5 days. This corresponds to abiological removal half-time of about 180 days for thyroidas against ICRP value of 120 days.


Continuing Thyroid monitoringIodine-125Effective half-life

8. REFERENCES :

Estimates of Internal Doses to DAE-Staff due to Intake ofIodine-125 from Radio-Immunoassay Procedures Sharda Bhatiand R.C.Sharma, Bull. Rad. Prot. Vol. 15(1), pp 30-32, 1992

107


Quality Control in Evaluation 2 - 3 5of Body Radioactivity byBioassay Measurements


Kamala Rudran, J.V. Sawant, S. Thampan, V.S. BangeraS.A. Dalvi, A.G. Hegde, V.S. Krishnan and J.R. YadhavHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A good quality control programme is essential to define thelikely errors in radiochemical analysis as well as evalua-tion of results. Intercomparisons are being carried out inthe laboratory both at the National as well as Internationallevel for this purpose. Intercomparison runs were carriedout on liquid effluent, ground water, milk, mineral water,sea fish, urine feces and tissue samples for H-3, Sr-90,Cs-134, Cs-137, Ra-226, U, Pu, Ca and K.

Errors in evaluation of bioassay data due to physiologicalvariations in daily excretions were checked by the. analysisof three consecutive days' urine samples in 15 cases. Maxi-mum variation was only by a factor of 3 indicating thatchronic exposure evaluations based on a single analysis arenot likely to err by a factor more than three due to dailyvariations in excretions. In a case study, the fitted curveof excretion versus time, after follow-up studies of excre-tion of tritium obtained in two different laboratoriesshowed the results were in good agreement thereby provingthe combined reliability and reproducibility of naturalbiological processes as well as the analytical techniquesused.


Continuing Quality controlIntercompar i sonsPhysiologicalvariations

8. REFERENCES :

Quality Control in Evaluation of Body Radioactivity byBioassay Measurements, Kamala Rudran, Conference-cum-workshop on Radiation Standards and Measurements held atBARC, January 4-6, 1993

108


A Methodology for Evaluation of 2 - 3 6Effective Dose to OccupationalWorkers Due to Inhalation of Cobalt-60

31 AUTHOR/S AND ADDRESS :

D.D. Rao, A. Baburajan and A.G. HegdeEnvironmental Survey LaboratoryTARAPUR - 401 504

4. ABSTRACT :

At ESL, the whole body counting of occupational workers iscarried out for estimating the radionuclide content. Elimi-nation rate equations were constructed based on the follow-up studies conducted over the years. Using these equationsobserved in Tarapur workers, internal dose computation hasbeen made according to ICRP-30 and ICRP-54 methodologies.Derived Recording and Investigation levels were determinedfor 180 d working period. Analysis of about 30 internalcontamination cases has been carried out. The comparison ofeffective dose computed from both models have resulted inno much variation when the monitoring interval is about 200days. The analysis of whole body counting results has indi-cated that only 1% of the personnel are exposed to radioac-tivity exceeding DRL.


Completed OccupationalEliminationEffective doseInternal

contamination

8. REFERENCES :

A Methodology for Evaluation of Effective Dose to Occupa-tional Workers due to Inhalation of Cobalt-60, Bulletin ofRadiation Protection, Vol. 16, No. 1&2, Jan-June, 1993

109


Experiences in Bio-assay Monitoring 2 - 3 7of IRE Workers for Thorium


H.S.Dang, D.D.Jaiswal, M. Nair, V.R.Pullat and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The bioassay monitoring of the Thorium plant (IRE} workerswas carried out by the estimation of daily urinary Th excre-tions, with a view to assess the exposure during the plantoperations in general and also in the case of individuals.Daily urinary Th excretions were determined for 154 workers,who were in different groups of occupational period. Asimple method involving preconcentration and neutron activa-tion analysis was employed to measure the concentration ofTh in urine samples. Ii all the five occupational groups ofIRE workers, the median daily urinary Th excretions werebelow the derived excretions corresponding to an exposure ofY class T.h, at the rate of the annual limit of intake (ALI).Tjhe results indicate that Th exposure in IRE plant workersin general are within the prescribed dose limits.


In Progress

7. KEYWORDS :

ThoriumExcretionALI

REFERENCES :

Experiences in Bio-assay Monitoring of IRE Workers forThorium, H. S. Dang, D. D. Jaiswal, M. Nair, V. R. Pull atand R.C.Sharma, Bulletin of Radiation Protection, Vol. 16,No. 1&2, IARP 20/7, January - June, 1993

110


Intake, Excretion and Tissue 2 - 3 8Distribution of Rb-87 for AGroup of Indian Population


M.Parameswaran, H.S.Dang and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Rb-87 is a naturally occurring long-lived radionuclide (Tj/2= 4.8 x lO1^ years). There is very little data available inthe literature on its intake, distribution, and excretionpattern for Indian population. A method using atomic absorp-tion spectrophotometry (AAS) was standarized and applied todetermine the concentrations of stable Rb in diet, drinkingwater, human tisues and urine samples. &?Rb concentrationswere worked out from stable Rb values. The mean concentra-tions of 8?Rb thus determined in human organs such as heart,kidney, liver and lungs were obtained to be 6.2, 7.2, 8.6and 6.9 mBq g"1 fresh weight respectively. Its intake andurinary excretion were calculated to be 2.4 and 1.4 mBq d~*respectively.


Completed RubidiumIntakeExcretion

8. REFERENCES :

Intake, Excretion and Tissue Distribution of Rb-87 for AGroup of Indian Population . M.Parameswaran, H.S.Dang andR.C.Sharma, Bulletin of Radiation Protection. Vol 16, pp

• 79-81, January- June 1993.

Ill

1. TITLE : 2, CATEGORY :

Experiences at Trombay in Monitoring 2 - 3 9Actinide Intakes by OccupationalWorkers by Direct External Counting


T. Surendran,T.K.Haridasan,R.C.Sharma and S. KrishnamonyHealth Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT :

Direct assessment of lung/liver/skeletal burdens of acti-nides (Pu/Am/U) for monitoring intakes forms part of theon-going internal dosimetry programme for occupationalworkers at Trombay. Majority of the measurements are per-formed with a 20 cm dia phoswich operating with pulse-shapediscrimination based on ORTEC electronics.In addition,NaKTl) (127 mm dia x 12.7 mm thick), a miniature Cd-Te (1cm dia x 2 mm thick) (Model B-101,RMD) and a HPGe(51 mm diax 20 mm thick) (ORTEC model LO-AX 51370/20) detectors arealso employed whenever needed. All the detection systems arelocated inside a graded lined 20 cm thick steel chamber.Calibration techniques include both in-vivo methods as wellas use of a realistic (LLNL)torso phantom.Utilizing thesefacilities routine, special/operational,confirmatory andfollow -up monitoring programmes have been extensivelyconducted. This paper presents a brief description of thefacilities, procedures employed and methodologies for compu-tation of CEDE. Monitoring data have also been analysed toobserve elimination patterns with respect to actinide aero-sols deposited in the lung. These have been compared withthe ICRP metabolic models. In particular, class Y behaviourof 241^,02 (embedded in Pu-matrix) and unusually long reten-tion half-times for Nat. U in lungs have been observed.


Completed ActinidesIntake monitoringExternal counting

8. REFERENCES :

Experiences at Trombay in Monitoring Actinide Intakes byOccupational Workers by Direct External Counting, T.Suren-dran, T.K.Haridasan, R.C.Sharma and S.Krishnamony, Workshopon Intakes of Radionuclides: Detection, Assessment andLimitation of Occupational Exposure, Bath, U.K, Sept. 13-17,1993

112


The Normal Concentration of Uranium 2 - 4 0in Body Fluids and Excretion Ratio


H.S.Dang and V. R. PullatHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

This paper reports the normal concentration of uranium inblood serum. The method involved neutron ctivation, radio-chemical separation and gamma counting. The mean and medianuranium concentrations obtained in present study are 14 and13 ng L~l respectively. The median value was used to obtainthe excretion ratio of 44% for uranium excreted in urine tothat present in blood serum pool.


Completed UraniumBody FluidsExcretion Ratio

8. REFERENCES :

The Normal Concentration of Uranium in Body Fluids andExcretion Ratio, H.S.Dang and V.R.Pullat, Health Physics,Vol. 66, 1993 (In press)

113


Detection Systems For Monitoring 2 - 4 1Intakes Of Actinides at Trombay


T.K.Haridasan, T. Surendran, R.C.Sharma and S. KrishnamonyHealth Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT :

A variety of detection systems are currently in operation atTrombay for monitoring intakes of actinides by occupationalworkers of fuel fabrication/reprocessing plants. This paperdescribes the detection systems,their associated electronicinstrumentation and performance characteristics and bringsout the advantages offered by them in investigating actualcases of actinide intakes. Illustrative data of one caseare presented which appeared initially to be of inhalationintake, at one stage as that of inhalation and injectionintakes, and was finally identified as that of an intake byinjection (i.e. through a contami-nated wound) alone,thanksto the availability of various detection systems andsophisticated data analysis techniques.


Completed ActinidesDetection Systems.Intakes

8. REFERENCES :

i) Detection Systems for Monitoring Intakes of Actinides atTrombay, T.K.Haridasan, T.Surendran, R.C.Sharma and S.Krish-namony, Rad.Prot.Dos.in Press, 1993

ii) Detection Systems for Intakes Monitoring of Actinidesat Trombay, T.K.Haridasan, T.Surendran, R.C.Sharma andS.Krishnamony, Proceedings of National Symposium on AdvancedInstrumentation for Nuclear Research held at Bombay, January27-29, pp 01-1 - 01-21, 1993

114


Identification of Radionuclides 2 - 4 2for External Exposures at MadrasAtomic Power Station


P.G. Mohandas, R.S. Vardhan and K. ChudalayandiHealth Physics UnitMadras Atomic Power StationKALPAKKAM - 603 102

4. ABSTRACT :

The collective dose to the workers at Madras Atomic PowerStation has been observed to be increasing over the years.About 70-80% of the station dose is received during mainte-nance work done during reactor shutdown, about 20-30% duringreactor operation. This paper presents the methodologyadopted to identify the radionuclides contributing to exter-nal exposures in reactor building during plant operation andshutdown and in service areas. Gamma spectrometry carriedout in several work areas indicated Co-60 as the majorradionuclide contributing (70-80%) to the external exposureof station personnel.


Completed External doseGamma spectrometry

8. REFERENCES :

i) MAPS Safety Reportii) EG&G ORTEC Manual for HP-Ge Co-axial Detector System

115

3. OPERATIONAL HEALTH PHYSICS AND NUCLEAR SAFETY

1. TITLE :

Containment of Radium from UraniumTailings

2. CATEGORY :

3 -


P.M. MarkoseHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

One of the essential requirements of operations in a uraniummine-mill complex is the treatment and containment of tail-ings so that their discharge to the environment meets theaccepted release standards. The treatment is directed- to-wards fixation of radium, the potentially hazardous radionu-clide associated with uranium processing. Conventional limeneutralisation treatment itself has not been proved com-pletely adequate in achieving this target.

A recent approach effecting the containment of radium in-volves its extraction from the tailings. Ferric chloride inhydrochloric acid was found to be an effective medium forthis purpose. Laboratory experiments have proved that morethan 90% of the radium could be extracted in 0.3M FeCl3 in0.5M HCL leaving the residue having Ra less than 1 KBq Kg'1.Presence of sulphate reduced the leaching efficiency con-siderably. Ra can be subsequently removed along with Fe(OH)3by addition of lime. This method has the added advantage ofremoving the bulk of manganese also from the tailings, beingcarried by Fe(OH)3.


Completed

7. KEYWORDS :

ContainmentTailingsFixationRadium

8. REFERENCES :


Reliability Analysis of 500 MW(e) 3 - 2Power Supply System


V.V.S. Sanyasi Rao, Health Physics Division,A.K. Babar, R.K. Saraf, Reactor Safety DivisionR« N. Bhawal, D. Chatterjee, M. Das, 500 MW(e) Project, NPCILBARC, Bombay-400085

4. ABSTRACT :

The reliability analysis of two alternative class IV powersupply schemes for the 500 MW(e) Project were carried out. InScheme 1, the 400 KV supply acts as a backup to the 200 KVsupply through interconnecting transformer, where as inscheme 2 the 400 KV supply acts as an alternative source tothe unit transformers provided the generator breaker isisolated through a generator breaker. The class IVunavailability evaluations were done using PSAPACK (an IAEApackage for probabilistic safety analysis) and the class IVfailure frequency evaluations were carried out using a MarkovModel setup for the power supply system. The effect of gridstation and grid-grid interactions on the class IV failurefrequency were also considered in the analysis. In scheme 2,the generator isolation breaker carries very large currents.The sensitivity of the system failure frequency, in scheme 2, to the generator breaker failure rate was also analysed.Frorr. this analysis it turns out that scheme 2 has a low classIV unavailability as well as low failure frequency. Thisscheme has also been found to be less susceptible to gridstation as well as grid grid interactions.


Completed ReliabilityPower Supply SystemUnavailabilityFailure Frequency

8. REFERENCES:

Reliability Analysis of 500 MW(e) Power Supply System,V.V.S.Sanyasi Rao et. al., National Symposium on Advances inUtility Systems for Industrial and NuclearInstallations,BARC,Bombay, Jan 9-11,1992

117


Control of fission product Iodine 3 - 3contamination in the spent fuelBuilding of a PHWR


V. K. Sharma and S. KrishnamonyHealth Physics Division BARC, Bombay - 400085

4. ABSTRACT:

Discharge of defective reactor fuel to the Spent Fuelservices Building (SFSB) of a PHWR is often accompanied byradio-iodine contamination at the bay water and of thebuilding air. Air-borne iodine contamination interferes withnormal work and personnel occupancy for a period of up to aday, and could result in enhanced release of iodine to theenvironment through the ventilation system. For the 500 MWePHWR currently under design, it was required to quantify thehazard posed by radio-iodines in the SFSB and to suggestremedial measures. An integrated approach to the air - watersystem indicated need for control not only in the air phasebut also in the aqueous phase and at the air - waterinterface.

The main parameters that influence the build-up of air-borneradio-iodine were identified, and a computer code SFSB 500was set up to model the distribution of radio-iodine in theSFSB. Various techniques for controlling the airborne iodineare discussed.


Completed SFSBPHWRIodine

8. REFERENCES:

Control of fission product Iodine contamination in the spentfuel Building of a PHWR, V. K. Sharma and S. Krishnamony,National Symposium on Safety of nuclear Power Plants andother Facilities, BARC, Trombay, Bombay-400085, March 11-13,1992

118


Probabilistic Safety Assessment 3 - 4of an Operating Plant - MAPS


V.V.S. Sanyasi Rao, A.K. Babar*, R.K. Saraf*Health Physics Division, BARC,Bombay - 400085

* Reactor Safety Division, BARC

4. ABSTRACT:

Probabilistic Safety Assessment, level I study c* MadrasAtomic Power Station has been carried out basea on theoperating experience. Initiating events (IEs) applicable tothis reactor have been identified and it is seen that thefollowing are dominating IEs contributing to core damagefrequency (CDF).

1. Class IV Power failure 2. Medium loss of coolant accident3. Process water failure and 4. Feed water failure.

Dominating accident sequences have been identified and thevarious importance measures like risk achievement worth, riskreduction worth etc. have been obtained for all safetysystems and operators actions. It is seen that secondarysteam relief (including boiler pressure control, steam dumpand discharge components), emergency power supply , emergencycore cooling system, fire fighting system are importantcontributors to CDF. Common cause failures ( involving humanerrors also ) have been observed in FFS, SSR. There have beeninstances where dump valves' operating time exceeded thepermissible time. In order to minimise the impact of processand safety systems failures, various accident mitigatingfeatures of a pressurized heavy water reactor such asdeaerator water, FFS are available. However, the effectiveutilization of such measures necessitates the provision ofunambiguous operating procedures and operator training in themitigation of accident consequences.

5. REMARKS: 6. STATUS.- 7. KEYWORDS:

Completed Initiating EventsAccident sequencesCore damagefrequencyRisk achievementworth

8. REFERENCES:

Probabilistic Safety Assessment of An operating Plant - MAPS,A.K. Babar , R.K. Saraf and V.V.S. Sanyasi Rao

PSA of an Operating Plant, V.V.S. Sanyasi Rao, R.K. Saraf,A.K. Babar, National Symposium on Safety of Nuclear PowerPlants and other Facilities,BARC, Bombay, March 11-13, 1992

119


AERB Guidelines on Intervention 3 - 5levels and Derived Interventionlevels for off-site Radiation Emergency


K.K. Narayanan, Health Physics Division, BARCT.N. Krishnamurthi, V.K. Gupta, George Thomas, AERB, BombayD. Krishnan, R.Ph. Division, BARCA.R. Sunderarajan, IGCAR, Kalpakkam

4. ABSTRACT :

Control of radiation exposures to the public followingnuclear accidents with off-site radiological consequences,can be achieved through intervention. The intervention isimplemented by means of a range of protective measures suchas administration of stable iodine, sheltering, evacuation,control of food stuff etc. The guidelines for introduction ofsuch countermeasures expressed in the form of InterventionLevels and Derived Intervention Levels, as formulated byAERB, are presented in this paper.

S. REMARKSt 6. STATUS: 7. KEYWORDS:

Completed Off-Site radiationemergencyProtective measuresDerived interventionlevelsStable iodine.

8. REFERENCES:

AERB Safety Guide lines on Intervention Levels and DerivedIntervention Levels for Off-site Radiation Emergency, T.N.Krishnamurthi, V.K. Gupta, George Thomas, K.K. Narayanan,D.Krishnan, A.R. Sunderarajan, National Symposium on Emergen-cy Preparedness and Disaster Management,Bombay,(SEMP-93), Aug3-5,1993

120


A Comparison between Plant related 3 - 6and Natural Radiation Exposure atNuclear Power Plant Sites in India

3. AUTHOR/S AND ADDRESS ,:

K.K Narayanan and S. KrishnamonyHealth Physics DivisionBhabha Atomic Research CentreBombay 400 085

4. ABSTRACT :

International Commission on Radiological Protection (ICRP)has prescribed limit for radiation exposure for members ofthe public. The currently applicable limit is 1 mSv per yearaveraged over 5 year period with a provision of 5 mSv in agiven year from all sources, exclusive of exposure resultingfrom natural background radiation as well as medicalexposures. Natural background radiation exposure in differentparts of India, excluding the monazite areas, varies from1.30 mSv/year in Madhya Pradesh to 2.50 mSv/year in UttarPradesh. Medical exposure to individuals can vary from 0.1mSv to as high as 10 mSv from diagnostic X-ray examinations.The percaput medical exposure for the Indian population isestimated as 0.048 mSv/year. A six hour travel by jetaircraft results in exposure of approximately 0.05 mSv.

Based on operating experience of nuclear power plants for thelast ten tears with respect to effluent releases and makinguse of conservative dose assessment models and maximisingassumptions, it is estimated that annual average of maximumindividual exposure at the plant boundary of the threeoperating NPP sites at Tarapur, Rawatbhata & Kalpakkam are0.10, 0.05 and 0.07 mSv/year, respectively. The exposures atfurther distances are far less. These small additionalexposures are indistinguishable in the large variation ofnatural background.

Plant related radiation exposure to members of the publiclocated even close to plant boundary when viewed againstnatural background radiation exposure, medical exposure andsimilar common sources result in negligible radiologicalimpact in the public domain.

5. REMARKS: 6. STATUS: 7. KEYWORDS :

Completed Natural RadiationPlant relatedradiationMedical exposure

8. REFERENCES :

A Comparison between Plant related and Natural RadiationExposure at Nuclear Power Plant Sites in India, K.K Narayanan& S. Krishnamony, National Symposium on Radiation, Environ-ment and Man, Dept. of Physics Mysore University,Mysore,October 8-9, 1992

121


Radiological Evaluation of the 3 - 7Uranium Tailings Pond at Jaduguda


A.H. Khan, G.K. Srivastava, Shankar Jha and D. VidyasagarHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

After recovery of uranium from its low grade ore, nearly 50%of the treated tailings remaining after backfilling in themine, is safely contained in a tailings pond where publicaccesss is limited. The low specific activity tailings withradium-226 content of about 8.5 KBq Kg"1 and other radionu-clides of U-238 series-is a source of technologically en-hanced radiation exposure.

The potential of the tailings pond as a source of radiationexposure has been evaluated. The gamma radiation levelsdirectly in contact with the tailings surface vary from 1.2to 5.5 uGy/hr averaging at 2.4 uGy/hr and those at 1 m abovethe surface range from 1.0 to 4.0 uGy/hr averaging at 2.9uGy/hr. On the peripheral boundary the gamma radiation level1 m above the ground ranges from 0.1 to 2.5 uGy/hr averagingaround 0.5 uGy/hr.

The environmental radon concentrations 1 m above the tail-ings surface range from about 5 to 95 Bq m~3. The impact oftailings pond on radiation exposure at the nearby hamletsappears to be rather small.

24 hour continuous air sampling about 30 m from I stage T.P.for 3 weeks in summer indicated dust concentration range of10 to 150 ug m"3.

5. REAMRKS : 6. STATUS : 7. KEYWORDS :

Inprogress RadiologicalRadonTailings Pond

8. REFERENCES :

Environmental radon and gamma radiation in the vicinity ofuranium mining and ore processing industry, presented atNational Seminar on Radiation, Man and Environment, MysoreUniversity, October 7-9, 1992

122


Shutdown Risk Analysis of an operating 3 - 8Pressurized Heavy Water Reactor PowerPlant


V.V.S.Sanyasi Rao,V. Venkat Raj*, A.K. Babar* and R.K. Saraf*Health Physics Division, BARC,Bombay - 400085

* Reactor Safety Division ,BARC

4. ABSTRACT :

Shutdown state of a reactor though generally believed to be asafe state of the reactor, has the potential for accidentsbecause redundancies in safety systems are affected due topreventive maintenance. Actuation of safety systems may alsoinvolve operator intervention in shutdown state. To study theeffect of these system configurational changes, a shutdownrisk analysis of an operating pressurized heavy water reactorhas been initiated. The objectives of this study are

i) To obtain estimate of the contribution of postulatedaccident sequences, in shutdown state, to core damagefrequency

ii) Identification of critical human actions called forvarious accident sequences in the shutdown state and

iii) Development of appropriate and adequate procedures tomitigate the effects of dominating accident sequences.

The dominating IEs identified as potential contributors tocore damage frequency under shutdown conditions are asfollowsi) Grid Power Supply Failureii) Loss Of Coolant Accidentiii) Reactivity Transients andiv) Process water failure

The various accident sequences that result from these IEs arebriefly discussed in this paper. In addition, the potentialaccident sequence during " Header Level Control1 operation,which is carried out when the maintenance of pumps & valvesin the primary heat transport system is undertaken duringshutdown, is also discussed.

5. REMARKS: 6. STATUS:

Completed

7. KEYWORDS:

Shutdown riskInitiating eventsAccident sequencesHeader level control

8. REFERENCES:

Shutdown Risk Analysis of an Operating Pressurized Heavywater Reactor Power Plant, V.Venkat Raj, A.K.Babar,R.K.Saraf, V.V.S.Sanyasi Rao, IAEA TCM on Modeling of Acci-dent sequences During Shutdown andStockholm, Nov 30 - Dec 3,1992

Low Power conditions,

123


Radon and Radiation Dose Evaluation 3 - 9in Jaduguda and Bhatin U Mines


A.H. Khan, Shankar Jha, D. Vidyasagar and G.K. SrivastavaHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

Radon and gamma radiation are measured in different loca-tions of the uranium mine to evaluate the status of workingenvironment, compliance to derived limits and estimation ofeffective dose both internal and external. Monitoring forradon is given more emphasis as over 75% of the total doseto workers in underground U mines is contributed by radondaughters.

The equivalent radon concentrations in Jaduguda uranium mineduring the last five years have averaged around 0.55 KBq m"3

and the gamma radiation has been in the range of 0.10 to10.0 uGy/hr averaging around 4.0 uGy/hr. The measured effec-tive dose to Jaduguda mine workers during this period aver-aged around 15 mSv/y (occassionally exceeding the pro-posed ICRP-60 dose limit of 20 mSv/y during the lastcouple of years).

The monitoring programme extended to Bhatin uranium mineshowed radon cconcentrations (EER) averaging around 0.6 KBqm"3 and gamma radiation varying from 0.1 to 2.1 uGy/hr. The.average effective dose for Bhatin mine workers in 1992 wasestimated at 14.2 mSv/y.

The study indicates that ventilation will need to be en-hanced/ modified to be well below the average effectivedoses to meet the new limit for individual miners.


Continuing RadonGammaEffective doseUranium miner

8. REFERENCES :

Annual Reports of Health Physics Unit, Jaduguda, from 1988to 1992

124


Minimising Difficulties in 3 - 1 0Clearing Radiological Work Permits

3. AUTHOR/S & ADDRESS :

R.K.Kannan, K.R.Viswambharan, V.Mohan, P.G.Mohandas,K.Venkataramana, B.S.K.Nair, E.Subramani and V.JagannathanModel Quality CircleHealth Physics UnitMadras Atomic Power StationKalpakkam, Tamilnadu - 603 102

4. ABSTRACT :

Model Quality Circle (MQC) members identified 10 work relat-ed problems in their work areas. The problem related todifficulties in clearing Radiological Work Permits duringreactor shutdown periods was selected for analysis andfinding solutions to minimise the difficulties. The detailsof work permits received at the shift Health Physicist'soffice were collected. The details of other works to beperformed by the shift Health Physicists were also collect-ed. After systematic analysis of the data collected feasiblesolutions were identified. The work procedures were reviewedand additional facilities were provided. The report gives abrief account of the above aspects.


The report was Model QCpresented before Radiological workthe steering permitscommittee onDec. 26, 1992

B. REFERENCES :

125


Ground Gamma Dose Rate as an 3 - 1 1Indicator for Initiating CounterMeasures in Offsite Radiation Emergency

3. AUTMOR/S AND ADDRESS :

K.K. Narayanan, Health Physics Division, BARC, BombayT.N. Krishnamurthi, V.K. Gupta, AERB, Bombay

4. ABSTRACT :

In any off-site radiation emergency, radiological parametersthat can be easily measured and interpreted, are used toinitiate various countermeasures in the public domain. Gammadose rate from ground deposited activity serves as areference parameter for initiating protective actions. Theoff-site areas are categorised into three Domains based onground gamma dose rates. A relationship between the groundgamma dose rate as a Derived Intervention Level DID and theIntervention Level (ID of dose to thyroid is established inthis paper for initiating countermeasures such as sheltering,stable iodine administration and evacuation.


Completed CountermeasuresOffsite radiationemergencyProtective actionsDerived intervention1eve1sShelteringStable IodineEvacuation

8. REFERENCES:

Ground Gamma Dose Rate as an Indicator for Initiating CounterMeasures in Offsite Radiation Emergency, K.K. Narayanan, T.N.Krishnamurthi, V.K. Gupta, National Symposium on Emergencypreparedness and Disaster Management (SEMP-93), 1993

126


Radiation Protection at MAPS 3 - 1 2- A Perspective View


V. Mohan, R.S. Vardhan, K. Chudalayandi and N. Parasuram*Health Physics Unit,Madras Atomic Power Station

* NPC, MAPSKALPAKKAM - 603 102

4. ABSTRACT :

The paper discusses the mode and content of radiation pro-tection training course given to various categories ofpersonnel. A brief note on Public Awareness Programme ofwhich radiation protection training is a part, is given.


Radiation protectionTraining

8. REFERENCES :

Radiation Protection at MAPS - A Perspective View, Paperpresented in a Workshop on Human Resources Development onTraining Issues, BARC, Nov. 18-19, 1993

127


Containment of Radioactivity from 3 - 1 3the Liquid Effluent of New ThoriumPlant of IRE Ltd., OSCOM, Orissa


S.C. SahaHealth Physics Unit, IRE Ltd, OSCOMOrissa

4. ABSTRACT :

Liquid effluent generated from the operation of the NewThorium Plant was found to contain gross alpha and betaactivity higher than the discahrge limit. Hence studies werecarried out for chemical precipitation of the radioactivitycontent (due to presence of U, Th and their daughters). Theeffluents were treated with spent acid (containing 50-60 gplof Fe and 5-8% of HCL) which is the waste from the SyntheticRutile Plant of OSCOM. Studies were repeated with solutionof FeCl3 and FeSO4 etc. An extraction efficiency of morethan 90% was achieved when effluents were treated with abovesolution at a concentration of 200-500 ppm of Fe at 10 pH.Iron hydroxide precipitated out more than 90% of the grossalpha and gross beta activity from the effluent into solidphase, the resulting effluent after filtration could bedirectly discharged to the environment.

S. REMARKS : 6. STATUS : 7. KEYWORDS :

• Completed Liquid effluentGross alphaGross betaSpent acidExtraction efficiency

8. REFERENCES :

128


Characterisation of Aerosols 3-14Generated during MineralSeparation at IRE, OSCOM

3. AUTHOK/S AND ADDRESS :

S.C. SanaHealth Physics Unit, IRE Ltd, OSCOMOrissa

4. ABSTRACT :

IRE has set up Orissa Sands Complex (OSCOM) to separateminerals from beach sand by utilising difference in physicalproperties - mainly electrical conductivity, magnetic sus-ceptibility, surface characteristics, specific gravity andair tabling. Because of presence of Thorium and Uranium inmineral dusts, mineral separation give rise to radiologicalhazards in addition to conventional hazards. Studies wereundertaken to evaluate the AMAD, MMAD, CMAD and CMD andshape factors of these aerosols generated during mineralseparation. It is found that the average AMAD of aerosols isabout (4.2 + 1.2)um. Taking into account all the character-istics of aerosols measured, derived air concentration (DAC)have been computed. Concentration of 0.1 Bqm"3 alpha activi-ty has been adopted as derived air concentration for airborne dust at OSCOM.


Completed Beach sandMineral separationAMAD, MMAD, CMAD, CMD

Shape factorDerived air

concentration

8. REFERENCES :

129


Tritium in Air at MAPS - 3 - 1 5A Profile of Tritium DAC andStack Release in 1992


V.Mohan, N.Kalyanasundaram and K.ChudalayandiHealth Physics UnitMadras Atomic Power StationKalpakkam, Tamilnadu - 603 102

4. ABSTRACT :

Tritium in Air Profiles in RB-1 and RB-2 of MAPS were stud-ied first in 1991. The DAC and release trends were objec-tively analysed under reactor operation and shutdown condi-tions in the year 1992. In this report, the features high-lighted are that RB-1 was having higher ambient DAC comparedto RB-2. During operation and shutdown, RB-1 released triti-um to environment at the rate of 1.5 to 3 times higher thanthose of RB-2. Compared to 1991, the average DAC and releaserates show enhanced trend in RB-1 by a factor of 1.5. ForRB-2, the yearly average DAC has remained more or less sametin 1991 and 1992. The overall analysis suggests that RB-2exhibits consistent and better containment and releasebehaviour compared to RB-1.

5. REMARKS : 6. STATUS : 7. KEYWORDS :TritiumDACStack release

8. REFERENCES

130


Estimation of Dose Rate Profiles 3 - 1 6on the Calandria Tube and PressureTubes of T-ll Channel of MAPS-2


V. Mohan, P. Ayappan*, B.S.K. Nair,S. Venkatraman and K. ChudalayandiHealth Physics UnitMadras Atomic Power StationKALPAKKAM - 603 102

* TLD Lab., MAPS

4. ABSTRACT i

Dose Rate profiles of calandria tube and coolant tube re-moved from T-ll lattice position were estimated using TLDs.Contact dose rate on the tubes were also estimated by graph-ical extrapolation. This method of estimation of contactdose rate was used in 1991 while T- 10 channel calandriatube and coolant tubes were removed. This method is usefulas there is no suitable instrumentation available at MAPS tomeasure contact dose- rate of "very hot* materials < >1000 R/h).

5. REMARKS i 6. STATUS i 7. KEYWORDS :

Completed Dose rate profileCoolant TubeCalandria tube

8. REFERENCES t

131


Derived Working Levels for 3 - 1 7

Surface Contamination

3.AUTHOR/S AMD ADDRESS :

S. KrishnamonyHealth Physics Division, BA2CBOMBAY - 400 085

4. ABSTRACT :Radio-active contamination on surfaces of floors and equip-ment as well as that on the skin and hands of workers and onthe protective clothing they wear, can result in externalexposure and/or internal exposure on account of the possi-bility of ingestion or inhalation of radio-active materialor absorption through skin. Derived Working Levels forsurface contamination have been worked out based on theradiation protection standards prescribed in ICRP-26 and theAnnual Limit of intake values recommended in ICRP-30 takinginto consideration all the likely routes of exposure. Themost restrictive value is recommended for practical controlpurposes. Values have been given for commonly encounteredalpha and beta emitting radio-nuclides as well as a table ofvalues for general application.

5. REMARKS t 6. STATUS : 7. KEYWORDS :

Completed Surface contaminationICRPRadiation protectionProtective clothing

8. REFERENCES :

Derived Working Levels for Surface Contamination, S.Krishna-mony, BARC Report, BARC/I-1012, 1990

132


An Approach to the Derivation of 3 - 1 8Authorised Limits for RadioactiveEffluents from Nuclear Facilities


K.K. Narayanan, S. Krishnamony and K.C. PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A more rigorous and systematic approach for establishing theauthorised limit for radioactive effluents from nuclearfacilities is employed by apportioning the EDL of 1 mSv/yamong facilities in operation and for those planned, as wellas for the exposure pathways. Specific apportionment ismade for nuclides of significance based on the nature ofoperation, their likely abundance in the effluent and radio-logical significance. This approach enables the operator toconform to limit* prescribed and to obtain feed back fromenvironmental monitoring results.

5. REMARKS > 6. STATUS : 7. KEYWORDS t

Completed Radioactive effluentsEnvironmental

monitoring

8. REFERENCES :

An Approach to the Derivation of Authorised Limits forRadioactive Effluents from Nuclear Facilities, K.K. Naraya-nan, S. Krishnamony and K.C. Pillai, National Symposium onEnvironment, Scientific Approach to Environmental Issues,BARC, Bombay, pp 115-117, February 3-5, 1992

133

1. TITLE : 2. CATEGORY :i

Laboratory Investigations for the 3 - 1 9Assessment of Inhalation HazardsAssociated with the Handling ofRadioactive Solutions


R.C. Purwar and S. KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

A. ABSTRACT :

Air-borne activity likely to occur while handling radioac-tive solutions was assessed by conducting laboratory experi-ments in which air was bubbled through solutions of knownspecific activity at different rates, since air is commonlyused in radio-chemical operations for level determination,sparging etc. Entrainment coefficients obtained for differ-ent bubbling rates are presented. An approximate linearrelationship was found to exist between air-borne activityand bubbling rate. The results also indicated that opera-tions giving rise to disturbances in plutonium solution at aconcentration of approximately 100 MBq m~3 can be expectedto result in air-borne activity in the range 10-20 DAC andactivity concentration of approximately 5 GBq m"3 can giverise to air-borne activity of 50-100 DAC.

5. REMARKS t 6. STATUS : 7. KEYWORDS :»

Completed Inhalation hazardsPlutonium

8. REFERENCES t

Laboratory Investigations for the Assessment of InhalationHazards Associated with the Handling of Radioactive Solu-tions, R.C. Purwar and S. Krishnamony, Bulletin of RadiationProtection, Vol. 13, Nos. 3&4, pp 45-47, December, 1990

134


Radiological Measurements and 3 - 2 0Experience during Commissioningand Early Power Operation ofNarora Atomic Power Station


M.L. Joshi, Lalchand, H.C. Tiwari, S. Krishnamony,B.M.L. Sah , K.C. PillaiHealth Physics Division, BARCBOMBAY - 400 085

* HP Group, NPCIL, Bombay-400 094

4. ABSTRACT :

This paper details the experience with respect to radiationprotection aspects during commissioning and early poweroperation of NAPP-1. The ambient levels in reactor buildingaccessible areas were higher than the design value. Neutronfield was also observed in some locations which were notobserved in earlier PHWRs. Inadequate shielding arrange-ments, some deficiencies in penetrations were the mainreasons for the increased gamma dose rate. The reason fornsutron field in these areas was the design of verticalmovement of fuelling machine which resulted in neutronleakage from F/M vault to F/M maintenance area.

Another radiological aspect observed at NAPP but not seen inother PHWRs was the presence of higher radiation field dueto Co-60 in the moderator system. A higher buildup thanexpected of H-3 activity in the calandria vault coolingsystem was observed.

Environmental releases have been below the technical speci-fication limits for both gaseous and liquid effluents.Occupational dose has been low, primarily due to absence ofAr-41. This shows that the initial experience at NAPP inrespect of radiation protection has been a mixed one.

5. REMARKS < 6. STATUS : 7. KEYWORDS :

Completed NAPPRadiation ProtectionShieldingDoseExposure

8. REFERENCES :

135


Radiological Measurements Following 3 - 2 1a Heavy Water Spill at Madras AtomicPower Station


K. Chudalayandi, R.X. Kannan, R.S. Vardhan andS. KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

On March 5, 1991, heavy water from moderator system ofMAPS-1 escaped from the north stiffener ring cooling lineflow element: Temperory blanking of the leak and recovery ofspilled D2O was' done on the next day. But on 7th, whenefforts were made to remove the blank and rectify the leak,D2O started leaking again. Finally the flow element wasremoved, rectified and reinstalled. The high DAC of tritiumin moderator room (max. value 3225 DAC on March 5) wasbrought down by purging the tritium-laden air through the RBexhaust system. Totally 847 Kg of D2O escaped from themoderator system, out of which 350 Kg was recovered frommoderator room, 22 Kg transferred to CWMF, 449 Kg releasedthrough stack and 26 Kg discharged to sea. Among the 68people engaged in the job, the maximum dose was 37.6 mSv,and the total dose was 0.228 person-Sv.

Detailed studies were conducted to evaluate tritium elimi-nation patterns subsequent to high uptakes, and the protec-tion factors of different plastic suits available in- thestation. No long lived biological component was observed inthe tritium elimination studies. Also, protection factors of100-300 can be provided by ventilated plastic suits.

5. REMARKS : 6. STATUS : 7. KEYWORDS :t

Completed MAPSHeavy waterTritiumProtection factors

8. REFERENCES :

136


Health Physics Aspects of 3 - 2 2Refuelling a BWR


R.G. Purohit, S.A. Sukhesawalla and S. KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Observations show that about one-half of the total occupa-tional exposure at TAPS occurs during unit operation andshort-term forced outages, and the rest during the refuell-ing shutdowns. In the latter phase, the main jobs undertakenare (i) activities connected with opening and closing ofreactor vessel head (ii) removal, reconditioning and re-placement of control rod drives (iii) instrumentation andcabling works in the drywell (iv) maintenance of sump-pumps,pumps, valves and motors in the dry-well (v) reconditioningand replacement of reactor safety/relief and isolationvalves and (vi) in-service inspection and replacement ofaged equipment.

During the 10th refuelling outage of Unit-I in 1987, removaland replacement of feed water sparger of the reactor wascarried out. The work lasted for about 9 months, and depart-mental and contractor's manpower numbering 1500 consumed 7.5person-reins.

Individual maintenance activities show reduction in collec-tive dose, almost by a factor of two after the tenth ref-uelling shutdown. Some of the reasons for this are : Im-proved fuel performance, isolation of SSGs, discharge ofclean-up spent resin to underground storage tank, replace-ment of asbestos insulation with mirror insulation, andstation dose budgeting and setting up. of ALARA committee.Collective dose at TAPS has thus been showing a downwardtrend.


Completed RefuellingBWRRadiation ProtectionDoseSparger

8. REFERENCES :

137

4. SITE EVALUATION STUDIES


Impact Evaluation Program for 4 - 1Toxic Gas releases at HWPs

3. AUTHOR\S AND ADDRESS :V.N.BapatHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Heavy water plants based on H£S steam exchange deal with alarge quantity of H2S which is a toxic gas. In such installa-tions apart from routine process releases of H2S or possibil-ity of unplanned incidences are likely to lead to largeleakage of H2S.

A computer program which can give the concentration distribu-tion in and around this plant area is developed. This cangenerate concentration distribution for planned or accidentalreleases and graphically identifying the area affected whichwould help to carry out the emergency management plan. Thisprogram can also identify the source as well as quantity thesource term and effective wind direction from the data avail-able from field survey instruments and would lead to morerealistics impact evaluations.

5. REMARKS : 6. STATUS : 7. KEYWORD :

Completed Effluent managementComputer software

8. REFERENCE :

Impact Evaluation Program for Toxic Gas Releases atHWPs,V.N.Bapat,BARC Report, BARC/I-005,1991

138


Effluent management in Nuclear 4 - 2Industry


V.N.Bapat and T.M. KrishnamoorthyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Any industry which releases effluents to Atmosphere or hydro-sphere has to have a plan for management of its effluents.Various effluents released through various plants of NuclearIndustry as a whole are identified. Various methodologies andmodels used for estimating the concentration distribution andsteps taken to keep the levels of these effluents to a lowlevel compared to the Ambient Air Quality standards as wellas other standards recommended by ICRP for radioactive efflu-ents are discussed.


Completed Effluent management

8. REFERENCE :

Effluent Management in Nuclear Industry, V.N.Bapat &T.M.Krishnamoorthy, National Symposium on Environment, Feb 3-5, Bombay, 1992

139


Migration of Radionuclides from a 4 - 3Granite Repository


T.M.Krishnamoorthy, R.N.Nair and T.P.SarmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Migration of radionuclides in the fracture of a host rockmatrix surrounding a high-level waste repository is dis-cussed in terms of two coupled one-dimensional equations,one for the fracture and the other for the porous rockmatrix. The temporal and spatial distribution of concentr-aions and flux for some typical radionuclides has beencomputed using two- component leaching from the waste matrixand budgeting the total inventory. It is obsereved that theconcentration of Sr-90 and Pu-239 markedly decreases withdistance along the fracture. However, either traval time orsorption do not present enouogh delay for significant decayof 1-129 in fracture water.


Completed Waste management

8. REFERENCE:

Migration of Radionuclides from a Granite Repository,T.M.Krishanmoorthy, R.N.Nair and T.P.Sarma, Water Resour.Res., 28, pp 1927-1934, 1992

140

1. TITLE i • • 2. CATEGORY :

Radionuclide Migration from 4 - 4Shallow Land Burial Facilities

3. AUTHOR/S AMD ADDRESS t

T.M. Krishnainoorthy 'Health Physics Division, BARC,BOMBAY - 400 085

4. ABSTRACT : *

Temporal and spatial distribution of radionuclides in groundwater, commonly encountered in low level solid radioactivewastes is discussed in relation to discharge modules, typeof aquifers, waste composition and parameters employed.

5. REMARKS i 6. STATUS : 7. KEYWORDS t

Completed Radionuclidemigration

Land burialTemporalSpatial distribution

8. REFERENCES :

Radionuclide Migration from Shallow Land Burial Faciities,T.M.Krishnainoorthy, Seminar on Transport and dispersion inaquatic and atmospheric media , IGCAR, Kalpakkam, 1992

141


Radiotracer study of the disper- 4 - 5sion of sewage off Bombay coast

3. AUTHORS AND ADDRESS :

R.N.Nair and T.M.KrishnamoorthyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A suitable advection dispersion model has been used tostimulate the spatial and temporal distribution of a radio-tracer (Br-82) which is injected through the sewage pipeline at Colaba. The experimental and simulated resultsfairly match for the characteristic hydrological parameters.


Completed Dispersion

8. REFERENCE :

Radiotracer Study of the Dispersion of Sewage off BombayCoast, R.N.Nair and T.M.Krishanmoorthy, Proc. 2nd Nat. Symp.on Environment, 163-166, 1993

142


Nomograms for Evaluation of Stack 4 - 6Design Parameters from Air QualityConsideration


V.J.Daoo, V.N. Bapat and T.M.KrishnamoorthyHealth Physics Division, BARC,BOMBAY - 400. 085

4. ABSTRACT :

Methodology to evaluate stack design parameters from ait-quality considerations is described and the results arepresented in the form of Nomograms for quick and reasonablyaccurate estimates of the parameters. Basic concept of themethodology relies on the optimision of effective releaseheight of the effluent so as to maintain the maximum groundlevel concentration(GLC) within a desired distance.DoubleGaussian model for plume rise estimation are used. TheNomograms presented are in the form of graphs which whenused in succession starting from known maximum concentrationand its downwind distance of occurrence gives estimates ofphysical stack height, heat emmission rate, volume flow rateand stack top radious.

5. REMARKS t 6. STATUS 7. KEYWORD:

Completed Air qualityStack design

parameters

8. REFERENCES :

Nomograms for Evaluation of Stack Design Parameters from AirQuality Considerations, V.J.Daoo, V.N. Bapat and T.M.Krish-namoorthy, Proc.2nd National Symposium on Environment,Jodhpur, pp 89-92, 1993

143


Radiological Evaluation of U Ore 4 - 7Deposit and Test Recovery Plant atDomiasiat, Meghalaya


A.H. Khan, P.M. Markose and S. KrishnamonyHealth Physics Unit, UCIL, Jaduguda

4. ABSTRACT :

Preoperational radiological evaluation has been carried outnear the ore deposit of realtively elevated grade . uraniumat Domiasiat (Meghalaya) and at the Test Uranium RecoveryPlant operated by AMD/DAE at the site. The background gammaradiation levels in the region varied from 0.04 to 0.12uGy/hr whereas on the ore deposit site it varied from 0.1 to0.5 uGy/hr and at a few out- crop locations it ranged from2/0 to 8.0 uGy/hr. The gamma radiation levels in the testuranium recovery plant generally ranged from 0.1 to 0.6uGy/hr with a couple of ore handling locations showing 2.5to 15.0 uGy/hr.

Recommendations have been made for safe management of thetailings. Analysis of water samples from 8 nearby riversindicated pre-operational dissolved uranium content general-ly below 3 mg m"3 with only one sample showing 19 mg m~3.The background levels of dissolved radium-226 was generallybelow 60 Bq m~3, except one river which showed concentra-tions ranging from 230 to 768 Bq m"3.

The site being near Cherapunji has annual rainfall averagingaround 8000 mm with thick forest but very thin population.

5. REMARKS.: 6. STATUS : 7. KEYWORDS :

In progress DomiasiatUranium ore depositTest Recovery PlantBackground radiation

8. REFERENCES t

Radiological survey of Uranium Test Recovery Plant, MT LabAMD/DAE, Domiasiat, West Khasi Hills (Meghalaya), A.H.Khan, Report submitted to AMD/DAE

144

5. MICKOMBTBOROLOGY

1. TITLE s 2. CATEGORY :

Solar UV Radiation Measurements 5 - 1at Bombay


V.J.Daoo ,Faby Sunny and V.V.Shirvaikar *Health Physics Division,BARCBOMBAY - 400 085

* Nuclear Power Corpn,World Trade Centre, Tower 1,Colaba,Bombay-400 005

4. ABSTRACT :

Measurements of Solar UV radiation (UVR) concurrent withglobal solar radiation (GSR) at Bombay during 1986-87 arereported. Annual and diurnal trends in the UVR and its ratiowith the GSR are examined with respect to prevailing atmos-pheric conditions in the region. Prevalence of overcast andlow dust content conditions can affect the variation consid-erably.


Completed Solar UV radiationGlobal solar radiation

8. REFERENCE t

Solar UV Radiations Measurement at Bombay, V.J.Daoo, FabySunny and V.V.Shirvaikar, Indian Journal of Pure and AppliedPhysics, Vol.29,71-72, 1991

145


Effects of Time Dependent Invers- 5 - 2ion on Concentration Distributionof Atmospheric Effluents


V.N.Bapat and V.J.DaooHealth Physics Division, BARCBOMBAY - 400 08 5

4. ABSTRACT :

Formation of inversion boundary layer plays a vital role inthe concentration distribution of the atmospheric effluents.The data on variation of inversion layer throughout the dayis rarely available and its elevation depends on weathercategory existing in the day. It is thought that inversionalways leads to increase in concentration. However, this isnot necessarily so. This has been broughtout clearly in thispaper giving the default values of minimum inversion heightto be used and their effect on concentrtion distribution withdownwind distnace and category.


Completed Atmospheric disper-sionInversion layer

8. REFERENCE :

Effects of Time Dependent Inversion on Concentration Distri-bution of Atmospheric Effluents,V.N.Bapat and V.J.Daoo,Bulletin of Radiation Protection, Vol. 15, pp 15-17,1992

146


Solar UV Irradiance and some Bio- 5 - 3logical Consequences: Bombay-India


V.J.DaooHealth Physics Division, BA.RCBOMBAY - 400 08 5 • '•

4. ABSTRACT :

Measurements of Solar UV radiation (UVR) at Bombay wererecorded using Epplay UV radiometer for a 2 year period(1986-87). The consequences of Solar UVR and its projectedincrease are discussed with special reference to its biologi-cal effects and results of UVR on experimental animal systemvis a vis epidemiological data in its Indian context.


Completed Solar UV radiationBiological conse-quence

8. REFERENCE :

Solar UV Radiationand and some Biological Consequences:Bombay, India, V.S.Bamane et al.,The Science of total envi-ronment, 121, pp 195-201, 1992

147


A Study on the Relationship between 5 - 4Incoming Solar Radiation andCloud Cover.


V.J.DaooHealth Physics Division, BARCBOMBAY - 444 085

4. ABSTRACT :

This study presents an empirical relationship between theincoming solar uv radiation and concurrently measured cloudcover at Bombay based on data pertaining to two year (1986-87} .period. It is compared with a similar relationship usedelsewhere and found to differ in its form as well as in thrregression coefficients. Possible reasons for this discrepan-cy are discussed. Conditions under which the two relation-ships agree are examined.


Completed Solar UV radiationCloud cover

8. REFERENCE:

A Study on the Relationship between Incoming Solar UV Radia-tion and Cloud Cover, V.J. Daoo, Proc. of IRPA 8 Congress,Montreal, Canada, Vol. I, 787-789, 1992

148


Onset Characteristics of Land/Sea 5 - 5Breeze Circulation and Its Effecton>Meteorological Parameters at aCoastal Site


N.S.PanchalHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

This study discusses the climatological characteristics ofsen breeze systems and their influence on meteorologicalparameters at Kalpakkam, Madras Atomic Power Project site onthe east coast of India. Continuous data recorded at themeteorological laboratory at the site is used in the study.The change in the characteristics of the parameters wasmainly governed by the onset time of sea/land flow. Thechange is more significant during the onset of sea breeze.Analysis of the data revealed that the change was due toadvection and the regular diurnal variation of the parame-ters. Based on the variation in upper winds both the season-al change in onset time for sea/land flows and its influenceon meteorological parametrs are discussed and explainedqualitatively. The relative role of advection and diurnalvariation of the parameters on the observed changes are alsodiscussed.


Completed Sea breeze

8. REFERENCE :

Onset Characteristics of Land/Sea Breeze Circulation and ItsEffect on Meteorological Paramters at a Coastal Site,N.S.Panchal, Atmosfera, 6, pp 155-162, 1993

149


A Comparative Study of Annual 5 - 6Atmospheric Dispersion Factors atdifferent Reactor Sites in India

3. AUTHORSS AND ADDRESS :

V.J.Daoo, B.B.Adiga,R.P Gurg,E.Chandrasekhran,L.N.Sharma and T.M.KrishnamoorthyHealth Physics Division, BARCBOMBAY - 444 085

4. ABSTRACT :

A three year (1987-1989) averaged annual atmospheric Disper-sion factor' for five Indian reactor sites viz, Trombay,TAPS,RAPS,MAPS and NAPS has been evaluated at 1.6 km downwinddistance from the source, using site meteorological data andexamined for its site specific nature and directional depend-ence. A site average value of the sector weighted factor (thevalue averaged over 16 directions of comapss) over allfive sites (having topographic features comparable) consid-ered in the study, is arrived at.


Completed Atmospheric dispersionfactor,Reactor sites

8. REFERENCE:

A Comparative Study of Annual Atmospheric Dispersion Factorsat different Sites in India. V.J.Daoo et al. Bulletin ofRadia. Protect., Vol 16, No. 182, pp 59-61, 1993

150


A Study on Estimation of Surface 5 - 7.Fluxes & Atmospheric Stabilityat Trombay


V.J.Daoo, Faby Sunny and V.SitaramanHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The study estimates the surface fluxes and atmospheric sta-bility from solar elevation angle and weather data on cloudcover, air temperature and wind speed measured routinely atTrombay using on the procedure based on standard surface ofthe estimated fluxes were compared with field measurements atTrombay. Certain empirical relationships involved in .theprocedure are found to be site specific which are modifiedbased on the field measurements.


Completed Surface fluxesAtmospheric Stability

8. REFERENCE :

151


Return Period of Moderate and 5 - 8Severe Drought over various Partsof India


V.AbrolHealth Physics Division, BARCBOMBAY - 400 08 5 •

4. ABSTRACT :

Extreme value analysis by Gumbel's method is carried outover 115 years long time series of rainfall data for 29meteorological subdivisions covering India. Return periods ofmeteorological droughts of severe and moderate intensitiesoccurring over one and consequtive two and three years areestimated and tabulated. These estimated return periods arefurther narrowed down to values of 95% confidence level by asuitable technique*.


Completed DroughtReturn periods

8. REFERENCE :

Return Period of Moderate and Severe Drought over variousParts of India, V.Abrol., Irrigation and Power Journal (inpress)

152

1. TITLE :

Progress Report of EnvironmentalSurvey & Micrometeorology LaboratoryNarora Atomic Power Station for theyear 1989

2. CATEGORY :

5 - 9


L.N. Sharma, P.C. Verma, B. Dube, M.S. Balagurunathan,Suma Nair, M. Kumar, S. Sitaraman, P. Sundara Rajan,Avinash Kumar, D.C. Garg, B.M.L. Sah and K.C. PillaiHealth Physics Division, BARCBombay 400 085

4. ABSTRACT :

Environmental surveillance and micrometeorological workcarried out by the Environmental Survey andMicrometeorological Laboratory, Narora Atomic Power Station(NAPS) during the year 1989 is reported. To monitor theconsequence of different radionuclides in atmospheric,aquatic and terrestrial environment of NAPS, a total numberof 1065 samples were collected at various locations aroundNAPS. Wind speed, ambient air temperature, relativehumidity, solar radiation and rain fall were measured oncontinuous basis. The data are given. Annual atmosphericdilution factors for stack release were computed fordifferent distances in different directions and isoplethsdrawn.

5. REMARKS : 6.

Completed

7. KEYWORDS :

Narora-I & IIReator siteEnvironment RadiationMonitoringStack disposalEnvironmental impactsRadiation doses

8. REFERENCES :

Progress Report of Environmental Survey and MicrometeorologyLaboratory, Narora Atomic Power Station, for the year 1989,L.N. Sharma., P.C. Verma, B. Dube, M.R. Balagurunathan, SumaNair, M. Kumar, S. Sitaraman, P. Sundara Rajan, AvinashKumar, D.C. Garg, B.M.L. Sah and K.C. PillaiBARC Report No.BARC/I-1015, 1990

153

6 . INSTRUMENTS & TECHNIQUES


A Bulk Counting System Based on 6 - 1Gamma Ray Spectrometry


S. R. Rao and V.S. LondheHealth Physics Division, BARCBOMBAY - 400 085 .

4. ABSTRACT :

The presence of extremely small quantities of radioisotopesin environmental samples necessitates the handling of largersamples for better overall signal response and hence, in-creases the reliability of the results. A bulk countingsystem based on Gamma Spectrometry was therefore installedat the basement of low level counting laboratory, BARCHospital. It consists of a Nal(Tl) Scintillation detector20 cm dia and 10 cm thick integral assembly (Bicron make)well shielded from outside radiation with 15 cm thick castiron at top and bottom and 10 cm of lead sideways. A trolleyarrangement is provided for closing and opening of the topshield. This facilitates the placement and removal of thebulk sample from the detector face. The free space insidethe shielding is 55 cm x 45.5 cm and 61 cm in height whichis sufficient to keep back-scattering to the minimum. Sampleis contained in a specially made polyvinyl chloride samplebox with tight fitting lid with sample height of 2 cm andinside diameter matching exactly with the diameter of thescintillator. Standards are also compared in the samegeometry. For environmental samples the counting time ismaintained at 60000 seconds. The characteristics of the bulksample counter are given in the paper. A wide variety ofmaterials such as soil, sediments, salt building mate-rials,milk powder, food materials, fertilizers, fossil coalfly ash etc. have been counted using bulk Material counter.


Environmental samplesGamma Counter

8. REFERENCES :

i) Low Level Radioactivity Measurements Using GAmma RaySpectrometry, Rao S.R., Londhe V.S. and Pillai K.C., Bull.of Radiat. Prot., Vol.6, No.2, pp 33-41, 1983

ii) Assessment of Natural Radioactivity Levels in BuildingMaterials and Evaluation of Indoor Radiation Exposure,Londhe V.S., Rao S.R. and Pillai K.C., Environmental Tech-nology Letters, Vol. 5, 1984

154


Development arid use of a Continuous 6 - 2Radon Monitor and an Instant WorkingLevel Meter


A.H. Khan, Shankar Jha and M. RaghavayyaHealth Physics Unit, Jaduguda,Health Physics Division, BARC

4. ABSTRACT :

A continuous radon monitor having a 600 ml perforatedcylindrical chamber with a negative charge plate at thebottom and an alpha counting system at the top with amicroprocessor for recording hourly readings has beendeveloped. The instrument has been in use at Jaduguda forstudying temporal variations in atmospheric radon.

An instant radon progeny working level meter has also beendeveloped with a programmed sampling and countingsimultaneously. A microprocessor attached to the countingsystem records the counts for 2, 5 and 10 min durations anddisplays the alpha counts as well as the concentrations interms of WL. The results can be displayed again until thesystem is reset. The minimum detection limit for a 1.9 lpmsampling rate and total sampling/counting duration of 13 minis 3 mWL. The instrument has been used in Jaduguda mine. Itmay be slightly modified to reduce the size and weight foreasy portability in mines.


Completed Continuous radonmonitorInstant WL meterTemporal variationRadon progeny

8. REFERENCES :

Development of a Continuous Radon Monitor and Instant WLMeter, A.H. Khan, M. Raghavayya, D.N. Sharma, N. Raman, P.S.Jethmalani, G. Krishnamachary and M.R. Iyer., Bull, ofRad.Prot., Vol.12, No.3, 1989

155


A DC Power Vacuum Cryoprogrammer for 6 - 3TSC and the associated TL Measurements.


B.D.BhasinHealth Physics Division, BARCBOMBAY - 400 085

4. ABSRRACT :

In order to optimise the experimental conditions for simulta-neous measurements of TL and TSC it is necessary to usevacuum cryoprogrammer. The usual AC powered strip-heaternormally employed for the TL measurements cannot be used forthe purpose. An insulated type of heater is an essentialrequirement. This requires design modifications for thecryostat programmer and the associated electronics. The papergives details of the design of the cartridge heater and asiding proportional band for the temperature controller andthe factors affecting the thermal time constant are dis-cussed. Finally the results obtained by the system for TLD-100 crystals are shown and discussed.

5. REMARKS : / 6. STATUS : 7. KEYWORDS :

Completed CryprogrammerCryostatTSC/TL

8. REFERENCES :

A DC Power Vacuum Cryoprogrammer for TSC and the associatedTL Measurements, B.D.Bhasin, National Seminar on Thermolumi-nescence and its Applications, M.S.University of Baroda,Baroda, pp 77-82, Feb 7-9,1991

156


Study of Sample-Detector Assemblies 6 - 4for Application to In-SituMeasurement of Radioactivity inLiquid Effluents


K.A. Pendharkar, K. Narayanan Kutty and S. KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

this paper descibes the experimental investigations carriedout on four different types of sample-detector assemblieswith a view to determining their detection limits and rela-tive merits for application to in-situ measurement of radio-activity in liquid effluents. The four systems studied were(i) gamma detection using 11 cm x 8 cm Nal (Tl) scintilla-tion detector inserted in the cavity of a specially designedstainless steel chamber of capacity 15 litres (ii) gammadetection using a metal-walled G.M. counter in a similarmanner (iii) beta detection using twin thin-walled G.M.counters immersed in liquid and (iv) end window G.M. counterpositioned above the liquid surface in a shallow tray. Thedesign features of an in-line monitor employing a 11 cm x 8cm Hal (Tl) detector used for the routine monitoring of betagamma activity concentrations in the low level effluents ofthe Tarapur Fuel Processing Plant are described.


Completed Liquid effluents

8. REFERENCES :

Study of Sample-Detector Assemblies for Application to In-Situ Measurement of Radioactivity in Liquid Effluents, K.A.Pendharkar, K. Narayanan Kutty and S. Krishnamony, Bulletinof Radiation Protection, Vol. 14, Nos. 3&4, pp 24-26, July-December, 1991

157

1. TITLE : 2. CATEGORY ;

Standardisation and Comparison of 6 - 5Quench Indicating Parameters inModern Liquid Scintillation Analysis


D.D. Rao, S. Chandramouli, A.G. HegdeEnvironmental Survey LaboratoryTARAPUR - 40l*'504

4. ABSTRACT :

In the liquid scintillation analysis interferences likequenching, chemiluminescence, variation in background,sample volumes and scintillator affect the measurementconsiderably. A study was carried out to verify the validityof Quench Indicating Parameter (QIP) like Spectral Index ofSamples (SIS) and Sample Channel Ratio (SCR) and also theeffect of variation of sample volume and scintillator. Itwas found that the QIP, SIS and SCR are not usable in verylow active samples ( < 1 Bq/ 3 ml).


Completed Liquid scintillationQuench indicating

parameter

8. REFERENCES t

Standardisation and Comparison of Quench Indicating Parame-ters in Modern Liquid Scintillation Analysis, Bulletin ofRadiation Protection, Vol 15, No.l, pp 57-59, Jan - March,1992

158


A Sensitive Method for Prompt 6 - 6Measurement of Low Levels ofAirborne Plutonium


K.A. Pendharkar, M.D. Deshpande and S. KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Detection of low level plutonium aerosols in the workingenvironment is complicated by the interference of short-lived radon and thoron daughters that can be present to theextent of 10 to 100 times the Derived Air Concentration ofair-borne plutonium. Methods such as delayed counting andparticle size selective sampling technique can be employedto overcome the problem. The latter technique uses annularkinetic impactor to take advantage of the higher activitymedian aerodynamic diameter of plutonium particles. A tech-nique which combines both the above methods offers scope fordetecting low level of plutonium in air. This method isespecially useful in situations where thoron concentrationsare significant since the relatively long life of thorondaughters (106 hrs) does not provide delayed counting tech-nique to be used in practice for reasonably prompt assess-ment of plutonium air-borne concentration.


Completed Airborne plutonium' Thoron

8. REFERENCES :

A Sensitive Method for Prompt Measurement of Low Levels ofAirborne Plutonium, K.A. Pendharkar, M.D. Deshpande and S.Krishnamony, Bulletin of Radiation Protection, Vol. 15,No.l, IARP 19/27 pp 60-62, January-March, 1992

159


C-14 Emission from Nuclear 6 - 7Reactors and Techniques for itsMeasurements-A Review


G.R.Doshi and T.M.KrishnamoorthyHealth Physics Division, BARCBOMBAY - 400 08 5 •

4. ABSTRACT :

The mode, the amount of C-14 production and the physi-cochemical forms of releases from different types of nuclearinstallations are discussed. Different types of physical andchemical methods currently employed for its estimations indifferent system samples viz. primary water/coolant, heavywater- moderator, stack effluents, solid samples like swipeor aerosol filter samples are described in detail along withthe steps needed to purify these samples from the accompany-ing fission and activation products. Methods for the estima-tion of reduced forms present in liquid and stack effluentsare also given. A discussion on lower Detection Limit (LDL)of various techniques gives a guideline for employing aparticular type of method with reference to its concentra-tion present in the sample.

5. REMARKS : 6. STATUS : 7. KEYWORDS

Completed

8. REFERENCE :

C-14 Emission from Nuclear Reactors and Techniques for itsMeasurements-A review, G.R.Doshi and T.M.Krisnamoorthy,Bulletin of Radiation Protection, Vol 15, No 2, pp 1-8, 1992

160


Calibration for Efficiency 6 - 8Determination of GM Gas FlowDetector for Measurement ofYttrium-90


S. Venkataraman and M.A.R. IyengarEnvironmental Survey LaboratoryHealth Physics Division, BARCKalpakkam - 603 102

4. ABSTRACT :

In environmental measurement counting of beta activity ofdifferent radionuclide such as Sr-90 + Y-90, Cs-137, 1-131etc. in low background GM gas flow beta counting system isgenerally done using efficiency of K-40 beta source <~ 40%}.This may not led to a correct estimation of the specificradionuclide counted, since K-40 beta energy (1.23 Mev E max)is different from other radionuclides like Sr-90 <0.54 Mev Emax) and Y-90 (2.27 Mev E max), Cs-137 (0.51 Mev E max) for adetermination of radionuclides like Y-90, in Sr-90estimation, it is more appropriate to have the same Y-90standard source similar to sample geometry form acquiredestimation. With this in view Y-90 standard source ofdifferent activity levels were prepared by separating Y-90,from Sr-90 / Y-90 equilibrated standard solution, by usingstandard analytical procedure. Known Y-90 activity sourceswere counted in the beta counting system and the efficiencieswere determined. Efficiency of the counting system for 11different Y-90 sources was found to vary from 57.4 % to 87.4%with an average of 73.8%. The relatively higher efficiencyof the counting system in the present study due to probableback scattering and breamstrahlung produced within thecounting system by high energy Y-90 beta particles. Also thevariation in efficiency is due to the variation in thicknessof Y-90 oxalate precipitate. This factors need to be kept inview in the proper estimation of beta activities in HealthPhysics and Environmental survey activities.


Completed CalibrationefficiencyLow background GMgas flow counterY-90.

8. REFERENCES :

Calibration for Efficiency Determination of GM Gas FlowDetector for Measurement of Yttrium-90, S. Venkataraman andM.A.R. Iyengar.

161


Application of Pulse Shape Discrimi- 6 -- 9nation Technique to Improve theEnergy Resolution of a Gas Scintilla-tion Proportional Counter


S.P.Garg, K.B.S.Murthy and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 08 5

4. ABSTRACT :

'Pulse shape discrimination technique has been applied toimprove the energy resolution of a single wire anode (SWA)gas scintillation proportional counter (GSPC). Resolution at5.9 keV photon energy is improved from 33% to 16% ffiSjj.vsup-pressing pulses due to interactions in the scintillationproduction region (SPR) in a 1.7 nun dia. rod anode cylindri-cal design GSPC operated with Ar + 2.5% N2 in continuousflow. For the optimum operating conditions of the GSPC therise time of the pulses due to 5.9 keV X-rays was typically300 ns for interactions outside the SPR and a broad continu-um from 300 ns down to about 40 ns for interactions insidethe SPR. In order to select a certain narrow time window aspecial time to amplitude converter unit was developed witha time resolution capability to distinguish pulses havingrise time differing only by a few ns.


Completed Radiation DetectionGas Scintillation

8. REFERENCES :

i) Application of Pulse shape discrimination technique toimprove the energy resolution of a GSPC, S.P.Garg,K.B.S.Murthy and* R.C.Sharma,Nucl. Instr. and Meth. A (Inpress)

ii) Investigations of X-ray response of single wire anodeAr-N2 flow type GSPCs, S.P.Garg and R.C.Sharma, Nucl. Instr.and Meth. 222, pp 574-581, 1984

iii) A pill-box design flow type GSPCC, S.P.Garg,R.C.Sharma, S.Bhati and S. Somasiuuiaram, Nucl. Instr. andMeth., 198, pp 471 -478, 1982

162


Observations On Search For A Phoswich 6 - 1 0Detector Of Improved Performance


T.K.Haridasan and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

At Trombay, a 20 cm dia phoswich detector (Model 203YBE 3)housed inside a graded lined steel chamber and operatingwith pulse-shape discrimination(PSD) technique has beenextensively used for monitoring intakes of actinides byoccupational workers since 1975. The life span of a phoswichdetector is not truely known. Therefore, we initiated ef-forts to procure a new detector of improved performance withthe ostensible purpose of replacing the aged one. Improvedfigure of merit, S^/B, where S is the detection efficiencyfor a standard point source of 239pu o r 2 4 1 ^ located at 10cm on detector axis and B the background rate(for both,counts recorded in appropriate low-energy bands), was set asthe selection criterion. Over the past seven years,two phos-wich detectors-one BICRON make (Model 8xH.12 Csl(Tl)Q/(3)3BSSL-X) and another Quartz & Silica make (Model 203 YBEA 12-7W51) have been tested. PSD electronics based on ORTECpulse-shape analyser (either model 458 or 555) was optimisedseparately for each detector. In general, the phoswichdetectors coupled to three (7.5 cm dia.each ) photomultipli-er tubes exhibited slightly better energy resolutions anddetection efficiencies as compared to that mounted on asingle large diameter photomultiplier. Nevertheless, theperformances of both new detectors when compared with theone currently in use since 1975, on the basis of figure ofmerit, were found to be poorer by factors of about 4 and 10respectively.


In progress PhoswichPSD

8. REFERENCES :

i) A Report On Performance Evaluation Of A Bicron PhoswichDetector, R.C.Sharma, T.K.Haridasan and T.Surendran, Privatecommunication to BICRON Corporation, USA (1990)

ii) A Report On Performance Evaluation 'Of A New Quartz &Silica Phoswich Detector, T.K.Haridasan and R.C.Sharma,Private conununication to Quartz & Silice, France (1993)

iii) Detection Systems For Monitoring Intakes Of ActinidesAt Trombay, T.K.Haridasan, T.Surendran, R.C.Sharma andS.Krishnamony, Rad.Prot.Dos. (in Press)

163

7. RADIATION PHYSICS


Re-assessment of Absorbed Dose 7 - 1using Photo-Transferred TL in LiF TLD-100


B.D.Bhasin and S.P.KathuriaHealth Physics Division, BARCBOMBAY - 400 085

4. ABSRRACT :

The paper analysis and identifies the experimental condi-tions required for optimum stimulation of the photo-transferprocess for dose reassessment purposes. The TLD-100 ribbonare first tested for their uniform sensitivity. A batch often chips are selected within +.2.9% standard deviation. Forreassessment of dose pre-gamma exposed samples are heated inthe TL reader G200°C/min upto 350°C. Using calibrated UVsources the Phototransfer characteristics are recorded atdifferent ambient temperatures. The reassessment of doses forexposures corresponding to absorbed doses of 2mGy are morecan be done with an error of ± 5.8% at 95% confidence level.The limit of dose reassessment can be further reduced to0.75mGy when samples are exposed to UV light at 120°C foraffecting photo-transfer. This detection level^ is 7-10 timeslower than the values reported by earlier workers.


Completed Dose-ReassessmentPhoto-transferTLD-100

8. REFERENCES :

Re-assessment of Absorbed Dose using Photo-Transferred TL inLiF TLD-100, B.D.Bhasin and S.P.Kathuria, National Seminar onThermoluminescence and its applications, M.S.University ofBaroda, Baroda, pp 182-186, Feb 7-9, 1991

164


Neutron Production from Thick 7 - 2Targets Bombarded by Alpha Particles:Experiment and Theoretical Analysisof Neutron Energy Spectra.


P K Sarkar, T.Bandyopadhay, G.Muthukrishnan andSudip Ghosh*Health Physics Unit,Variable Energy Cyclotron Centre,1/AF Bidhan Nagar,Calcutta-700 064.

* Saha Institute of Nuclear Physics, 'Calcutta 700 064.

4. ABSTRACT :

The neutron energy spectra and angular distributions havebeen measured for thick targets of Be-9, Ta-181 and Au-197bombarded by 40-60 MeV alpha particles. These data as well asthose of other authors have been analyzed in terms ofthe extended exciton model formalism of nuclear reac-tions. The model takes into account the emission of neutronsthrough the single-step direct, multistep direct,multistep compound, and compound-nuclear evaporation proc-esses .


Neutron yieldNuclear reactions

8. REFERENCES :

Neutron Production from Thick Targets Bombarded by AlphaParticles: Experiment and Theoretical Analysis of NeutronEnergy Spectra,P.K.Sarkar, T.Bandyopadhay, G.Muthukrishnanand Sudip Ghosh. Physical Review C Vol. 43, No. 4, April 1991

165


An improve! Monte Carlo Technique 7 - 3for Radiation Shield Design.


P.K. Sarkar and M.A.Prasad*Health Physics Unit,Variable Energy Cyclotron Center,1/AF Bidhan Nagar,Calcutta-700 064.Division of Radiological Protection,Bhabha Atomic Research Centre,Bombay, 400 085.

4. ABSTRACT :

Reduction of statistical error in Monte Carloshielding calculations is achieved by using antitheticvariates with geometrical surface splitting while solvingthe radiation transport problems. Numerical results arepresented for sample calculations for slab shields ofdifferent dimensions. The present method shows great improve-ment inefficiency for thick slabs and therefore is useful forpractical shielding calculations.


Radiation shieldingAntithetic variates

8. REFERENCES :

An improved Monte Carlo Technique for Radiation Shield De-sign, P.K. Sarkar and M.A.Prasad, Sadhana Vol. 16,Part l,pp75-84, June 1991

166


Development of a Neutron Source 7 - 4for Therapeutic Investigations.


P.K.Sarkar, T.Bandyopadhyay,M Bar, G.Muthukrishnan, S.K.Basu,S-P.Chakraborty and B.K.KhasnabisHealth Physics Unit,Variable Energy Cyclotron Centre,1/AF Bidhan Nagar,Calcutta-700 064.

4. ABSTRACT :

A collimated source is being developed for possible applica-tion to neutron therapy. The source is produced by thebombardment of 40 MeV alphas on a thick Be target. Using atissue equivalent proportional counter, dose distributionswere measured along the central and lateral axes. The quan-tity of the radiation is estimated using dosimetric calcula-tions.


Neutron TherapyRBEMicrodosimetry

8. REFERENCES :

Development of a Neutron Source for Therapeutic Investiga-tions, P.K.Sarkar, T.Bandyopadhyay, M.Bar, G.Muthukrishnan,S.K.Basu, S.P.Chakraborty and B.K.Khasnabis, Indian J. Phys.65A(5),pp 446-449,1991

167


Optimization of Radiation Protection 7 - 5in Accelerators :Decision making under Uncertainty and Risk.


P.K.SarkarHealth Physics Unit,Variable Energy Cyclotron Centre,1/AF Bidhan Nagar,Calcutta-700 064^

4. ABSTRACT :

For medium and high energy accelerators cost optimiza-tion of shields and ventilation systems are to beconsidered from radiation protection point of view. Since,the optimum level of protection depends on the operatingstate (beam energy, beam current, extraction efficiency etc)of the accelerator, the best level of protection can bedecided using the probability distribution of the operatingstates. The paper discusses the decision problem when noprior distribution is available (decision making underuncertainty), and when prior information is availableabout the distribution (decision making under risk).


Radiation protectionDecision theoryAccelerator

8. REFERENCES :

Optimization of Radiation Protection in Accelerators: Deci-sion making under Uncertainty and Risk, P.K.Sarkar, IndianJ.Phys. 65A(6), pp 451-454, 1991

168


Pre-equi1ibrium Emission Effects 7 - 6in the Measured Isomeric Yield Ratiosin Alpha-induced Reactions on Au-197.


N.Chakravarty, P.K.Sarkar* and Sudip Ghosh**Radiochemistry Division,Bhabha Atomic Research Centre,Bombay 400 085.

* Health Physics Unit,

**Variable Energy Cyclotron Centre, CalcuttaSana Institute of Nuclear Physics,1/AF Bidhan Nagar, Calcutta 700 064.

4. ABSTRACT :

Excitation functions of isomeric yields have been meas-ured for Tl-198, Hg-197, Au-198, and Au-196 produced by a +Au-197 reactions in the 35-50 MeV range. The isomericyield ratios are analysed in terms of pre-equi1ibriumand evaporation emissions. Single as well as two-nucleonpre-equi1ibrium emissions are taken into account. Variouscombinations of pre-equi1ibrium and equilibrium emissionstogether with different sequences in which the ejectilesmay be emitted are explicitly considered to evaluate theaverage spin distribution of the final nucleus. The choiceof the spin cutoff parameter and the effect of forward-angle emissions of pre-equi1ibrium particles have been inves-tigated. The isomeric yield ratios are found to dependsensitively on the pre-equi1ibrium angular distribution andon the spin cutoff parameter for equilibrium emissions.Inadequate description of the reaction mechanism leads toincorrect predictions of excitation functions as well asisomeric yield ratios.


Isomer ratioNuclear reactions

8. REFERENCES :

Pre-equi1ibrium Emission Effects in the Measured IsomericYield Ratios in Alpha-induced Reactions on Au-197, N. Chakra-varty, P.K.Sarkar and Sudip Ghosh, Physical Review C Vol. 45,No.3, March 1992

169

1. TITLE :

Correction for Pressure inCalibration of ScintillationCell Technique for Measurementof Thoron

2. CATEGORY:

7 - 7



4. ABSTRACT :

For calibration of scintillation cell for estimation ofconcentration of thoron which has only a 55 sec half-life,counting is done while sampling. During this process whenair is drawn through the cell using a pump, it has to over-come resistance due to filter paper, water column in thebubbler and tubing etc in the sampling circuit. This causesbuild up/drop of pressure in the cell. Accordingly concen-tration of thoron in the cell is also effected.

The following mathematical expression describing the rela-tion between observed concentration and true concentrationfor measured variation during sampling has been worked out.

cTn * X/E.qtexpl-v.p. A/p.q} - exp {-(v+V).p.A /P.q}]

Where "X1 is observed countration, NE' is counter efficien-cy, *v' is volume of tubing etc., KV is volume of scintil-lation cell, ~p' is pressure in cell at the time of sam-pling, *Pf is atmospheric pressure, " A • is decay constantfor radon and *q' is flow rate.

Experimental data is found to be in good agreement withcomputed values.

the

5. REMARKS t 6. STATUS t

Completed

7. KEYWORDS :

ThoronScintillation cellPressure dropcorrection

8. REFERENCES :

Correction for Pressure in Calibration of Scintillation Cellfor Measurement of Thoron/ G.K. Srivastava and A.H. Khan,Bulletin for Radiation Protection, Vol 15, No. 2, 1992

170

1. TITLE

Development of a Semi-EmpiricalExpression for Light Gain FactorsIn Gas Scintillation ProportionalCounters

' 2. CATEGORY

7 - 8


S.P.Garg, K.B.S.Murthy and R.C.SharmaHealth Physics Division, BARCBOMBAY - 400 085

ABSTRACT :

An attempt is made to develop a semi-empirical expressionfor light gain factors in single wire anode (SWA) gas scin-tillation proportional counters (GSPC) as a function ofvarious other counter parameters like operating voltage,anode and cathode radii, filling gas mixture and its pres-sure. Experimental data of charge gain and light gain fac-tors has been taken frqm four GSPCs having anode diametersfrom 25 um to 1.7 mm and operated with Ar or Ar + 2.5% N2mixture. First the quality of our experimental data has beeninvestigated by fitting the values of charge gain factorsfrom one of the four GSPCs to four different semi-empiricalexpressions selected from the literature which have beendeveloped for charge gain factors in ordinary ionizationproportional counters and which are suitable for experimen-tal verification. Subsequently, assuming appropriate func-tional forms of electron excitation and ionization coeffi-cients and using derived or assumed values of some otherunknown parameters, the relevant integral have been evaluat-ed. Then the assumed values of unknown parameters are ad-justed in such•a way that the calculated values of lightgain factors are comparable to the experimental values. Thusa correlation between the ligh't gain factors and othercounter parameters is established. The values of the effec-tive electron excitation coefficients as a function ofelectric field strength per unit pressure in Ar + 2.5% N2from these GSPCs having considerably different electricfield gradients have also been estimated.


Completed

7. KEYWORDS :

Light gainGas ScintillationRadiation Detection

8. REFERENCES :

i) Development of a semi-empirical expression for lightgain factors in GSPC, S.P.Garg, K.B.S.Murthy and R.C.Sharma,Nucl. Instr. and Meth. (in press)ii) Gas Scintillation Proportionalpotential radiation detector, S.PR.C.Sharma, Nat.Sym on Adv.Instr.Bombay, January 1993iii) S.P.Garg, Ph.D.Thesis (Phys.1988

Counter: A new Type of.Garg K.B.S.Murthy andfor Nuclear Research,

), University of Bombay

171


Interaction of Positronium with 7 - 9Co + 2 and Cu + 2 ions in AqueousChloride and Sulphate Media


P.K.Sarkar and B. Nandi Ganguly*Health Physics UnitVariable Energy Cyclotron Center,1/AF Bidhan Nagar, Calcutta-700 064.

* Sana Institute of Nuclear Physics,Calcutta

4. ABSTRACT :

The interactions of positronium in aqueous solutions of Co + 2

and Cu + 2 ions at 297 K in the presence of chloride and sul-phate ions were studied at varying concentrations of theions using LS and DABRL techniques. In the case of Co + 2,the results suggest a spin conversion reaction, Whilefor Cu + 2, there is predominantly an oxidation reaction with asmall contribution of spin conversion. In both cases thereaction rate constants were calculated. The differentbehaviours of Co(+2) and Cu + 2 ions are discernable from theresults. A different trend in the variation of the DAliRLnarrow component with concentration is observed from Cu + 2

ions in Cl~ and SO"2 media.


Positronium intreac-tion

8. REFERENCES :

Interaction of Positronium with Co + 2 and Cu + 2 ions in AqueousChloride and Sulphate Media, P.K.Sarkar and B. Nandi Ganguly,Les Editions de Physique (in press)

172


Semi-empirical Depth Dose Distribution 7 - 1 0Formula for Co-60 Gamma-rays.


R- Ravishankar, Mausumi Sengupta*,Tapas Bandyopadhyay, G Muthukrishnan, A M Ghose*Health Physics Unit,Variable Energy Cyclotron Centre,Variable Energy Cyclotron Centre,1/AF Bidhan Nagar,Calcutta-700 064.

4. ABSTRACT : .

A semi-empirical formulation has been carried out for thedepth dose distribution in patients exposed to Co-60 gamma-rays during radiotherapy. Dose has been expressed as aproduct of the axial depth dose and the correspondingoff-axis ratio. We have been able to express these twofactors using four empirical constants each. Comparison ofexperimental data shows good agreement with semi-empiricallycalculated values.


Dose-distributionDepth-doseRadiotherapy

— . . _ _ _ — «.»..a.^,..— — — — .•»••••.••*•••.••••«••••.— ~ — — — — — .— • - — • - — — — - • - . — — — — — — — — — — — — — — — — — — —

8. REFERENCES :

Semi-empirical Depth Dose Distribution Formula for Co-60Gamma-rays, R. Ravishankar, Mausumi Sengupta, Tapas Bandyo-padhyay, G Muthukrishnan, A M Ghose, Radiat. Phys. Chem. (inpress)

173


Estimation and Analysis of Neutron 7 - 1 1Skyshine Dose from Particle

. Accelerators


G.Prabhakara Rao and P.K.SarkarHealth Physics Unit, Variable Energy Cyclotron Centre,1/AF Bidhan Nagar,Calcutta-700 064.

4. ABSTRACT :.

An algorithm for fast and inexpensive calculation ofneutron skyshine dose from particle accelerator facilitiesis described. Numerical results are obtained at variousdistances (100m to 2000m) from' the accelerator neutronsource for different roof thicknesses and for 50- and 60-MeValphas incident on Ta targets. A study of the variation inthe neutron skyshine dose with respect to roof thicknessand source neutron energy distribution is made. Theresults indicate that neutron dose at large distancesis sensitive to the high energy component of the sourceneutrons and thereby to the energy of the accelerated ions.


Neutron skyshine

8. REFERENCES :

Estimation and Analysis of Neutron Skyshine Dose from Parti-cle Accelerators, G.Prabhakara Rao and P.K.Sarkar, Ann.Nucl. Energy,(in press)

174

8. MATHEMATICAL MODELLING & SOFTWARE DEVELOPMENT


Evaluation of Finite Plume Gamma 8 - 1Dose by Particle Trajectory Simul-aton Technique


V.SitaramanHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

The study presents a method of estimating gamma dose from afinite plume of gaseous effluents released from a continuoussource using particle trajectory simulation. The approach isin two steps:(1) Simulate continuous plume by a succession ofparticle trajectories whose evolution is given by Langevinequation (2) Compute for each trajectory the gamma flux at areceptor location and the dose rate as a sum of contributionsfrom all trajectories. The method is particularly suitablefor appliation in inhomogeneous turbulent fields. Thegamma dose estimates were made at ground level at variousdownwind distances for Pasquill A and D weather categories.Dose rates were evaluated both for straight-line and sectoraveraged plumes. Model results were compared with resultsfrom conventional models using Double Gaussian distributionof material in the plume.


Completed Gamma doseParticle trajectorysimulationFinite plumedoseRandom walk model

8. REFERENCES :

Evaluation of Finite Plume Gamma Dose by Particle TrajectorySimulation Technique, V.Sitaraman, Health Physics, Vol. .58,pp 93,1990

175


Numerical Modelling of Tidal 8 - 2Circulation and Tide InducedWater Level Variation in BombayHarbour Bay

3. AUTHORS AND ADDRESS :

V. AbrolHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A non-linear hydrodynamic numerical model has been appliedto Bombay harbour waters subjected to tidal forcing at themouth of the harbour. Build up of water level and associatedcurrent pattern of the circulation have been studied. Modi-fication of flow field due to presence of Elephenta Islandin the harbour is studied by excluding and including theIsland in the computational grid for a typical tidal cycle.The study brings out the utility of nemerical modellingtechnique in estimating tidal dynamics of semi- enclosedwater bodies.


Completed

8. REFERENCE :

Numercal Modelling of Tidal Circulation and Tide InducedWater Level Elevation in Bombay Harbour Bay, V.Abrol, Ind.Journal of Marine Sciences, Vol. 19, pp 89- 94, 1990

176


. Estimation of Wash-out of 8 - 3Tritiated Water (HTO) Effluentby Raindrops


V. AbrolHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

As compared with wash-out by rains of air pollutants inparticulate form, the wash-out scavenging of gaseous materi-als is a reversible process. Raindrops as they fall throughthe plume of gaseous entrainment may scavenge the pollutantgas, but they can also desorb if they meet cleaner air belowthe plume. In this study of HTO wash-out, the process ofwash-out is modelled and wash-out coefficients are presentedfor a range of rainfall rates and plume travel distancesboth for case of reversible (gaseous) and irreversible(particulates) wash-out. There is significant difference inwash-out coeffcients in both cases.


Completed

3. REFERENCE :

Estimation of Wash-out of Tritiated Water (HTO) Effluent byRaindrops, V.Abrol, Bulletin of Radiation Protection, Vol13, No 1, 1990

177


Computer Program for Dose Calculation 8 - 4and Processing of WBC Data of OutsideManpower Working in Tarapur AtomicPower Station


D.D. Rao, A.G. Hegde and I.S. Bhat*Environmental Survey LaboratoryTARAPUR - 401 504

* E & PA, Nuclear Power Corporation,World Trade Centre, Bombay

4. ABSTRACT :

A computer program was developed on a standard PC/AT fordose calculation and processing of whole body counting data.The program has various facilities like data entry, dosecalculation, sorting of data, updating of dose records,printing of monthly reports and simple statistics. The dose(CEDE) computations are performed according to ICRP-54recommendations. The program computes derived recording andderived investigation levels for a given working period(usually 15 d) for radionuclides like 134+137Cs an(j 60Co. I tperforms data interpetation with recording levels before theCEDE computation and signals the user of any over exposedcases with required details.


Completed Computer dosecalculation

Derived recording/investigation levels

8. REFERENCES :

Computer Program for Dose Calculation and Processing of WBCData of Outside Manpower Working in Tarapur Atomic PowerStation, Bulletin of Radiation Protection, Vol. 14, No. 1&2,Jan-June, 1991

178


Models for Shallow Land Disposal 8 - 5of Low and Intermediate LevelRadwaste


T.M.Krishnamoorthy, R..N.Nair, T.P.Sarma and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Two kinds of models have been developed to study the migra-tion of radionuclides from shallow land burial site. Thefirst model, single layer leach model, is based on near-surface disposal leadling to leaching of radioactivity to asubstrata sandy acquifer. The second model, double layerleach model, is based on migration of radionuclides to ac-quifer through an impervious clay zone.


Completed Rad waste managementMigration throughrock strata

8. REFERENCES :

Models for Shallow Land Disposal of Low and IntermediateLevel Radwaste, T.M.Krishanmoorthy,T.P.sarma and K.C.Pillai,Proc. 1991 Joint Int. Waste Management Conf., Korea, pp 127-132, 1991

179


Estimation of Source Term in 8 - 6Radiation Emergencies from FieldMeasurements:Its Potential andLimitations


R.K.Hukkoo and V.N.BapatHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

During the "early phase1 of a radiation emergency the data onthe nature and quantity of releases to assess the radiologi-cal impact may not be readily available thus delaying theinitiation of necessary steps to contain the event and miti-gate its effect. An iterative method based on the fieldmeasurements carried out at two concentric rings around thepoint of release is proposed to estimate the atmosphericrelease is proposed to estimate the atmospheric release atground level and stack height. The program logic has beenevaluated for internal consistency and its utility and limi-tations are discussed.


Completed Source termsEnvironmentRadiation

8. REFERENCE :

Estimations of Source Term in Radiation Emergency from FieldMeasurements - Its Potentials and Limitations, R.K.Hukkooand V.N.Bapat., BARC Report, BARC/1991/E/005

180


Analysis and Limitations of MATHEW 8 - 7-ADPIC Model


R.K.Hukkoo and V.N.BapatHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Double Gaussian Dispersion model has been extensively usedfor estimation of concentration distribution. With the adventof computers, numerical transport and diffusion models whichincorporate the effect of terrain and three dimensional windfield have come into vogue. This paper discusses the • advan-tages and limitations of such a model.


Completed

8. REFERENCE:

Analysis and Limitations of MATHEW-ADPIC Model, R.K.Hukkooand V.N.Bapat, Proceedings of National Symposium on Environ-ment, Bombay, Feb. 3-5, 1992

181


A Diffusion-deposition Model of 8 - 8Surface Reactive Gaseous Plume fromContinuous Ground Level Source


V.SitaramanHealth Physics Division, BARCBOMBAY - 4 00 085

4. ABSTRACT :

A model was developed to describe diffusion effluents in theatmosphere from a continuous ground level source. The modelis applicable to effluents which have pronounced surfacereactivity (HNO3, HF etc.;). The basic approach rests on thepremise that surface resistance to deposition is very low forthese effluents and their deposition is essentially governedby aerodynamic flow characteristics. Hence deposition can bespecified in terms of standard micrometeorological parametersused in Gaussian plume model and the molecular properties ofthe effluent.

Using simple parametrization of deposition velocity, themodel derives expressions for plume depletion and depositionflux for various downwind distances and atmospheric stabilityclasses as in Pasqui11-Gifford model.

The model derived deposition velocities were compared withfield data for HNO3 and 12 vapour and agreement is obtainedfor over all stability effects.


Completed DiffusionDeposit ionSurface reactivegasesDispersion modelPlume depletion

8. REFERENCE :

A Diffusion-depletion Model of Surface Reactive Gaseous Plumefrom Continuous Ground Source, V.Sitaraman, Proceedings ofNational Symposium on Environment, Bombay,Feb. 3-5, 1992

182

1. TITLE :

Intercomparison of Fault TreeAnalysis Programs

2. CATEGORY :

8 - 9


V.V.S.Sanyasi Rao, Health Physics Division,Prem Prasad, Inspection Sect ion(Factory Act),Y. Chellam, Reactor Safety Division,Senthil Kumar, R.N. Kulkarni, Atomic Energy Regulatory BoardD. Chatterjee, 500 MWe Project, NPCIL

4. ABSTRACT:

Quantitative measures of safety associated with a system putin to prespective the risk associated with it. Such measuresof risk at the system level, in probabilistic safetyanalysis, are evaluated using fault tree analysis (FTA)methods. To have confidence in such measures , it isessential to standardise the analysis techniques and data. Inthis work the available FTA codes within BARC, NPC and AERBare assessed for their suitability to carry out suchanalysis. However no attempt is made to assess theuncertainty handling aspects of the packages.Such an exercise indicated the needa) for a standard code for components, failure modes and

failure causes andb) a standard failure data base for carrying out such

evaluations.The Analysis also indicated that human errors while dataprocessing, cannot be underestimated. As far as systemreliability predictions are concerned, the results indicatedthat1) the system unavailability predictions are within 15% of

PSAPACK (an IAEA package) value.2) the number of first order cutsets and the first order

cutsets are the same.3) there is a difference in the number of second order

cutsets, probably due to different algorithms used for,cutset evaluation.

4) some measures of importance, useful for design evaluationand maintenance planning, are availablepackages like TREEMASTER and FTAP.

in certain


Completed

7. KEYWORDS :

Fault tree analysisComputer codesIntercomparison

8. REFERENCES :

Intercomparison of Fault Tree Analysis Programs. V.V.S.Sanya-si Rao et. al., National Symposium on Safety of Nuclear PowerPlants and other Facilities, BARC, Bombay, March 11-13, 1992

183

1. TITLE ? . 2. CATEGORY :

Dispersion of Radionuclides in 8 - 1 0Coastal Sea


R.N.Nair and V.N.SastryHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Various coastal dispersion models employed for the dispersionof radionuclides in coastal sea are discussed in relation toassumptions used, source terms and input parameters applica-bility.


Completed Aquatic Dispersion

8. REFERENCE :

Dispersion of Radionuclides in Coastal Sea, R.N.Nair and V.N.Sastry, Seminar on Transport and Dispersion of Pollutants inAcquatic and Atmospheric Media, Kalpakkam, 1992

184


Development of a PC Based Software 8 - 1 1for NPP Operator


D. Datta and H.S. Rajput*Health Physics Division, BARCBombay 400 085

* Tarapur Atomic Power Station, Tarapur

4. ABSTRACT :

The accidents at Three Mile Island as well as Chernobylreactors highlight the important role operators play in thesafety of Nuclear Power Plants. In order to assess theoperators during the operation of the plant, a computerprogramme that relax the operating power to the thermalstresses in the fuel and clad is developed. Any change inthe operating power, e.g. due changes in reactivity, reflextin the thermal stresses in fuel and clad. A comparison ofthese with the stresses under normal operating conditions canprovide guidance to the operator integrity. This program isPC based program and can act as aid to the operator in thecontrol room. The details of this program are discussed.


Work in Operating powerprogress Fuel clad

Thermal stress

8. REFERENCES :

Development of a PC Based Software for NPP Operator, D. Dattaand H.S. Rajput, 1992.

185


Atmospheric Dispersion Models 8 -12


V.N.BapatHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Various atmospheric dispersion models exist in literature andare in use for generating concentration distribution for theatmospheric releases. This paper gives various models in useand their comparative advantages and limitations. It alsogives various modifications to Gaussian approach, which havebeen used to handle various scenerios in the field.


Completed Atmospheric disper-sion

8. REFERENCE :

Atmospheric Dispersion Models, V.N.Bapat, Seminar on Trans-port and Dispersion of Pollutants in Acquatic and Atmospher-ic Media, Kalpakkam, 1992.

186


Migration of Radionuclides from 8 - 1 3A Shallow Land Burial Site :A Sensitivity Study


T.M.Krishnamoorthy, R.N.Nair and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A double layer leach model incorporating a finite clay zonein between the burial site and the sandy acquifer is de-veloped to study the migrational behaviour of radionuclidesfrom a shallow land burial site.


Completed Waste managementMi gra t i on throughrock

8. REFERENCE :

Migration of Radionuclides from a Shallow Land Burial Site:A Sensitivity Study, T.M;Krishanmoorthy, R.N.Nair andK.C.Pillai, Bull. Rad. Prot. 15, pp 25-26, 1992

187


Application of NAIJA Containment 8 - 1 4Code for Source Term and Analysis


V.K.Sharma, V.Sitaraman and Balwinder KaurHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

NAUA is containment code that describes the behaviour ofaerosols inside a reactor containmemnt atmosphere.lt has beendeveloped essentially to study fission product aerosol trans-port and removal in the containment following core meltdownin a light water reactor and forms part of source term codepackage. A parametrization study was made to model theaerosol behaviour and removal in the containment when Engi-neered Safety Features(ESFs) are used in the containment. Theeffect of containment sprays, air coolers and reciruculatingfilters were studied using the code. Two cases were studied:standard case (when no ESFs were included) and ESFs included.The effects of ESFs on aerosol size distribution, mass load-ing and activity were studied as a function of time. Twodifferent models of containment sprays with varying flowrates of containment sprays varying flow rates and drop sizeswere studied.

5. REMARKS : 6. STATUS : 7. KEYWORDS t

Completed

8. REFERENCES :

Application of NAUA Containment Code for Source Term Analy-sis, V.K.Sharma, V.Sitaraman and Balwinder Kaur, FourthAnnual Conference of IASTA at NIOH, Ahmedabad, Oct.12-13;1992

188


. Variance Reduction in Monte-Carlo 8 - 1 5Radiation Transport usingAntithetic Variates.


P. K. Sarkar and M.A.Prasad*Health Physics UnitVariable Energy Cyclotron.Centre1/AF Bidhan Nagar,Calcutta-700 064.

* Division of Radiological Protect ion,BARC, Bombay

4. ABSTRACT :

The use of antithetic variates in conjunction withgeometrical surface splitting/Russian roulette is numeri-cally studied for one-group Monte-Carlo radiation trans-port problems in slab geometry. Numerical solutions ofthe coupled set of integral equations for the first andsecond moments around the scores, and thereby estimates ofvariances are obtained. Derivations of the equations forthe score accumulation probability and the moments aroundthe score are presented. Two types of antithetictransformations are considered. The results indicatethat antithetic transformations always lead to the reduc-tion of variance. A substantial reduction in variance isobtained when antithetic variates are used with the rule ofthe thumb splitting. The reduction in variance is attrac-tively large for thick slabs (~ 20 m.f.p.) and low scatter-ing probability.


Monte CarloRadiation TransportAntithetic Variates

8. REFERENCES :

Variance Reduction in Monte-Carlo Radiation Transport usingAntithetic Variates, P. K. Sarkar and M.A.Prasad, Ann. Nucl.Energy, Vol. 19, No. 5,pp. 253-265, 1992

189

TITLE : 2. CATEGORY :

An Approach for Computing the 8 - 1 6Disposal Rate Limit for ShallowLand Burial Site

AUTHOR\S AND ADDRESS :

T.M.Krishnamoorthy and R.N.NairHealth Physics Division, BARCBOMBAY - 400 08 5

ABSTRACT :

An approach to the computation of site burden for shallowland burial sites is presented using geospheric models andassociated radiological model.


Completed Waste managementSite burden

8. REFERENCE :

An Approach for Computing the Disposal Rate Limit for Shal-low Land Burial Sites, T.M.Krishanmoorthy and R.N.Nair,SMART-93, National Symposium on Management of Radionuclideand Toxic Wastes, IGCAR , March 17-19, 1993

190


A Generalized Optimization of. 8 - 1 7Monte Carlo Particle TransportSchemes.


A. V. StarkovComputing CentreRussian Academy of Sciences, 630 090Novosibrisk Russia.

andP. K. Sarkar & B.Nandi Ganguly*Health Physics Unit,Variable Energy Cyclotron Center,1/AF Bidhan Nagar,Calcutta-700 064.

* Saha Institute of Nuclear Physics,Calcutta

4. ABSTRACT :

Formulations and algorithms for optimizing biased randomwalk problems in radiation transport are described. Amatrix-integral equation is constructed by coupling thesecond moment and its derivative with respect to the biasingparameter. The optimization is based on estimation of thesecond moment around the score and the Monte Carlo perturba-tion algorithm to treat the variation in the biasing param-eter.


Monte Carlo simula-tionPerturbation algorithmOptimization

B. REFERENCES :

A Generalized Optimization of Monte Carlo Particle TransportSchemes,A. V .Starkov,P. K. Sarkar & B.Nandi Ganguly, PramanaD J. Phys., Vol.40,No.5, May 1993

191

TITLE : 2. CATEGORY :

Prediction Of Diurnal Variation 8-18Of Surface Temperature By. EnergyBaiance Method


Rajendra Oza and V.SitaramanHealth Physics Division, BARC,BOMBAY - 400 085

ABSTRACT :

Surface temperature is an important boundary condition inatmospheric planetary boundary layer models and also animportant parameter for calculating turbulent fluxes atearth-atmosphere interface (e.g. sensible heat flux,latentheat flux and longwave radiation). Present model predictsthe surface temperature and its variation with time usingenergy balance method. For the same data period, resultswere also obtained for an alternative and widely used ForceRestore Method. Agreement between model computation and datacollected at Nebraska,U.S.A. were found to be satisfactory.


Completed Soil heat fluxEnergy balanceSurface tamp.

8. REFERENCES :

Prediction Of Diurnal Variation Of Surface Temperature ByEnergy Balance Method, Rajendra 02a and V.Sitaraman,Proc.Second National Symposium on Environment, Jodhpur,1993.

192


Desorption Kinetics of Radio- 8 - 1 9Nuclides fixed in Cement Matrix.

3. AUTHOR\S AMD ADDRESS :

T.M.Krishnamoorthy, S.N.Joshi,G.R.Doshi and R.N.NairHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

Leach characteristics of some typical nuclides such asCs,Sr,Co,I~* and CO3"2 from ordinary Portland cement wasteforms have been studied using the ISO test method and radio-tracers of the respective nuclides. A mathematical model hasbeen simulated to describe the leaching kinetics of thesenuclides from the cement matrix.

5. REMARKS: 6. STATUS : 7. KEYWORD :

Completed LeachingWaste disposal

8. REFERENCE :

Desorption Kinetics of Radionuclides fixed in Cement Matrix,T.M.Krishnamoorthy, S.N.Joshi, G.R.Doshi and R.N.Nair, Nucl.Technol (in press}

193


Radionuclide Transport through 8 - 2 0Fractured Porous.Media


R.N.Nair,T.M.Krishnamoorthy and K.C.PillaiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A simplified model has been developed to arrive at spatialand temporal distribution of radionuclide concentration infracture waters of granite host rock containing high levelradioactive waste repository. The processes considered areadvection, radioactive decay and adsorption on the surfacein the case of fracture and diffusion, radioactive decayand adsorption in the microfissures of the medium in case ofhost rock. The concentrations of various radionuclides arediscussed in relation to physico- chemical prameters of thesystem.


Completed Waste managementMigration throughrock

8. REFERENCE :

Radionuclide Transport through Fractured Porous Media,R.N.Nair,T.M.Krishanmoorthy and K.C.Pillai, Isotopenpraxis(in press)

194


A Generalised Code "FANTCAL1 for 8 - 2 1Calibration of an External Detectorwith Cristy's Mathematical Phantom

— — — - • — — — — — — — . — . — — . — — — — — — — — _ - _ — . _ — - • — — — .-. — _ - _ — — — ,•.».•••__.—.^.»».»___ _ _ _ _ _ — „„__.«_


Sharda BhatiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A Monte-Carlo photon transport code FANTOM (RSIC/1980)developed earlier for computing response of a phoswichdetector to various source distributions of several low-energy photon emitters such as Pu, Am, Cm, Cf, Pd and 1-125present in the relevant organs (lungs, liver or thyroid) ofa MIRD phantom, has been modified and made comprehensive.The modified code -FANTCAL' makes use of CRISTY's adultphantom incorporating improved heart-lung model, as a cali-brating device in place of the MIRD phantom. In addition tomono-energetic photons, the program simulates and treatshistories of energy spectrum of bremsstrahlung photonsemitted by beta-sources e.g. Pm-147. The generalised com-puter program can be used to simulate pulse-height-responseof any scintillation detector with known detection parame-ters such as intrinsic efficiency, resolution function andiodine K-X-ray escape efficiency. To obtain calibrationfactors applicable to Indian radiation Workers of bodybuilds smaller than the adult phantom, the code scales downthe adult phantom uniformly by a factor Q < 1.0, to simulatevarious smaller phantoms characterised by their weight /height ratio. The details of the program describing genera-tion of source photons in relevant organs, tracing historiesof photons through heterogeneous tissue media of the trunkregion, considering photo-electric and Compton scatteringinteractions and computation of "Exit Photon Spectrum (EPS)incident on the detector, and finally,the correspondingobservable pulse-heigh-spectrum by smearing the EPS with theknown detector Gaussian resolution function, are given inthe paper^.


Completed Monte-CarloCristy's PhantomPhoswich

8. REFERENCES :

1. Radiation Shielding Information Centre Computer codecollection, Oak Ridge; TNs ORNL; RSIC news letter No. 186,CCC-375/ FANTOM, 19802. A monte-carlo Approach to assessing *47pm in the Liver ofthe Adult phantom, Sharda Bhati, Health Physics 64(6): pp638-646, 1993

195


A Monte-Carlo Approach to Assessing 8 - 2 2Promethium-147 in the Liver of theAdult Phantom


Sharda BhatiHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A low-background phoswich detector is used to detect smallamounts of 147pm - a pure beta emitting nuclide present inthe liver of an occupational worker. The assessment has beenbased on the measurement of bremsstrahlung radiation, pro-duced by the beta particles in the tissue. Computer programsbased on Monte-Carlo techniques for photon transport havebeen developed to calculate the response of an externalphoswich detector to: 1) a 147pm point source embedded intissue-equivalent slabs of various thicknesses; and 2)various source distributions of 147Pm in the liver of anadult phantom designed by Cristy and Eckerman, with a viewto theoretically calibrate the phoswich detector for eachsource distribution and to study the variation of maxima ofthe spectra with the depth of the source in the liver andtissue-equivalent slabs. The initial bremsstrahlung photondistribution of H?Pm in water has been computed usingWyard's as well as Pratt's method. These calculations havebeen compared with experimental measurements using perspexslabs. Good agreements have been noted when the initialbremsstrah lung spectrum is obtained by using Wyard's method.These results find applications in monitoring the liverburdens in occupational workers handling 147Pm based radio-luminous paints. This study is being extended to includeindividuals of body-builds smaller than the adult phantom.


In progress Phoswich detectorPm-14 7Adult phantom

8. REFERENCES :

A Monte-Carlo Approach to Assessing * 4 7 Pm in the Liver ofthe Adult Phantom, Sharda Bhati, Health Physics Vol. 64 (6);pp 638-646, 1993

196


An Application of CRAC-2 Model 8 - 2 3to NPP Sites:


V.Sitaratnan ,V.K.Sharma and K.D.SinghHealth Physics Division. BARCBOMBAY - 400 085

4. ABSTRACT :

The study considers the application of the Reactor AccidentConsequence Model CRAC 2 code to Probabilistic Risk Assess-ment (Level III) of NPP sites. Site Meteorological data (oneyear hourly data for 1990) were used for statistical samplingand categorizing them in 29 weather bins. Uniform populationdistribution for NAPS site was assumed over a radial distanceof 16 km considered in the study. In the abscence of relevantsite data, default values suggested in the code were used forvarious model parameters.

Results are presented in the form of Cumulative distriblutionfunction of different consequences for the accident scenerioconsidered ( triple failure).

.5* REMARKS : 6. STATUS : 7. KEYWORDS :•

Completed Impact assessmentProbabilistic RiskAssessmentLevel IIIReactor accidentmodel .

8. REFERENCES :

An Application of CRAC 2 Model to NPP Sites,V.Sitaraman,V.K.Sharma and K.D.Singh, Health Physics Division Report,1993 . " • •

197

9. INDUSTRIAL HYGIENE


Particle Size Distribution Studies 9 - 1within A Beryllium Processing Plant

3. AUTHOH/S AND ADDRESS :

D.D.Thorat1, T.N.Mahadevan2, S.Narayan3, P.N.Bhat3 andG.Subramanian^^Beryllium Machining Fscility^Environmental Assessment Division^Health Physics Division^Radiation Safety Systems DivisionBhabha Atomic Research CentreBOMBAY - 400 085

4. ABSTRACT :

Beryllium is a very hazardous substance. Since the humanrespiratory system is the primary route for exposure to airborne particle, the associated health effects are in partdepend upon the size and shape of the particles that arepresent in the work environment. The present study attemptsto give an account of the size distribution of the berylliumparticles in the occupational environment based on themeasurements carried out at the Beryllium Pilot Plant,Vashi.


BerylliumParticle sizeWork environmentAir sampling

8. REFERENCE :

Particle Size Distribution Studies within A Beryllium Processing Plant, D.D.Thorat, T.N.Mahadevan, S.Narayan, P.N.Bhatand G.Subramanian, Third Annual Conference of Indian Aero-sol Science and Technology Association, Bombay, October 10-11, 1991

198


Health and Safety Aspects of 9 - 2Beryllium Processing


A.Ramamurthy and S NarayanHealth Physics Division,BARCBOMBAY - 400 085

4. ABSTRACT :

Beryllium metal finds many applications in space, electronicsand electrical engineering industries due to its lightweight, hardness, and dimensional stability. Efforts arebeing made to meet the Country's needs of the metal indige-nously.

Beryllium and its compounds are among the very toxic sub-stances produced on industrial scale . Considerable ef-forts have been made, in the recent years, in the study ofits toxicity and handling hazards.

Beryllium compounds can be handled without any adverse ef-fects by adopting control measures needed for each operation.

The toxicity of beryllium, the occupational exposure limit aswell as the methods of control and protection are brieflydiscussed in this paper.

5. KEYWORDS : 6. STATUS : 7. KEYWORDS :

BerylliumToxicityControl measures

8. REFERENCE :

Health and Safety Aspects of Beryllium Processing , A.Rama-murthy and S Narayan, National Workshop on Beryllium Technol-ogy, organised by Materials Group, Bhabha Atomic ResearchCentre, Bombay, December 5-6, 1991

199


Safety Aspects of Fused Quartz/Silica 9 - 3Glass Working Operations


S.NarayanHealth Physics Division,BARCBOMBAY - 400 085

4. ABSTRACT :

As in any other operations, working on fused quartz/silicaglass presents various types of hazards. The hazards encoun-tered in the operations are : Physical agents, unsafe work-ing conditions and unsafe work practices. The physical agentswhile working quartz are ultraviolet, visible,infrared radia-tions and noise. The main effects of emittedultraviolet,visible and infrared radiations are on the humaneye. Working on glass, produces high noise levels and insti-tution of control measures are essential for controlling thehearing capacities of workers.The main chemical agents thatare responsible for causing impairment of health among theworkers while working on quartz glass are silica dusts,oxidesof nitrogen and ozone. During cleaning and degreasing opera-tions, workers are likely to be exposed to chemical agentssuch as chromic acid mists and solvent vapours. These chemi-cals are toxic and in addition, some are flammable. Acci-dents can result during working on glass and when handlingand storing of glass and compressed gas cylinders,ifproper precautions are not taken.

In this paper, effects of physical and chemical agents onhuman are briefly described along with control measures tobe taken to protect the health of workers. The hazards inhandling different chemicals and compressed gas. cylindersare also briefly given.Importance of maintaining safety inglass working areas is indicated in this paper.


Completed ' Glass blowingSilica glassQuart2

B. REFERENCES :

Safety Aspects of Fused Quartz/Silica Glass Working Opera-tions, S.Narayan, Workshop on Fused Quartz/Silica GlassWorking Techniques, Indian Society of Scientific Glass Blow-ers, BARC, Bombay, March 1992

200


Safety Aspects in the Design and 9 - 4Operation of a Chemical Laboratory


P.G.G.Menon, Girija Bharathan and A.RamamurthyHealth Physics Division,BARCBOMBAY - 400 085

4. ABSTRACT :

A laboratory is defined as a building set aside for experi-ments in science and engineering and involved work in manydisciplines. The varied functions of a laboratory, the exten-sive service installations and the specialised equipment poseproblem to those involved in planning, building, equippingand operating the laboratory. The best method of elimi-nation of hazard from the laboratory is the incorporation ofsafety from the design stage. This paper deals withlocation, design factors,laboratory layout, ventilation,illumination, noise & vibration, service facilitiessuch as storage of chemicals, safe practices, emergencypreparedness and day to day managemnt guidelines.


LaboratorySafetyChemical laboratoryDesign factors

8. REFERENCE :

Safety Aspects in the Design and Operation of a ChemicalLaboratory, P.G.G.Menon, Girija Bharathan and A.Ramamurthy,Industrial. Safety Chronicle, VOL. XXIII, No. 2, July-September1992

201


Occupational Hygiene Practices in an 9 - 5Industrial Environment


A.RamamurthyHealth Physics Division,BARCBOMBAY - 400 085

4. ABSTRACT :

In1 the modern industrial environment persons are exposed toa number of hazardous agents. Even when the existing occupa-tional hazards have not been effectively dealt with, newhazards are constantly added. Preventive action towardsminimising the industrial hazards is of primary importanceand should be incorporated in the design stage itself. Con-trol of hazards front the various hazardous agents can be donethrough a multi-disciplinary approach involving occupationalhygiene and occupational medicine. An effective occupationalhygiene programme is based on recognition, evaluation andcontrol of occupational hazards. This paper deals with theprinciples of organising an occupational hygiene programme.Some of the occupational hygiene practices adopted at BARCare also highlighted.


Industrial environmentOccupational hygieneBerylliumNoise

8. REFERENCES :

Occupational Hygiene Practices in an Industrial Environment,A.Ramamurthy, Fourth Annual Conference of Indian AerosolScience and Technology Association, Ahmedabad, October 1992

202

1. TITLE :

Safety and Emergency Preparedness inHandling Sulphur Hexafluoride inPelletron Accelerator

2. CATEGORY

9 - 6

3. AUTHOR/S AND ADDRESSES :

A.Raju, P.G.G.Menon, V.Sitaraman and A.RamamurthyHealth Physics Division,BARCBOMBAY - 400 085

4. ABSTRACT :

Sulphur hexafluoride (SFg) is used in Pelletron acceleratordue to its excellent insulation properties. Being an inertgas it does not constitute any major toxic hazard. However,as huge quantities are involved its large scale releases, canresult in asphyxia. The possible reductJbn in oxygen percent-age in case of accidental release of SFg has been workedout based on an atmospheric dispersion model. Emergencyprocedures to be followed are also given.


Sulphur hexafluoridePelletronAsphyxia

8. REFERENCES :

Safety and Emergency Preparedness in Handling SulphurHexafluoride in Pelletron Accelerator, A.Raju, P.G.G.Menon,V.Sitaraman and A.Ramamurthy, National Symposium on Emergen-cy preparedness & Disaster Management (SEMP-93), IndianNuclear Society, Bombay,August 3-5, 1993

203


Hydrogen Sulphide :Hazards and Control 9 - 7


S.Narayan, S.Soundararajan and A.RamamurthyHealth Physics Division,BARCBOMBAY - 400 08 5

4. ABSTRACT :

Hydrogen sulphide is a corrosive, flammable and highly toxicgas with the characteristic 'rotten egg' smell. It is foundin nature in volcanic eruptions and artesian springs, and inoil and natural gas deposits; it is also manufactured indus-trially in large quantities for production of heavy waterusing hydrogen sulphide-water exchange process. Effects ofH2S poisoning depend on type of exposure - inhalation routebeing the main route of entry. The gas causes eye irritationand conjunctivitis at low concentrations of 50 ppm onwards;it gives rise to failure of smelling ability (olfactoryparalysis) at about 150. ppm and, on prolonged exposure, cancause pulmonary edema. An acute exposure to concentration ofabout 800 ppm or more can be fatal.

In view of the high toxicity of the gas and the large quanti-ties handled, stringent safety precautions have to be fol-lowed in planning and operating H2S facilities. Hazard analy-sis and incorporation of safety features at design stage,meticulous observance of operating safety requirements andstrict adherence to environmental protection regulations arenecessary.

Air monitoring and effluent monitoring for gaseous as well asliquid effluents are required.

The present report discusses various aspects of safety inhandling of hydrogen sulphide. Toxic effects of the gas alongwith control measures are given. Relevant legal requirementsin manufacturing and handling the gas are dealt with in thereport. Details about emergency preparedness, risk managementand analytical procedures are also covered.


Hydrogen sulphide

8. REFERENCES :

Hydrogen Sulphide : Hazards and Control, S.Narayan, S.Soun-darara jan and A.Ramamurthy, Internal Report No. BARC / 1993 /I / 016

204


Health and Safety Aspects of 9 - 8Beryllium Operations


S.Narayan and A.RamamurthyHealth Physics Division,BARCBOMBAY - 400 085

4. ABSTRACT :

Beryllium and its compounds are among the highly toxic sub-stances produced on industrial scale. The health and safetyaspects of beryllium handling are briefly described inthis paper. The control measures to be adopted for protectionagainst the hazards are mentined.


Beryl HumToxicityControl measures

8. REFERENCE :

Health and Safety Aspects of Beryllium Operations, S.Narayanand A.Ramamurthy, Mineral Processing and Extractive Metal-lurgy Review, An International Journal (in press)

205


An Improved Passive Sampler for 9 - 9Monitoring NO2 in Ambient Air


A. Balaiah, A.R. Lakshmanan, T. Krishna Rao andS. ViswanathanHealth Physics UnitNuclear Fuel ComplexHYDERABAD - 500 762

4. ABSTRACT :

A new passive sampler based on the principle of diffusionhas been developed for measurement of NO2 in ambient air.The sampler consists of a plastic container with 5 cm open-ing at the centre, fiber glass filter paper, 6 mm dia "0'rings, si.ntered disc of pore size 150-250 urn and 6 cm dia.The *0* rings provide internal diffusion path. NO2 diffusedacross the glass fibre filter paper is absorbed in thesintered disc impregnated with triethanolamine (TTA). Theabsorbed NO2 in the disc was recovered at ambient tempera-ture using mixed solution of 0.003 M NaHCC>3 & 0.0024 M

CC

A diffusion rate of 400 ml/min has been observed. The sam-pler was tested at different environmental conditions andfound the diffusion of NO2 independent of NO2 concentration,temperature, pressure and relative humidity. A minimumdetectable limit of 2 ug/m3 NO2 is observed in this method.

1% is ideally suited for environmental monitoring for as-sessing time weighted average concentration of NO2 in ambi-ent air and work atmosphere.


Completed NO2Passive samplerAmbient air

8. REFERENCES :

206


Evaluation of Surface Area of 9-10Airborne Mineral Dust at IRE, OSCOM


S.C. SanaHealth Physics Unit, IRE Ltd, OSCOMOrissa

4. ABSTRACT :

A simple device has been developed to measure the surfacearea of fine dust particles generated during the mineralseparation processes. The apparatus employed is a modifiedversion of Blaine Fineness Tester. It works on the principleof air permeability. Both the specific surface area andequivalent surface volume diameter of dust particles havebeen evaluated using the apparatus.

The specific surface area of air borne dust is found to be10,000 to 20,000 cm2/g for mineral dust and 20,000 to 30,000cmz/g for monazite air borne dust. When it is converted toequivalent surface volume diameter it varies from 6 urn to 12urn for mineral dust and 4 um to 6 um for monazite dust.


Completed Surface areaSurface volume

diameterMonazite dust

8. REFERENCES t

Evaluation of surface area of air borne mineral dust at IRELtd, OSCOM - S.C. Saha

207

10 . TRAINING

1. TITLE t 2. CATEGORY :

Stipendiary Training Course on 1 0 - 1Health Physics


S.P. Kathuria, S.A. Sukheswalla, M. Sundaramand S. KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

A comprehensive training course on Health Physics of dura-tion 1 year, covering the complete fuel cycle namely uraniummining and milling, fuel fabrication, reactor operation,fuel reprocessing and waste management, is conducted on anannual basis to meet the trained man power requirement.Science graduates are recruited as stipendiaries for thispurpose. The training course consists of 380 lectures, 30practicals and in-plant training. The lecture courses in-clude foundation as well as applied courses. The graspingpower and communication skill of stipendiaries is developedby assigning them individually a topic for seminar under theguidance of a senior scientist.

After completing the lecture courses and practicals in about7 months, the trainees are given in-plant training for 4months at Research and Power Reactors, Fuel ReprocessingPlant, Waste Management Facilities and Environmental SurveyLaboratories. The performance of stipendiaries is evaluatedby conducting 20 written examinations, 2 practical examina-tions and 3 viva-voces. The successful stipendiaries areposted to different units of DAE. About 125 science gradu-ates have been trained so far in 4 batches and have joinedBARC, NPCIL and AERB.

5. REMARKS t 6. STATUS t 7. KEYWORDS :

On-going Lecture coursesIn-plant trainingCommunication skill

t. REFERENCES :

Man Power Development in Health Physics, Kathuria S.P.,Swarup J. and Pillai K.C., Vaigyanik, Vol. 23, pp 71-73,1991

208


Training Course on Planning, 1 0 - 2Preparedness and Response toRadiological Emergencies


S.P. Kathuria, S.A. Sukheswalla, S. Krishnamony,B.K. Bhasin* and D.V. GopinathHealth Physics Division, BARCBOMBAY - 400 085

* Tarapur Atomic Power Station, NPCIL

4. ABSTRACT t

Off-site emergency plans are prepared for all nuclear plantswhich have potential to release radioactivity in publicdomain under accidental conditions. As a part of the plan,training courses on Planning, Preparedness and Response toRadiological Emergencies are being conducted since 1991 byHealth, Safety & Environment Group in collaboration withNuclear Power Corporation of India Ltd (NPCIL) at Tarapur.The courses are conducted for the following groups of offi-cers who have the responsibility to protect the personneland minimise the loss of equipment and property in the eventof any off-site radiation emergency:

- Senior officers from the operating plants of DAE- Medical doctors from district and DAE hospitals- Public authorities

The course duration varies from 2 days for public authori-ties to 6 days for DAE officers. The syllabi! for thesecourses were prepared in consultation with experts fromBARC, IGCAR, CMS, NPCIL and AERB. Desk top exercises arealso included in the programme. The number of participantsin each course is limited to 15-20 for close interaction andabout 130 officers have attended the courses during the last3 years.

5. REMARKS t 6. STATUS : 7. KEYWORDS :

On-going Emergency prepared-ness

Off-site emergencyplan

Desk top exercise

8. REFERENCES t

Training Programmes on Radiation Protection for IndianNuclear Facilities, Kathuria S.P. and Pillai K.C., Regional(RCA) Workshop on the Development of Training Techniques andMethods of Instruction in Radiation Protection, ANSTO,Sydney, Australia, February 17-26, 1992

209


Development of a PC-Software 'EMER' 10-3for the Educational Program onEmergency Preparedness


D. Datta, S.A. Sukheswalla, S.P. Kathuria andS. KrishnamonyHealth Physics Division, BARCBOMBAY - 400 085

4. ABSTRACT :

An interactive, menu driven* user friendly, graphics cumdata base, educational software on Emergency Preparednesscalled EMER has been developed. The algorithm of the packageconsists of two parts.(i) Graphics routine for animation ofplume dispersion and (ii) Data base supporting text informa-tion required for the projection of answers to the queriesgenerated by the package. The software is developed in anadmixture of C language and clipper language and has thedistinctive features of transperency, aesthetics and philos-ophy, self validation, user friendliness and bullet- proof-ness.

Execution of the programme displays questions and answersthrough a flat window. Concept of countermeasure are pro-jected through slides and related queries.

5. REMARKS » 6. STATUS : 7. KEYWORDS :

Completed SoftwareEmergency Prepared-

nessAnimationCountermeasures

8. REFERENCES :

Development of a PC-Software "EMER' for the EducationalProgram on Emergency Preparedness, D. Datta, S.A. Sukheswal-la, S.P. Xathuria and S. Krishnamony, Twenty First IARPConference on Radiation Protection Monitoring, OccupationalWorkers and Public, Bombay, Feb. 1-3, 1994

210

11. APPENDIX

- IAEA RESEARCH PROJECT

- THESES TITLES

- AUTHOR INDEX

IAEA RESEARCH PROJECT

1. Title Reference Asian Man

2. Agreement No. 5583/JN,A Co-ordinated Research Project

Principal Investigator Dr. H. S. DangInternal Dosimetry Section,Health Physics Division,BARC, Bombay - 400 085

Other Participants Sh. S. D. SomanDr. D. D. JaiswalSh. M. Parameswaram

5. Period of Study & Status 1989-93Nearing Completion

6. Objectives : Collection and collation ofphysical, anthropometric,Physiological, anatomical andmetabolic characteristics ofIndian population in differentage groups for application inradiation protection.

7. Present State of the Work : The work on the physical,anatomical, physiological andmetabolic characteristics ofadult population is completeand Reference values areavailable, however for youngerpopulation additional data inphysiological and metaboliccharacteristics needs to becollected.

211

THESES TITLES

Dr.D.K.Ghosh A Study of Correlations Of DustExposure With Lung Function TestParameters Among Uranium MineWorkers

University of Bombay (1992)

Ph. D. (Physics)

Guide : Dr. K.S.V.Nambi

SUMMARY :

Relationship between siliceous exposure and pulmonaryfibrosis in mining is widely recognised. Investigationswere carried out on the underground work environment inUranium mining industry to assess the dust concentra-tion and cumulative dust exposure to a cohort of minersin order to determine its impact to the lung functionparameters and subsequent comparison with radiological(X-ray) findings. Random selection of 376 miners in theage group of 22 - 56 (37 + 0.38 S.E.), with knownlife-time dust exposure, formed the cohort for thesestudies. Incidences of respiratory symptoms, withrespect to job category, dust-year and smoking habitswere evaluated. Pulmonary impairment, respiratorysymptoms and radiological abnormalities were evidentmore in smokers than in non-smokers. Regional andethnic variations in vital capacity were observed. Theeffect of age, height, smoking and dust on pulmonaryfunctions established by multivariate linear regressionanalysis on miners are presented.

212

Dr. P.M.B.Pillai : Physico Chemical • Behaviour ofAirborne Radionuclides in Radio-active Mineral Processing

Ph.D.(Chemistry)

Bombay University (1992)

Guide : Dr.K.C.Pillai.

SUMMARY :

Measurements carried out at the Minerals and Monaziteprocessing plants have shown that the mean values ofMMAD for airborne mineral dust is 4.5 urn (respirabieregion), and AMAD for Th 232 in Monazite processing is7.9 urn. In-vitro solubility studies with lung serumsimulant have shown that oxides and hydroxides ofthorium belong to inhalation class Y Pb 212 was foundto be attached to particles of mean AMAD of 0.10 urn.Deposition of Pb 212 in lungs was determined as 68%.The .deposited Pb 212 was observed to clear from thelungs with an effective half life of 6.6 hours.

213

Dr. V. Abrol : S6me problems.in hydrodynamics


Ph. D. (Applied. Mathematics)

Guide : Dr. S.V. Lavapde

SUMMAEY :

In this thesis some applied problems in the field ofhydrodynamics are considered. First we consider theproblem of long wave generation in a natuarl waterbodywith a free surface. In this the eyelone-inducedwater level variation and associated currewnt patternin Bombay harbour are studied. In the second study, theprocess of washout of gaseous air pollutants is mo-delled highlighting the reversibility of the processconsidering both the case of linear (tritiated water)and nonlinear (gaseous Iodine) washout. Thirdly weconsider the molecular dispersion of a solute in achannel when the flow is oscillating under the influ-ence of a sinusoidally varying pressure field. In thefinal study, we deal with the geophysical problem ofdouble diffusive convection when there is an additionalrestraint due to rotation in the system. Presence ofchaos and onset of turbulence is seen.

214

Shri P.N.Bhat : Studies on Environmental Distri-bution of Beryllium and onWaste Material from BerylliumProduct ion

M.Sc. (Chemistry)


Guide : Dr. K.C.Pillai

SUMMARY :

The distribution pattern of beryllium was studied innatural environmental materials near the BerylliumPlant at Vashi, New Bombay and its concentration statusin various environmental materials were obtained. Thefollowing aspects were covered in detail in the study.

1) Sampling and analysis of air, water and soil forberyllium in environment near the beryllium process-ing plant.

2) Beryllium concentrations in working environment indifferent stages of beryllium production at theberyllium processing plant. The particle size dis-tribution in the various stages of beryllium extrac-tion were also covered.

3) LeachabiIity studies of beryllium in toxic wastered-mud generated during extraction step from itscore.

4) Studies on immobilisation of leachable berylliumfrom red-mud under certain condition (i.e. fixing inconcrete mixture and casting it in block) and itsleaching characteristics over a period of about twoyears. This was taken up to get suitable method forthe disposal of toxic waste and to minimise theenvironmental impact of beryllium containing residu-al waste from processing of beryl ore.

215

Dr. G.R. Doshi : Studies on the long lived nu-clides 1-129 and C-14 in . theenvironment


Ph. D. (Chemistry)

Guide : Dr. K.C. Pillai

SUMMARY :

Chapter one contains literature survey on the naturaloccurrence, production and releases of 1-129 and C-14from nuclear reactors and reprocessing plants alongwith the discussion on various methods developed andpractised by earlier workers to study the impact ofthese radionuclides in the environment.

Chapter 2 contains a non combustion technique involvingdistillation, collection of distillate in alkalinesolution, soxhlet extraction followed by neutron irra-diation for thexdetermination of 1-129. Post irradia-tion purification steps are discussed in this chapter.This technique with certain modification has beenemployed to measure concentration of 1-129 in algae,leaf, soil, rain water, and grass samples collectednear Tarapur and within Trombay region.

Chapter 3 describes techniques developed for both C-14measurement in D20, Ion excahnge resins, stack efflu-ents. The production rates of C-14 in Apsara, Cirus andTAPS have been calculated. The release rates have beenexperimentally evaluated.

Chapter 4 deals with incorporation of C-14 in chemicalconstituents of algae, air-water interaction of C-14and metabolisom of labelled C-14 in domestic animalslike cow and hen.

216

Dr D. D. Jaiswal : Assessment of Thorium in Man andEnvironment : Application toHuman Bio-kinetics

Ph. D. (Physics)University of Bombay (1993)

Guide : Dr. C. M. Sunta

SUMMARY :

The research work was undertaken with the followingobjectives:

1) Quantitatively establish the daily intake of thori-um, its distribution in human body and rate ofexcretion through urine

2) Correlation of the above data to arrive at importantconclusions about the metabolism of Th in humansystem and to study how far it differed from thatrecommended by International Commission on Radiolog-ical Protection (ICRP) which is largely based onanimal experiments.

To achieve these objectives, relevant environmentalsamples (drinking water & air), different food ingradi-ents, duplicate diet, blood, urine of normal personsand autopsy samples of different organs from normalcases were collected and analysed for their Th concen-trations using the sensitive technique of neutronactivation analysis. Blood and urine samples of occupa-tional ly exposed persons, working in a Th plant, werealso analysed.

The data on metabolism (intake, distribution & excre-tion) of thorium obtained in this study clearly indi-cate that the biological half life (Tfc) values forthorium deposited in different compartments in humanbody are likely to be much longer than those adopted byICRP 30 (1979). Measured daily urinary Th excretion inoccupational workers was much lower than expected basedon application of the ICRP model to the body burdendata measured by whole body counting. This observationfurther supports the inference that Tfc, of thorium inhumans body is much higher than that assumed by ICRP30.

On the basis of this study, it is concluded that themetabolic model for thorium needs to be modified. Intune with this, the proposed ICRP limits of derivedurinary excretion levels for thorium in occupationalworkers would need downward revision.

217

Dr. T.M. Krishnamoorthy : Studies on predictive models forapplication in waste disposalpractices


Ph. D. (Chemistry)

Guide : Dr. K.C. Pillai

SUMMARY :

The work deals with development of predicitve modelsfor the migration of radionuclides from shallow landburial, Deep ocean disposal, Deep geological and Sub-seabed disposals.

Shallow land burial considered 5 diferent releasescenarios viz: continuous and constant release, leachflux into the ground water from single dump and multi-ple dumps through single layer and leach flux into theground water from single dump and multiple dumpsthrough a clay layer. The Ia6ch fluxes are computedbased on differential retentivity of waste forms.

Deep ocean disposal model takes into account disper-sion, geochemical elimination, decay and reflection atboundaries. The disposed solid at the sea bottom isassumed to be soluble instantly, as a first approxima-tion. Alternatively, the model is modified to take intoaccount the integrity of the canisters assuming differ-ential leaching from canisters.

Deep geological disposal model uses coupled equationsto describe behaviour of radionuclides in fracture andhost rock. The basic processes include advection anddispersion in fracture, decay and sorption in fracture;deacy, diffusion in host rock and sorption with in therock. Two componental leach flux from vitrified wasteis used as the input to the fracture.

The emplacement of vitrified waste 50 m underneathseabed is considered as an alternative option to thedeep geological disposal. Diffusion and advectioncontrolled migration of radionuclides through seabedsediments is analysed to determine the flux at sedi-ment-water boundary using geospheric model.

218

Dr K.Anthony Importance of Chemical Speciatio.nand Metal Interaction on Bioaccu-mulation and Detoxification ofCadmium, Impact on Physiologicaland Biochemical Processes inMar i ne Lame11i branchs


Ph. D. (Zoology)

Guide : Dr. B.Patel

Or.P.M.Markosa Studies on the EnvironmentalBehaviour of Radium from UraniumMill Tailings


Ph. D. (Chemistry)

Guide : Dr. K.C.Pillai

Shri G.K.Srivastava A Study of Internal ContaminationHazards and its Control in Urani-um Mining and Ore ProcessingIndustry

University of Bombay(Under review for submission)

Ph. D. (Physics)

Guide : Dr. M.E.Iyer

219

NAME

Abani M C

Abrol V

Adiga B B

Anthony K

Asokan R

Avinash Kumar

Ayappan P

Babar A K

Baburajan A

Balachandran N

Balagurunathan M R

Balaiah A

Balaiah B

Balani M C

Balwinder Kaur

Bandyopadhyay T

Bangera V S

Bapat V N

Bar M

Basu A S

Basu S K

Bhasin B D

Bhasin B K

Bhat I S

AUTHOR INDEX

ABSTRACT CATEGORY

2-21

5-8,

1-51,

1-26

1-54

5-93-16

3-2,

2-36

1-31

5-9

9-9

1-31,

1-15,

, 2-22

8-2, 8-3

, 5-6

3-4, 3-8

2-25

1-68, 1-69

8-14

7-2, 7-4, 7-10

1-12, 2-15, 2-35

1-28, 1-69, 4-1, 4-2, 4-6, 5-2, 8-6,

8-7, 8-12

1-37

7-4

6-3, 7-1

10-2

1-2, 1-5, 1-9, 1-15, 1-18, 1-22, 1-24,

Bhat P N

Bhawal R N

Borkar M D

1-35,

1-62,

2-26,

9-1

3-2

1-44

1-39, 1-44, 1-48, 1-49, 1-59,

1-67, 1-71, 1-72, 1-73, 2-9,

8-4

220

NAME ABSTRACT CATEGORY

Chakraborty S P

Chakravarty N

Chandramouli S

Chandrasekharan E

Chandy J P

Chattarj«« 0

Chaurasiya G

Challam Y

Chudalayandi K

Dalvi S A

Dang H S

Daoo V J

Dao S J

Dai M

Datta D

D«sai M V M

Dashpand* M 0

Dhandayutham R 2-33

Doshi Q R 1-21, 1-27, 1-29, 1-70, 6-7, 8-19

Dub* B 1-6, 5-9

Faby S 1-28, 5-1, 5-7

Ganapathy S 1-8, 1-32

Ganguly B M 7-9, 8-17

Garg D C 5-9

Garg S P 2-9, 2-32, 6-9, 7-8

Ghose A M 7-10

Ghoah S 7-2, 7-6

Girija Bharathan 9-4

221

7-4

7-6

1 - 2 ,6-5

1-51

1-163-2 ,1-138-91-203-21

2-351-402-102-291-285-6,1-693-2

2-9,1-626-6

19, 1-

, 2-14,

8-9

, 2-42

, 1-50,, 2 -11 ,, 2-30,, 1-51,5-7

8-11 ,

15, 1-18, 1-35, 1-48, 2-26,

5-6

, 3-12, 3-15, 3-16,

2-3, 2-4, 2-5, 2-6, 2-7,2-13, 2-16, 2-27, 2-28,2-31, 2-37, 2-38, 2-404-6, 5-1, 5-2, 5-3, 5-4,

10-3

NAME . ABSTRACT CATEGORY

Gohel C 0 2-18

Gopinath D V 10-2

Gupta R K 1-47

Gupta V K 3-5, 3-11

Gurg R P ' 1-6, 1-13, 1-36, 1-37, 1-47, 1-51, 5-6

Haridasan P P 1-57

Haridasan T K 2-1, 2-17, 2-18, 2-20, 2-39, 2-r41

Hegde A G 1-2, 19, 1-15, 1-18, 1-35, 1-48, 2-26,

2-35, 2-36, 6-5, 8-4

Hemalata P 1-22, 1-62

Hukkoo R K 8-6, 8-7

Iyengar M A R 1-8, 1-19, 1-33, 1-38, 1-52, 1-54,

1-63, 1-64, 2-14, 6-8

Iyer M R 1-59, 2-9, 2-18

Iyer R S 1-2, 19, 1-15, 1-18, 1-35, 1-48, 2-26

Jagannathan V 3-10

Jaiswal D D 1-40, 1-50, 2-4, 2-5, 2-6, 2-10, 2-11.

2-13, 2-16, 2-27, 2-31, 2-37

Joshi M L 3-20

Joshi S N 1-21, 1-29, 1-70, 8-19

Jyoti V S 2-15, 2-19, 2-35

Kale S P 1-69

Kalyanasundaram N 3-15

Kamala Rudran 2-15, 2-19, 2-24, 2-35

Kannan R K 3-10, 3-21

Kannan V 1-8, 1-38, 1-54

Kathuria S P 7-1, 10-1, 10-2, 10-3

Katoch D S 2-33

Kelkar D N 2-9

Khan A H 1-1, 1-10, 1-43, 1-53, 1-65, 1-66,

3-7, 3-9, 4-7, 6-2, 7-7

Khandekar R N 1-69

Khasnabis B K 7-4

222


Kothari B U 1-44

Krishnamachari G 2-9

Krishnamony S 1-34, 2-23, 2-39, 2-41, 3-3, 3-6,

3-17, 3-18, 3-19, 3-20, 3-21, 3-22,

4-7, 6-4, 6-6, 10-1, 10-2, 10-3

Krishnamoorthy T M 1-4, 1-51, 1-69, 4-2, 4-3, 4-4, 4-5,

4-6, 5-6, 6-7, 8-5, 8-13, 8-16, 8-19,

8-20

Krishnamurthi T N 3-5, 3-11

Krishnan D 2-12, 3-5

Krishnan V S 2-35

Krishna Rao T 2-25, 9-9

Kshirsagar R L 2-9

Kulkarhi R N 8-9

Kulkarni V V 1-69

Kumar M 5-9

Lakshmanan A R 1-3, 1-31, 2-25, 9-9

Lalchand 3-20

Londhe V S 6-1

Mahadevan T N 1-17, 1-42, 1-69, 9-1

Maniyan C G 1-61

Markose P M 1-10, 1-24, 1-55, 1-65, 3-1, 4-7

Matkar V M 1-5, 1-14, 1-22, 1-39, 1-41

Mehendarge S T 1-18, 1-48

Mehta D J 2-7, 2-33

Menon P G G 9-4, 9-6

Mohandas P G . 2-42, 3-10

Mohan Rao A M 1-69

Mohan V 3-10, 3-12, 3-15, 3-16

More A K 1-4 9

Murthy K B S 2-21, 2-22, 2-27, 6-9, 7-8

MuthukriBhnan G 7-2, 7-4, 7-10

Nair B S K 3-10, 3-16

223


Nair M G 2-11

Nair R N 1-4, 4-3, 4-5, 8-5, 8-10, 8-13, 8-16,

8-19, 8-20

Nair Suma 5-9

Nambiar P P V J 2-27

Nambi K S V 1-37, 1-69

Narayanan K K 1-7, 1-34, 2-12, 3-5, 3-6, 3-11, 3-18

Narayanan Kutty K 6-4

Narayan S 9-1, 9-2, 9-3, 9-7, 9-8

Oza Rajendra 8-18

Panchal N S 5-5

Pandit G G 1-69

Parameswaran M 1-40, 1-50, 1-60, 2-10, 2-38

Parasuram N 3-12

Patel B 1-12, 1-16, 1-25, 1-26

Patel S 1-16, 1-25

Paul A C 1-11, 1-23, 1-45, 1-46, 1-56, 1-57,

1-58, 1-59, 1-60, 1-61, 2-8

Pendharkar K A 6-4, 6-6

Pillai K C 1-5, 1-7, 1-11, 1-14, 1-21, 1-23,

1-24, 1-27, 1-29, 1-34, 1-36, 1-41,

1-46, 1-59, 1-60, 1-61, 1-62, 1-70,

2-3, 2-8, 2-10, 2-13, 2 -24, 2-28,

2-29, 2-30, 3-18, 3-20, 5-9, 8-5,

8-13, 8-20

Pillai P M B 1-11, 1-56, 1-59, 1-61

Pimpale K G 1-15, 1-18

Prasad M A 7-3, 8-15

Prem Prasad 8-9

Pullat V R 2-3, 2-5, 2-28, 2-29, 2-30, 2-37, 2-40

Purohit R G 3-22

Purwar R C 3-19

Pushparaja 2-18

Raghavayya M 1-1, 6-2

224


Raghu K 1-69

Rajagopalan S 1-3

Rajagopal V 2-14

Rajan M P 1-8, 1-33, 1-38, 1-52, 1-64

Rajaram S 1-8

Rajput H S 8-11

Raju A 9-6

Ramachandran T V 1-68

Ramamurthy A 9-2, 9-4, 9-5, 9-6, 9-7, 9-8

Rao D D 1-15, 2-36, 6-5, 8-4

Rao G P 7-11

Rao S R 6-1

Ravishankar R 7-10

Sachan S R 1-49

Sana S C 1-30, 3-13, 3-14, 9-10

Sah B M L 1-6, 1-7, 3-20, 5-9

Sankhesara B M . 1-44

Sanyasi Rao V V S 3-2, 3-4, 3-8, 8-9

Saraf R K 3-2, 3-4, 3-8

Sarkar P K 7-2, 7-3, 7-4, 7-5, 7-6, 7-9, 7-11,

8-15, 8-17

Sarma T P 1-4, 4-3, 8-5

Sastry V N 1-69, 8-10

Sathe A P 1-69

Sathi S Kumar 1-62

Saxena M B 1-47

Sebastian L 1-13

Sebastian T A 1-6, 1-13,. 1-36

Sengupta M 7-10

Senthil Kumar 8-9

Shahul Hamid P 1-54

Shankar Jha 3-7, 3-9, 6-2

Sharda Bhati 2-24, 2-34, 8-21, 8-22

Sharma L N 1-51, 5-6, 5-9

225


Sharma R C

Sharma V K

Shirvaikar V V

Singhal R K

Singh K D

Sitaraman S

Sitaraman V

Soman S D

Soundararajan S

Srivastava G K

Starkov A V

Subharamu M C

Subramanian G

Subratnan i E

Sukheswalla S A

Sundaram M

Sundararajan P

Sunderarajan AR

Sunta C M

Surendran T

Suresh Kumar S

Thampan S

Thorat D D

Thulasi Brinda A P

Tiwari H C

Tripathi R M

1-50

2-21

2-34

7-8

3-3,

5-1

1-67

8-23

5-91-17

8-23

2-6

9-7

1-43

8-17

2-12

9-1

3-10

3-22

10-1

5-9

3-5

2-1,

2-22

2-1,

1-30

2-15

9-1

1-64

3-20

1-69

, 2-1, 2-7, 2-16, 2-17, 2-18, 2-20,

, 2-23, 2-27, 2-31, 2-32, 2-33,

, 2-34, 2-37, 2-38, 2-39, 2-41, 6-9,

8-14, 8-23

, 1-71, 1-72, 1-73

, 1-42, 5-7, 8-1, 8-8, 8-14, 8-18,

, 9-6

, 1-53, 1-66, 2-2, 3-7, 3-9, 7-7

, 10-1, 10-2, 10-3

2-3, 2-4, 2-6, 2-7, 2-11, 2-21,

, 2-27

2-17, 2-18, 2-20, 2-39, 2-41

, 2-35

Usha Narayanan 1-5, 1-39, 1-67, 1-71, 1-73

226

NAME

Vardhan R S

Varughese K G

Velayudhan T

Venkataramana K

Venkataraman S (ESL)

Venkataraman S (MAPS)

Venkat Raj V

Verma P C

Vidyasagar D

Vinod Kumar A

Viswambharan K R

Viswanathan S

Vyas P V

ABSTRACT CATEGORY

2-42,1-6,1-11,3-101-20,1-20,

3-8

5-9

1-66,

1-693-101-31,

1-6,

3-12,

1-13,1-56,

1-63,3-16

3-7,

2-25 ,1-13

3-21

1-361-61

2-14,

3-9

9-9

6-8

Yadhav J R 2-35

227

Published by: Dr. M.R. Balakrishnan, Head Library & Information Services DivisionBhabha Atomic Research Centre, Bombay - 400 085, INDIA.

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