simulation of tagged neutron imaging technique
TRANSCRIPT
Amar Sinha, Y. Kashyap, Tushar Roy, P.S. Sarkar, Mayank Shukla
Laser and Neutron Physics section,
Bhabha Atomic Research Centre,Trombay, Mumbai -400 085
SIMULATION OF TAGGED SIMULATION OF TAGGED
NEUTRON IMAGING TECHNIQUENEUTRON IMAGING TECHNIQUE
About Our workAbout Our work
�� Imaging neutron and XImaging neutron and X--rayray
�� Imaging with low intensity neutron Imaging with low intensity neutron
sourcessources
�� Design of neutron sources Design of neutron sources ––
photoneutronphotoneutron source source --MicrotronMicrotron
�� Simulation studies for design of source Simulation studies for design of source
and its application and its application ––radiography, radiography,
tomographytomography
�� XX--ray ray –– 3D tomography, phase imaging 3D tomography, phase imaging
etcetc
�� Real time applications to high speed Real time applications to high speed
phenomenonphenomenon
Test tube
With water Zircloy piece loaded
With hydrogen
Plastic screw
14 MeV Generator
108n/s
n-scintillation
We have used Pu-Be source for
imaging – can be used for imaging at inaccesible places
Also used 108 n/s 14 MeV neutron generator
This generator is under renovation and
you may get opportunity to see this
APPLICATION DEVELOPMENTAPPLICATION DEVELOPMENT
�� 2D & 3D NEUTRON TOMOGRAPHY 2D & 3D NEUTRON TOMOGRAPHY
(USING REACTOR(USING REACTOR))
0 Volume rendered image obtained using Fig. 11 Cut away view to show broken
the broken rod.
a b
MICROTRON BASED NEUTRON SOURCEMICROTRON BASED NEUTRON SOURCE
BeTantalum
electron-photon- neutron
e
nγγγγ
Why Be?
Are there other combinations-composite
Target?
THE DESIGN FROM BASICS?
high energy electrons to produce photons
- Photons then produce neutrons through photo-neutron reaction
-Advantages are that photon yields are very high and can make up
for lower cross-sections
Why Be?
Reason –Cross-section-If using low energy accelerator Be
is the only choice –Lower Cross-section is compensated by utilization of large softer spectrum between 1.66 and 3 MeV.
At Higher EnergiesBe cross-section lowerby several factors
For Higher Electron
Energy –use composite Target Be for lower part
Of spectrum and U for
Higher energy component
DESIGN OF MICROTRON BASED DESIGN OF MICROTRON BASED
NEUTRON SOURCE AND NEUTRON SOURCE AND
APPLICATIONSAPPLICATIONS
�� Electron beam Electron beam -- 99--12 MeV12 MeV
�� current current --30mA(peak), 1030mA(peak), 10µµµµµµµµA (avg..)A (avg..)
�� Pulse width Pulse width –– 2.7 2.7 µµµµµµµµss
�� Pulse repetition rate: 50Pulse repetition rate: 50--250 Hz(max)250 Hz(max)
�� Bremsstralung Target Bremsstralung Target --tantalumtantalum�� Expected photon yield at 9 MeV electron energy : Expected photon yield at 9 MeV electron energy :
6x106x101313 p/s and for 12 MeV : 9.7 x10p/s and for 12 MeV : 9.7 x101313p/s (Ep/s (Ephph>1.67 >1.67 MeV) MeV)
�� TargetTarget-- BeBe--Uranium compositeUranium composite
�� our design 4cm Be in front optimum+1cm Uour design 4cm Be in front optimum+1cm U
�� Present Present ––30 30 mAmA, 2 , 2 µµµµµµµµss ,50 Hz ,50 Hz –– 2x102x109 9
n/sn/s --6 6 µµµµµµµµAA
�� expected yield of neutron for 9 expected yield of neutron for 9 MeVMeVelectron with optimized target design electron with optimized target design : ~2x10: ~2x101010n/s ,For 12 n/s ,For 12 MeVMeV: ~4x10: ~4x101010n/sn/s
High Pressure Physics Division, BARCHigh Pressure Physics Division, BARC
E- 9 MeV; Rep rate: 50Hz ; Pulse width: 2µµµµs
Peak Current:30mA
Thickness of Be Experimental
n/Sec
Simulation
2cm 1.4361*109 1.34*109
4cm 2.2866*109 2.25*109
6cm 2.6024*109 2.91*109
8cm 3.0708*109 3.37*109
Polyethylene Be Uranium
Lead
Thermal Neutron Radiography
In collaboration with other institutionsWe are part of a team designing indigenous high energy cargo system – our responsibility in
this project is high energy x-ray imaging system
Is High Energy cargo XIs High Energy cargo X--ray inspection system ray inspection system
––also a neutron source???also a neutron source???
Can Electron accelerators used as photo neutron sourcesCan Electron accelerators used as photo neutron sources
be used for elemental characterization??be used for elemental characterization??
��There are serious obstacle to this approachThere are serious obstacle to this approach--
��What about the enormous high energy XWhat about the enormous high energy X--ray photons which ray photons which
are the source of neutrons itself are the source of neutrons itself --background???? background???? --Is there Is there
a solution to this?a solution to this?
��if it can be used it provides cheaper solution and can act if it can be used it provides cheaper solution and can act
as second check with no extra generatoras second check with no extra generator
This possibility –actually next part of CRP
What has been our What has been our
interest in this CRPinterest in this CRP
Aim has been evaluation of various methods for the detection of illicit materials in marine cargo, vehicles
In particular we are interested in exploring Associated Particle Imaging method , exploring use of PTFNA for vehicle borne explosives, Photo-neutron sources for cargo inspection
Our focus has been on simulation studies of such systems
We also plan to develop detection system for photo neutron sources.
AIM OF PRESENT CRPAIM OF PRESENT CRP
�� Simulation of tagged Neutron based Simulation of tagged Neutron based
techniques and elemental techniques and elemental
characterization for illicit materials and characterization for illicit materials and
explosivesexplosives
�� Development of reconstruction Development of reconstruction
algorithm for prompt gamma spectrum algorithm for prompt gamma spectrum
and their testing for 3D imaging of and their testing for 3D imaging of
explosives and illicit material and explosives and illicit material and
detection of fissionable material.detection of fissionable material.
�� Feasibility of explosive detection and Feasibility of explosive detection and
elemental characterization using elemental characterization using
photoneutronphotoneutron and/or isotope based and/or isotope based
sourcesource
Key signatures inelastic gamma C , O, N
For explosives and in case illicit Materials lines of Cl.
Neutron based explosive detection methodsdetect explosives by identifying their
elemental components.
Simulations : Neutron based techniques
What useful info can be What useful info can be
obtainedobtained
Explosive detection Explosive detection
technique using neutronstechnique using neutrons
We feel API method also called tagged Neutron Method has potential to be used in large cargo/container scanning which is of interest to us.
We are coordinating with several agencies in evaluation of such system and for this reason we are evaluating several technologies including API system
Basics of TaggingBasics of Tagging
Simulation to evaluate the technique
Simulation ModelSimulation Model
VARYING DENSITY OF ORGANIC / METALLIC MATRIX
Cargo 250 (W), 250 (H), 100 (L)
50 X 50 X50 cm3
Detector moduleDetector module
NaI detector 5 inch dia 10 inch length
TOP DETECTOR RESPONSE AS A TOP DETECTOR RESPONSE AS A
FUNCTION OF TIMEFUNCTION OF TIME
Tagging Interval
signal to noise ratio increases in 30-50ns time interval indicating presence of an anomaly
FRONT DETCTOR FRONT DETCTOR
RESPONSE AS A RESPONSE AS A
FUNCTION OF TIMEFUNCTION OF TIME
Tagging interval
TOP detector response TOP detector response
Increase signal
Count vs individual detector position
Front detector responseFront detector response
CONCLUSIONCONCLUSION
�� TOP detectors are more sensitive TOP detectors are more sensitive
to the presence of anomaly due to to the presence of anomaly due to
absence of less direct neutronsabsence of less direct neutrons
�� One can use more efficient TOP One can use more efficient TOP
detector array while simple detector array while simple NaINaI will will
suffice in front panel of detectors suffice in front panel of detectors
with reduced numberswith reduced numbers
�� If contribution of direct neutrons If contribution of direct neutrons
can be avoided front detectors may can be avoided front detectors may
be of great value. be of great value.
Case study Case study
�� Varying explosive quantityVarying explosive quantity
�� Varying explosive locationVarying explosive location
�� Varying density of embedded Varying density of embedded
matrixmatrix
�� Different types of material such Different types of material such
as Nylon, Cocaine etcas Nylon, Cocaine etc
200kg explosive in 200kg explosive in
0.2gm/cc0.2gm/cc
N14 C12N14
O16
sum of counts of all top detector
in 27-45ns
200kg explosive in 200kg explosive in
0.2gm/cc0.2gm/cc
N14 C12N14
O16
Front DetectorFront Detector
C12
O16
100kg of explosive in 100kg of explosive in
0.2gm/cc0.2gm/cc
12C 12O
Front detectorsFront detectors
50kg explosive in 50kg explosive in
0.2gm/cc0.2gm/cc
Front Front detctorsdetctors
25kg explosive in 25kg explosive in
0.2gm/cc matrix0.2gm/cc matrix
FRONT DETECTORSFRONT DETECTORS
CONCLUSIONSCONCLUSIONS
�� As the explosive quantity As the explosive quantity
decreases it becomes difficult decreases it becomes difficult
to detect the explosivesto detect the explosives
200kg in 0.5gm/cc 200kg in 0.5gm/cc
matrixmatrix
FRONT DETECTORSFRONT DETECTORS
100Kg in 0.5gm/cc 100Kg in 0.5gm/cc
matrixmatrix
FRONT DETECTORSFRONT DETECTORS
50Kg in 0.5gm/cc 50Kg in 0.5gm/cc
matrixmatrix
FRONT DETECTORSFRONT DETECTORS
25Kg in 0.5gm/cc 25Kg in 0.5gm/cc
matrixmatrix
FRONT DETECTORSFRONT DETECTORS
CONCLUSIONSCONCLUSIONS
�� For high density matrix the For high density matrix the
detection of small quantity of detection of small quantity of
explosive/illicit material using explosive/illicit material using
this technique is not possiblethis technique is not possible
�� This imposes a limit on This imposes a limit on
minimum detectable quantity of minimum detectable quantity of
such materials in a high such materials in a high
density matrixdensity matrix
25 kg explosive in 25 kg explosive in
0.5gm/cc matrix located 0.5gm/cc matrix located
near to top detectorsnear to top detectors
25 kg explosive in 25 kg explosive in
0.5gm/cc matrix located 0.5gm/cc matrix located
away from top detectorsaway from top detectors
100 kg explosive in 100 kg explosive in
0.5gm/cc matrix located 0.5gm/cc matrix located
away from top detectorsaway from top detectors
ConclusionConclusion
�� Location of detectors with Location of detectors with
respect to explosive plays a respect to explosive plays a
important role.important role.
�� Double sided scanning may Double sided scanning may
help to improve the possibility help to improve the possibility
of detection of explosivesof detection of explosives
Cocaine in a organic Cocaine in a organic
matrix of 0.5gm/cc matrix of 0.5gm/cc
ConclusionConclusion
�� Organic matrix has self Organic matrix has self
background which may be background which may be
sufficient to shield these sufficient to shield these
materials if put in high density materials if put in high density
matrixmatrix
�� Need additional tool or Need additional tool or
information to distinguish these information to distinguish these
from organic materialsfrom organic materials
100kg Nylon in metallic 100kg Nylon in metallic
matrix of 0.5gm/ccmatrix of 0.5gm/cc
ConclusionConclusion
�� Materials such as nylon can be Materials such as nylon can be
easily distinguished by weak easily distinguished by weak
presence of Opresence of O1616 signature signature
�� However as stated earlier However as stated earlier
organic cargo scanning need organic cargo scanning need
special treatment to improve special treatment to improve
signal to noise ratiosignal to noise ratio
Overall CONCLUSIONOverall CONCLUSION
�� Detection of explosive with Detection of explosive with
Tagged Neutron method will be Tagged Neutron method will be
dependent of several factorsdependent of several factors�� Quantity of explosiveQuantity of explosive
�� Matrix densityMatrix density
�� Type of matrixType of matrix
�� Location of explosive in the cargoLocation of explosive in the cargo
�� Nature of surrounding matrixNature of surrounding matrix
�� Nature of background etcNature of background etc
Next 18 months planNext 18 months plan
Continuation of these simulation studies of tagged Continuation of these simulation studies of tagged
neutron system to know its limitations and potentials neutron system to know its limitations and potentials
--also for vehicle borne system and smaller luggage. also for vehicle borne system and smaller luggage.
�� Simulation of PTFNA method for medium sized Simulation of PTFNA method for medium sized
system such as vehicle borne explosive systemsystem such as vehicle borne explosive system
Analysis of various scenarios such asdifferent explosive quantities within organic
Medium of various densities
-Simulation for testing suitability of Tagged neutron method for smaller objects
Fast Neutrons
Thermal Neutrons
10 µs 90 µs
Reactions
Gamma
Elements
(n,n’γ), (n,pγ)
Prompt
C, O
(n,γ)
Prompt
H, S, Cl, Fe, N ...
Activation
(n,α), (n,p)
Delayed
O, Al, Si
Feasibility study of using high energy XFeasibility study of using high energy X--ray ray
system for simultaneous neutron inspectionsystem for simultaneous neutron inspection
�� As it was discussed earlier, there are major problem As it was discussed earlier, there are major problem such as high primary gamma. However many of the such as high primary gamma. However many of the electron electron LinacLinac that are being used for cargo scanning that are being used for cargo scanning are high rep rate pulsed system (a few microare high rep rate pulsed system (a few micro--sec sec
pulsed) pulsed)
�� One of the solutions to the problem of detecting neutron One of the solutions to the problem of detecting neutron induced gamma in presence of primary gamma could induced gamma in presence of primary gamma could bebe to gate the detector system such that first to gate the detector system such that first few microfew micro--sec the detector system is shutoff.sec the detector system is shutoff.
�� Such a concept will be tested by simulationSuch a concept will be tested by simulation
�� This will be followed by testing this concept on This will be followed by testing this concept on microtronmicrotron based neutron system which also based neutron system which also has similar characteristics. has similar characteristics.
Fast Neutrons
Thermal Neutrons
10 µs 90 µs
Reactions
Gamma
Elements
(n,n’γ), (n,pγ)
Prompt
C, O
(n,γ)
Prompt
H, S, Cl, Fe, N ...
Activation
(n,α), (n,p)
Delayed
O, Al, Si
Decision algorithm Decision algorithm
DevelopmentDevelopment
�� As pointed out by Prof As pointed out by Prof
KuznetsovKuznetsov and Prof and Prof LanzaLanza, the , the
decision making algorithm decision making algorithm
plays important role.plays important role.
�� We plan to address this We plan to address this
problem in next part of CRP.problem in next part of CRP.