PARCS code multi-group neutron diffusion constants generation using Monte Carlo method

• PARCS code multi-group neutron diffusion constants are generated by Monte Carlo method.
• A new tool in MATLAB software is developed to compute MGDCs from the MCNPX 2.7 code.
• PTRAC file and weight to flux ratio method are applied for MGDCs generation.
• PMAXS files which contain the two-group constants are prepared using MCNPX results.
• The method is verified for two-group constants generation of Tehran research reactor.

PARCS code is a three-dimensional (3D) reactor core simulator which solves the steady-state and time-dependent multi-group neutron diffusion equations if the multi-group diffusion constants (MGDCs) are provided. The MGDCs are mostly prepared for reactor physics problems using deterministic lattice codes. Beside approximation in the geometry, a lattice code inherently applies estimates to the neutron transport model. On the other hand, the geometric flexibility and use of continuous energy cross sections data library associated with the Monte Carlo (MC) method makes it a good candidate for the generation of highly accurate multi-group cross sections. In this study, a new MC based methodology is applied to generate the MGDCs which can be utilized in the PARCS code input file directly or as PMAXS files for a reactor core simulation. To achieve this, a new tool in MATLAB software is developed to compute the MGDCs from the MCNPX 2.7 MC code outputs. Verification of the proposed method for two-group constants generation is carried out using Tehran research reactor (TRR) core simulation in different steady state conditions. The calculated values of axial and radial power distributions and multiplication factor using the PARCS code are verified against the MCNPX 2.7 code results. The results illustrate that the proposed method has high accuracy in MGDCs generation.