VVER-Specific Features [core degradation] (csni-r98-20)

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VVER-Specific Features [core degradation] (csni-r98-20)

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মান নির্ণয়ের জন্য বইটি ডাউনলোড করুন

ডাউনলোড করা ফাইলগুলির মান কিরকম?

সাল:

1998

ভাষা:

english

পৃষ্ঠা:

36

ফাইল:

PDF, 102 KB

IPFS:

,

english, 1998

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আপনি আগ্রহী হতে পারেন

J.N. Lillington — Light Water Reactor Safety: The Development of Advanced Models and Codes for Light Water Reactor Safety Analysis

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)

— Behavior of LWR Core Materials Under Accident Conditions (IAEA TECDOC-921)

— Direct Containment Heating (csni89-153)

— In-Vessel Core Degradation [validation martrix] (csni-r2000-21)

— Mgmt of Ageing of PWR Vessel Internals (IAEA TECDOC-1119)

— Proceedings of Topical Meeting on RIA Vol 1 (csni-r2003-8-vol1)

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

— PWR Program Progress Rpt [Sep 9 - Oct 20, 1955] [declassified]

— Status of Degraded Core Issues (csni-r2001-5)

— Steam Explosions and Reactor Safety (csni82-74)

— System 80+ Standard [nucl. powerplnt] Design - Vol 04

— 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 2 [20th, Transactions]

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

— Zircalloy Clad [nuclear] Fuel Analysis

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

Manfred Firnhaber; Gesellschaft für Reaktorsicherheit (Köln) — CORA-13 experiment on severe fuel damage : comparison report

T J Haste; K Trambauer; OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — Degraded core quench : summary of progress, 1996-1999 : executive summary

Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — In-vessel core debris retention and coolability : summary and conclusions : OECD/CSNI workshop, 3-6 March 1998, Garching near Munich, Germany

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

G Bandini; OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations.; et al — Molten material relocation into the lower plenum : a status report

OECD Nuclear Energy Agency — International standard problem isp36 : cora-w2 experiment on severe fuel damage for a russian type pwr

Colin Tucker — How to Drive a Nuclear Reactor

Prof.Dr. H. Bock — VVER- Russian Reactor type overview

Alan Edward Waltar, Albert Barnett Reynolds — Fast Breeder Reactors

Bengt Pershagen — Light Water Reactor Safety

John Graham (Eds.) — Fast Reactor Safety

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

W. Krischer — Phebus Fission Product Project: Presentation of the experimental programme and test facility (Publication No. Eur 13520 En of the Commission of the Europe)

Lillington J.N. — Light water reactor safety : the development of advanced models and codes for light water reactor safety analysis

coll. — TopFuel'97 : proceedings of the conference organized by the British Nuclear Energy Society and held in Manchester on 9-11 June 1997

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