Design measures for prevention & mitigation of severe...

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Design measures for prevention & mitigation of severe accidents at advanced water cooled reactors : proceedings of a technical committee meeting hedl in vienna, 21-25 october 1996

International Atomic Energy Agency

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ఈ పుస్తకం ఎంతగా నచ్చింది?

దింపుకొన్న ఫైల్ నాణ్యత ఏమిటి?

పుస్తక నాణ్యత అంచనా వేయడాలనుకుంటే దీన్ని దింపుకోండి

దింపుకొన్న ఫైళ్ళ నాణ్యత ఏమిటి?

సంవత్సరం:

1998

ప్రచురణకర్త:

International Atomic Energy Agency

భాష:

english

పేజీల సంఖ్య:

222

పుస్తక శ్రేణి:

IAEA-TECDOC, 1020

ఫైల్:

PDF, 11.52 MB

IPFS:

,

english, 1998

ఆన్‌లైన్‌లో చదవండి

దింపుకోలు (pdf, 11.52 MB)

కి మార్పిడి జరుగుతూ ఉంది.

కి మార్పిడి విఫలమైంది!

మీకు ఆసక్తిగా కనిపించ వచ్చు

Gianni Petrangeli — Nuclear Safety

G.F. Hewitt, John G. Collier — Introduction to Nuclear Power (Series in Chemical and Mechanical Engineering)

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

— Performance of Operating and Advanced Light-Water Reactor Designs (IAEA TECDOC-1245)

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

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

— Siting of Research Reactors (IAEA TECDOC-403)

— Accid. Anal. - Nuclear Powerplants with PHWRs

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

— Approaches to the Safety of Future Nuclear Powerplants (IAEA TECDOC-905)

— Devel of Safety Principles for Design of Future Nucl Powerplants (IAEA TECDOC-801)

— Generic Safety Issues for Nucl Powerplants with LWRs (IAEA TECDOC-1044)

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

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

— Performance of Operating, Adv. Light-Water Nuclear Reactor Designs (IAEA TECDOC-1245)

— 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)

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

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

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

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

Fauske & Associates, Sandia National Laboratories — High-Pressure Melt Ejection (HPME) and Direct Containment Heating (DCH)

Gubler R. (red.) — Use of PSA Level 2 analysis for improving containment performance

Kuznetsov V. — Current Status, Technical Feasibility and Economics of Small Nuclear Reactors

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

Haskin E., Camp L. — Perspectives on Reactor Safety

John N Lillington — The Future of Nuclear Power

Gianni Petrangeli — Nuclear safety

Bal Raj Sehgal (Eds.) — Nuclear Safety in Light Water Reactors. Severe Accident Phenomenology

Igor Pioro — Handbook of Generation IV Nuclear Reactors: A Guidebook, 2nd Edition

Daniel T. Ingersoll, Mario D. Carelli — Handbook of Small Modular Nuclear Reactors: Second Edition

F E Haskin; U.S. Nuclear Regulatory Commission. Office of Human Resources. Technical Training Center.; Sandia National Laboratories.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Technical Training Division. — Perspectives on reactor safety

Charles Perrow — Normal Accidents

Gianni Petrangeli (Auth.) — Nuclear Safety

Mirela Gavrilas, Pavel Hejzlar, Neil E. Todreas, Youssef Shatilla — Safety features of operating light water reactors of western design

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