会议专题

CFD Analysis of Core Melt Spreading on the Reactor Cavity Floor

In the very unlikely event of a severe reactor accident involving core melt and reactor pressure vessel failure, it is important to provide an accident management strategy that would allow the molten core material to cool down, resolidify and bring the core debris to a stable coolable state for Light Water Reactors (LWRs). One approach to achieve a stable coolable state is to quench the core melt after its relocation from the reactor pressure vessel into the reactor cavity. This approach typically requires a large cavity floor area on which a large amount of core melt spreads well and forms a shallow melt thickness for small thermal resistance across the melt pool. Spreading of high temperature (~3000 K), low superheat (~200 K) core melt over a wide cavity floor has been a key question to the success of the ex-vessel core coolability. A computational model for the melt spreading requires multiphase treatment of liquid melt, solidified melt, and air, and solidification and thermal radiation physics should be included. This paper reports the approach and computational model development for the ANSYS-CFX code to simulate core melt spreading on the reactor cavity. Solidification and thermal radiation heat transfer were modeled in the code and analyses of experiments have been carried out to check the validity of the model.

Severe accident Spreading Ex-vessel coolability Core catcher ANSYS-CFX

Wan-Sik Yeon Sang-Kun Lee Kwang-Hyun Bang Youngjo Choi Jaegon Lee

Department of Mechanical Engineering, Korea Maritime University, Busan, Korea Mechanical Design Team, Korea Hydro & Nuclear Power Co., Daejeon, Korea

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

2152-2163

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)