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Knowledge base for the effect of debris on pressurized water reactor emergency core cooling sump performance [electronic resource] / prepared by D.V. Rao, principal investigator ... [et al.] NUREG/CR-6808 LA-UR-03-0880

Knowledge base for the effect of debris on pressurized water reactor emergency core cooling sump performance [electronic resource] / prepared by D.V. Rao, principal investigator ... [et al.] NUREG/CR-6808 LA-UR-03-0880
Microform図書
2003<YCA-Y 3.N 88:25/6808>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems

GSI-191 [microform] : thermal-hydraulic response of PWR reactor coolant system and containments to selected accident sequences / prepared by D.V. Rao, K.W. Ross, S.G. Ashbaugh

GSI-191 [microform] : thermal-hydraulic response of PWR reactor coolant system and containments to selected accident sequences / prepared by D.V. Rao, K.W. Ross, S.G. Ashbaugh
Microform図書
2002<YCA-Y 3.N 88:25/6770>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems -- United States

GSI-191 [microform] : the impact of debris induced loss of ECCS recirculation on PWR core damage frequency / prepared by J.L. Darby ... [et al.]

GSI-191 [microform] : the impact of debris induced loss of ECCS recirculation on PWR core damage frequency / prepared by J.L. Darby ... [et al.]
Microform図書
2002<YCA-Y 3.N 88:25/6771>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems -- United States

GSI-191 [microform] : separate-effects characterization of debris transport in water / prepared by D.V. Rao ... [et al.]

GSI-191 [microform] : separate-effects characterization of debris transport in water / prepared by D.V. Rao ... [et al.]
Microform図書
2002<YCA-Y 3.N 88:25/6772>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems -- United States

Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions [microform] : phase I final report / prepared by S. Majumdar, W. Shack

Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions [microform] : phase I final report / prepared by S. Majumdar, W. Shack
Microform図書
2003<YCA-Y 3.N 88:25/6792>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems -- Reliability Pressurized wa...

RELAP/MOD3 analysis of BETHSY test 6.9c [microform] : loss of RHRS, SG manway open / prepared by G.R. Kimber, M.A. George (International agreement report ; NUREG/IA-0187)

RELAP/MOD3 analysis of BETHSY test 6.9c [microform] : loss of RHRS, SG manway open / prepared by G.R. Kimber, M.A. George (International agreement report ; NUREG/IA-0187)
Microform図書
2000<YCA-Y 3.N 88:53/0187>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems -- Testing

Consequences of the loss of the residual heat removal systems in pressurized water reactors [microform] / prepared by L.W. Ward, W. Arcieri, C. Heath

Consequences of the loss of the residual heat removal systems in pressurized water reactors [microform] / prepared by L.W. Ward, W. Arcieri, C. Heath
Microform図書
1992<YCA-Y 3.N 88:25/5820>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems

Draft regulatory guide DG-1107 [microform] : water sources for long-term recirculation cooling following a loss-of-coolant accident : (proposed revision 3 to Regulatory Guide 1.82)

Draft regulatory guide DG-1107 [microform] : water sources for long-term recirculation cooling following a loss-of-coolant accident : (proposed revision 3 to Regulatory Guide 1.82)
Microform図書
2003<YCA-Y 3.N 88:6-3/1107>
National Diet Library
  • Subject Heading...ty regulations Pressurized water reactors -- Emergency core cooling systems -- Standards -- United States

An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2 [microform] / prepared by J.M. Rogers (International agreement report ; NUREG/IA-0052)

An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2 [microform] / prepared by J.M. Rogers (International agreement report ; NUREG/IA-0052)
Microform図書
1992<YCA-Y 3.N 88:53/0052>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems -- Testing

Analysis of semiscale test S-LH-1 using RELAP5/MOD2 [microform] prepared by P.C. Hall, D.R. Bull (International agreement report ; NUREG/IA-0064)

Analysis of semiscale test S-LH-1 using RELAP5/MOD2 [microform] prepared by P.C. Hall, D.R. Bull (International agreement report ; NUREG/IA-0064)
Microform図書
1992<YCA-Y 3.N 88:53/0064>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems -- Testing

Reliability study [microform]

Reliability study [microform]
Microform図書
1998<YCA-Y 3.N 88:25/5500/V.1>
National Diet Library
  • Subject Heading... -- Evaluation Pressurized water reactors -- Emergency core cooling systems -- United States -- Reliabili...

Safety aspects of the Yankee Rowe Nuclear Powerplant : oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, One Hundred Second Congress, first session ... hearing held in Washington, DC, August 1, 1991

Safety aspects of the Yankee Rowe Nuclear Powerplant : oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, One Hundred Second Congress, first session ... hearing held in Washington, DC, August 1, 1991
Microform図書
1992<YCA-Y 4.In 8/14:102-20>
National Diet Library
  • Subject Heading...isk assessment Pressurized water reactors -- Emergency core cooling systems

TRAC-PF1 analyses of potential pressurized-thermal-shock transients at Calvert Cliffs/Unit 1 : a combustion engineering PWR / Gregory D. Spriggs, Jan E. Koenig, Russell C. Smith

TRAC-PF1 analyses of potential pressurized-thermal-shock transients at Calvert Cliffs/Unit 1 : a combustion engineering PWR / Gregory D. Spriggs, Jan E. Koenig, Russell C. Smith
Microform図書
1985<YCA-Y 3.N 88:25/4109>
National Diet Library
  • Subject HeadingPressurized water reactors -- Emergency core cooling systems Atomic power-plants -- Maryla...

Analysis of risk reduction measures applied to shared essential service water systems at multi-unit sites / prepared by P. Kohut, Z. Musicki, R. Fitzpatrick

Analysis of risk reduction measures applied to shared essential service water systems at multi-unit sites / prepared by P. Kohut, Z. Musicki, R. Fitzpatrick
Microform図書
1991<YCA-Y 3.N 88:25/5526>
National Diet Library
  • Subject Heading... Deterioration Pressurized water reactors -- Emergency core cooling systems -- Cost of operation Nuclear ...

Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor : case study / prepared by W.R. Cramond, D.M. Ericson, Jr., G.A. Sanders

Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor : case study / prepared by W.R. Cramond, D.M. Ericson, Jr., G.A. Sanders
Microform図書
1987<YCA-Y 3.N 88:25/4710>
National Diet Library
  • Subject Heading...ical heat flux Pressurized water reactors -- Emergency core cooling systems Nuclear power plants -- Flori...

Regulatory guide 1.82, (Task MS 203-4) : water sources for long-term recirculation cooling following a loss-of-coolant accident Revision 1, Nov. 1985

Regulatory guide 1.82, (Task MS 203-4) : water sources for long-term recirculation cooling following a loss-of-coolant accident Revision 1, Nov. 1985
Microform図書
1985<YCA-Y 3.N 88:6-2/1.82/rev.1>
National Diet Library
  • Subject Heading... United States Pressurized water reactors -- Emergency core cooling systems -- Standards -- United States

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