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Block, R.C.; Feiner, F.
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Osaka (Japan). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1995
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Osaka (Japan). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1995
AbstractAbstract
[en] This document, Volume 3, includes papers presented at the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-7) September 10--15, 1995 at Saratoga Springs, N.Y. The following subjects are discussed: Progress in analytical and experimental work on the fundamentals of nuclear thermal-hydraulics, the development of advanced mathematical and numerical methods, ad the application of advancements in the field in the development of novel reactor concepts. Also combined issues of thermal-hydraulics and reactor/power-plant safety, core neutronics and/or radiation. Selected abstracts have been indexed separately for inclusion in the Energy Science and Technology Database
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Sep 1995; 1001 p; 7. international meeting on nuclear reactor thermal hydraulics; Saratoga, NY (United States); 10-15 Sep 1995; CONF-950904--VOL.3; Also available from OSTI as TI95017079; NTIS
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Report
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Conference
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BWR TYPE REACTORS, COMPUTER CODES, COMPUTERIZED SIMULATION, CONTAINMENT, CORIUM, EXPLOSIONS, FLUID FLOW, FUEL-COOLANT INTERACTIONS, HEAT FLUX, HEAT TRANSFER, HTGR TYPE REACTORS, HYDRAULICS, LEADING ABSTRACT, LOSS OF COOLANT, MEETINGS, MELTDOWN, NUCLEAR POWER PLANTS, PWR TYPE REACTORS, REACTOR COOLING SYSTEMS, REACTOR SAFETY, STEAM
ABSTRACTS, ACCIDENTS, COOLING SYSTEMS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, NUCLEAR FACILITIES, POWER PLANTS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, SAFETY, SIMULATION, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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