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1. Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia

Author

Yavar, A.R., Khalafi, H., Kasesaz, Y., Sarmani, S., Yahaya, R., Wood, A.K., and Khoo, K.S.

Subjects
*NEUTRON flux, *MONTE Carlo method, *NUCLEAR reactors, *PARTICLES (Nuclear physics), *PARAMETER estimation
Abstract

Abstract: A 3-D model for 1MW TRIGA Mark II research reactor was simulated. Neutron flux parameters were calculated using MCNP-4C code and were compared with experimental results obtained by k0-INAA and absolute method. The average values of and by MCNP code were (2.19±0.03)×1012 cm−2 s−1, (1.26±0.02)×1011 cm−2 s−1 and (3.33±0.02)×1010 cm−2 s−1, respectively. These average values were consistent with the experimental results obtained by k 0-INAA. The findings show a good agreement between MCNP code results and experimental results. [Copyright &y& Elsevier]

Published
2012
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