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Akimoto, Hajime; Kukita; Ohnuki, Akira
Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements1997
Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements1997
AbstractAbstract
[en] The Japan Atomic Energy Research Institute (JAERI) is conducting several research programs related to thermal-hydraulic and neutronic behavior of light water reactors (LWRs). These include LWR safety research projects, which are conducted in accordance with the Nuclear Safety Commission's research plan, and reactor engineering projects for the development of innovative reactor designs or core/fuel designs. Thermal-hydraulic and neutronic codes are used for various purposes including experimental analysis, nuclear power plant (NPP) safety analysis, and design assessment
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Ebert, D.; Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Nuclear Energy Agency, 75 - Paris (France); SCIENTECH, Inc., Boise, ID (United States); 824 p; Jul 1997; p. 262-273; Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements; Annapolis, MD (United States); 5-8 Nov 1996; Also available from OSTI as TI97008508; NTIS; GPO
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