Emergency Core Cooling Systems

42 books
PIUS core performance analysisUnknown Author
⏱ 59m

PIUS core performance analysis

Unknown Author

199659 pp.
Knowledge base for the effect of debris on pressurized water reactor emergency core cooling sump performanceUnknown Author

Knowledge base for the effect of debris on pressurized water reactor emergency core cooling sump performance

Unknown Author

2003No page data
GSI-191Unknown Author

GSI-191

Unknown Author

2002No page data
GSI-191D. V. Rao
⏱ 4h 45m

GSI-191

D. V. Rao

2002285 pp.
GSI-191Unknown Author

GSI-191

Unknown Author

2002No page data
Consequences of the loss of the residual heat removal systems in pressurized water reactorsL. W. Ward
⏱ 2h 33m

Consequences of the loss of the residual heat removal systems in pressurized water reactors

L. W. Ward

1992153 pp.
Draft regulatory guide DG-1107U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
⏱ 30m

Draft regulatory guide DG-1107

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

200330 pp.
A criterion for the onset of quench for low flow refloodY. Y Hsu
⏱ 28m

A criterion for the onset of quench for low flow reflood

Y. Y Hsu

198228 pp.
USI A-43 resolution positionsU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.

USI A-43 resolution positions

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.

1983No page data
Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =Jan Taler
⏱ 2h 3m

Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =

Jan Taler

1993123 pp.
RELAP/MOD3 analysis of BETHSY test 6.9cG. R Kimber
⏱ 49m

RELAP/MOD3 analysis of BETHSY test 6.9c

G. R Kimber

200049 pp.
An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2J. M. Rogers
⏱ 39m

An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2

J. M. Rogers

199239 pp.
Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold ShutdownSarah E. Colpo
⏱ 37m

Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown

Sarah E. Colpo

199937 pp.
Analysis of semiscale test S-LH-1 using RELAP5/MOD2P. C. Hall
⏱ 32m

Analysis of semiscale test S-LH-1 using RELAP5/MOD2

P. C. Hall

199232 pp.
Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)F. Curca-Tivig
⏱ 53m

Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)

F. Curca-Tivig

199353 pp.
GSI-191Unknown Author

GSI-191

Unknown Author

2002No page data
Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditionsS. Majumdar

Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions

S. Majumdar

2003No page data
GSI-191Unknown Author

GSI-191

Unknown Author

2002No page data
SUNYAB/ERPI Combined Injection ECCS ProgramState University College at Buffalo.
⏱ 1h 2m

SUNYAB/ERPI Combined Injection ECCS Program

State University College at Buffalo.

197762 pp.
Transient response of Babcock & Wilcox-designed reactorsU.S. Nuclear Regulatory Commission. B & W Reactor Transient Response Task Force
⏱ 4h 32m

Transient response of Babcock & Wilcox-designed reactors

U.S. Nuclear Regulatory Commission. B & W Reactor Transient Response Task Force

1980272 pp.
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