title: Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia.
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.
authors.affiliation: School of Applied Physics, Faculty of Science and Technology, The National University of Malaysia (UKM), 43600 Bangi, Selangor, Malaysia.
authors.forename: A R
authors.initials: AR
authors.lastname: Yavar
authors.forename: H
authors.initials: H
authors.lastname: Khalafi
authors.forename: Y
authors.initials: Y
authors.lastname: Kasesaz
authors.forename: S
authors.initials: S
authors.lastname: Sarmani
authors.forename: R
authors.initials: R
authors.lastname: Yahaya
authors.forename: A K
authors.initials: AK
authors.lastname: Wood
authors.forename: K S
authors.initials: KS
authors.lastname: Khoo