摘要
钠冷快堆是第4代核反应堆的主力堆型,瞬态热工水力及安全特性是其设计研发和安全评审的重要工作,需要专用的分析工具。本文基于模块化建模思想,建立了钠冷快堆系统关键部件的热工水力模型和辅助模型,采用具有高稳定性和自动变步长能力的Gear算法,开发了钠冷快堆瞬态热工水力及安全分析软件THACS,并通过了国际基准题EBR-Ⅱ的有保护失流事故实验SHRT-17的初步验证。结果表明,THACS程序能较好模拟此实验的瞬态过程,具备钠冷快堆瞬态热工水力及安全分析的能力,可为我国钠冷快堆研发提供支持。
Sodium-cooled fast reactor is one of the Generation-Ⅳ nuclear reactors.Research on its transient thermal-hydraulic and safety characteristics is the significant work for its design and licensing,which requires specific analysis tools.Based on the modular modeling idea,the thermal-hydraulic models and auxiliary models were established for the key components of the sodium-cooled fast reactor system.The Gear algorithm with high stability and automatic step-changing capacity was adopted to develop the transient thermal-hydraulic analysis code for sodium-cooled fast reactors (THACS),which was validated by the protected loss-of-flow test SHRT-17 of the international benchmark EBR-Ⅱ.The results show that THACS can simulate the test transient process well,which indicates that THACS code has possessed the capability to perform the transient thermal-hydraulics and safety analysis for sodium-cooled fast reactor,and support the development of China sodium-cooled fast reactor.
作者
秋穗正
张大林
宋苹
王式保
梁禹
王心安
周磊
刘雅鹏
QIU Suizheng;ZHANG Dalin;SONG Ping;WANG Shibao;LIANG Yu;WANG Xin’an;ZHOU Lei;LIU Yapeng(State Key Laboratory of Multiphase Flow in Power Engineering,School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2019年第10期1941-1950,共10页
Atomic Energy Science and Technology
基金
国家自然科学基金资助项目(11605131,11705139)
关键词
钠冷快堆
瞬态热工水力
安全分析
程序开发
THACS
sodium-cooled fast reactor
transient thermal-hydraulics
safety analysis
code development
THACS
