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Water Reactor Safety Info Meeting Vol 2 [20th, Transactions]

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Yıl:

1992

Yayımcı:

US NRC

Dil:

english

Sayfalar:

572

Dosya:

PDF, 31.80 MB

IPFS:

,

english, 1992

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İlginizi çekebilir

Bengt Pershagen — Light Water Reactor Safety

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

G.F. Hewitt, John G. Collier — Introduction to Nuclear Power (Series in Chemical and Mechanical Engineering)

— Advanced Containment Systems for Next-Gen Water Reactors (IAEA TECDOC-752)

— Behavior of LWR Core Materials Under Accident Conditions (IAEA TECDOC-921)

— 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)

— Iodine Chemistry in Reactor Safety [workshop] (csni-r91-15)

— LWR Lower Head Failure Analysis

— Probability of Mark-I Containment Failure by Melt-Attack of Liner

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

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

— Status of Degraded Core Issues (csni-r2001-5)

— Steam Explosions and Reactor Safety (csni82-74)

— Tech Feas, Reliability of Passive Safety Systems for Nucl Powerplants (IAEA TECDOC-920)

— VVER-Specific Features [core degradation] (csni-r98-20)

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

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

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

A. L. Wright, Oak Ridge National Laboratory — Primary system fission product release and transport: A state-of-the-art report to the committee on the safety of nuclear installations

Paul D Bayless; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; et al — Severe accident natural circulation studies at the INEL

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

Manfred Firnhaber; Gesellschaft für Reaktorsicherheit (Köln) — CORA-13 experiment on severe fuel damage : comparison report

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

T J Haste; K Trambauer; OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — Degraded core quench : summary of progress, 1996-1999 : executive summary

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

G Bandini; OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations.; et al — Molten material relocation into the lower plenum : a status report

A L Wright; Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; et al — Primary system fission product release and transport : a state-of-the-art report to the Committee on the Safety of Nuclear Installations

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

C M Allison; E C Johnson; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Idaho National Engineering Laboratory.; et al — SCDAP/RELAP5/MOD3.1 code manual

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)

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