Nuclear Reactor Pressure Vessel Welds: A Critical and Historical Review of Microstructures, Mechanical Properties, Irradiation Effects, and Future Opportunities
Author:
Funder
US Nuclear Regulatory Commission
US Department of Energy Office of Nuclear Energy
Publisher
Elsevier BV
Reference249 articles.
1. Radiation Embrittlement in the Pressure-Vessel Steels of Nuclear Power Plants;Wechsler;JOM,1989
2. Temperature effects on low-cycle fatigue behavior of SA533B steel in simulated reactor coolant environments;Yeh;Mater. Chem. Phys.,2007
3. Dynamic strain aging and grain size reduction effects on the fatigue resistance of SA533B3 steels;Huang;J. Nucl. Mater.,2004
4. BAW-2308: “Initial RTNDT of Linde 80 Weld Materials,” 2003.
5. G.L. Stevens, Evaluation of the Beltline Region for Nuclear Reactor Pressure Vessels, 2014.
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