Computational Methodology of Sodium-Water Reaction Phenomenon in Steam Generator of Sodium-Cooled Fast Reactor

被引:22
|
作者
Takata, Takashi [1 ]
Yamaguchi, Akira [1 ]
Uchibori, Akihiro [2 ]
Ohshima, Hiroyuki [2 ]
机构
[1] Osaka Univ, Suita, Osaka 5650871, Japan
[2] Japan Atom Energy Agcy, Oarai, Ibaraki 3111393, Japan
关键词
computational fluid dynamics; sodium-water reaction; multiphase analysis; steam generator; sodium-cooled fast reactor; FLOW;
D O I
10.3327/jnst.46.613
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A new computational methodology of sodium-water reaction (SWR), which Occurs in a steam generator of a liquid-sodium-cooled fast reactor when a heat transfer tube in the steam generator fails, has been developed considering multidimensional and multiphysics thermal hydraulics. Two kinds of reaction models are proposed in accordance with a phase of sodium as a reactant. One is the surface reaction model in which water vapor reacts directly with liquid sodium at the interface between the liquid sodium and the water vapor. The reaction heat will lead to a vigorous evaporation of liquid sodium, resulting in a reaction of gas-phase sodium. This is designated as the gas-phase reaction model. These two models are coupled with a multidimensional, multicomponent gas, and multiphase thermal hydraulics simulation method with compressibility (named the 'SERAPHIM' code). Using the present methodology, a numerical investigation of the SWR under a pin-bundle configuration (a benchmark analysis of the SWAT-1R experiment) has been carried out. As a result, the maximum gas temperature of approximately 1,300 degrees C is predicted stably, which lies within the range of previous experimental observations. It is also demonstrated that the maximum temperature of the mass weighted average in the analysis agrees reasonably well with the experimental result measured by thermocouples. The present methodology will be promising to establish a theoretical and mechanical modeling of secondary failure propagation of heat transfer tubes due to such as an overheating rupture and a wastage.
引用
收藏
页码:613 / 623
页数:11
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