首页> 外文期刊>Nuclear Engineering and Design >Treatment of the thermal-hydraulic uncertainties in the pressurized thermal shock analysis
【24h】

Treatment of the thermal-hydraulic uncertainties in the pressurized thermal shock analysis

机译:加压热冲击分析中热工水力不确定性的处理

获取原文
获取原文并翻译 | 示例
       

摘要

The pressurized thermal shock (PTS) analysis is a quantitative analysis to calculate the vessel failure probability of the embrittled reactor pressure vessel. The PTS analysis consists of three major parts, such as the probabilistic safety analysis (PSA), the thermal-hydraulic analysis (T/H), and the probabilistic fracture mechanics (PFM) analysis. Because each analysis involves many parameters and assumptions associated with the uncertainties, it is important to identify and incorporate them into the analysis. Though the PSA and PFM analysis can be easily treated statistically, the thermal-hydraulic analysis results are very difficult to be treated statistically. Instead, sensitivity analyses of the thermal-hydraulic inputs were performed to understand the significance of the variation in the thermal-hydraulic inputs to the PFM analysis. In this study, the existing PFM code was modified to incorporate the uncertainties in the thermal-hydraulic inputs for the PFM analysis. The effects of the uncertainties in the thermal-hydraulic inputs for the vessel failure probabilities were evaluated using the modified code. The results showed the effects of uncertainties in the thermal-hydraulic inputs on the vessel failure probabilities are not significant for the ranges of the transient types. Even for the larger uncertainties, the effects on the vessel failure probabilities are small. Also, the effects of the thermal-hydraulic uncertainties vary depending on the transient characteristics such that the effects are greatest for the pressure dominant transient. Within the transient, the relative increases in the failure probabilities are greatest for the circumferentially oriented semi-elliptical flaws. It was found that the results of the sensitivity analysis using one standard deviation are conservative enough to bound the analysis results considering the uncertainties in the thermal-hydraulic inputs.
机译:加压热冲击(PTS)分析是用于计算脆化反应堆压力容器的容器故障概率的定量分析。 PTS分析包括三个主要部分,例如概率安全分析(PSA),热工液压分析(T / H)和概率断裂力学(PFM)分析。由于每种分析都涉及许多与不确定性相关的参数和假设,因此重要的是将其识别并纳入分析中。尽管PSA和PFM分析很容易进行统计处理,但热工分析结果却很难进行统计处理。取而代之的是,对热工液压输入进行灵敏度分析,以了解热工液压输入变化对PFM分析的重要性。在本研究中,对现有的PFM代码进行了修改,以将不确定性纳入用于PFM分析的热工液压输入中。使用修改后的代码评估了热工液压输入中不确定性对容器故障概率的影响。结果表明,在过渡类型范围内,热工液压输入的不确定性对船舶失效概率的影响并不显着。即使对于较大的不确定性,对船舶故障概率的影响也很小。而且,热工不确定性的影响根据瞬态特性而变化,从而对于压力主导型瞬态,影响最大。在瞬变内,故障概率的相对增加对于圆周方向的半椭圆形缺陷最大。已经发现,考虑到热工液压输入的不确定性,使用一个标准偏差的灵敏度分析结果足够保守,足以限制分析结果。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2007年第2期|p.143-152|共10页
  • 作者

    Changheui Jang;

  • 作者单位

    Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701, Republic of Korea;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:46:10

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号