Structural Integrity Assessment of High-Strength Anchor Bolt in Nuclear Power Plant based on Fracture Mechanics Concept

被引：3

作者：

Lim, Eun-Mo ^{[1
]}

Huh, Nam-Su ^{[1
]}

Shim, Hee-Jin ^{[2
]}

Oh, Chang-Kyun ^{[2
]}

Kim, Hyun-Su ^{[2
]}

机构：

[1] Seoul Natl Univ Sci & Technol, Dept Mech Syst Design Engn, Seoul, South Korea

[2] KEPCO Engn & Construct Co Inc, Power Engn Res Inst, Gimcheon, South Korea

来源：

TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A | 2013年 / 37卷 / 07期

关键词：

Anchor Bolt; Bolt Pretension; Finite Element Analysis; Steam Generator; Stress Corrosion Cracking; Stress Intensity Factor;

D O I：

10.3795/KSME-A.2013.37.7.875

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

The failure of a bolted joint owing to stress corrosion cracking (SCC) has been considered one of the most important structural integrity issues in a nuclear power plant. In this study, the failure possibility of bolting, which is used to support the steam generator of a pressurized water reactor, owing to SCC and brittle fracture was evaluated in accordance with guidelines proposed by the Electric Power Research Institute, which are called the Reference Flaw Factor method. For this evaluation, first, detailed finite element stress analyses were conducted to obtain the actual nominal stresses of bolting in which either service loads or bolt preloads were considered. Based on these nominal stresses, the structural integrity of bolting was addressed from the viewpoints of SCC and toughness. In addition, the accuracy of the EPRI Reference Flaw Factor for assessing bolting failure was investigated using finite element fracture mechanics analyses.

引用

页码：875 / 881

页数：7