Fast neutron multiplicity counting (FNMC) analysis method is a new nondestructive method for nuclear materials, which defines sample plutonium quality by the fast neutron detection array with multiplicity counting technique. Referring to the most advanced FNMC experimental device, fast neutron multiplicity counter model was constructed in this paper. A series of typical plutonium material sample models were designed, which includes the plutonium metal with different isotopic abundance and different quality and the plutonium oxide. The correctness of the equations and the necessity to amend the original equation were verified by computer simulated measurement through C++ language programming with the help of Geant4 simulation toolbox, fission software library function by Lawrence Livermore National Laboratory, and the IAEA provided neutron reaction data in Geant4 format. The simulation results showed the advantage of the new equation calculations than original equation calculations and the error of the new equations is less than half of that of the original equations.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5004-6
PROCEEDINGS PAPER
Fast Neutron Multiplicity Simulation of Nuclear Material Based on Geant4
Sufen Li,
Sufen Li
Xi’an Jiaotong University, Xi’an, China
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Suizheng Qiu,
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
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Quanhu Zhang,
Quanhu Zhang
Xi’an Research Institute of Hi-Tech, Xi’an, China
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Yonggang Huo,
Yonggang Huo
Xi’an Research Institute of Hi-Tech, Xi’an, China
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Limin Liu
Limin Liu
Xi’an Jiaotong University, Xi’an, China
Search for other works by this author on:
Sufen Li
Xi’an Jiaotong University, Xi’an, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
Quanhu Zhang
Xi’an Research Institute of Hi-Tech, Xi’an, China
Yonggang Huo
Xi’an Research Institute of Hi-Tech, Xi’an, China
Limin Liu
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE24-61015, V004T11A015; 6 pages
Published Online:
October 25, 2016
Citation
Li, S, Qiu, S, Zhang, Q, Huo, Y, & Liu, L. "Fast Neutron Multiplicity Simulation of Nuclear Material Based on Geant4." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T11A015. ASME. https://doi.org/10.1115/ICONE24-61015
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