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Round robin posttest analysis of a steel containment vessel model [microform] / prepared by V.K. Luk, E.W. Klamerus

Round robin posttest analysis of a steel containment vessel model [microform] / prepared by V.K. Luk, E.W. Klamerus
マイクロ図書
2000<YCA-Y 3.N 88:25/5678>
国立国会図書館

Characterization of flaws in U.S. reactor pressure vessels [microform] / prepared by G.J. Schuster, S.R. Doctor, P.G. Heasler

Characterization of flaws in U.S. reactor pressure vessels [microform] / prepared by G.J. Schuster, S.R. Doctor, P.G. Heasler
マイクロ図書
1998<YCA-Y 3.N 88:25/6471/V.1>
国立国会図書館

Pretest round robin analysis of a prestressed concrete containment vessel model [microform] / prepared by V.K. Luk

Pretest round robin analysis of a prestressed concrete containment vessel model [microform] / prepared by V.K. Luk
マイクロ図書
2000<YCA-Y 3.N 88:25/6678>
国立国会図書館

RR-PRODIGAL [microform] : a model for estimating the probabilities of defects in reactor pressure vessel welds / prepared by O.J.V. Chapman, F.A. Simonen

RR-PRODIGAL [microform] : a model for estimating the probabilities of defects in reactor pressure vessel welds / prepared by O.J.V. Chapman, F.A. Simonen
マイクロ図書
1998<YCA-Y 3.N 88:25/5505>
国立国会図書館

Statistically based reevaluation of PISC-II round robin test data microform / prepared by P.G. Heasler, T.T. Taylor, S.R. Doctor

Statistically based reevaluation of PISC-II round robin test data microform / prepared by P.G. Heasler, T.T. Taylor, S.R. Doctor
マイクロ図書
1993<YCA-Y 3.N 88:25/5410>
国立国会図書館

Experimental results from pressure testing a 1:6-scale nuclear power plant containment [microform] / prepared by D.S. Horschel

Experimental results from pressure testing a 1:6-scale nuclear power plant containment [microform] / prepared by D.S. Horschel
マイクロ図書
1992<YCA-Y 3.N 88:25/5121>
国立国会図書館

Experimental results of tests to investigate flaw behavior of mechanically loaded stainless steel clad plates [microform] / prepared by S.K. Iskander ... [et al.]

Experimental results of tests to investigate flaw behavior of mechanically loaded stainless steel clad plates [microform] / prepared by S.K. Iskander ... [et al.]
マイクロ図書
1992<YCA-Y 3.N 88:25/5785>
国立国会図書館

Analysis of H.B. Robinson PWR vessel fluence for cycle 10 utilizing partial length shield assemblies / prepared by M.L. Williams, R.L. Childs, M. Asgari

Analysis of H.B. Robinson PWR vessel fluence for cycle 10 utilizing partial length shield assemblies / prepared by M.L. Williams, R.L. Childs, M. Asgari
マイクロ図書
1990<YCA-Y 3.N 88:25/5530>
国立国会図書館

Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels : progress report / P.H. Hutton, R.J. Kurtz

Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels : progress report / P.H. Hutton, R.J. Kurtz
マイクロ図書
1985<YCA-Y 3.N 88:25/4300/v.4,no.1>
国立国会図書館

Viscoplastic stress-strain characterization of A533 grade B class 1 steel / prepared by J.H. Giovanola, R.W. Klopp

Viscoplastic stress-strain characterization of A533 grade B class 1 steel / prepared by J.H. Giovanola, R.W. Klopp
マイクロ図書
1989<YCA-Y 3.N 88:25/5226>
国立国会図書館

Structural integrity of water reactor pressure boundary components / edited by F.J. Loss

Structural integrity of water reactor pressure boundary components / edited by F.J. Loss
マイクロ図書
1984<YCA-Y 3.N 88:25/3228/v.5>
国立国会図書館

Historical summary of the Heavy-Section Steel Technology Program and some related activities in light-water reactor pressure vessel safety research / G.D. Whitman ; prepared by the Oak Ridge National Laboratory

Historical summary of the Heavy-Section Steel Technology Program and some related activities in light-water reactor pressure vessel safety research / G.D. Whitman ; prepared by the Oak Ridge National Laboratory
マイクロ図書
1986<YCA-Y 3.N 88:25/4489>
国立国会図書館

Heavy-Section Steel Technology Program : five-year plan, FY 1983-1987 ; prepared by the staff of the Heavy-Section Steel Technology Program, Oak Ridge National Laboratory ; prepared by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40-552-75 ; prepared by the Oak Ridge National Laboratory

Heavy-Section Steel Technology Program : five-year plan, FY 1983-1987 ; prepared by the staff of the Heavy-Section Steel Technology Program, Oak Ridge National Laboratory ; prepared by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40-552-75 ; prepared by the Oak Ridge National Laboratory
マイクロ図書
1984<YCA-Y 3.N 88:25/3595>
国立国会図書館

Status of USA nuclear reactor pressure vessel surveillance for radiation effects / sponsored by the Metal Properties Council ; L.E. Steele, editor. (ASTM special technical publication ; 784)

Status of USA nuclear reactor pressure vessel surveillance for radiation effects / sponsored by the Metal Properties Council ; L.E. Steele, editor. (ASTM special technical publication ; 784)
紙図書
American Society for Testing and Materialsc1983.<NG41-96>
国立国会図書館
  • 件名Nuclear pressure vessels -- Testing. Steel -- Effect of radiation ...

Advances in non-destructive examination for structural integrity / edited by R.W. Nichols.

Advances in non-destructive examination for structural integrity / edited by R.W. Nichols.
紙図書
Applied Sciencec1982.<NG41-158>
国立国会図書館全国の図書館

First International Conference on NDE in Relation to Structural Integrity for Nuclear and Pressurised Components 1 2

First International Conference on NDE in Relation to Structural Integrity for Nuclear and Pressurised Components 1 2
紙図書
[edited on behalf of the Technical Organising Committee by Michel Bièth and Jean Louis Monjaret ; organised by: IAM, European Commission Joint Research Centre]Woodhead1999
全国の図書館

More precise investigations of the mechanical characteristics, in the heat affected zone, of welded seams on thick-walled forged pieces of fine-grained construction steel 22 NiMoCr 37 / Egon Klausnitzer (NRC-TR ; 2) (Translation series)

More precise investigations of the mechanical characteristics, in the heat affected zone, of welded seams on thick-walled forged pieces of fine-grained construction steel 22 NiMoCr 37 / Egon Klausnitzer (NRC-TR ; 2) (Translation series)
マイクロ図書
1976<YCA-Y 3.N 88:39/2>
国立国会図書館

Analysis of reactor vessel radiation effects surveillance programs. Prepared by L. E. Steele and C. Z. Serpan, Jr. (ASTM Special technical publication 481)

Analysis of reactor vessel radiation effects surveillance programs. Prepared by L. E. Steele and C. Z. Serpan, Jr. (ASTM Special technical publication 481)
紙図書
American Society for Testing and Materials[1970]<NG41-31>
国立国会図書館全国の図書館
  • 件名Nuclear pressure vessels -- Testing. Steel -- Effect of radiation ...

NDE in the nuclear and pressure vessel industries : proceedings of the 14th International Conference on NDE in the Nuclear and Pressure Vessel Industries, 24-26 September 1996, Stockholm, Sweden

NDE in the nuclear and pressure vessel industries : proceedings of the 14th International Conference on NDE in the Nuclear and Pressure Vessel Industries, 24-26 September 1996, Stockholm, Sweden
紙図書
sponsored by ASM International ... [et al.]ASM Internationalc1997
全国の図書館

Status of USA nuclear reactor pressure vessel surveillance for radiation effects

Status of USA nuclear reactor pressure vessel surveillance for radiation effects
紙図書
sponsored by the Metal Properties Council ; L.E. Steele, editorAmerican Society for Testing and Materialsc1983
全国の図書館
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