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Brookhaven Science AssociatesU.S. Department of Energy
Stand-off Nuclear Radiation Detection
Peter E. VanierDetector Development and Testing Div.
Nonproliferation and National Security Dept.Brookhaven National Laboratory
Presented at the 18th Annual NDIA
Special Operations / Low Intensity Conflict Symposium and Exhibition
Hyatt Crystal CityFebruary 26 –28, 2007
BROOKHAVEN NATIONAL LABORATORY SITEBROOKHAVEN NATIONAL LABORATORY SITE
• Established in 1947 on Long Island, Upton, New York, Brookhaven is a multi-program national laboratory operated by Brookhaven Science Associates for the U.S. Department of Energy (DOE).
• Six Nobel Prizes have been awarded for discoveries made at the Lab.
• Brookhaven has a staff of approximately 3,000 scientists, engineers, technicians and support staff and over 4,000 guest researchers annually.
• Brookhaven National Laboratory's role for the DOE is to produce excellent science and advanced technology with the cooperation, support, and appropriate involvement of our scientific and local communities.
Collision of gold nuclei at RHIC
Camp Upton
Lab work with Industry:Radiation Portal Monitor Testing and Evaluation
Lab work with Industry:Radiation Portal Monitor Testing and Evaluation
Lab work with Industry:Cadmium Zinc Telluride material evaluation
Lab work with Industry:Cadmium Zinc Telluride material evaluation
Synchrotron Radiation
10-µm pinhole
10x10-μm2
beam
CZT planar detector
Translation stage
Correlations between x-ray map & IR imageThis x-ray map shows the degraded regions precisely correspond to Te precipitates on the right
This IR image shows Te precipitates, which could be identified by shape with IR microscope
100% correlations were found for all CZT samples tested in this work.
Lab Work with Industry – Compressed Xenon Spectrometers
0
20
40
60
80
100
120
140
100 150 200 250 300 350 400 450 500
ENERGY (keV)
375 keV
414 keV
451 keV
208 keV
333 - 345 keV
Pu-239 spectrum using xenon
Operate at room temperatureSufficient resolution to identify isotopesScalable to large volumes - increased sensitivityIdentify special nuclear materialsAllow passage of medical isotopesAllow naturally occurring radioactive materialsReduce false positive rate
planar design
CTC coaxial design
Microelectronics Group
AREAS OF EXPERTISE• CMOS monolithic circuits
• charge-sensitive sensor interface
• analog signal processing
• low noise, low power techniques
• VLSI custom design + layout
High-speed, radiation-tolerant sampling/digitizing board
Gamma Imaging
National Security
Gamma spectrometer for detection of nuclear materials
Gamma spectrometer for detection of nuclear materialsPositron emission tomograph for
imaging the awake animal brain Positron emission tomograph for imaging the awake animal brain
240-channel multichip module for Si drift detector readout
240-channel multichip module for Si drift detector readout
Handheld imaging probe for gamma radiation
Handheld imaging probe for gamma radiation
0 200 400 600 800 1000 12000
200
400
60057CoFWHM ≈ 3.8% at 122keV
CZT 3x3x7 mm3
Peaking Time τP ≈ 1.2µs
Cou
nts
Channel
57Co spectrum
CZT pixel
reset
high-ordershaper
baseline stabilizer
to external ADC
amplitude and timing extractor
chargepreamplifier
shaper back-end processing & data concentration
CZT pixel
reset
high-ordershaper
baseline stabilizer
to external ADC
amplitude and timing extractor
chargepreamplifier
shaper back-end processing & data concentration
Preamplifier/shaper ASIC block diagramPreamplifier/shaper ASIC block diagram
Low-power ASICs
p+ substratep- epitaxial layer
light shield
nwell photodiode
MOSFET circuitry
2 - 5 μm
light shield
Radiation sensitive pixel readout
Radiation sensitive pixel readout
Technology investment by BNL that can be helpful in solving SOLIC challenges
• Assume that terrorists will use any means to get attention, including radioactive materials
• Develop of new radiation detectors– Gamma spectrometers– Neutron imagers
• Improve interdiction of radioactive materials traffic– Force protection from Radiation Dispersal Devices– Force protection from Improvised Nuclear Devices
Interrogation of containers and trucks
Accelerator
Gamma spectrometer or neutron imager
Container
Target
n,γ
n,γ
Directional Detection and Imaging
• Pinhole camera• Poor sensitivity
FISSION SOURCE
MODERATORPINHOLE
He-3 WIRE CHAMBER
neutron
4. Cadmium-linedcoded aperture camera
Thermal Neutron Imager
G(i,j)
Reconstructing the image from the shadowgram
(-1)
(+1) R(k,l) = N(i, j)G(k + i,l + j)j=1
r
∑i=1
r
∑
N(i,j)
SHADOWDATAN(i,j)
MASK ARRAYG(k,l)
G(i,j)
Reconstructing the image from the shadowgram
(-1)
(+1) R(k,l) = N(i, j)G(k + i,l + j)j=1
r
∑i=1
r
∑
N(i,j)
Actually, use Fast Fourier Transforms
Lab test of imaging capability
Three 10-cm cubes of polyethylene, with two Cf-252 sources embedded(courtesy of A. Caffrey, INL)
20 cm
Neutron image
R = 300 cm, f = 30 cm
Neutron image
R = 300 cm, f = 30 cm
20 cm
Tests in the lab
Photograph Neutron Image
BPE Shielding Wooden wedge
Neutron sourcebehind
paraffin cylinder
Tests in the field
Thermal neutronimage
Spent nuclear fuel storage casks at Idaho National Lab
SOURCE IN TRUNK OF CAR THERMAL NEUTRON IMAGE
0
1
2
3
4
5
6
7
8
0 50 100 150 200 250 300
PIXEL INTENSITY
NU
MB
ER O
F PI
XELS
BACKGROUND
SOURCE
PIXEL INTENSITY HISTOGRAM
Count rate as a function of distance
0.001
0.01
0.1
1
10
100
1000
0.1 1 10 1000.001
0.01
0.1
1
10
100
1000
0.1 1 10 100
corridorcartheory
CO
UN
T R
ATE
(cps
)
DISTANCE (m)
Simple attenuation model for neutron point source in air
0.1
1
10
100
1000
10000
100000
1 10 100
r (m)
Neu
tron
flux
Direct ThermalFastTotal scattered
Fast neutron mfp ~ 100 m
Direct thermal neutron mfp ~ 20 m
Scattered
Detectors can be scaled up to increase count rates
20 cm x 140 cm
100 cm x 100 cm
Active interrogation• A pulsed electron accelerator
produces high-energy x-rays (10-MeV) to generate photonuclear reactions
• Nuclear materials will undergo photofission and generate prompt and delayed neutrons
• The delayed neutrons continue to be emitted after each prompt neutron emission
D.R. Norman, J.L. Jones, K.J. Haskell, P. Vanier and L. Forman, IEEE NSS-MIC Conference Record, October 23-29, 2005
Active Interrogation with Imaging
10 MeV electron accelerator
Neutron imagerContainer
n
X-ray continuum
D.R. Norman, J.L. Jones, K.J. Haskell, P. Vanier and L. Forman, IEEE NSS-MIC Conference Record, October, 2005
Image analysis
0
2
4
6
8
10
12
1 51 101 151 201 251
Relative Neutron Intensity
• Depleted uranium in polyethylene– 6.5-17.5 ms image window– 69k neutrons, mean = 72, σ
= 28
Image 2• Tungsten in polyethylene– 6.5-17.5 ms Image window– 17k neutrons, mean = 122, σ
= 41
Neutron Response for Image 3
0.1
1
10
100
1000
10000
100000
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20
Time (ms)
Cou
nts
DU PNDDU Bare He-3W PNDW Bare He-3 Imaging Window
0
2
4
6
8
10
12
1 51 101 151 201 251
Relative Neutron Intensity
PIXEL INTENSITY HISTOGRAMS
6 σ
• Use time gate to distinguish prompt neutrons from delayed fission
8-element fast neutron double-scatter spectrometer
Experimental data, Fast neutron source centered
Plane spacing = 50 cm, Range = 100 cm
Large area fast-neutron double-scatter directional detector
Area 40 cm x 100 cmModular design is expandable
• Directional detection helps find a neutron source in a uniform background
• There are few naturally occurring neutrons• Ongoing issues
– Detector size – Efficiency– Angular resolution– Uniformity– Gamma rejection– Spectroscopy
CONCLUSIONS
Acknowledgement
The BNL Detector Development and Testing Division is grateful for continuing support from
DOE NA-22, DHS and DTRA