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7 th International Workshop on Radiation Safety, May810,2013,BNL

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Page 1: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

7th International Workshop on Radiation Safety May8‐102013BNL

CONTENTS1 Description Status of SESAME 2 Shielding objectives beam losses assumptions3 Analytical Swanson Jenkins and FLUKA (latest)4 Radiation estimations5 Gas bremsstrahlung estimations for the straight section6 Storage ring recommendations7 SESAME general strategy 8 Mazes and ducts 9 Skyshine10 XRFXAFS beamline

1277th International Workshop on Radiation Safety May8‐102013BNL

1 DescriptionStatus of SESAME

1‐ A 225MeV circular microtron hasbeen commissioned first beam was onMonday 28 November 2011 at113am2‐ The transport line from microtron tobooster (TL1)

3‐ A 800 MeV booster synchrotronsuppose t be commissioned by the endof 20134‐ The transport line from booster to storage ring (TL2)5‐ A 25GeV 400mA storage ring firstday beamlines suppose t becommissioned by the beginning of2016 (hopefully)

2277th International Workshop on Radiation Safety May8‐102013BNL

Natural emittances εx εz 256400 02564 nmrad

Decay mode Beam life time ~ 20hrs

3rd generation light source

IR

XAFSXRF

VBL

3277th International Workshop on Radiation Safety May8‐102013BNL

Booster

SR

SR

EH

21 Shielding objectives

The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation

The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear

Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear

Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear

Total number of electrons injected per year 15 1015 electronsyear

4277th International Workshop on Radiation Safety May8‐102013BNL

The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring

‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring

We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)

527

22 Beam loss assumptions

7th International Workshop on Radiation Safety May8‐102013BNL

31 Analytical formula

The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power

r

i

d

r

R

ePCE

ri

i

2

With Effective dose rate in Svh-1

Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2

P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm

The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155

Shielding material Density(gcm3)

Attenuation length (cm) for Gamma

Attenuation length (cm) for (GRN)

Attenuation length(cm) for (HEN)

Ordinary Concrete 230 213 174 2766

Pb 1135 22 142 168

Steel 787 43 127 175

Table31 Attenuation lengths and densities for different shielding materials

6277th International Workshop on Radiation Safety May8‐102013BNL

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 2: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

CONTENTS1 Description Status of SESAME 2 Shielding objectives beam losses assumptions3 Analytical Swanson Jenkins and FLUKA (latest)4 Radiation estimations5 Gas bremsstrahlung estimations for the straight section6 Storage ring recommendations7 SESAME general strategy 8 Mazes and ducts 9 Skyshine10 XRFXAFS beamline

1277th International Workshop on Radiation Safety May8‐102013BNL

1 DescriptionStatus of SESAME

1‐ A 225MeV circular microtron hasbeen commissioned first beam was onMonday 28 November 2011 at113am2‐ The transport line from microtron tobooster (TL1)

3‐ A 800 MeV booster synchrotronsuppose t be commissioned by the endof 20134‐ The transport line from booster to storage ring (TL2)5‐ A 25GeV 400mA storage ring firstday beamlines suppose t becommissioned by the beginning of2016 (hopefully)

2277th International Workshop on Radiation Safety May8‐102013BNL

Natural emittances εx εz 256400 02564 nmrad

Decay mode Beam life time ~ 20hrs

3rd generation light source

IR

XAFSXRF

VBL

3277th International Workshop on Radiation Safety May8‐102013BNL

Booster

SR

SR

EH

21 Shielding objectives

The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation

The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear

Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear

Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear

Total number of electrons injected per year 15 1015 electronsyear

4277th International Workshop on Radiation Safety May8‐102013BNL

The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring

‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring

We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)

527

22 Beam loss assumptions

7th International Workshop on Radiation Safety May8‐102013BNL

31 Analytical formula

The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power

r

i

d

r

R

ePCE

ri

i

2

With Effective dose rate in Svh-1

Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2

P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm

The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155

Shielding material Density(gcm3)

Attenuation length (cm) for Gamma

Attenuation length (cm) for (GRN)

Attenuation length(cm) for (HEN)

Ordinary Concrete 230 213 174 2766

Pb 1135 22 142 168

Steel 787 43 127 175

Table31 Attenuation lengths and densities for different shielding materials

6277th International Workshop on Radiation Safety May8‐102013BNL

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 3: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

1 DescriptionStatus of SESAME

1‐ A 225MeV circular microtron hasbeen commissioned first beam was onMonday 28 November 2011 at113am2‐ The transport line from microtron tobooster (TL1)

3‐ A 800 MeV booster synchrotronsuppose t be commissioned by the endof 20134‐ The transport line from booster to storage ring (TL2)5‐ A 25GeV 400mA storage ring firstday beamlines suppose t becommissioned by the beginning of2016 (hopefully)

2277th International Workshop on Radiation Safety May8‐102013BNL

Natural emittances εx εz 256400 02564 nmrad

Decay mode Beam life time ~ 20hrs

3rd generation light source

IR

XAFSXRF

VBL

3277th International Workshop on Radiation Safety May8‐102013BNL

Booster

SR

SR

EH

21 Shielding objectives

The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation

The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear

Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear

Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear

Total number of electrons injected per year 15 1015 electronsyear

4277th International Workshop on Radiation Safety May8‐102013BNL

The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring

‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring

We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)

527

22 Beam loss assumptions

7th International Workshop on Radiation Safety May8‐102013BNL

31 Analytical formula

The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power

r

i

d

r

R

ePCE

ri

i

2

With Effective dose rate in Svh-1

Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2

P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm

The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155

Shielding material Density(gcm3)

Attenuation length (cm) for Gamma

Attenuation length (cm) for (GRN)

Attenuation length(cm) for (HEN)

Ordinary Concrete 230 213 174 2766

Pb 1135 22 142 168

Steel 787 43 127 175

Table31 Attenuation lengths and densities for different shielding materials

6277th International Workshop on Radiation Safety May8‐102013BNL

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 4: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

3277th International Workshop on Radiation Safety May8‐102013BNL

Booster

SR

SR

EH

21 Shielding objectives

The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation

The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear

Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear

Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear

Total number of electrons injected per year 15 1015 electronsyear

4277th International Workshop on Radiation Safety May8‐102013BNL

The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring

‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring

We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)

527

22 Beam loss assumptions

7th International Workshop on Radiation Safety May8‐102013BNL

31 Analytical formula

The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power

r

i

d

r

R

ePCE

ri

i

2

With Effective dose rate in Svh-1

Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2

P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm

The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155

Shielding material Density(gcm3)

Attenuation length (cm) for Gamma

Attenuation length (cm) for (GRN)

Attenuation length(cm) for (HEN)

Ordinary Concrete 230 213 174 2766

Pb 1135 22 142 168

Steel 787 43 127 175

Table31 Attenuation lengths and densities for different shielding materials

6277th International Workshop on Radiation Safety May8‐102013BNL

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 5: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

21 Shielding objectives

The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation

The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear

Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear

Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear

Total number of electrons injected per year 15 1015 electronsyear

4277th International Workshop on Radiation Safety May8‐102013BNL

The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring

‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring

We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)

527

22 Beam loss assumptions

7th International Workshop on Radiation Safety May8‐102013BNL

31 Analytical formula

The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power

r

i

d

r

R

ePCE

ri

i

2

With Effective dose rate in Svh-1

Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2

P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm

The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155

Shielding material Density(gcm3)

Attenuation length (cm) for Gamma

Attenuation length (cm) for (GRN)

Attenuation length(cm) for (HEN)

Ordinary Concrete 230 213 174 2766

Pb 1135 22 142 168

Steel 787 43 127 175

Table31 Attenuation lengths and densities for different shielding materials

6277th International Workshop on Radiation Safety May8‐102013BNL

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 6: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring

‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring

We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)

527

22 Beam loss assumptions

7th International Workshop on Radiation Safety May8‐102013BNL

31 Analytical formula

The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power

r

i

d

r

R

ePCE

ri

i

2

With Effective dose rate in Svh-1

Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2

P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm

The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155

Shielding material Density(gcm3)

Attenuation length (cm) for Gamma

Attenuation length (cm) for (GRN)

Attenuation length(cm) for (HEN)

Ordinary Concrete 230 213 174 2766

Pb 1135 22 142 168

Steel 787 43 127 175

Table31 Attenuation lengths and densities for different shielding materials

6277th International Workshop on Radiation Safety May8‐102013BNL

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 7: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

31 Analytical formula

The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power

r

i

d

r

R

ePCE

ri

i

2

With Effective dose rate in Svh-1

Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2

P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm

The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155

Shielding material Density(gcm3)

Attenuation length (cm) for Gamma

Attenuation length (cm) for (GRN)

Attenuation length(cm) for (HEN)

Ordinary Concrete 230 213 174 2766

Pb 1135 22 142 168

Steel 787 43 127 175

Table31 Attenuation lengths and densities for different shielding materials

6277th International Workshop on Radiation Safety May8‐102013BNL

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 8: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

32 Swanson

Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows

r

i

d

e

R

ePEE

ri

i

2

6 10

r

i

d

HENR

ePE

ri

i

2

4

r

i

d

GRNR

ePE

ri

i

2

722

Where

Effective dose rate in Svh-1

P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)

Shield material Attenuation length (cm)λϒ λHEN λGRN

Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185

Table32 Attenuation length for different shielding materials in forward direction

7277th International Workshop on Radiation Safety May8‐102013BNL

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 9: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300

2

21

214

cos7201

)cosexp(26701cos9801

)cosexp(133

11063

iri

iri

e df

ecd

REJE

iGRN

iIEN

iHEN

en

ecdZ

df

ecdf

REJE

)cosexp(793cos7501

)cosexp(10cos7201

)cosexp(

11063

730

2

2

1

214

Whereeffective dose rate Ee electron energy in GeV

Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)

Shieldingmaterial

Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN

Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522

Table33Attenuation length for different shielding materials in lateral direction

827

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 10: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Table 41a Total dose rate and accumulated dose in the forward direction at different locations

41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)

Radiation loss sourceIn the direction of experimental hall

Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA

SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12

Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead

Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with

15 cm in thickness leadAnalytical Swanson

SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7

927

Fig41 SR straight sections

7th International Workshop on Radiation Safety May8‐102013BNL

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 11: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Normal operation losses and the direction losses in microSvh

Total dose rates - accumulated dose perpendicular to losses directions

Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006

Table42 Total dose rate and accumulated dose in the perpendicular directions

42 Radiation estimations (NOT GB) in all directions of the injection area

1027

Fig42 Booster to SR Injection part

7th International Workshop on Radiation Safety May8‐102013BNL

Service area

Experimental area

TL2

Fig41 SR straight sections

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 12: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

5 Gas bremsstrahlung estimations from the straight sections

Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m

Short straight section (SSS) 505m

ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar

Distance to Safety shutter 925m for SSS735 m for LSS

Real distance to ratchet wall 1035m for SSS85m for LSS

Table51a SESAME front ends parameters

1127

Fig51a Not used beamlines lateral view

7th International Workshop on Radiation Safety May8‐102013BNL

dLSSPe‐beam W

Fig51b used beamlines lateral view

LSSPe‐beam Pb

Not to Scale

Ray tracing

Lead collimators

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 13: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

atmppILE

43216-

0 10 17 10mD

by Rindi and Tromba

0

672

227-

0 10 25 (Svh)DppI

dLdL

mcE

Ferrari

by Frank

0

2

26-

0 10 3 (Svh)DXI

dLdL

mcE

Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter

12277th International Workshop on Radiation Safety May8‐102013BNL

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 14: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS

Gas bremsstrahlung Dose Rate(Svh)SSS

Rindi and Tromba 1074 0764

Ferrari 45 25

Frank 16 09

Table51b Total dose rates just before Safety shutter

t- exp D D 0A

Used formulaDose rates

After 20 cm safety shutter LSS in microSvh

Dose ratesAfter 20cm safety shutter

SSS in microSvhRindi and Tromba 025 0177

Ferrari 104 058Frank 037 021

Table51c shows the difference in the estimated values using three different empirical formulas

WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm

13277th International Workshop on Radiation Safety May8‐102013BNL

WD0 DA

t

Fig51c MSS

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 15: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added

6 Storage Ring Tunnel Recommendations

14277th International Workshop on Radiation Safety May8‐102013BNL

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 16: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like

a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall

4- Keeping some areas as controlledsupervised areas (gt 05microSvh)

7 SESAME general strategy

15277th International Workshop on Radiation Safety May8‐102013BNL

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 17: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

81Radiationstreaming fromSESAMEstorageringmazes

Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value

For the first leg gamma ray dose attenuation ratio γ1 is3

11 )L(d 022 And

3)L(d 026 ii (i=2 3hellip) for other legs

While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN

Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed

The leakage dose outside the maze can be calculated using an empirical formula given by KTesch

16277th International Workshop on Radiation Safety May8‐102013BNL

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 18: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274

Single losses in microS 0088 075

Table81 Total gamma and neutron dose rates and accumulated doses at exit doors

Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident

17277th International Workshop on Radiation Safety May8‐102013BNL

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 19: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

82 Cabling and cooling ducts radiation streaming

2

22N1N41F F)(D Svh)(D 0

LdhSv NN

2

221 41F F)(D Svh)(D 0

LdhSv

Simon‐Clifford formulaWhereD N

0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface

respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm

21221 )(cos F zxxrx

1

2 )cos(2

1 F

d1

2 )cos(2

1 F

NN

d

e‐beam

floor

Lat Sh wall

Cabling amp cooling

θ

1827

Fig82a Real duct

Fig82b Cross section duct center

x

zr

7th International Workshop on Radiation Safety May8‐102013BNL

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 20: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively

Duct dimensions

WtimesHtimesL

Total dose rate normal

operation inside duct

surface center microSvh

Total doseSingle loss inside duct surface center

microSv

Total dose rate normal loss operation

outside duct surface center

microSvh

Total doseSingle loss

outside duct surface center

microSv

Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA

10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418

1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386

a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter

Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts

19277th International Workshop on Radiation Safety May8‐102013BNL

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 21: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

9 Estimates of Skyshine

Rindi and Thomas

20

0 Svh)(D rerDa

Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public

Neutron sourcecomponent

Dose rate on theconcrete roof

mSvy

Skyshine Doseat 50 mmSvy

Skyshine Doseat 100 mmSvy

Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173

Total skyshine dose 5073 001398 000344

Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof

20277th International Workshop on Radiation Safety May8‐102013BNL

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 22: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses

Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad

Fig101 Hutches layout

Photon beam

OHEH

Ratchet wall

Control room

21277th International Workshop on Radiation Safety May8‐102013BNL

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 23: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

ComponentsPosition (m)With respect

To Notes

Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm

Be window 1134 0557 A and water cooled 250 microm thickness be window

Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2

Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)

Double Crystal Monochromator(DCM)

151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm

Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2

Exit window 275 1670 Be window with a thickness of 250 microm

Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system

VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical

HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal

Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)

Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall

2227

Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components

7th International Workshop on Radiation Safety May8‐102013BNL

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 24: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

‐1E+09

0

1E+09

2E+09

3E+09

4E+09

5E+09

6E+09

7E+09

8E+09

0 5 10 15 20 25 30

pseVmradmA

Photon energyKeV

Fig102 Photon Spectrum through C filter

0E+00

1E+10

2E+10

3E+10

4E+10

5E+10

6E+10

1 11 21 31 41

peVsecmradmA

Photon energyKeV

Fig103 Spectrum of photon source

23277th International Workshop on Radiation Safety May8‐102013BNL

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 25: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Results of STAC‐8 simulations for Optical Hutch

Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall

Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 2602 1153 1054 015

Table 104 Effective dose rates (only for SR) outside optical hutch roof

Roof wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 382 1653 016

Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall

Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 112 053 005

Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall

Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)

Effective dose rate inmicroSh

1 3653 225 4 0325

Additional lead around the photon beam tube downstream hutch wall

24277th International Workshop on Radiation Safety May8‐102013BNL

Lead hutches donation

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 26: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

92 Transport beam pipe

93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness

Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh

25277th International Workshop on Radiation Safety May8‐102013BNL

94 OH basic FLUKA simulation

Fig94a OH Lateral viewFig94b OH top view

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 27: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall

2627

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 28: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

Special thanks

Dr Y Asano

7th International Workshop on Radiation Safety May8‐102013BNL2727

7th International Workshop on Radiation Safety May8‐102013BNL

Page 29: 1. Description/Status of SESAMEAt SESAME the ALARA principle is applied by guaranteeing the radiation limits for non‐exposed workers (1mSv/y, corresponding to 0.5mSv/h, for 2000

7th International Workshop on Radiation Safety May8‐102013BNL