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検索結果 7 件

Assessment of pressurized water reactor primary system leaks [microform] / prepared by V.N. Shah ... [et al.]

Assessment of pressurized water reactor primary system leaks [microform] / prepared by V.N. Shah ... [et al.]
マイクロ図書
1998<YCA-Y 3.N 88:25/6582>
国立国会図書館
  • 件名Pressurized water reactors -- Reliability Nuclear reactors -- Reliabili...

Incorporating aging effects into probabilistic risk assessment [microform] : a feasibility study utilizing reliability physics models / prepared by C.L. Smith ... [et al.]

Incorporating aging effects into probabilistic risk assessment [microform] : a feasibility study utilizing reliability physics models / prepared by C.L. Smith ... [et al.]
マイクロ図書
2001<YCA-Y 3.N 88:25/5632>
国立国会図書館
  • 件名Pressurized water reactors -- Reliability Nuclear power plants -- Relia...

Resolution of the direct containment heating issue for combustion engineering plants and Babcock & Wilcox plants [microform] / prepared by M.M. Pilch ... [et al.]

Resolution of the direct containment heating issue for combustion engineering plants and Babcock & Wilcox plants [microform] / prepared by M.M. Pilch ... [et al.]
マイクロ図書
1998<YCA-Y 3.N 88:25/6475>
国立国会図書館
  • 件名Nuclear reactors -- Containment -- Reliability Pressurized water reactors -- Reliability

Aging assessment of component cooling water systems in pressurized water reactors microform / prepared by R. Lofaro ... [et al.]

Aging assessment of component cooling water systems in pressurized water reactors microform / prepared by R. Lofaro ... [et al.]
マイクロ図書
1992<YCA-Y 3.N 88:25/5693>
国立国会図書館
  • 件名Pressurized water reactors -- Reliability Pressurized water reactors --...

Aging assessment of the Westinghouse PWR control rod drive system / prepared by W. Gunther, K. Sullivan

Aging assessment of the Westinghouse PWR control rod drive system / prepared by W. Gunther, K. Sullivan
マイクロ図書
1991<YCA-Y 3.N 88:25/5555>
国立国会図書館
  • 件名...-- Reliability Pressurized water reactors -- Reliability Nuclear fuel rods -- Evaluati...

Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment / prepared by T.L. Dickson, R.D. Cheverton, and D.K. Shum

Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment / prepared by T.L. Dickson, R.D. Cheverton, and D.K. Shum
マイクロ図書
1990<YCA-Y 3.N 88:25/5473>
国立国会図書館
  • 件名...matical models Pressurized water reactors -- Reliability -- Mathematical models Fractu...

The In-plant reliability data base for nuclear plant components : interim report : the valve component / Raymond J. Borkowski ... [et al.] ; prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Risk Analysis under interagency agreement DOE 40-550-75 ; prepared by the Oak Ridge National Laboratory for the U.S. Department of Energy

The In-plant reliability data base for nuclear plant components : interim report : the valve component / Raymond J. Borkowski ... [et al.] ; prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Risk Analysis under interagency agreement DOE 40-550-75 ; prepared by the Oak Ridge National Laboratory for the U.S. Department of Energy
マイクロ図書
1983<YCA-Y 3.N 88:25/3154>
国立国会図書館
  • 件名Pressurized water reactors -- Reliability Nuclear facilities -- United ...

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