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Rok:

1996

Wydawnictwo:

BNL

Język:

english

Strony:

166

Plik:

PDF, 9.27 MB

IPFS:

,

english, 1996

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Bengt Pershagen — Light Water Reactor Safety

— Aging Management of LWR Components - Vol 5 [Metal Containments]

— Assessing Human Reliability in Nuclear Powerplants (csni83-75)

— Check Valve Degradation, Failure Exper. in Nucl. Pwr Ind. (1984-1990) Vol 1

— Design of Reactor Containment Systems for Nuclear Powerplants (IAEA NS-G-1.10)

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

— Indiv. Plant Exam Pgm - Perspectives on Plant Safety, Performance Vol 1

— Indiv. Plant Exam Pgm - Perspectives on Plant Safety, Performance Vol 2

— Managing Aging in Nuclear Powerplants

— Managing Aging in Nuclear Powerplants - Insights from NRC Insp. Team Rpts

— NRC ASME Symposium [3rd] on Valve, Pump Testing Vol 2

— Operator Performance in Cognitively Demanding Simulated Emergencies

— Reliability of Safety-Related Steam-Turbine-Driven Standby Pumps

— Safety Aspects of Nuclear Powerplant Ageing (IAEA TECDOC-540)

— Shutdown, Low-Power Operation at Commercial Nuclear Powerplants

— Std Tech Specs - GE Plants BWR 4 Vol 1

— Std Tech Specs - GE Plants BWR 6 Vol 1

— System 80+ Standard [nucl. powerplnt] Design - Vol 02

— System 80+ Standard [nucl. powerplnt] Design - Vol 03

— System 80+ Standard [nucl. powerplnt] Design - Vol 05

— System 80+ Standard [nucl. powerplnt] Design - Vol 06

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

— System 80+ Standard [nucl. powerplnt] Design - Vol 08

— System 80+ Standard [nucl. powerplnt] Design - Vol 10

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

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

— System 80+ Standard [nucl. powerplnt] Design - Vol 18

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

H.L. Ornstein — Operating Experience Feedback Report - Turbine-Generator Overspeed Protection Systems: Commercial Power Reactors

— Water Reactor Safety Info Meeting Vol 3 [21st, Transactions]

— Water Reactor Safety Info Meeting Vol 3 [24th, Transactions]

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

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

D A Conley; Jerald L Edson; C F Fineman; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering — Aging study of boiling water reactor high pressure injection systems

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