Nuclear power unit reactor pressure vessel time limit aging analysis method designed and built based on French RCCM standard

Abstract

The invention relates to a nuclear power unit reactor pressure vessel time limit aging analysis method designed and built based on the French RCCM standard. The method comprises the steps that 1, predicting and calculating the fast neutron fluence and the ductile-brittle transition temperature of a reactor pressure vessel material serving to the end of a license continuation period; 2, performing comparative analysis on the ductile-brittle transition temperature determined in the step 1 and the ductile-brittle transition temperature of the original design stress analysis report; if the ductile-brittle transition temperature value in the original design stress analysis report is smaller than or equal to the ductile-brittle transition temperature value determined in the first step, carrying out the third step and the fourth step; 3, referring to the original design standard of the nuclear power unit, and calculating a pressure and temperature limit curve of the reactor pressure vessel; and 4, referring to the original design standard of the nuclear power unit, and carrying out fracture mechanical analysis and evaluation on the reactor pressure vessel under various working conditions. The technical risk of nuclear power design and construction standard mixing is avoided, and the blank of the nuclear power unit reactor pressure vessel time limit aging analysis method designed and constructed based on the French RCCM standard is filled.

Description

technical field [0001] The invention belongs to the technical field of nuclear power plant operating license continuation (OLE) demonstration, in particular to a method for analyzing the time-limited aging of reactor pressure vessels of nuclear power units designed and built based on the French RCCM standard. Background technique [0002] The time-limited aging analysis of reactor pressure vessel (RPV) is an important work that must be carried out when the license of a nuclear power plant is renewed. The so-called time-limited aging analysis refers to calculation and analysis involving aging effects. As far as the reactor pressure vessel is concerned, the material aging effect involved is mainly radiation embrittlement, and its analysis results directly affect the service life of the nuclear power plant. [0003] At present, my country's nuclear power plant operating license validity period extension technical policy is similar to the relevant regulations of the US Nuclear ...

AI Technical Summary

Problems solved by technology

At present, my country is still in its infancy in the demonstration of the renewal of nuclear power plant operating licenses. The time-limited aging analysis method for nuclear power unit reactor pressure vessels designed and built based on the French RCCM standard is still blank. Demonstration and review work brings great constraints

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