Lessons learned from the plant-specific pressurized thermal shock integrity analysis on an embrittled reactor pressure vessel

Ill-Seok Jeong; Changhuei Jang; Jun-Hyun Park

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Lessons learned from the plant-specific pressurized thermal shock integrity analysis on an embrittled reactor pressure vessel

机译：在脆性反应堆压力容器上从工厂特定的加压热冲击完整性分析中学到的经验教训

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The reference temperature of pressurized thermal shock (PTS) of the reactor pressure vessel (RPV) for the oldest pressurized water reactor in Korea had been predicted to exceed screening criteria of 10CFR50.61. To cope with this issue, a plant-specific PTS analysis bad been performed following the methodology and procedures suggested in Reg. Guide 1.154. In this paper, the details of the plant-specific PTS analysis were described. To quantify the PTS risk of the embrittled RPV, the PTS-significant transient sequences were selected and their frequencies were quantified. Then, thermal hydraulics characteristics of the selected transients were analyzed considering fluid mixing in the downcomer region of RPV. The through-wall cracking (TWC) frequencies of the RPV due to various PTS transients were calculated using the probabilistic fracture mechanics analysis technique. The integrated PTS risk, or the total TWC due to all PTS-significant transient sequences, was lower than the Reg. Guide 1.154 limit during and beyond its design life. Finally, the lessons learned and technical issues found through the analysis are described in detail.

机译：预测韩国最老的压水堆的反应堆压力容器（RPV）的加压热冲击（PTS）的参考温度将超过10CFR50.61的筛选标准。为了解决这个问题，按照Reg.3建议的方法和步骤进行了特定于工厂的PTS分析。指南1.154。在本文中，详细描述了工厂特定的PTS分析。为了量化脆性RPV的PTS风险，选择了PTS重要的瞬时序列，并对它们的频率进行了量化。然后，考虑到RPV降液管区域内的流体混合，分析了选定瞬态的热工水力特性。使用概率断裂力学分析技术计算了由于各种PTS瞬变而引起的RPV的贯穿壁开裂（TWC）频率。归因于所有PTS重要瞬时序列的PTS综合风险或总TWC低于Reg。指南1.154在其设计寿命期间及以后的限制。最后，将详细介绍通过分析获得的经验教训和发现的技术问题。

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《International Journal of Pressure Vessels and Piping》 |2001年第3期|共11页
作者
Ill-Seok Jeong; Changhuei Jang; Jun-Hyun Park;
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正文语种 eng
中图分类蒸汽动力工程;
关键词
plant-specific pressurized thermal-shock analysis; integrity of reactor pressure vessel; PTS sequence; thermal hydraulics; thermal stratification; probabilistic fracture mechanics;

机译：特定工厂的加压热冲击分析;反应堆压力容器的完整性;PTS顺序;热力学;热分层;概率断裂力学;

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1. Lessons learned from the plant-specific pressurized thermal shock integrity analysis on an embrittled reactor pressure vessel [J] . Ill-Seok Jeong, Changhuei Jang, Jun-Hyun Park International Journal of Pressure Vessels and Piping . 2001,第2a3期

机译：在脆性反应堆压力容器上从工厂特定的加压热冲击完整性分析中学到的经验教训
2. Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects [J] . Gonzalez-Albuixech V. F., Qian G., Sharabi M., Engineering Fracture Mechanics . 2016,第Null期

机译：考虑冷却羽流和约束效应的实际压力热冲击反应堆压力容器的完整性分析
3. Integrity analysis of reactor pressure vessels subjected to pressurized thermal shocks by XFEM [J] . Gonzalez-Albuixech V. F., Qian G., Niffenegger M. Nuclear Engineering and Design . 2014,第auga期

机译：用XFEM分析承受压力热冲击的反应堆压力容器的完整性
4. Case Study on the Relationship between Safety Margin and Conditional Probability for the Integrity Analysis of Reactor Pressure Vessel under Pressurized Thermal Shock [C] . Y.B. Li, Z.L. Gao, Y.B. Lei International Conference on Pressure Vessel Technology . 2016

机译：电加压热冲击下反应堆压力容器完整性分析与条件概率关系的案例研究
5. Assessment of pressure vessel failure due to pressurized thermal shock with consideration of probabilistic-deterministic screening and uncertainty analysis. [D] . Li, Fei. 2001

机译：考虑到概率确定性筛选和不确定性分析，评估由于加压热冲击导致的压力容器故障。
6. On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels [O] . N. Almirall, P. B. Wells, H. Ke, -1

机译：高辐照反应堆压力容器钢中较低温度下形成的纳米Mn-Ni-Si沉淀物的高温热稳定性研究
7. Case Study on the Relationship between Safety Margin and Conditional Probability for the Integrity Analysis of Reactor Pressure Vessel under Pressurized Thermal Shock [O] . Li Y.B., Gao Z.L., Lei Y.B. 2015

机译：加压热冲击下反应堆压力容器完整性分析中安全裕度与条件概率关系的案例研究
8. Pressure Vessel Fracture Studies Pertaining to the PWR (Pressurized Water Reactor) Thermal-Shock Issue: Experiment TSE-7 (Thermal-Shock Experiment-7). [R] . Cheverton, R. D., Bolt, S. E., Ball, D. G., 1985

机译：压水容器断裂研究与pWR（压水反应堆）热冲击问题有关：实验TsE-7（热冲击实验-7）。

Lessons learned from the plant-specific pressurized thermal shock integrity analysis on an embrittled reactor pressure vessel

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