Development and application of safety assessment system in PFM analysis for RPV to study the influence of the neutron fluence estimate

摘要

The reactor pressure vessel (RPV) is the most important core container for the power generation system of a nuclear power plant. However, the vessel shell is prone to radiation embrittlement because of the operational environment of the power generation process which may lead to crack growth in the shell wall. For the purpose of estimating and ensuring the integrity of the RPV structure, the risk to and reliability of the structure after a period of operation needs to be analyzed under a variety of transient loading conditions.