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Books by U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch:

Books in the extended shelves:

• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Cold leg integrity evaluation, phase 1 : final report, July 1978 - September 1978 (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, Metallurgy & Materials Research Branch ;, 1979), also by R. J. Eiber and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Environmentally assisted cracking in light water reactors : critical issues and recommended research (The Commission :, 1982), also by W. J. Shack and Argonne National Laboratory. Materials Science Division (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Inspection of nuclear reactor welding by acoustic emission : final report November 1974 through November 1977 (Washington, D. C. : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, Metallurgy and Materials Research Branch, 1978., 1978), also by D. W. Prine, T. A. Mathieson, U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, and inc Gard (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Inspection of nuclear reactor welding by acoustic emission : progress report November 1977-November 1978 (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, Metallurgy and Materials Research Branch ; a Springfield, Va. :, 1979), also by D. W. Prine, T. A. Mathieson, and inc Gard (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Low cycle fatigue evaluation of primary piping materials in a BWR environment (San Jose, California : Boiling Water Reactor Systems Department, General Electric Company, 1977., 1977), also by D. A. Hale and General Electric Company. Boiling Water Reactor Systems Department (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Mechanistic aspects of stress-corrosion cracking of type 304 stainless steel in LWR systems (Washington, D. C. : U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, 1983., 1983), also by F. A. Nichols and Argonne National Laboratory (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: The octavia computer code : PWR reactor pressure vessel failure probabilities due to operationally caused pressure transients (The Commission, 1978), also by W. E. Vesely, F. F. Goldberg, E. K. Lynn, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Reactor primary coolant system pipe rupture study method for detection of sensitization in stainless steel (The Commission, 1965), also by W. L. Clarke and General Electric Company. Nuclear Energy Engineering Division (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Reactor primary coolant system pipe rupture study method for detection of sensitization in stainless steel : progress report no. 44, April - June 1978 (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1978., 1978), also by W. L. Clarke and General Electric Company (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Reactor primary coolant system pipe rupture study method for detection of sensitization in stainless steel : progress report no. 45, July - September 1978 (U.S. Nuclear Regulatory Commission, 1979), also by W. L. Clarke and General Electric Company (page images at HathiTrust)
• U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch: Reactor primary coolant system pipe rupture study method for detection of sensitization in stainless steel : progress report no. 46, October - December 1978 (U.S. Nuclear Regulatory Commission, 1979), also by W. L. Clarke and General Electric Company (page images at HathiTrust)

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