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

► We use 3-D neutronic model to enhance the utilization of the economical use of reactor.► The MCNP code is modified to analyze the neutronic parameters. ► The neutron flux distributions are homogeneous and consistent with experimental results. ► A complete simulation of the calculated neutron flux parameters in 40 RR irradiation channels is achieved.