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RELAP5 MOD 3 Code Manual Vol 7 - [Summaries, Reviews] - US...

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RELAP5 MOD 3 Code Manual Vol 7 - [Summaries, Reviews] - US NRC

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Tahun:

1995

Bahasa:

english

Halaman:

139

Fail:

PDF, 9.71 MB

IPFS:

,

english, 1995

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Mungkin anda berminat

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— Aging Assessment - Westinghouse PWR, GE BWR Containment Isol Fns

— Code Validation Matrix - Thermohydraulic Codes for LWR LOCA (csni87-132)

— RELAP5 MOD 3 Code Manual Vol 1 - [Code, Sys Modules] - US NRC

— RELAP5 MOD 3 Code Manual Vol 2 - [Users Guide] - US NRC

— RELAP5 MOD 3 Code Manual Vol 4 - [Models, Correlations] - US NRC

— RELAP5 MOD 3 Code Manual Vol 5 - [User Guidelines] - US NRC

— Separate Effects Matrix - Thermal-Hydraulic Effects Code Validation (csni-r1993-14)

— Thermo-Hydraulic Codes for VVER LOCA and Transients (csni-r2001-4)

— Water Reactor Safety Info Meeting Vol 1 [21st, transactions]

Paul D Bayless; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; et al — Severe accident natural circulation studies at the INEL

P S Damerell; J W Simons; Nihon Genshiryoku Kenkyūjo.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; et al — Reactor safety issues resolved by the 2D/3D program

OECD Nuclear Energy Agency — State-of-the-art report on containment thermalhydraulics and hydrogen distribution

A L Wright; Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; et al — Primary system fission product release and transport : a state-of-the-art report to the Committee on the Safety of Nuclear Installations

M Pilch; H Yan; T G Theofanous; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Sandia National Laboratories — The probability of containment failure by direct containment heating in Zion

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

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

John C. Lee, Norman J. McCormick — Risk and Safety Analysis of Nuclear Systems

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