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U.S. DOE Nuclear Energy Research Advisory Committee (2002)
U.S. DOE Nuclear Energy Research Advisory Committee (NERAC) and the Generation IV International Forum (GIF). A technology roadmap for generation IV nuclear energy systems. GIF-002-00, Washington D C, 2002
U. Doe (2002)
A Technology Roadmap for Generation IV Nuclear Energy Systems
Guo Juanyan Liu Zhiming (2007)
Liu Zhiming, Guo Juanyan, Shi Wenbao. The technological progress on material research and development for SCWR advanced reactor. The 3rd International Symposium on Supercritical Water-Cooled Reactors—Design and Technology, Shanghai, China, 2007
Jaewoon Yoo, Y. Oka, Y. Ishiwatari, Jie Liu (2006)
Thermo-mechanical analysis of supercritical pressure light water-cooled fast reactor fuel rod by FEMAXI-6 codeAnnals of Nuclear Energy, 33
Allegheny Ludlum Corporation. Stainless steel AL- (1998)
Allegheny Ludlum Corporation. Stainless steel AL-6XN alloy. UNS Designation N08367. Technical Data Blue Sheet, Pittsburgh, PA, 1998
S. Nemat-Nasser, W. Guo, D. Kihl (2001)
Thermomechanical response of AL-6XN stainless steel over a wide range of strain rates and temperaturesJournal of The Mechanics and Physics of Solids, 49
Abstract Modified AL-6XN austenite steel was patterned after AL-6XN superaustenitic stainless steel by introducing microalloy elements such as zirconium and titanium in order to adapt to recrystallizing thermomechanical treatment and further improve crevice corrosion resistance. Modified AL-6XN exhibited comparable tensile strength, and superior plasticity and impact toughness to commercial AL-6XN steel. The effects of aging behavior on corrosion resistance and impact toughness were measured to evaluate the qualification of modified AL-6XN steel as an in-core component and cladding material in a supercritical water-cooled reactor. Attention should be paid to degradation in corrosion resistance and impact toughness after aging for 50 hours when modified AL-6XN steel is considered as one of the candidate materials for in-core components and cladding tubes in supercritical water-cooled reactors.
"Frontiers in Energy" – Springer Journals
Published: Jun 1, 2009
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