• Title/Summary/Keyword: 스터드 암나사

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Managing method for stud female threads used long period under high temperature on the power plants (장기간 사용된 발전설비용 고온 스터드 암나사부 관리방법)

  • Chung, Nam-Yong;Kim, Moon-Young
    • Proceedings of the KSME Conference
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    • 2000.11a
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    • pp.199-205
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    • 2000
  • The stud female threads for stud bolts tend to degrade faster by high temperature over 450 C. Therefore, inspection for replacement cycle of stud bolts is used to carry out many kinds of method such as ultrasonic test(UT), magnetic test(MT), wobble test, visual test and hardness test. The visual inspection among those has been only applied for stud female threads generally and wobble test is often used to apply stud bolts. In this paper, wobble test is applied for evaluation of stud female threads on the contrary stud bolts especially. It is also applied three types of inspection method included wobble test on the two sites which is used for each other different operation cycle and three kinds of acquisition data are compared with evaluation methods. From the results, we have studied the characteristic exchanging of integrity evaluation data distribution according to using time and proposed managing method for female thread of stud on the power plants.

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Integrity Evaluation for Stud Female Threads on Pressure Vessel according to ASME Code using FEM (유한요소해석에 의한 ASME Code 적용 압력용기 스터드 암나사산의 건전성 평가)

  • Kim, Moon-Young;Chung, Nam-Yong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.27 no.6
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    • pp.930-937
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    • 2003
  • 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.