Water Reactor Safety Info Meeting [19th, transactions]

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Water Reactor Safety Info Meeting [19th, transactions]

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ఈ పుస్తకం ఎంతగా నచ్చింది?

దింపుకొన్న ఫైల్ నాణ్యత ఏమిటి?

పుస్తక నాణ్యత అంచనా వేయడాలనుకుంటే దీన్ని దింపుకోండి

దింపుకొన్న ఫైళ్ళ నాణ్యత ఏమిటి?

సంవత్సరం:

1991

ప్రచురణకర్త:

US NRC

భాష:

english

పేజీల సంఖ్య:

206

ఫైల్:

PDF, 16.32 MB

IPFS:

,

english, 1991

ఆన్‌లైన్‌లో చదవండి

దింపుకోలు (pdf, 16.32 MB)

కి మార్పిడి జరుగుతూ ఉంది.

కి మార్పిడి విఫలమైంది!

మీకు ఆసక్తిగా కనిపించ వచ్చు

R. Finnegan — Why Do We Quote - The Cult. and Hist. of Quotation

Bengt Pershagen — Light Water Reactor Safety

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

Gianni Petrangeli — Nuclear Safety

— 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)

— Accid. Anal. - Nuclear Powerplants with PHWRs

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

— Control of Release of Fission Products by Severe Accident (csni-r2000-9)

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

— Iodine Chemistry in Reactor Safety [workshop] (csni-r91-15)

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

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

— Status of Adv. Light-Water Nuclear Reactor Designs (IAEA TECDOC-1391)

— System 80+ Standard [nucl. powerplnt] Design - Final Safety Eval Rpt Vol 2

— System 80+ Standard [nucl. powerplnt] Design - Vol 17

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

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

— Water Reactor Safety Info Meeting Vol 2 [20th, Transactions]

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

— Water Reactor Safety Info Meeting [25th, transactions]

D A Conley; Jerald L Edson; C F Fineman; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering — Aging study of boiling water reactor high pressure injection systems

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

Call, D.W.; Leggett, W.D.; McShane, W.J.; Fauske, H.K.; McAdoo, J.D.; Strawbridge, L.E. . Nuclear and Advanced; Liparulo, N.J.; Toto, G. . Nuclear Services Div.; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Westinghouse Savannah River — Westinghouse independent safety review of Savannah River production reactors

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

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

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

NUCLEAR ENERGY AGENCY — Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant

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

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

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

James H. Rust (Eds.) — Nuclear Power Safety

Bengt Pershagen — Light Water Reactor Safety

Gianni Petrangeli — Nuclear safety

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