- Volume 37 Issue 7
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Structural Integrity Assessment of High-Strength Anchor Bolt in Nuclear Power Plant based on Fracture Mechanics Concept
원자력발전소 고강도 앵커 볼트의 파괴역학적 건전성평가
- Lim, Eun-Mo (Dept. of Mechanical System Design Engineering, Seoul Nat'l Univ. of Science and Technology) ;
- Huh, Nam-Su (Dept. of Mechanical System Design Engineering, Seoul Nat'l Univ. of Science and Technology) ;
- Shim, Hee-Jin (Power Engineering Research Institute, KEPCO Engineering & Construction Company, Inc.) ;
- Oh, Chang-Kyun (Power Engineering Research Institute, KEPCO Engineering & Construction Company, Inc.) ;
- Kim, Hyun-Su (Power Engineering Research Institute, KEPCO Engineering & Construction Company, Inc.)
- 임은모 (서울과학기술대학교 기계시스템디자인공학과) ;
- 허남수 (서울과학기술대학교 기계시스템디자인공학과) ;
- 심희진 (KEPCO E&C 전력기술연구소) ;
- 오창균 (KEPCO E&C 전력기술연구소) ;
- 김현수 (KEPCO E&C 전력기술연구소)
- Received : 2012.12.28
- Accepted : 2013.04.15
- Published : 2013.07.01
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.
Anchor Bolt;Bolt Pretension;Finite Element Analysis;Steam Generator;Stress Corrosion Cracking;Stress Intensity Factor
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