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

Yavar AR; Khalafi H; Kasesaz Y; Sarmani S; Yahaya R; Wood AK; Khoo KS

doi:10.1016/j.apradiso.2012.06.015

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

Yavar AR ¹ , Khalafi H , Kasesaz Y , Sarmani S , Yahaya R , Wood AK Show all authors , Khoo KS

Affiliations

¹ School of Applied Physics, Faculty of Science and Technology, The National University of Malaysia (UKM), 43600 Bangi, Selangor, Malaysia

Appl Radiat Isot, 2012 Oct;70(10):2488-93.

PMID: 22885391 DOI: 10.1016/j.apradiso.2012.06.015

Abstract

A 3-D model for 1 MW TRIGA Mark II research reactor was simulated. Neutron flux parameters were calculated using MCNP-4C code and were compared with experimental results obtained by k(0)-INAA and absolute method. The average values of φ(th),φ(epi), and φ(fast) by MCNP code were (2.19±0.03)×10(12) cm(-2)s(-1), (1.26±0.02)×10(11) cm(-2)s(-1) and (3.33±0.02)×10(10) 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.

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