Calculation And Analysis Of The RPV Fast Neutron Flux Based On The Monte Carlo Method

The reactor pressure vessel is of a component not allowed to change.The life of pressure vessel is directly related to the safety and economy of nuclear power plants. In order to guarantee the credible evaluation criteria of the RPV embrittlement and the Pressurized Thermal Shock(PTS),Regulatory Guide 1.190 of the NRC recommends detailed calculation of the RPV fast neutron fluence. This article uses the three-dimensional Monte Carlo transport calculation program MCNP and continuous cross-section database based on ENDF/B-VI,and also based on the detailed structural dimensions, source strength and the energy spectrum and other parameters of the reactor, the RPV fast neutron flux distributions are given. All of these supply references to the reactor owners to adjust the radiation surveillance and life extension scheme. Besides, the cross-section database used in this work is validated with H.B.R-2 benchmark,and the result indicates that it satisfies the accuracy requirement of engineering calculation.