Emergency Core Cooling Systems

45 books
GSI-191 technical assessmentUnknown Author

GSI-191 technical assessment

Unknown Author

2002No page data
GSI-191 technical assessmentUnknown Author

GSI-191 technical assessment

Unknown Author

2002No page data
Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October-December 1980J. A. Dearien
⏱ 30m

Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October-December 1980

J. A. Dearien

198130 pp.
ECC bypass studyMark J. Colby

ECC bypass study

Mark J. Colby

1977No page data
Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) systemRobert F Christie
⏱ 14m

Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system

Robert F Christie

198514 pp.
Analysis of ECC bypass dataW. D Beckner

Analysis of ECC bypass data

W. D Beckner

1979No page data
Reliability studyUnknown Author

Reliability study

Unknown Author

1998No page data
Reliability studyUnknown Author

Reliability study

Unknown Author

1998No page data
Regulatory guide 1.82, (Task MS 203-4)U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Regulatory guide 1.82, (Task MS 203-4)

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

1985No page data
USI A-43 regulatory analysisA. W. Serkiz

USI A-43 regulatory analysis

A. W. Serkiz

1985No page data
Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plantsU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force
⏱ 5h 43m

Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force

1980343 pp.
Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactorsB. Sheron
⏱ 1h 15m

Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors

B. Sheron

197975 pp.
Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applicationsU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force
⏱ 3h 42m

Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applications

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force

1980222 pp.
Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Westinghouse-designed operating plantsU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force
⏱ 11h 11m

Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Westinghouse-designed operating plants

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force

1980671 pp.
PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis reportU.S. Nuclear Regulatory Commission

PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report

U.S. Nuclear Regulatory Commission

1982No page data
Reliability studyUnknown Author

Reliability study

Unknown Author

1998No page data
Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactorWallis R. Cramond

Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor

Wallis R. Cramond

1987No page data
Compendium of ECCS research for realistic LOCA analysisU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research
⏱ 22h 38m

Compendium of ECCS research for realistic LOCA analysis

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research

19881358 pp.
Standard technical specifications for Westinghouse pressurized water reactorsUnknown Author

Standard technical specifications for Westinghouse pressurized water reactors

Unknown Author

1981No page data
USI A-43 regulatory analysisA. W Serkiz

USI A-43 regulatory analysis

A. W Serkiz

1985No page data
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