铅铋冷却沸水快堆热工水力系统安全分析程序开发
doi: 10.13832/j.jnpe.2018.04.0067
Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System
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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。
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关键词:
- 铅铋冷却沸水快堆（PBWFR） /
- 铅铋快堆 /
- 热工水力 /
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系统安全
Abstract: 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. -
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