超临界水堆的瞬态分析程序开发

超临界水堆（SCWR）是第4代核反应堆的优先发展对象之一，它在经济性上的明显优势使其受到广泛关注。本文以混合谱超临界水堆（SCWR-M）为研究对象，建立合理的数学模型，开发了针对超临界水堆系统的瞬态分析程序TACOS。运用TACOS程序对SCWR-M进行了稳态计算和部分失流事故的瞬态分析。稳态计算的结果与设计值符合良好。部分失流事故的分析结果表明，事故中包壳表面最高温度为702.6 ℃，与安全限值相比有很大裕度。部分失流事故过程中不需采取特殊的安全措施，堆芯可自行回到安全状态。

Development of Transient Analysis Code for SCWR

The supercritical water-cooled reactor (SCWR) is one of the six reactor technologies selected for research and development under the Generation-Ⅳ program. SCWRs are extensively attractive because of the significant economical competitiveness. In present study, a code TACOS (transient analysis code of SCWR) was developed to analyze the safety characteristics of SCWR with mixed spectrum core (SCWR-M). The steady state calculation of SCWR-M was carried out with TACOS. The results of steady state agreed well with the design value. Preliminary analysis of partial loss of flow accident was performed. The results indicate that the maximum cladding surface temperature (MCST) during the accident is 702.6 ℃, which is obviously lower than the limiting value of MCST. During the accident of partial loss of flow, reactor core can recover to safe state without additional action.