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検索結果 5 件

International comparative assessment study of pressurized thermal shock in reactor pressure vessels [microform] / prepared by B.R. Bass ... [et al.]

International comparative assessment study of pressurized thermal shock in reactor pressure vessels [microform] / prepared by B.R. Bass ... [et al.]
マイクロ図書
1999<YCA-Y 3.N 88:25/6651>
国立国会図書館
  • 件名Nuclear pressure vessels -- Cracking Fracture mechanics Thermal st...

Fatigue analysis of components for 60-year plant life [microform] / prepared by M.A. Khaleel ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Fatigue analysis of components for 60-year plant life [microform] / prepared by M.A. Khaleel ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
2000<YCA-Y 3.N 88:25/6674>
国立国会図書館
  • 件名Nuclear pressure vessels -- Cracking Nuclear reactors -- Materials...

Round-Robin analysis of the behavior of a 1:6-scale reinforced concrete containment model pressurized to failure microform : posttest evaluations / prepared by D.B. Clauss

Round-Robin analysis of the behavior of a 1:6-scale reinforced concrete containment model pressurized to failure microform : posttest evaluations / prepared by D.B. Clauss
マイクロ図書
1989<YCA-Y 3.N 88:25/5341>
国立国会図書館
  • 件名...ent -- Testing Nuclear pressure vessels -- Cracking High pressure (Science) -- Te...

Correlation of irradiation-induced transition temperature increases from Cv and Kjc/Kic data : final report / prepared by A.L. Hiser

Correlation of irradiation-induced transition temperature increases from Cv and Kjc/Kic data : final report / prepared by A.L. Hiser
マイクロ図書
1990<YCA-Y 3.N 88:25/5494>
国立国会図書館
  • 件名... United States Nuclear pressure vessels -- Cracking -- United States

A parametric study of PWR pressure vessel integrity during overcooling accidents, considering both 2-D and 3-D flaws / R.D. Cheverton, D.G. Ball ; prepared by the Oak Ridge National Laboratory ; Engineering Technology Division

A parametric study of PWR pressure vessel integrity during overcooling accidents, considering both 2-D and 3-D flaws / R.D. Cheverton, D.G. Ball ; prepared by the Oak Ridge National Laboratory ; Engineering Technology Division
マイクロ図書
1985<YCA-Y 3.N 88:25/4325>
国立国会図書館
  • 件名...g -- Accidents Nuclear pressure vessels -- Cracking Fracture mechanics -- Mathema...

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