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Ryu, Woo Seog; Jang, J. S.; Kim, D. W.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
AbstractAbstract
[en] Mainly two research areas were covered in this project. One is to establish the integrated database of nuclear materials, and the other is to study the behavior of reactor core materials, which are usually under the most severe condition in the operating plants. During the stage I of the project (for three years since 1999) in- and out of reactor properties of stainless steel, the major structural material for the core structures of PWR (Pressurized Water Reactor), were evaluated and specification of nuclear grade material was established. And the damaged core components from domestic power plants, e.g. orifice of CVCS, support pin of CRGT, etc. were investigated and the causes were revealed. To acquire more resistant materials to the nuclear environments, development of the alternative alloys was also conducted. For the integrated DB establishment, a task force team was set up including director of nuclear materials technology team, and projector leaders and relevant members from each project. The DB is now opened in public through the Internet
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Mar 2002; 711 p; Available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); 151 refs, 319 figs, 53 tabs
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Report
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ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, ENRICHED URANIUM REACTORS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MANAGEMENT, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, STAINLESS STEELS, STEEL-CR17NI12MO3, STEELS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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