原子能科学技术2018，Vol.52Issue(1)：41-47,7.DOI:10.7538/yzk.2017.youxian.0178
铅铋-水直接接触沸水快堆系统子通道耦合热工分析
Thermal-hydraulic Behavior of PBWFR Using Systematic Analysis Coupled with Sub-channel Analysis
摘要
Abstract
Pb-Bi cooled direct-contact-boiling water fast reactor (PBWFR) is of compact structure and portable characteristics ,which is of great value to use in remote areas or islands .In this paper ,the system analysis code SACOL and sub-channel analysis code SUBAS were coupled for analysis of the thermal-hydraulic characteristics of PBWFR . The results show that the relative errors of SACOL and coupled code do not exceed 4% , which proves the accuracy and rationality of the one-way coupling and step by step com-putation method . However ,using SACOL for system analysis cannot obtain the de-tailed information of the core .Using coupled code can make up this shortage .By analy-zing unprotected transient over power (UTOP) accident ,it is shown that the cladding temperature increases fast and will exceed the allowable safety limit .Therefore ,the cladding should be designed to have enough safety margins before the accident to ensure the safety operation in a long term under accident situation .关键词
PBWFR/系统分析/子通道分析/耦合分析Key words
PBWFR/systematic analysis/sub-channel analysis/coupling analysis分类
能源科技引用本文复制引用
魏诗颖,田永红,吴荣,王成龙,田文喜,秋穗正,苏光辉..铅铋-水直接接触沸水快堆系统子通道耦合热工分析[J].原子能科学技术,2018,52(1):41-47,7.基金项目
博士后创新人才支持计划资助项目(BX201600124) （BX201600124）
