Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/152 welds in simulated PWR primary water

Author:

Lim Yun Soo,Kim Dong Jin,Kim Sung Woo,Kim Hong Pyo

Funder

Korean Nuclear R&D

National Research Foundation (NRF)

Ministry of Science and ICT

Korea Atomic Energy Research Institute

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. A review of Alloy 600 cracking in operating nuclear plants: historical experience and future trends;Bamford,2003

2. Cracking of Alloy 600 nozzles and welds in PWRs: review of cracking events and repair service experience;Bamford,2005

3. Microstructural characterization of intergranular stress corrosion cracking of Alloy 600 in PWR primary water environment;Lim;J. Nucl. Mater.,2013

4. Study on grain boundary character along intergranular stress corrosion crack paths in austenitic alloys;Gertsman;Acta Mater.,2001

5. Microstructural characterization of primary water stress-corrosion cracks in Alloy 182 welds from PWR components and laboratory tests;Thomas,2009

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