Fuel-Coolant Interactions (csni-r1997-26)

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Fuel-Coolant Interactions (csni-r1997-26)

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डाउनलोड की गई फ़ाइलों की गुणवत्ता क्या है?

साल:

1997

भाषा:

english

पृष्ठ:

856

फ़ाइल:

PDF, 63.71 MB

IPFS:

,

english, 1997

ऑनलाइन पढ़ें

में रूपांतरण जारी है

में रूपांतरण विफल रहा

आप के लिए दिलचस्प हो सकता है

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

National Council of Examiners for Engineering and Surveying (NCEES) — Principles and Practices of Engineering PE Nuclear Reference Handbook

— Core-Damage Propagation During Flow-Blockage Accidents in ANS Reactor

— Specialists Meeting on Boron Dilution Reactivity Transients

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

— Alpha-Mode Containment Failure, Fuel-Coolant Interaction Issues

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

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

— Direct Containment Heating (csni89-153)

— Fuel-Coolant Interaction in Nuclear Reactor Safety (csni79-37)

— 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)

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

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

— Shutdown, Low-Power Operation at Commercial Nuclear Powerplants

— Sodium-Fuel Interaction in Fast Reactors (csni76-8)

— 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)

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

— Transient Behavior of High-Burnup Fuel (csni-r1996-23)

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

— 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 [21st, transactions]

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

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

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

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