Considerations for in-service inspection on pressure vessel of 200MW nuclear heating reactor

The 200MW nuclear heating reactor adopts an integrated arrangement for the primary circuit. It is designed to be operated at lower temperature and low er pressure as compared to large reactors. A steel containment serves a bar ricade for the reactor pressure vessel. The pressure vessel has some safety characteristics, such as low stress level, low induced integral neutron fl ux, and high toughness etc. Among them, the most important is its LBB behav ior. Based on the safety analysis for the pressure, the requirements and pr ocedures of in-service inspection are layed-out accordingly. (C) 2000 Elsev ier Science S.A. All rights reserved.