Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2010, Vol. 21 ›› Issue (1): 11-15 doi: 10.13538/j.1001-8042/nst.21.11-15

• LOW ENERGY ACCELERATOR AND RADIATION APPLICATIONS • Previous Articles     Next Articles

MC simulation of thermal neutron flux of large samples irradiated by 14 MeV neutrons

BAI Yunfei1,* WANG Dezhong1 MAUERHOFER Eric2 KETTLER John2   

  1. 1School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 200240 Shanghai, China 2Institute of Energy Research IEF-6: Safety Research and Reactor Technology,Forschungszentrum Jülich GmbH, 52425 Jülich, Germany
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BAI Yunfei, WANG Dezhong, MAUERHOFER Eric, KETTLER John. MC simulation of thermal neutron flux of large samples irradiated by 14 MeV neutrons.Nuclear Science and Techniques, 2010, 21(1): 11-15     doi: 10.13538/j.1001-8042/nst.21.11-15

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.

Key words: Prompt gamma neutron activation analysis, Large samples, MCNP-5 code