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  • Proceedings of the International Atomic Energy Agency specialists' meeting on subcritical crack growth : held at Freiburg, Federal Republic of Germany, May 13-15, 1981 / edited by W.H. Cullen ; sponsored by International Atomic Energy Agency, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research ; proceedings prepared by Materials Engineering Associates, Inc. under subcontract to ENSA, Inc.

    • Text
    • Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, VA : National Technical Information Service, 1983.
    • 1983
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 86-324Offsite

  • Proceedings of the Second CSNI Workshop on Ductile Fracture Test Methods : held at Paris, France, April 17-19, 1985 / edited by F.J. Loss ; sponsored by Organization for Economic Co-Operation and Development [and] U.S. Nuclear Regulatory Commission ; proceedings prepared by Materials Engineering Associates, Inc.

    • Text
    • [Washington, D.C.] : The Commission, 1988.
    • 1988

  • Experimental evaluation of residual stresses in a weld clad plate and clad test specimens / prepared by E.F. Rybicki, J.R. Shadley, A.S. Sandhu.

    • Text
    • Washington, DC : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986.
    • 1986

  • 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

  • Fracture toughness characterization of nuclear piping steels / prepared by A.L. Hiser.

    • 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], 1989.
    • 1989

  • 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

  • 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

  • Fatigue crack growth of part-through cracks in pressure vessel and piping steels [microform] : air environment results / prepared by W.H. Cullen, M.R. Jolles.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
    • 1988

  • Proceedings of the Third International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth [microform] : held at Moscow, USSR, May 14-17, 1990 / edited by W.H. Cullen ; sponsored by International Atomic Energy Agency, NPO Cniitmash, Central Research Institute for Technology of Machinery, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research ; proceedings prepared by Materials Engineering Associates, Inc. ... under contract to Argonne National Laboratory.

    • Text
    • Washington, D.C. : The Commission ; Springfield, VA : National Technical Information Service [distributor], 1990.
    • 1990

  • Accelerated irradiation test of Gundremmingen reactor vessel trepan material [microform] / prepared by J.R. Hawthorne.

    • 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

  • SANS investigation of low alloy steels in neutron irradiated, annealed, and reirradiated conditions [microform] / prepared by R. Kampmann ... [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

  • Fatigue strength of smooth and notched specimens of ASME SA 106-B steel in PWR environments / prepared by J.B. Terrell.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
    • 1988

  • Irradiation-anneal-reirradiation (IAR) studies of prototypic reactor vessel weldments / prepared by J.R. Hawthorne.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

  • Investigations of irradiation-anneal-reirradiation (IAR) properties trends of RPV welds : phase 2 final report / 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

  • Fracture evaluation of surface cracks embedded in reactor vessel cladding / prepared by D.E. McCabe.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

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

    • Text
    • Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, [1990]
    • 1990

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