Pressure Suppression System Containments (csni86-126)

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سال:

1986

زبان:

english

صفحات:

115

فائل:

PDF, 4.76 MB

IPFS:

,

english, 1986

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میں تبدیلی جاری ہے۔

میں تبدیلی ناکام ہو گئی۔

آپ کو دلچسپی ہوسکتی ہے

Bengt Pershagen — Light Water Reactor Safety

Gianni Petrangeli — Nuclear Safety

— Evolutionary Water-Cooled Reactors - Issues, Technologies (IAEA TECDOC-1117)

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

— Accid. Anal. - Nuclear Powerplants with PHWRs

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

— Ageing of Nuclear Powerplant Concrete Structures (csni-r95-19)

— Aging Assessment - Westinghouse PWR, GE BWR Containment Isol Fns

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

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

— Bubbler-Condenser-Related Research (csni-r2001-3)

— Code Validation Matrix - Thermohydraulic Codes for LWR LOCA (csni87-132)

— Control of Release of Fission Products by Severe Accident (csni-r2000-9)

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

— Design, Devel Status of Small and Medium Reactor Systems (IAEA TECDOC-881)

— Emergency Core Cooling System Recirculation Reliability (csni-r1995-11)

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

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

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

— Large Break LOCA [proceedings] Vol 1 (csni-r2003-17-vol1)

— Reactor Coolant System Leakage and Failure Probabilities (csni-r1995-6)

— Separate Effects Matrix - Thermal-Hydraulic Effects Code Validation (csni-r1993-14)

— Shutdown, Low-Power Operation at Commercial Nuclear Powerplants

— Std Tech Specs - GE Plants BWR 4 Vol 1

— Steam Explosions and Reactor Safety (csni82-74)

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

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

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

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

— Thermo-Hydraulic Codes for VVER LOCA and Transients (csni-r2001-4)

— Thermohydraulics of Emergency Core Cooling in LWRs (csni89-161)

— Use of Water to Cool a Molten Core in the Containment (csni-r1994-34)

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

— Wrkshop on Late Phase Fusion Product Aerosol-Vapor Source (csni-r1994-30)

International Atomic Energy Agency.; Agence Internationale de l'Energie Atomique — Experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors : proceedings of a Technical Committee meeting held in Villigen, Switzerland, 14-17 September 1998

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