Water Reactor Safety Info Meeting [21st, transactions]

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Water Reactor Safety Info Meeting [21st, transactions]

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عام:

1993

الناشر:

US NRC

اللغة:

english

الصفحات:

178

ملف:

PDF, 15.79 MB

IPFS:

,

english, 1993

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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

Gianni Petrangeli — Nuclear Safety

— Progress in Safety Systems for Advanced Water-Cooled Reactors (IAEA TECDOC-872)

— Development, Design Aspects of Advanced Water Cooled Reactors (IAEA TECDOC-677)

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

— Direct Containment Heating (csni89-153)

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

— Generic Safety Issues for Nucl Powerplants with LWRs (IAEA TECDOC-1044)

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

— Instrumentation to Manage Severe Accidents (csni-r1992-11)

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

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

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

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

— System 80+ Standard [nucl. powerplnt] Design - Final Safety Eval Rpt Vol 2

— 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 1 [21st, transactions]

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

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

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

— Water Reactor Safety Info Meeting [25th, transactions]

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

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 debris retention and coolability : summary and conclusions : OECD/CSNI workshop, 3-6 March 1998, Garching near Munich, Germany

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

M. Ishii; S. T. Revankar; U. S. Rohatgi; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Purdue University.; Brookhaven National Laboratory.; United States. Dept. of Energy. Oakland Operations Of — MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS

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

International Atomic Energy Agency — Design measures for prevention & mitigation of severe accidents at advanced water cooled reactors : proceedings of a technical committee meeting hedl in vienna, 21-25 october 1996

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

Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — PWG4 perspective on ex-vessel hydrogen sources

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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