Heat Transfer in Nuclear Reacter Safety

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Heat Transfer in Nuclear Reacter Safety

Heat Transfer in Nuclear Reacter Safety

George A. Greene, James P. Hartnett, Thomas F. Irvine and Young I. Cho (Eds.)

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سب زمرہ:

سال:

1997

ناشر کتب:

Academic Press

زبان:

english

ISBN 10:

0120200295

ISBN 13:

9780120200290

سیریز:

Advances in Heat Transfer 29

فائل:

DJVU, 2.94 MB

IPFS:

,

english, 1997

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آپ کو دلچسپی ہوسکتی ہے

J.N. Lillington — Light Water Reactor Safety: The Development of Advanced Models and Codes for Light Water Reactor Safety Analysis

— CO-H Combustion Chars in Severe Accident Cond (csni-r2000-10)

— Direct Containment Heating (csni89-153)

— Fuel-Coolant Interactions (csni-r1997-26)

— Fuel-Coolant Interactions [specialists meeting proceedings] (csni-r1993-8)

— In-Vessel Core Degradation [validation martrix] (csni-r2000-21)

— Selected Containment Severe Accident Mgmt Strategies (csni-r1994-33)

— Steam Explosions and Reactor Safety (csni82-74)

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— Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

— Water Reactor Safety Info Meeting [19th, transactions]

— Water Reactor Safety Info Meeting [21st, transactions]

Theofanous, T.G.; Liu, C.; Additon, S.; Angelini, S.; Kymaelaeinen, O.; Salmassi, T.[California Univ., Santa Barbara, CA (United States). Center for Risk Studies and Safety] — In-vessel coolability and retention of a core melt. Volume 1

OECD Nuclear Energy Agency — State-of-the-art report on containment thermalhydraulics and hydrogen distribution

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; OECD Nuclear Energy Agency — Proceedings of the CSNI Specialists Meeting on Fuel-Coolant Interactions : held in Santa Barbara, California, USA, January 5-8, 1993

Fauske & Associates, Sandia National Laboratories — High-Pressure Melt Ejection (HPME) and Direct Containment Heating (DCH)

Nuclear Energy Agency Committee on the Safety of Nuclear Installations — In-vessel core degradation code validation matrix

M Pilch; H Yan; T G Theofanous; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Sandia National Laboratories — The probability of containment failure by direct containment heating in Zion

Rudolph, J.C.; Parker, G.W.; Forsberg, C.W.; Osborne-Lee, I.W.; Kenton, M.A.; Oak Ridge National Laboratory.; United States. Dept. of Energy. Office of Energy Research.; United States. Dept. of Energy. Office of Scientific and Technical Information — Termination of light-water reactor core-melt accidents with a chemical core catcher : the core-melt source reduction system (COMSORS)

OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — Workshop on Large Molten Pool Heat Transfer : summary and conclusions : CEN, Grenoble, 9-11 March 1994

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Myer Kutz — Mechanical Engineers Handbook 4 Volume Set 4th Edition Volume 4

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Крайнов А.В., Швалова Г.В. — Основы теплоэнергетики

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Lillington J.N. — Light water reactor safety : the development of advanced models and codes for light water reactor safety analysis

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