Fracture mechanism of a dissimilar metal welded joint in nuclear power plant

Author:

Wang H.T.,Wang G.Z.,Xuan F.Z.,Tu S.T.

Publisher

Elsevier BV

Subject

General Engineering,General Materials Science

Reference30 articles.

1. Mechanical property variation within Inconel 82/182 dissimilar metal weld between low alloy steel and 316 stainless steel;Jang;Int J Press Ves Pip,2008

2. Local mechanical properties of alloy 82/182 dissimilar weld joint between SA508 Gr.1a and F316 SS at RT and 320°C;Kim;J Nucl Mater,2009

3. PWR Material reliability project, Interim alloy 600 safety assessment for U.S. PWR plants, Part 1: Alloy82/182 pipe butt welds. EPRI, Report TP-1001491; 2001.

4. Degradation of a Ni–Cr–Fe alloy in a pressurised water nuclear power plant;Celin;Mater Technol,2011

5. Jenssen A, Norrgard K, Lagerstron J. Assessment of cracking in dissimilar metal welds. In: Proc. of Tenth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. USA: NACE International: CD-ROM; 2001

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