An overview of the development of a multigroup Monte Carlo code for TRIGA reactors

International Nuclear Science, Technology and Engineering Conference 2018

Omar, M.R.^1 ; Karim, J.A.^2 ; Yoon, T.L.^1

School of Physics, Universiti Sains Malaysia, Penang

11800 USM, Malaysia^1

Reactor Technology Center, Technical Support Division, Malaysian Nuclear Agency, Selangor

43000, Malaysia^2

关键词: Effective diffusion;    Eigenvalue calculations;    Important features;    Neutron cross sections;    Neutron flux distributions;    Numerical results;    Performance comparison;    Stochastic simulations;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/555/1/012007/pdf
DOI  :  10.1088/1757-899X/555/1/012007

来源: IOP

【 摘 要 】

This paper discusses the overview of the development of TRIMON, a next-generation core management code for TRIGA reactors. The newly developed code employs Monte Carlo method which uses diffusion theory type homogenized neutron cross section data, thus, speeding up the stochastic simulation via simplification of a complex core geometry. It has the capability of running three-dimensional core simulation up to 16 neutron energy groups. In general, the group neutron cross sections are pre-processed and homogenized via the Effective Diffusion Homogenization (EDH) method. The important features of TRIMON include core eigenvalue calculation, fuel burnup management, three-dimensional power and neutron flux distribution prediction. In this paper, the numerical results obtained using TRIMON were compared with the actual measured operational data. The performance comparison was also made between TRIMON and MCNP.