SCDAP/RELAP5/MOD3.1 code manual

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SCDAP/RELAP5/MOD3.1 code manual

SCDAP/RELAP5/MOD3.1 code manual

C M Allison, E C Johnson, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory., et al

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সাল:

1995

ভাষা:

english

পৃষ্ঠা:

180

ফাইল:

PDF, 8.97 MB

IPFS:

,

english, 1995

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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

Dan Gabriel Cacuci — Handbook of Nuclear Engineering: Vol. 1-4

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

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

— Research Reactor Core Conversion Guidebook Vol 3 [Analytical Verification] (IAEA TECDOC-643v3)

— Advances in Control Assembly Mtls for Water Reactors (IAEA TECDOC-813)

— Behavior of a Fuel Bundle Simularor During Heatup, Flooding (csni85-98)

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

— Crit Exper, Physics Calcs for Low-Enriched, Hi-temp Gas Cooled Reactors (IAEA TECDOC-1249)

— Feasibility Study - Supercritical LWRs for Electrical Power Prodn

— Fuels (nuclear) Development Operations [Jul-Sep 1959] [Declassified]

— Fuels [nuclear] Development Operation [qtrly rpt, Apr-Jun 1961] [declassified]

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

— Probability of Mark-I Containment Failure by Melt-Attack of Liner

— Struct Behavior of Fuel Assys for Water-Cooled Nuclear Reactors (IAEA TECDOC-1454)

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

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

— 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 [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

L. L. Taylor; H. H. Loo; USDOE Office of Environmental Management (EM) (US); Idaho National Engineering and Environmental Laboratory.; United States. Dept. of Energy. Office of Scientific and Technical Information — Shippingport LWBR (Th

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

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; OECD Nuclear Energy Agency — Proceedings of the CSNI Specialists Meeting on Fuel-Coolant Interactions : held in Santa Barbara, California, USA, January 5-8, 1993

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 degradation code validation matrix

C M Allison; E C Johnson; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Idaho National Engineering Laboratory.; et al — SCDAP/RELAP5/MOD3.1 code manual

C M Allison; E C Johnson; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Idaho National Engineering Laboratory.; et al — SCDAP/RELAP5/MOD3.1 code manual

C M Allison; E C Johnson; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Idaho National Engineering Laboratory.; et al — SCDAP/RELAP5/MOD3.1 code manual

C M Allison; E C Johnson; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Idaho National Engineering Laboratory.; et al — SCDAP/RELAP5/MOD3.1 code manual

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

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

— Status Report on the Small Secure Transportable Autonomous Reactor (SSTAR), Lead-Cooled Fast Reactor (LFR) and Supporting Research and Development

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