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

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Tahun:

1962

Penerbit:

US AEC

Bahasa:

english

Halaman:

417

Fail:

PDF, 30.25 MB

IPFS:

,

english, 1962

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Bengt Pershagen — Light Water Reactor Safety

IAEA — Directory of Nuclear Reactors, Volume 1. Power Reactors

IAEA — Directory of Nuclear Reactors, Vol. 4. Power Reactors (Revised and Supplemented Edition of Vol. 1)

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

IAEA — Directory of Nuclear Reactors, Vol. 9. Power Reactors (Supplement to Vol. 4 and 7)

— Evaluation of Gas-Turbine Modular Helium Reactor

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

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

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

— Accid. Anal. - Nuclear Powerplants with PWRs

— Behavior of Water Reactor Fuel Elements Under Accident Conditions (csni77-13)

— Design and Construction of the Hanford Production Reactors [declassified]

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

— Feasibility Study - Supercritical LWRs for Electrical Power Prodn

— Hanford Production Reactors - Technical Specs

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

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

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

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

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

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

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

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

International Atomic Energy Agency — Unusual occurrences during LMFR operation

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

Warner E Unbehaun; U.S. Atomic Energy Commission — History and status of the EBR

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

Badulescu A. et al. — Liquid Metal Cooled Reactors: Experience in Design and Operation

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

Colin Tucker — How to Drive a Nuclear Reactor

— Proceeding International Group on Research Reactor 2 (IGORR 1992)

— Proceeding International Group on Research Reactor 3 (IGORR 1993)

— Proceeding International Group on Research Reactor 7 (IGORR 1999)

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