THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING

WANG RongShan; CHEN MingYa; LU Feng; ZHENG WeiDong; WANG DongHui; ZHANG YaPing; FAN Zhao

doi:10.16579/j.issn.1001.9669.2016.04.031

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THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING

更新时间：2022-09-22

- THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING
- Journal of Mechanical Strength Vol. 38, Issue 4, Pages: 838-843(2016)
- 作者机构：
  
  1. 苏州热工研究院
  2. 华东理工大学
  3. 国核电站运行服务技术公司
- 作者简介：
- 基金信息：
- DOI：10.16579/j.issn.1001.9669.2016.04.031
  CLC：
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WANG RongShan, CHEN MingYa, LU Feng, et al. THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING. [J]. 38(4):838-843(2016)
DOI：

WANG RongShan, CHEN MingYa, LU Feng, et al. THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING. [J]. 38(4):838-843(2016) DOI： 10.16579/j.issn.1001.9669.2016.04.031.

摘要

承压热冲击(PTS)是制约反应堆压力容器(RPV)长周期运行的主要因素,目前大多数国家(除了美国)均采用确定性断裂力学方法(DFM)开展PTS分析。在美国,核管理当局(NRC)已经批准了基于概率性断裂力学方法(PFM)的"鉴定准则"。本文基于美国橡树岭国家重点实验室开发的FAVOR软件,对比了PTS的PFM与DFM之间一些主要差别,并通过对IAEA-TECDOC-1627报告中基准考题的计算,介绍了FAVOR软件PFM的分析方法。最后,通过分析总结国内外最新的研究成果,指出当前版本FAVOR软件(6.1版本)中所考虑模型需要完善的部分。

Abstract

The pressurized thermal shock（ PTS） event poses a potentially significant challenge to the structural integrity of the reactor pressure vessel（ RPV） during the long time operation. In most countries（ with exception of the USA）,proving RPV integrity under the PTS load is based on the deterministic fracture mechanics（ DFM）. In the USA,the "screening criteria"for maximum allowable embrittlement of RPV material,which form part of the USA regulations,are based on the probabilistic fracture mechanics（ PFM）. In this paper,the FAVOR software of Oka Ridge National Laboratory is used to compare the difference between PFM and DFM analysis of the PTS even. The analysis method of FAVOR is shown through case study of the benchmark transient in the IAEA-TECDOC-1627 report. Finally,the limit of the current FAVOR（ Version6. 1） is shown.

关键词

反应堆压力容器承压热冲击概率断裂力学FAVOR长周期运行

Keywords

Reactor pressure vesselPressure thermal shockProbabilistic fracture mechanicalFAVORLong time operation

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