MC simulation of thermal neutron flux of large samples irradiated by 14 MeV neutrons |
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| Authors: | BAI Yunfei WANG Dezhong MAUERHOFER Eric KETTLER John |
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| Affiliation: | [1]School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 200240 Shanghai, China [2]Institute of Energy Research IEF-6： Safety Research and Reactor Technology, Forschungszentrum Jiilich GmbH, 52425 Jiilich, Germany |
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| Abstract: | The response of a 14 MeV neutron-based prompt gamma neutron activation analysis (PGNAA) system, i.e.the prompt gamma-rays count rate and the average thermal neutron flux, is studied with a large concrete sample and with a homogeneous large sample, which is made of polyethylene and metal with various concentrations of hydrogen and cadmium using the MCNP-5 (Monte Carlo N-Particle) code. The average thermal neutron flux is determined by the analysis of the prompt gamma-rays using the thermal neutron activation of hydrogen in the sample, and the thermal and fast neutron activation of carbon graphite irradiation chamber of the PGNAA-system. Our results demonstrated that the graphite irradiation chamber of the PGNAA-system fairly operates, and is useful to estimate the average thermal neutron flux of large samples with various compositions irradiated by 14 MeV neutrons. |
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| Keywords: | Prompt gamma neutron activation analysis Large samples MCNP-5 code |
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