Heat Rate Analysis Of The PWR Reactor Internals Based On The Monte Carlo Method

Reactor nuclear power plant safety within the components, mainly related to the aging of the reactor internals. Heat release problem is a significant element in design of reactor. When fission occurs to the nuclear fuel in core, it releases maximum Neutron andγradiation, which take Energy deposition in reactor internals and have influences on heat, Irradiation and so on.First, the MCNP code and cross-section database used in this work is validated with NUREG/CR-6115 benchmark, and the results indicate that they satisfy the accuracy requirement of engineering calculation. Second, This article uses the three-dimensional Monte Carlo transport calculation program MCNP and continuous cross-section database based on ENDF/B-Ⅵ, also based on the detailed structural dimensions, heat release distributions are given. Third, the distributions are validated by SN code TORT, the comparison results are in good agreement. The results could provide references for the stress analysis of reactor internals.