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http://dx.doi.org/10.3795/KSME-A.2003.27.6.930

Integrity Evaluation for Stud Female Threads on Pressure Vessel according to ASME Code using FEM  

Kim, Moon-Young (한전기공 기술연구소)
Chung, Nam-Yong (숭실대학교 기계공학과)
Publication Information
Transactions of the Korean Society of Mechanical Engineers A / v.27, no.6, 2003 , pp. 930-937 More about this Journal
Abstract
The extension of design life among power plants is increasingly becoming a world-wide trend. Kori #1 unit in Korea is operating two cycle. It has two man-ways for tube inspection in a steam generator which is one of the important components in a nuclear power plant. Especially, stud bolts fur man-way cover have damaged by disassembly and assembly several times and degradation for bolt materials for long term operation. It should be evaluated and compared by ASME Code criteria for integrity evaluation. Integrity evaluation criteria which has been made by the manufacturer is not applied on the stud bolts of nuclear pressure vessels directly because it is controlled by the yield stress of ASME Code. It can apply evaluation criteria through FEM analysis to damaged female threads and to evaluated safety fer helical-coil method which is used according to Code Case-N-496-1. From analysis results, we found .that it is the same results between stress intensity which got from FEM analysis on damaged female threads over 10％ by manufacture integrity criteria and 2／3 yield strength criteria on ASME Code. It was also confirmed that the helical-coil repair method would be safe.
Keywords
Finite Element Method; Steam Generator; Stress Intensity; Integrity Evaluation; Helical-coil; Female and Male Threads;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
연도 인용수 순위
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