Design of the Reactor Core for Nuclear Powerplants (IAEA...

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

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Rok:

2005

Język:

english

Strony:

74

Plik:

PDF, 513 KB

IPFS:

,

english, 2005

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— Study Materials for MIT Course [22.312]. Engineering of Nuclear Reactors

Richard T., Jr. Lahey, F. J. Moody — The Thermal-Hydraulics of a Boiling Water Nuclear Reactor

John R. Lamarsh — Introduction to Nuclear Reactor Theory

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)

— Control Assembly Materials for Water Reactors (IAEA TECDOC-1132)

— Specialists Meeting on Boron Dilution Reactivity Transients

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

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

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

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

— Accid. Anal. - Nuclear Powerplants with PHWRs

— Accid. Anal. - Nuclear Powerplants with PWRs

— Defense in Depth for Nuclear Powerplants (IAEA TECDOC-1218)

— Design of Fuel Handling, Storage Systems for Nuclear Powerplants (IAEA NS-G-1.4)

— Design of Reactor Coolant Systems in Nuclear Powerplants (IAEA NS-G-1.9)

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

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

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

— Nuclear Reactor Safety Design Criteria (US DOE 5480.30)

— Operational Limits, Conditions and Oper Procs for Nuclear Powerplants (IAEA NS-G-2.2)

Aspects of Design for Nuclear Powerplants (IAEA NS-G-1.13) — Radiation Protection

— Safety Anal of Nucl Powerplants - Low-Pwr and Shutdown Cond (IAEA TECDOC-1042)

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

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

— Standard Tech Specs - Babcock & Wilcox Plants Vol 1

— Std Tech Specs - Combustion Engineering Plants Vol 1

— Std Tech Specs - Westinghouse Plants Vol 2

— Strategic Nuclear Research Collaboration [1999 Annual Rpt]

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

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

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

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

— Fast Reactors and Related Fuel Cycles: Challenges and Opportunities

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

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