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

LOW ENERGY ACCELERATORS AND RADIATION APPLICATIONS

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

BAI Yunfei，

WANG Dezhong，

MAUERHOFER Eric，

KETTLER John

Nuclear Science and Techniques

Vol.21, No.1

pp.11-15

Published in print 20 Feb 2010

DOI：10.13538/j.1001-8042/nst.21.11-15

51103

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.

Prompt gamma neutron activation analysisLarge samplesMCNP-5 code

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