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

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عام:

1996

اللغة:

english

الصفحات:

369

ملف:

PDF, 23.14 MB

IPFS:

,

english, 1996

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IAEA — Directory of Nuclear Reactors, Vol. 7. Power Reactors (Supplement to Vol. 4)

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

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

— Cold-leg Break Experiment Vol 1 (csni-r1992-20-VOL1)

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

— Integral Design Concepts - Advanced Water Cooled Reactors (IAEA TECDOC-977)

— Intro of Small, Medium Reactors in Developing Countries (IAEA TECDOC-999)

Adv. Water-Cooled Nuclear Powerplant Designs (IAEA TECDOC-1281) — Natural Circ. Data, Methods

— Natural Circulation in Water-Cooled Nuclear Powerplants

— Pressure Suppression System Containments (csni86-126)

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

— Small Power, Heat - Gen. Systms - on Basis of Propulsion Reactor Tech (IAEA TECDOC-1172)

— Small, Med Sized Nuclear Reactor Designs - Design Feats, Safety Approaches (IAEA TECDOC-1451)

— Status of Adv. Light-Water Nuclear Reactor Designs (IAEA TECDOC-1391)

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

— 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)

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

— 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

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

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

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

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

Max Weber; U.S. Atomic Energy Commission. Division of Reactor Development and Technology — Status of LMFBR reheat in Western Europe, 1972 : report of the United States of America LMFBR Sodium Reheat Team visit to France, Germany (FRG), Netherlands, and United Kingdom, May 22-June 6, 1972

OECD Nuclear Energy Agency — State-of-the-art report on containment thermalhydraulics and hydrogen distribution

J C Cleveland; J C Conklin; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Oak Ridge National Laboratory — High temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research quarterly progress report, April 1-June 30, 1979

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

中国核能动力学会反应堆热工流体专业委员会空泡物理和自然循环国家级重点实验室 — 核反应堆热工词典

Kendall J. (red.) — Natural circulation data and methods for advanced water cooled nuclear power plant designs

Kuznetcov V. — Design Features to Achieve Defence in Depth in Small and Medium Sized Reactors

— Natural Circulation Phenomena, Modeling and Reliability of Passive Systems That Utilize Natural Circulation

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