A Research On Reactor Pressure Vessel Radiation Embrittlement Surveillance

Extending the designed life of the reactor from 40 years to 60 years is the key factor to improve the competition of the nuclear power plant. The writer summarized the mechanism and aspect which influencing the fast neutron radiation embrittlement trend of ferrite material of reactor pressure vessel. This summary has given a theory base for the optimization of reactor pressure vessel design, manufacture and operation, so as to reduce the embrittlement damage and get a longer service life reasonably.This thesis states the structural characteristics, technical specification of the material, design codes and main parameters of the reactor pressure vessel as well as the design, carry out, data process, data application about the reactor pressure vessel fast neutron radiation embrittlement surveillance program on the basis of Qinshan Second Nuclear power plant 650MWe Unit. This paper specified the object, the technique and applicable code on surveillance program.It come to a conclusion that the embrritlement damage effect of the reactor pressure of Qinshan Second Nuclear Power Plant meet the design limit, and at least it is in the same level compared with the similary plant of France. This conclusion comes from the comprehensive analysis of the test result of Sharpy-V impact test, tension test etc of the surveillance capsule of A and C of Unit 1.The lead factor of Qinshan Second Nuclear Power Plant is bigger than the others. The root cause of the bigger lead factor was analyzed deeply and the impact of bigger lead factor, possible counter-measures was discussed too.The service life of the reactor pressure vessel of Qinshan Second Nuclear Power Plant could be extended from 40 years to 60 years was proved by the result of fast neutron radiation embrittlement sueveillance result, design parameters and operation parameters.