Water Reactor Safety Info Meeting Vol 1 [21st,...

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Water Reactor Safety Info Meeting Vol 1 [21st, transactions]

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عام:

1991

الناشر:

US NRC

اللغة:

english

الصفحات:

588

ملف:

PDF, 45.73 MB

IPFS:

,

english, 1991

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قد تكون في قائمة إهتماماتك

Bengt Pershagen — Light Water Reactor Safety

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

— Specialists Meeting on Boron Dilution Reactivity Transients

— Accid. Anal. - Nucl. Powerplants w. Graphite-Moderated BW RBMK Reactors

— Accid. Anal. - Nuclear Powerplants with PHWRs

— Design of Reactor Coolant Systems in Nuclear Powerplants (IAEA NS-G-1.9)

— NPR Reactor Hazards Review (detailed) Phase I [Declassified]

— NPR Reactor Hazards Review Vol 1 (phase 1 - production) [declassified]

— Prelim Safety Rpt - Std MHTGR Vol 1

— RELAP5 MOD 3 Code Manual Vol 5 - [User Guidelines] - US NRC

— RELAP5 MOD 3 Code Manual Vol 7 - [Summaries, Reviews] - US NRC

— Safety Anal of Nucl Powerplants - Low-Pwr and Shutdown Cond (IAEA TECDOC-1042)

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

— Safety Improvements in Low-Power, Shutdown Modes (csni-r1997-17)

— Shutdown, Low-Power Operation at Commercial Nuclear Powerplants

— Standard Tech Specs - Babcock & Wilcox Plants Vol 1

— Std Tech Specs - Combustion Engineering Plants Vol 1

— Std Tech Specs - Westinghouse Plants Vol 1

— Std Tech Specs - Westinghouse Plants Vol 2

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

— System 80+ Standard [nucl. powerplnt] Design - Vol 07

— System 80+ Standard [nucl. powerplnt] Design - Vol 12

— System 80+ Standard [nucl. powerplnt] Design - Vol 15

— System 80+ Standard [nucl. powerplnt] Design - Vol 17

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

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

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

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

— Westinghouse AP600 Small-Break LOCA, Steam-Line Failure, etc., Scenarios - US NRC

Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs — Precursors to potential severe core damage accidents : a status report

R R Fullwood; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Brookhaven National Laboratory.; et al — Integrated systems analysis of the PIUS reactor

Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs — Precursors to potential severe core damage accidents : a status report

International Atomic Energy Agency.; Argonne National Laboratory — Safety of nuclear installations : future direction

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

Call, D.W.; Leggett, W.D.; McShane, W.J.; Fauske, H.K.; McAdoo, J.D.; Strawbridge, L.E. . Nuclear and Advanced; Liparulo, N.J.; Toto, G. . Nuclear Services Div.; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Westinghouse Savannah River — Westinghouse independent safety review of Savannah River production reactors

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