Accid. Anal. - Nuclear Powerplants with PHWRs

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Accid. Anal. - Nuclear Powerplants with PHWRs

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سال:

2003

ناشر کتب:

IAEA Pub 1161

زبان:

english

صفحات:

57

فائل:

PDF, 294 KB

IPFS:

,

english, 2003

آن لائن پڑھیں

ڈاؤن لوڈ کریں (pdf, 294 KB)

میں تبدیلی جاری ہے۔

میں تبدیلی ناکام ہو گئی۔

آپ کو دلچسپی ہوسکتی ہے

Bengt Pershagen — Light Water Reactor Safety

Gianni Petrangeli — Nuclear Safety

— Advances in Heavy Water Reactor Technology (IAEA TECDOC-984)

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

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

— Siting of Research Reactors (IAEA TECDOC-403)

— Accid. Anal. - Nucl. Powerplants w. Graphite-Moderated BW RBMK Reactors

— Accid. Anal. - Nuclear Powerplants with PWRs

— Accid. Anal. for Nuclear Powerplants

— Design of Reactor Coolant Systems in Nuclear Powerplants (IAEA NS-G-1.9)

— Design of the Reactor Core for Nuclear Powerplants (IAEA NS-G-1.12)

— Design, Devel Status of Small and Medium Reactor Systems (IAEA TECDOC-881)

— Devel of Oper Procs for Emergency Conds at Nucl Powerplants (IAEA TECDOC-341)

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

— Generic Safety Issues for Nuclear Power Plants with PHWR's - IAEA TECDOC-1554

— Modern Instrumentation and Control for Nuclear Powerplants (IAEA TRS-387)

— Safety Anal of Nucl Powerplants - Low-Pwr and Shutdown Cond (IAEA TECDOC-1042)

— Safety Assessment and Verification for Nuclear Powerplants (IAEA NS-G-1.2)

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

— Safety Improvements in Low-Power, Shutdown Modes (csni-r1997-17)

— Shutdown, Low-Power Operation at Commercial Nuclear Powerplants

— 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 12

— System 80+ Standard [nucl. powerplnt] Design - Vol 13

— System 80+ Standard [nucl. powerplnt] Design - Vol 15

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

— System 80+ Standard [nucl. powerplnt] Design - Vol 18

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

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

Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs — Precursors to potential severe core damage accidents : a status report

R R Fullwood; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Brookhaven National Laboratory.; et al — Integrated systems analysis of the PIUS reactor

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

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

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