原子能科学技术2016，Vol.50Issue(5)：798-804,7.DOI:10.7538/yzk.2016.50.05.0798
高瑞利数下熔融池换热特性试验研究
Experimental Study on Heat Transfer Characteristics in Corium Pool with High Rayleigh Number
摘要
Abstract
Based on test facility named COPRA , the natural convection heat transfer characteristics in corium pool inside the reactor pressure vessel lower plenum during severe accident were studied . The test apparatus was a two-dimensional 1/4 circular slice structure with an inner radius of 2.2 m to simulate the lower plenum of reactor pressure vessel at 1:1 scale for the Chinese independently-designed GEN-Ⅲ PWR .A non-eutectic binary mixture of 20% NaNO3-80% KNO3 (in mole fraction ) compositions was selected as the simulant material .The Rayleigh number within the pool could reach up to 1016 ,matching those in the prototypical situation for PWR .The influences of relocation position ,pool height ,power density and relocation times on pool temperature and heat flux distribution were studied in the experiments .The result shows that the Nu of the downward heat transfer from COPRA experiment is lower than those from other experiments within the same range of Rayleigh number .关键词
严重事故/熔融池/自然对流/COPRAKey words
severe accident/corium pool/natural convection/COPRA分类
能源科技引用本文复制引用
张卢腾,马如冰,周瑜琨,张亚培,田文喜,秋穗正,苏光辉,马卫民,元一单..高瑞利数下熔融池换热特性试验研究[J].原子能科学技术,2016,50(5):798-804,7.基金项目
国家能源应用技术研究及工程示范项目资助(NY20111002-1) （NY20111002-1）
