摘要
针对铅铋冷却沸水快堆(PBWFR)主回路系统建立了系统热工水力分析的数学物理模型,并开发了适用于PBWFR的热工水力系统安全分析程序SACOL。利用SACOL对PBWFR的稳态和瞬态热工水力特性进行了研究,并重点模拟了无保护超功率事故(UTOP)。计算结果表明:PBWFR在稳态时具有足够的安全性,但在UTOP中,功率短时间的迅速升高会导致包壳温度超过安全限值。
In this paper, mathematical models are established for PBWFR coolant system, and a system analysis code of PBWFR SACOL is developed. The steady-state and transient thermal-hydraulic performance of PBWFR is calculated and analyzed, especially the unprotected transient of over power. Results show that PBWFR is safe under steady state. However, during UTOP transient, the rapidly increasing of power in a short time would lead to cladding failure.
作者
魏诗颖
王成龙
苏光辉
田文喜
秋穗正
Wei Shiying;Wang Chenglong;Su Guanghui;Tian Wenxi;Qiu Suizheng(State Key Laboratory of Multiphase Flow in Power Engineering,Xi＇an Jiaotong University,Xi＇an,710049,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2018年第4期67-70,共4页
Nuclear Power Engineering
关键词
铅铋冷却沸水快堆(PBWFR)
铅铋快堆
热工水力
系统安全
Pb-Bi cooled direct-contact-boiling water fast reactor （PBWFR）
Lead-bismuth reactor
Thermal-hydraulics
System safety
