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Title: Design of a transportable high efficiency fast neutron spectrometer

A transportable fast neutron detection system has been designed and constructed for measuring neutron energy spectra and flux ranging from tens to hundreds of MeV. The transportability of the spectrometer reduces the detector-related systematic bias between different neutron spectra and flux measurements, which allows for the comparison of measurements above or below ground. The spectrometer will measure neutron fluxes that are of prohibitively low intensity compared to the site-specific background rates targeted by other transportable fast neutron detection systems. To measure low intensity high-energy neutron fluxes, a conventional capture-gating technique is used for measuring neutron energies above 20 MeV and a novel multiplicity technique is used for measuring neutron energies above 100 MeV. The spectrometer is composed of two Gd containing plastic scintillator detectors arranged around a lead spallation target. To calibrate and characterize the position dependent response of the spectrometer, a Monte Carlo model was developed and used in conjunction with experimental data from gamma ray sources. Multiplicity event identification algorithms were developed and used with a Cf-252 neutron multiplicity source to validate the Monte Carlo model Gd concentration and secondary neutron capture efficiency. The validated Monte Carlo model was used to predict an effective area for the multiplicitymore » and capture gating analyses. For incident neutron energies between 100 MeV and 1000 MeV with an isotropic angular distribution, the multiplicity analysis predicted an effective area of 500 cm 2 rising to 5000 cm 2. For neutron energies above 20 MeV, the capture-gating analysis predicted an effective area between 1800 cm 2 and 2500 cm 2. As a result, the multiplicity mode was found to be sensitive to the incident neutron angular distribution.« less
Authors:
 [1] ;  [2] ;  [2] ;  [3] ;  [2] ;  [3] ;  [3] ;  [3] ;  [4]
  1. Univ. of California, Berkeley, CA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  3. Sandia National Lab. (SNL-CA), Livermore, CA (United States)
  4. Univ. of California, Berkeley, CA (United States); Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)
Publication Date:
Report Number(s):
SAND-2016-0134J
Journal ID: ISSN 0168-9002; PII: S0168900216302042
Grant/Contract Number:
AC04-94AL85000; NA0000979; AC02-05CH11231
Type:
Accepted Manuscript
Journal Name:
Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment
Additional Journal Information:
Journal Volume: 826; Journal Issue: C; Journal ID: ISSN 0168-9002
Publisher:
Elsevier
Research Org:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; fast neutron spectroscopy; neutron multiplicity; capture-gating
OSTI Identifier:
1343265
Alternate Identifier(s):
OSTI ID: 1359658; OSTI ID: 1439999

Roecker, C., Bernstein, A., Bowden, N. S., Cabrera-Palmer, B., Dazeley, S., Gerling, M., Marleau, P., Sweany, M. D., and Vetter, K.. Design of a transportable high efficiency fast neutron spectrometer. United States: N. p., Web. doi:10.1016/j.nima.2016.04.032.
Roecker, C., Bernstein, A., Bowden, N. S., Cabrera-Palmer, B., Dazeley, S., Gerling, M., Marleau, P., Sweany, M. D., & Vetter, K.. Design of a transportable high efficiency fast neutron spectrometer. United States. doi:10.1016/j.nima.2016.04.032.
Roecker, C., Bernstein, A., Bowden, N. S., Cabrera-Palmer, B., Dazeley, S., Gerling, M., Marleau, P., Sweany, M. D., and Vetter, K.. 2016. "Design of a transportable high efficiency fast neutron spectrometer". United States. doi:10.1016/j.nima.2016.04.032. https://www.osti.gov/servlets/purl/1343265.
@article{osti_1343265,
title = {Design of a transportable high efficiency fast neutron spectrometer},
author = {Roecker, C. and Bernstein, A. and Bowden, N. S. and Cabrera-Palmer, B. and Dazeley, S. and Gerling, M. and Marleau, P. and Sweany, M. D. and Vetter, K.},
abstractNote = {A transportable fast neutron detection system has been designed and constructed for measuring neutron energy spectra and flux ranging from tens to hundreds of MeV. The transportability of the spectrometer reduces the detector-related systematic bias between different neutron spectra and flux measurements, which allows for the comparison of measurements above or below ground. The spectrometer will measure neutron fluxes that are of prohibitively low intensity compared to the site-specific background rates targeted by other transportable fast neutron detection systems. To measure low intensity high-energy neutron fluxes, a conventional capture-gating technique is used for measuring neutron energies above 20 MeV and a novel multiplicity technique is used for measuring neutron energies above 100 MeV. The spectrometer is composed of two Gd containing plastic scintillator detectors arranged around a lead spallation target. To calibrate and characterize the position dependent response of the spectrometer, a Monte Carlo model was developed and used in conjunction with experimental data from gamma ray sources. Multiplicity event identification algorithms were developed and used with a Cf-252 neutron multiplicity source to validate the Monte Carlo model Gd concentration and secondary neutron capture efficiency. The validated Monte Carlo model was used to predict an effective area for the multiplicity and capture gating analyses. For incident neutron energies between 100 MeV and 1000 MeV with an isotropic angular distribution, the multiplicity analysis predicted an effective area of 500 cm2 rising to 5000 cm2. For neutron energies above 20 MeV, the capture-gating analysis predicted an effective area between 1800 cm2 and 2500 cm2. As a result, the multiplicity mode was found to be sensitive to the incident neutron angular distribution.},
doi = {10.1016/j.nima.2016.04.032},
journal = {Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment},
number = C,
volume = 826,
place = {United States},
year = {2016},
month = {4}
}