Engineering critical assessment of RPV with nozzle corner cracks under pressurized thermal shocks

被引：15

作者：

Li, Yuebing ^{[1
,2
]}

Jin, Ting ^{[1
,2
]}

Wang, Zihang ^{[2
]}

Wang, Dasheng ^{[1
]}

机构：

[1] China Nucl Power Engn Co Ltd, State Key Lab Nucl Power Safety Monitoring Techno, Shenzhen 518172, Guangdong, Peoples R China

[2] Zhejiang Univ Technol, Inst Proc Equipment & Control Engn, Hangzhou 310032, Peoples R China

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2020年 / 52卷 / 11期

基金：

中国国家自然科学基金;

关键词：

Corner crack; Engineering critical assessment; Crack shape; Cladding; Pressurized thermal shocks; STRESS INTENSITY FACTORS; SET-IN NOZZLE; CYLINDER INTERSECTION; FRACTURE-ANALYSIS; REACTOR; VESSEL; PIPE;

D O I：

10.1016/j.net.2020.04.019

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Nozzle corner cracks present at the intersection of reactor pressure vessels (RPVs) and inlet or outlet nozzles have been a persistent problem for a number of years. The fracture analysis of such nozzle corner cracks is very important and critical for the efficient design and assessment of the structural integrity of RPVs. This paper aims to perform an engineering critical assessment of RPVs with nozzle corner cracks subjected to several transients accompanied by pressurized thermal shocks. The critical crack size of the RPV model with nozzle corner cracks under transient loading is evaluated on failure assessment curve. In particular, the influence of cladding on the crack initiation of nozzle corner crack under thermal transients is studied. The influence of primary internal pressure and secondary thermal stress on the stress field at nozzle corner and SIF at crack front is analyzed. Finally, the influence of different crack size and crack shape on the final critical crack size is analyzed. (C) 2020 Korean Nuclear Society, Published by Elsevier Korea LLC.

引用

页码：2638 / 2651

页数：14

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