摘要
A historical review of in-vessel melt retention （IVR） is given, which is a severe accident mitigation mea- sure extensively applied in Generation III pressurized water reactors （PWRs）. The idea of IVR actually originated from the back-fitting of the Generation 11 reactor Loviisa WER-440 in order to cope with the core-melt risk. It was then employed in the new deigns such as Westinghouse APIO00, the Korean APR1400 as well as Chinese advanced PWR designs HPRIO00 and CAP1400. The most influential phe- nomena on the IVR strategy are in-vessel core melt evolution, the heat fluxes imposed on the vessel by the molten core, and the external cooling of the reactor pressure vessel （RPV）. For in-vessel melt evolution, past focus has only been placed on the melt pool convection in the lower plenum of the RPV; however, through our review and analysis, we believe that other in-vessel phenomena, including core degradation and relocation, debris formation, and coolability and melt pool formation, may all contrib- ute to the final state of the melt pool and its thermal loads on the lower head. By looking into previous research on relevant topics, we aim to identify the missing pieces in the picture. Based on the state of the art, we conclude by proposing future research needs.
压水堆CAP1400是基于中国核工业研发体系和装备制造能力以及非能动压水堆AP1000的引进和消化吸收,并经过集成创新与再创新而形成的具有自主知识产权的第三代非能动先进压水堆核电型号。本文通过对CAP1400的总体设计思路、主要性能指标和技术参数、电站安全设计,以及在安全性、经济性和先进性等方面的阐述,论述了CAP1400作为第三代压水堆堆型的技术内涵和技术创新。此外,作为国家科技重大专项的成果,CAP1400型号的研发促进了中国自主核电在研发设计、试验和设备制造水平方面的整体提升,实现了核电设计与装备技术由第二代到第三代的升级。
