Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Alloy 600 Components Inspection Prioritization Using the Normalized PWSCC Susceptibility Index

정규화된 PWSCC 민감도 지수를 이용한 Alloy 600 기기 검사 우선순위 선정

  • Received : 2016.04.29
  • Accepted : 2016.05.11
  • Published : 2016.06.30
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Abstract

Alloy 600 widely used in nuclear power plant is susceptible to primary water stress corrosion cracking (PWSCC). It is important to prioritize the inspection of Alloy 600 components using PWSCC susceptibility index. Plant-specific model for the susceptibility index was reviewed. The normalized PWSCC susceptibility index to a reference value is suggested and applied. The result was found to be reasonable.

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References

  1. P. M. Scott, 2000, "Stress Corrosion Cracking in Pressurized Water Reactors- Interpretation, Modelling, and Remedies," Corrosion, Vol. 56, No.8.
  2. USNRC Order EA-03-009 (rev.1), 2004, "Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," USNRC.
  3. Korea Hydro and Nuclear Power Co., 2006, Periodic Safety Review Report for Continued Operation of Kori Unit 1 (in Korean), KHNP.
  4. C. King, 2004, Material Reliability Program: Generic Guidance for Alloy 600 Management (MRP-126), EPRI.
  5. C. Amzallag, 2007, 13th Environmental Degradation Conference, Whistler, Canada.
  6. H. Tanaka, 2003, KEPCO report Alloy 600 PWSCC.