Neutron Detection Spring 2002
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1 Neutron Detection Spring 2002
2 Neutrons vs. X-rays
3 Ideal Large Detector Pulse Height
4 Neutron Interactions
5 Total Cross section for Moderators
6 Neutron Slowing Down
7 Neutron Histories in Moderated Detector
8 Inelastic Neutron Scattering
9 Elastic Scattering Kinematics
10 Elastic Scattering Kinematics
11 Recoil Proton Energy for Monenergetic Neutrons
12 Neutron Moderator Energy Distributions
13 Pulse Height vs. Energy in Plastic
14 Recoil Spectrum Distortion in Plastic
15 Fission Cross section for Slow Neutrons
16 Fission Cross section for Fast Neutrons
17 Fission Fragments
18 Cross section for Neutron Detector Reactions
19 Some Reactions for Neutron Detectors n+ 3 He p+ 3 H kev n B á Li MeV (94%) á Li MeV (6%) n+ 6 Li 3 H + á + ~ 4.8 MeV
20 He-3 and Li-6 Cross sections
21 He-3 Detector Spectrum
22 BF-3 Pulse Heights
23 Wall Effects
24 Degradation of BF3 Counters
25 Neutron Scintillator Choices Thermal ( < 0.5 ev) load scintillator with materials with high capture crosssection such as Li. B, Gd Epithermal (0.5 ev - 50 kev) Moderate neutrons and then use thermal techniques Fast neutrons (> 50 kev) detect through (n,p) or (n,d) elastic scatters hydrogen rich materials such as plastic scintillators
26 Neutron Scintillators
27 Li Scintillators - Glass and Phosphors Neutron Energy Glass Type Glass Thickness ev All types mm Thermal GS mm 10 ev KeV GS mm 100 ev - 1 MeV GS mm KeV KG2, GS mm 1-6 Mev GS20 25 mm 6 3 n+ Li H + α + ~ 4.8 MeV
28 Li Glass Pulse Height Response
29 Applications of Neutron Detection Reactors
30 PWR Out of Core Instruments
31 PWR Ranges
32 Instrument Requirements Start-up gamma Flux dominates require discrimination against gammas pulse mode possible Intermediate gamma still important switch to current mode reject gammas» CIC» MSV Full Power gammas not important simplicity for safety ion chambers
33 Compensated Ion Chamber
34 Mean Square Value Counter
35 BWR Ranges
36 BWR In-Core Fission Counter
37 Memory Effects
38 Operating Voltages
39 Self powered Neutron Detector
40 Applications of Neutron Detection Radiography
41 707 Body Panel
42 Fast Neutron Radiograph
43 C, O, and N Cross-sections
44 Nitrogen Cross-section
45 Early Experiment at NAC Cross section: barns Total Neutron Cross Section H1 C12 N14 O En: MeV Detecting explosives by taking difference of two radiographic images. The contrast comes from nitrogen and oxygen.
46 High Resolution Neutron Images
47 Resonant Images of Carbon
48 Neutron Resonance Radiography 9 Figure 1. Total Neutron Cross Section 8 7 H1 C12 N14 O16 Cross Section: barns N off N on C off O on C on O off En: Mev
49 Resonance Radiography Drug simulant Explosive simulant En=2.37MeV H:1.5g C:16.3g N:0.9g O:5.2g H:1.0g C:7.1g N:7.1g O:12.3g C:10.6g H:1.8g C:10.6g N:24.9g O-At-Valley/O-On-Res. Graphite Melamine 200 N-Off-Res./N-On-Res C-Off-Res./C-On-Res
50 Composite Picture
51 D-D Kinematics 10 8 Outgoing Neturon Energy (MeV) Incoming Deuteron Energy (MeV)
52 Using a D-D Neutron Source Ed = 2.3MeV Ed=0.8MeV (thick target) Different energies are obtained by rotating object-detector assembly around the source D-D Neutron Energy at Different Angles Deuteron Target 0 o En: MeV o 25 o Ed: MeV 115 o 100 o 90 o 80 o 70 o 50 o 60 o Object Detector
53 A terrorist overnight bag Simulation of NRR Bag size: 40 X 30 X 10 cm. Contents of interest: a bag of sugar (105g), a stash of cocaine- HCl (105g), a paperback book, a block of plastic explosive (270 g). Heavily loaded with various of items and has an average density of around 0.5g/cm 3. Source-Object: ~150cm; Object-Detector: ~50cm.
54 Neutron and X-Ray Images Neutron Image(0 degree) X-Ray Image(140kev) Simulations were run on Blue Pacific supercomputer at Lawrence Livermore National Laboratory, with 5x10 8 source particles for each image.
55 Elemental Mapping
56 All Element Mapping Other Elements Mapping 0.3 All Elements Mapping Elements other than H, C, N, O are reported as one component All-elements mapping is the total projected content. (atoms/cm 2)
57 Detecting Mines
58
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