धन उगाहना 15 सितंबर, 2024 – 1 अक्टूबर, 2024 धन उगाहने के अभियान के बारे में

Precursors to potential severe core damage accidents : a...

Main
Precursors to potential severe core...

Precursors to potential severe core damage accidents : a status report

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

0 / 0

यह पुस्तक आपको कितनी अच्छी लगी?

फ़ाइल की गुणवत्ता क्या है?

पुस्तक की गुणवत्ता का मूल्यांकन करने के लिए यह पुस्तक डाउनलोड करें

डाउनलोड की गई फ़ाइलों की गुणवत्ता क्या है?

साल:

1997

प्रकाशन:

ORNL

भाषा:

english

पृष्ठ:

328

फ़ाइल:

PDF, 17.74 MB

IPFS:

,

english, 1997

ऑनलाइन पढ़ें

में रूपांतरण जारी है

में रूपांतरण विफल रहा

आप के लिए दिलचस्प हो सकता है

Kenneth D. Bergeron — Tritium on Ice: The Dangerous New Alliance of Nuclear Weapons and Nuclear Power

Selby, Lucas, Hyman, Freels, Wiliams, Chang, Hill, various — High Flux Isotope Reactor Cold Neutron Source Reference Design

— Specialists Meeting on Boron Dilution Reactivity Transients

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

— Accid. Anal. - Nuclear Powerplants with PHWRs

— Accid. Anal. - Nuclear Powerplants with PWRs

— Accid. Anal. for Nuclear Powerplants

— Alpha-Mode Containment Failure, Fuel-Coolant Interaction Issues

— Devel of Safety Principles for Design of Future Nucl Powerplants (IAEA TECDOC-801)

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

— Indiv. Plant Exam Pgm - Perspectives on Plant Safety, Performance Vol 1

— Indiv. Plant Exam Pgm - Perspectives on Plant Safety, Performance Vol 2

— LWR Containment Systems Performance - Safety Assessment (csni-r1992-19)

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

— Reliability of Safety-Related Steam-Turbine-Driven Standby Pumps

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

— Sensitivity, Uncert. Analyses Appl to Criticality Safety Valid. [appls, guidance]

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

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

— TRITON - Advanced Lattice Code for MOX Fuel Calculations

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

— Water Reactor Safety Info Meeting Vol 1 [22nd, transactions]

— Water Reactor Safety Info Meeting Vol 1 [24th, Transactions]

— Water Reactor Safety Info Meeting Vol 3 [24th, Transactions]

— Water Reactor Safety Info Meeting [19th, transactions]

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

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

A. L. Wright, Oak Ridge National Laboratory — Primary system fission product release and transport: A state-of-the-art report to the committee on the safety of nuclear installations

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

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

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

OECD NEA — Five Years after the Fukushima Daiichi Accident

Smith C. — Risk-Informed Methods and Applications.Nuclear..Energy Engineering 2023.

सबसे उपयोगी शब्द