DocumentCode
3527985
Title
Time dependent neutron detector response simulation for 252Cf
Author
Prasad, Shikha ; Clarke, Shaun D. ; Miller, Eric C. ; Pozzi, Sara A. ; Larsen, Edward W.
Author_Institution
Dept. of Nucl. Eng. & Radiol. Sci., Univ. of Michigan, Ann Arbor, MI, USA
fYear
2010
fDate
Oct. 30 2010-Nov. 6 2010
Firstpage
911
Lastpage
914
Abstract
Liquid scintillator detectors are valuable for detection of special nuclear material since they are capable of detecting both neutrons and gamma rays. Furthermore, scintillators can also provide energy information which can help in identification and characterization of the source. In order to deign scintillation based measurement systems appropriate simulation tools are needed. MCNPX-PoliMi is capable of simulating scintillator detector response, however, simulations have traditionally been run in analog mode which leads to longer computation times. In this paper nonanalog MCNPX-PoliMi mode which uses variance reduction techniques is applied and tested. The nonanalog MCNPX-PoliMi simulation test case uses source biasing variance reduction technique to efficiently simulate pulse height distribution and then time-of-flight for a heavily shielded case with a 252Cf source. Neutron time-of-flight measurements are essential to nonproliferation and safeguards efforts to identify and characterize special nuclear material. The resulting simulation is marked by an improvement in the figure of merit (FOM) by a factor of 3.4.
Keywords
gamma-ray detection; liquid scintillation detectors; neutron detection; neutron sources; nuclear materials safeguards; shielding; 252Cf source; gamma ray detection; liquid scintillator detector; neutron detection; neutron time-of-flight measurement; nonanalog MCNPX-PoliMi mode; nuclear material safeguards; nuclear nonproliferation analysis; pulse height distribution; scintillation based measurement system; time dependent neutron detector response simulation; variance reduction technique; Atmospheric measurements; Computational modeling; Detectors; Laboratories; Monte Carlo methods; Neutrons; Particle measurements;
fLanguage
English
Publisher
ieee
Conference_Titel
Nuclear Science Symposium Conference Record (NSS/MIC), 2010 IEEE
Conference_Location
Knoxville, TN
ISSN
1095-7863
Print_ISBN
978-1-4244-9106-3
Type
conf
DOI
10.1109/NSSMIC.2010.5873894
Filename
5873894
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