气溶胶模型对安全壳旁路释放类事故源项的影响  

Effect on Source Term of Containment Bypass Releases by Different Aerosol Deposition Model

作　　者：佟立丽[1] 曹学武[1] 

机构地区：[1]上海交通大学机械与动力工程学院,上海200240

出　　处：《核科学与工程》2014年第3期397-402,共6页Nuclear Science and Engineering

基　　金：国家自然科学基金项目资助(11205099);国家重点基础研究发展计划(2009CB724301)

摘　　要：本文开发了针对蒸汽发生器（SG）二次侧复杂流道结构的气溶胶沉积模型,并移植在核电厂一体化严重事故分析程序中。并以600 MW压水堆核电厂为研究对象,基于原模型与新开发的SG二次侧气溶胶沉积模型,对蒸汽发生器传热管破裂事故（SGTR）源项进行了计算,并对新模型对安全壳旁路释放类的影响进行了分析。结果表明,采用新的二次侧气溶胶沉积模型后将会有更多的气溶胶沉积在SG二次侧,新开发的SG二次侧气溶胶沉积模型导致安全壳旁路释放类中对环境释放份额减少26.6％～71.1％。A new aerosol deposition model of the secondary steam generator （SG） is developed for the complex flow path configuration and the new model is integrated into the severe accident analysis code. The integrated safety analysis model for 600 MW nuclear power plant with the new aerosol deposition model is built. The accident sequence of steam generator tube rupture （SGTR） and the bypass containment accidents are analyzed with the old model and the new model. The results show that more fission products deposit in the secondary of the SG and the fractions of the fission products releasing to the environment with the new model decreases 26.6 ～ 71.1% for the containment bypass release category.

关 键 词：严重事故 安全壳旁路释放类 气溶胶 沉积模型 

分 类 号：TL364.4[核科学技术—核技术及应用]