Explore Books on
emergency core cooling systems
1-24 of 34 Books
USI A-43 regulatory analysis
USI A-43 regulatory analysis
By A. W. Serkiz
Draft regulatory guide DG-1107
Draft regulatory guide DG-1107
By U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
USI A-43 regulatory analysis
USI A-43 regulatory analysis
By A. W Serkiz
Consequences of the loss of the residual heat removal systems in pressurized water reactors
Consequences of the loss of the residual heat removal systems in pressurized water reactors
By L. W. Ward
USI A-43 resolution positions
USI A-43 resolution positions
By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
SUNYAB/ERPI Combined Injection ECCS Program
SUNYAB/ERPI Combined Injection ECCS Program
By State University College at Buffalo.
Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =
Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =
By Jan Taler
Knowledge base report on emergency core cooling sump performance in operating light water reactors
Knowledge base report on emergency core cooling sump performance in operating light water reactors
By K. Natesan
RELAP/MOD3 analysis of BETHSY test 6.9c
RELAP/MOD3 analysis of BETHSY test 6.9c
By G. R Kimber
Regulatory guide 1.82, (Task MS 203-4)
Regulatory guide 1.82, (Task MS 203-4)
By U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Safety aspects of the Yankee Rowe Nuclear Powerplant
By United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment.
An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2
An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2
By J. M. Rogers
Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE
Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE
By S. Belaïd
Compendium of ECCS research for realistic LOCA analysis
Compendium of ECCS research for realistic LOCA analysis
By U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research
Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants
Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants
By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force
Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown
Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown
By Sarah E. Colpo
Analysis of semiscale test S-LH-1 using RELAP5/MOD2
Analysis of semiscale test S-LH-1 using RELAP5/MOD2
By P. C. Hall
Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors
Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors
By B. Sheron
Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)
Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)
By F. Curca-Tivig
Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applications
Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applications
By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force
Transient response of Babcock & Wilcox-designed reactors
Transient response of Babcock & Wilcox-designed reactors
By U.S. Nuclear Regulatory Commission. B & W Reactor Transient Response Task Force