Review of PWSCC and mitigation management strategies of Alloy 600 materials of PWRs

Author:

Hwang Seong Sik

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference46 articles.

1. IAEA, Nuclear energy series no. NP-T-3.13, Stress corrosion cracking in light water reactors: Good practices and Lessons, IAEA, Vienna, Austria, 2011.

2. EPRI-1007832, PWSCC of Alloy 600 Type Materials in Non-Steam Generator Tubing Applications-Survey Report through June 2002: Part 1: PWSCC in Components Other Than CRDM/CEDM Penetrations (MRP-87), EPRI, Palo Alto, CA, USA, 2003.

3. NUREG-1823, U.S. Plant Experience With Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials, U.S. Nuclear Regulatory Commission, Washington DC, 2005.

4. EPRI-103696, PWSCC of Alloy 600 Materials in PWR Primary System Penetrations, EPRI, Palo Alto, CA, USA, 1994.

5. S. Fyfitch, Alloy 600 PWSCC: Historical Perspective, EPRI PWSCC, Workshop 2007.

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