Research Catalog

  • Quality control in fabrication of nuclear pressure vessels [by] Robert D. Wylie and Warren J. McGonnagle.

    • Text
    • New York, Rowman and Littlefield [c1964]
    • 1964
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 73-1577Offsite
    Not available - Please for assistance.
  • Rules for construction of nuclear power plant components. Division 2: Code for concrete reactor vessels and containments. 1975 ed.

    • Text
    • New York, American Society of Mechanical Engineers, 1975.
    • 1975
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 76-54Offsite
    Not available - Please for assistance.
  • Periodic inspection of pressurized components : a conference / arranged by the Pressure Vessels Section of the Applied Mechanics Group and the Nuclear Energy Group of the Institution of Mechanical Engineers, London, 4-6 June 1974.

    • Text
    • London ; New York : Mechanical Engineering Publications for the Institution of Mechanical Engineers, 1975.
    • 1975
    • 1 Item
    FormatCall NumberItem Location
    Text JSG 76-129Offsite
    Not available - Please for assistance.
  • Lumped-parameter analysis for shear failure in the end slab of cylindrical prestressed concrete pressure vessels, by R. Higashionna and W. C. Schnobrich.

    • Text
    • Urbana, University of Illinois, 1970.
    • 1970
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 76-209Offsite
    Not available - Please for assistance.
  • The design and construction of prestressed concrete reactor vessels / [FIP Commission on Concrete Pressure and Storage Vessels].

    • Text
    • Slough [Eng.] : FIP, 1978.
    • 1978
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 80-185Offsite
    Not available - Please for assistance.
  • Nuclear heat transport / M. M. El-Wakil.

    • Text
    • La Grange Park, Ill. : American Nuclear Society, c1978.
    • 1978
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 80-866Offsite
    Not available - Please for assistance.
  • Trends in reactor pressure vessel and circuit development / edited by R.W. Nichols.

    • Text
    • London : Applied Science Publishers, c1980.
    • 1980
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 81-1154Offsite
    Not available - Please for assistance.
  • Stress indices and stress intensification factors of pressure vessel and piping components : presented at the joint conference of the Pressure Vessels and Piping, Materials, Nuclear Engineering, Solar Energy Divisions, Denver, Colorado, June 21-25, 1981 / sponsored by the Pressure Vessels and Piping Division, ASME ; edited by R.W. Schneider, E.C. Rodabaugh.

    • Text
    • New York, N.Y. (345 E. 47th St., New York 10017) : American Society of Mechanical Engineers, c1981.
    • 1981
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 82-320Offsite
    Not available - Please for assistance.
  • Plate inspection programme, PISC : report / from the Plate Inspection Steering Committee (PISC) on the ultrasonic examination of three test plates using the "PISC" procedure based upon the ASME XI code.

    • Text
    • Paris (France): Nuclear Energy Agency, Committee on the Safety of Nuclear Installations, Organisation for Economic Co-operation and Development, 1979.
    • 1979
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 82-407Offsite
    Not available - Please for assistance.
  • Ultrasonic inspection of heavy section steel components : the PISC II final report / edited by R.W. Nichols and S. Crutzen.

    • Text
    • London ; New York : Elsevier Applied Science, c1988.
    • 1988
    • 1 Item
    FormatCall NumberItem Location
    Text JSD 89-312Offsite
    Not available - Please for assistance.
  • Radiation embrittlement of nuclear reactor pressure vessel steels : an international review (fourth volume) / Lendell E. Steele, editor.

    • Text
    • Philadelphia, PA : ASTM, c1993.
    • 1993
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 93-464Offsite
    Not available - Please for assistance.
  • Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension / William R. Corwin, Fahmy M. Haggag, and William L. Server, editors.

    • Text
    • Philadelphia, PA : ASTM, c1993.
    • 1993
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 94-411Offsite
    Not available - Please for assistance.
  • Three Mile Island reactor pressure vessel investigation project : achievements and significant results : proceedings of an open forum sponsored by the OECD Nuclear Energy Agency and the United States Nuclear Regulatory Commission, Boston (USA), 20-22 October 1993.

    • Text
    • Paris : Organisation for Economic Co-operation and Development ; Washington, D.C. : OECD Publications and Information Centre [distributor], c1994.
    • 1994
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 94-2102Offsite
    Not available - Please for assistance.
  • Effects of radiation on materials : 17th international symposium / David S. Gelles ... [et al.], editors.

    • Text
    • West Conshohocken, PA : ASTM, c1996.
    • 1996
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 96-1244Offsite
    Not available - Please for assistance.
  • Contenitore metallico per impianti nucleari.

    • Text
    • Roma, 1964.
    • 1964
    • 1 Item
    FormatCall NumberItem Location
    Text PAWF (Cesari, F. Contenitore metallico per impianti nucleari) 1964Offsite
    Not available - Please for assistance.
  • Analysis of reactor vessel radiation effects surveillance programs. Prepared by L. E. Steele and C. Z. Serpan, Jr.

    • Text
    • Philadelphia, American Society for Testing and Materials [1970]
    • 1970
    • 2 Items
    FormatCall NumberItem Location
    Text VEE (American Society for Testing Materials. Special technical publication. no. 481)Offsite
    Not available - Please for assistance.
    FormatCall NumberItem Location
    Text VEE (American Society for Testing Materials. Special technical publication. no. 481) no. 481 Offsite
    Not available - Please for assistance.
  • Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology.

    • Text
    • Washington, D.C. : Materials Engineering Branch, Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission, [distributor
    • unknown-present
  • LWR pressure vessel surveillance dosimetry improvement program / Hanford Engineering Development Laboratory ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

    • Text
    • Washington, DC : The Division : NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission, [distributor
    • unknown-present
  • Heavy-section steel technology program / prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.

    • Text
    • Washington, D.C. : The Office : Available from Supt. of Docs., U.S. G.P.O. ; Springfield, Va. : National Technical Information Service, [distributor
    • unknown-present
  • Heavy-section steel technology program [microform] / prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research ; prepared by the Oak Ridge National Laboratory, Engineering Technology Division.

    • Text
    • Washington, D.C. : The Office : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service
    • unknown-present
  • Compilation of contract research for the Materials Branch, Division of Engineering Safety [microform].

    • Text
    • Washington, D.C. : Materials Branch, Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission, [distributor], -1987.
    • 198-1986
  • Compilation of contract research for the Materials Engineering Branch, Division of Engineering [microform].

    • Text
    • Washington, D.C. : Materials Engineering Branch, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
    • 1987-present
  • Heavy-section steel irradiation program [microform] / prepared by Oak Ridge National Laboratory ; prepared for the Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

    • Text
    • Washington, DC : The Division : Supt. of Docs., U.S. G.P.O. [distributor], 1990-
    • 1990-present
  • Heavy-section steel irradiation program [microform] / prepared by Oak Ridge National Laboratory ; prepared for the Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

    • Text
    • Washington, DC : The Division : Supt. of Docs., U.S. G.P.O. [distributor], 1990-
    • 1990-present
  • An overview of the low-upper-shelf toughness safety margin issue / prepared by J.G. Merkle.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1990.
    • 1990
  • Analysis of the VENUS-3 experiments / prepared by R.E. Maerker.

    • Text
    • Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Extension and extrapolation of J-R curves and their application to the low upper shelf toughness issue / prepared by J.A. Joyce, E.M. Hackett.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
    • 1991
  • Post-irradiation fracture toughness characterization of four lab-melt plates / prepared by A.L. Hiser.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Detection and characterization of indications in segments of reactor pressure vessels / prepared by K.V. Cook, R.A. Cunningham, Jr., R.W. McClung.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commisson, 1989.
    • 1989
  • A finite element analysis of a reactor pressure vessel during a severe accident / prepared by R.S. Chambers.

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Neutron exposure parameters for the metallurgical test specimens in the sixth heavy-section steel irradiation series / prepared by L.F. Miller ... [et al.].

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990
  • 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.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990
  • Core-concrete interactions using molten steel with zirconium on a basaltic basemat : the SURC-4 experiment / prepared by E.R. Copus ... [et al.].

    • Text
    • Washington, D.C. : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Universal treatment of plumes and stresses for pressurized thermal shock evaluations [microform] / prepared by T.G. Theofanous, S. Angelini, H. Yan.

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
    • 1992
  • Experimental and analytical investigation of the shallow-flaw effect in reactor pressure vessels [microform] / prepared by T.J. Theiss, D.K. Shum, S.T. Rolfe.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
    • 1992
  • Post-irradiation fracture toughness characterization of four lab-melt plates / prepared by A.L. Hiser.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Preliminary structural evaluation of Trojan RCL subject to postulated RPV support failure / prepared by S.C. Lu.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990
  • Influence of fluence rate on radiation-induced mechanical property changes in reactor pressure vessel steels : final report on exploratory experiments / prepared by J.R. Hawthorne, A.L. Hiser.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990
  • PR-EDB, power reactor embrittlement data base, version 1 : program description / prepared by F.W. Stallmann, F.B.K. Kam, B.J. Taylor.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990-
    • 1990-present
  • Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure" / C.C. Graves.

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990
  • Mission survey for the Pressure Vessel Research User's Facility (PVRUF) / prepared by W.E. Pennell, C.E. Pugh.

    • Text
    • Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Warm prestress modeling : comparison of models and experimental results / prepared by R.B. Stonesifer, E.F. Rybicki, D.E. McCabe.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Development of equipment parameter tolerances for the ultrasonic inspection of steel components [microform] / prepared by E.R. Green ... [et al.].

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992-
    • 1992-present
  • 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.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989
  • Crack propagation in high strain regions of Sequoyah containment [microform] / prepared by L. Greimann, F. Fanous, D. Bluhm.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
    • 1993
  • Analysis of thermal mixing and boron dilution in a PWR [microform] / prepared by J.G. Sun, W.T. Sha.

    • Text
    • Washington, DC : Division of Safety Programs, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
    • 1993
  • Generic analyses for evaluation of low Charpy upper-shelf energy effects on safety margins against fracture of reactor pressure vessels [microform] / prepared by T.L. Dickson.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
    • 1993
  • Initial results of the influence of biaxial loading on fracture toughness [microform] / prepared by T.J. Theiss ... [et al.].

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
    • 1993
  • CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE) [microform] / prepared by B.R. Bass ... [et al.].

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1993.
    • 1993
  • Statistically based reevaluation of PISC-II round robin test data [microform] / prepared by P.G. Heasler, T.T. Taylor, S.R. Doctor.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1993.
    • 1993

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