Neutron Detection Spring 2002

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Transcription:

Neutron Detection 22.104 Spring 2002

Neutrons vs. X-rays

Ideal Large Detector Pulse Height

Neutron Interactions

Total Cross section for Moderators

Neutron Slowing Down

Neutron Histories in Moderated Detector

Inelastic Neutron Scattering

Elastic Scattering Kinematics

Elastic Scattering Kinematics

Recoil Proton Energy for Monenergetic Neutrons

Neutron Moderator Energy Distributions

Pulse Height vs. Energy in Plastic

Recoil Spectrum Distortion in Plastic

Fission Cross section for Slow Neutrons

Fission Cross section for Fast Neutrons

Fission Fragments

Cross section for Neutron Detector Reactions

Some Reactions for Neutron Detectors n+ 3 He p+ 3 H + 765 kev n+ 10 5 B á + 7 3 Li + 2.310 MeV (94%) á + 7 3 Li + 2.792 MeV (6%) n+ 6 Li 3 H + á + ~ 4.8 MeV

He-3 and Li-6 Cross sections

He-3 Detector Spectrum

BF-3 Pulse Heights

Wall Effects

Degradation of BF3 Counters

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

Neutron Scintillators

Li Scintillators - Glass and Phosphors Neutron Energy Glass Type Glass Thickness 0.01-20 ev All types 0.1-10 mm Thermal GS20 1.3 mm 10 ev - 100 KeV GS20 3.2 mm 100 ev - 1 MeV GS20 25.4 mm 1-600 KeV KG2, GS20 9.5 mm 1-6 Mev GS20 25 mm 6 3 n+ Li H + α + ~ 4.8 MeV

Li Glass Pulse Height Response

Applications of Neutron Detection Reactors

PWR Out of Core Instruments

PWR Ranges

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

Compensated Ion Chamber

Mean Square Value Counter

BWR Ranges

BWR In-Core Fission Counter

Memory Effects

Operating Voltages

Self powered Neutron Detector

Applications of Neutron Detection Radiography

707 Body Panel

Fast Neutron Radiograph

C, O, and N Cross-sections

Nitrogen Cross-section

Early Experiment at NAC Cross section: barns 18 16 14 12 10 8 6 4 2 Total Neutron Cross Section H1 C12 N14 O16 0 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 En: MeV Detecting explosives by taking difference of two radiographic images. The contrast comes from nitrogen and oxygen.

High Resolution Neutron Images

Resonant Images of Carbon

Neutron Resonance Radiography 9 Figure 1. Total Neutron Cross Section 8 7 H1 C12 N14 O16 Cross Section: barns 6 5 4 3 2 N off N on C off O on C on O off 1 0 0.5 1 1.5 2 2.5 En: Mev

Resonance Radiography Drug simulant 50 100 150 200 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 50 100 150 200 O-At-Valley/O-On-Res. Graphite 50 100 150 Melamine 200 N-Off-Res./N-On-Res. 50 100 150 200 C-Off-Res./C-On-Res. 50 100 50 100 150 150 200 200 50 100 150 200 50 100 150 200

Composite Picture

D-D Kinematics 10 8 Outgoing Neturon Energy (MeV) 6 4 2 0 0 1 2 3 4 5 6 7 8 9 10 Incoming Deuteron Energy (MeV)

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 6.5 6 5.5 5 0 30 60 90 120 D-D Neutron Energy at Different Angles Deuteron Target 0 o En: MeV 4.5 4 40 o 25 o 3.5 3 2.5 2 0 0.5 1 1.5 2 2.5 3 Ed: MeV 115 o 100 o 90 o 80 o 70 o 50 o 60 o Object Detector

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.

Neutron and X-Ray Images Neutron Image(0 degree) X-Ray Image(140kev) 50 50 100 100 150 150 200 50 100 150 200 200 50 100 150 200 Simulations were run on Blue Pacific supercomputer at Lawrence Livermore National Laboratory, with 5x10 8 source particles for each image.

Elemental Mapping

All Element Mapping Other Elements Mapping 0.3 All Elements Mapping 0.6 0.25 0.5 50 0.2 50 0.4 100 0.15 0.1 100 0.3 0.2 150 0.05 150 0.1 200 50 100 150 200 0-0.05 200 50 100 150 200 0 Elements other than H, C, N, O are reported as one component All-elements mapping is the total projected content. (atoms/cm 2)

Detecting Mines