Uncertainty Analysis of Transportable Fluoride-Salt-Cooled High Temperature Reactor（TFHR）
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摘要: 基于不确定分析软件DAKOTA、反应堆热工水力最佳估算程序RELAP5,编写程序耦合接口,对新型20 MWth棱柱式熔盐冷却高温堆稳态热工水力特性进行不确定性分析。选取关键热工参数(如功率、物性、几何尺寸)作为变量输入,基于现有实验堆安全运行经验,指定各参数概率密度分布,经过大量重复性计算,最终得到在95%置信水平下燃料峰值温度的统计分布,进而分析反应堆安全特性。统计结果表明:传热系数和燃料气隙的不确定性对燃料峰值温度影响最为显著且为负相关;燃料峰值温度有0.5%的概率超过燃料稳态运行极限,现有反应堆设计方案需进一步优化。
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关键词:
- 可移动式熔盐冷却高温堆 /
- 不确定性分析 /
- DAKOTA /
- RELAP5
Abstract: The uncertainty and sensitivity quantification investigation of MIT proposed 20 MWth prismatic Transportable Fluoride-salt-cooled High Temperature Reactor（TFHR） is performed with the DAKOTA code coupled to the commercial nuclear best-estimate software RELAP5.Model input parameters were selected with specified variations and probability density functions,a total of 200 steady state calculations were then conducted in order to statistically determine 95% peak fuel temperature tolerance intervals with 95% confidence level.It was found that uncertainties in the heat transfer coefficient and helium gap were the most significant contributors to the propagated peak fuel temperature uncertainty.About 0.5% of calculated fuel temperatures exceeded the fuel damage.The current design of THFR needs further optimization from the prospective of thermal-hydraulics.-
Key words:
- TFHR /
- Uncertainty Analysis /
- DAKOTA /
- RELAP5
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