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ISBN 10:

9264991786

ISBN 13:

9789264991781

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PDF, 1.85 MB

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İlginizi çekebilir

Bengt Pershagen — Light Water Reactor Safety

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)

— Research Reactor Core Conversion Guidebook Vol 1 [Summary] (IAEA TECDOC-643v1)

— Research Reactor Core Conversion Guidebook Vol 2 [Analysis] (IAEA TECDOC-643v2)

— Weapons-Grade Plutonium Dispositioning Vol 3 [new reactor concept]

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

— Accid. Anal. - Nuclear Powerplants with PWRs

— Adv Fuel Pellet Mtls, Designs for Water-Cooled Reactors (IAEA TECDOC-1416)

— Adv in Fuel-Pellet Tech for Imprvd Perf at High Burnup (IAEA TECDOC-1036)

— Design of the Reactor Core for Nuclear Powerplants (IAEA NS-G-1.12)

— Feasibility Study - Supercritical LWRs for Electrical Power Prodn

— Fuel Safety Criteria - Tech Review (csni-r99-25)

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

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

— Nuclear Fuel Behavior Modelling at High Burnup (and exper support) (IAEA TECDOC-1233)

— Nuclear Reactor Tech Manual (Physics Section, 100-N) Vol 1 [draft] [Declassified] -

— Proceedings of Topical Meeting on RIA Vol 2 (csni-r2003-8-vol2)

— Scientific Issues in (nuclear) Fuel Behavior (NEA 0213)

— Std Tech Specs - GE Plants BWR 4 Vol 2

— Std Tech Specs - GE Plants BWR 6 Vol 2

— Std Tech Specs - Westinghouse Plants Vol 2

— Strategic Nuclear Research Collaboration [1999 Annual Rpt]

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

— Transient Behavior of High-Burnup Fuel (csni-r95-22)

— Water Channel Reactor Fuels, Fuel Channels [des, perf] (IAEA TECDOC-997)

— Water Reactor Fuel Element Modeling at High Burnup (IAEA TECDOC-0957)

— Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

International Atomic Energy Agency — Fuel failure in normal operation of water reactors : experience, mechanisms and management : proceedings of a Technical Committee meeting held in Dimitrovgrad, Russian Federation, 26-29 May 1992

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

Nuclear Energy Agency Committee on the Safety of Nuclear Installations — In-vessel core degradation code validation matrix

International Atomic Energy Agency. Technical Committee on Recycling of Plutonium and Uranium in Water Reactor Fuel — Recycling of plutonium and uranium in water reactor fuel : proceedings of a Technical Committee meeting held in Newby Bridge, Windermere, United Kingdom, 3-7 July 1995

OECD Nuclear Energy Agency.; Westinghouse Electric Corporation.; United States. Department of Energy — Status of LMFBR safety technology. 1, Fission gas release from fuel pins

Onoufriev V. (ред.) — Fuel failure in water reactors

OECD — Nuclear fuel safety criteria technical review

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