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

A. R. Yavar, H. Khalafi, Y. Kasesaz, Sukiman Sarmani, R. Yahaya, A. K. Wood, Khoo Kok Siong Kok Siong

Research output: Contribution to journalArticle

3 Citations (Scopus)

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 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 12cm -2s -1, (1.26±0.02)×10 11cm -2s -1 and (3.33±0.02)×10 10cm -2s -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.

Original languageEnglish
Pages (from-to)2488-2493
Number of pages6
JournalApplied Radiation and Isotopes
Volume70
Issue number10
DOIs
Publication statusPublished - Oct 2012

Fingerprint

Malaysia
flux (rate)
reactors
simulation

Keywords

  • K - Instrumental neutron activation analysis
  • MCNP-4C code
  • Neutron flux parameters
  • TRIGA Mark II reactor

ASJC Scopus subject areas

  • Radiation

Cite this

Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia. / Yavar, A. R.; Khalafi, H.; Kasesaz, Y.; Sarmani, Sukiman; Yahaya, R.; Wood, A. K.; Kok Siong, Khoo Kok Siong.

In: Applied Radiation and Isotopes, Vol. 70, No. 10, 10.2012, p. 2488-2493.

Research output: Contribution to journalArticle

Yavar, A. R. ; Khalafi, H. ; Kasesaz, Y. ; Sarmani, Sukiman ; Yahaya, R. ; Wood, A. K. ; Kok Siong, Khoo Kok Siong. / Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia. In: Applied Radiation and Isotopes. 2012 ; Vol. 70, No. 10. pp. 2488-2493.
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AU - Kasesaz, Y.

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AU - Yahaya, R.

AU - Wood, A. K.

AU - Kok Siong, Khoo Kok Siong

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