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Books by Materials Engineering Associates:

Books in the extended shelves:

• Materials Engineering Associates: Alternative procedures for J-R curve determination (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), also by A. L. Hiser, F. J. Loss, Inc ENSA, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Behavior of subcritical and slow-stable crack growth following a post-irradiation thermal anneal cycle (Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984., 1984), also by W. H. Cullen, A. L. Hiser, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Effects of temperature on fatigue crack growth of a 508-2 steel in LWR environment (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), also by W. H. Cullen, M. Kemppainen, Kari Torronen, Inc ENSA, Valtion teknillinen tutkimuslaitos (Finland), and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Fatigue crack growth rates in pressure vessel and piping steels in LWR environments : final report (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by W. H. Cullen and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Fatigue crack growth rates of A 508-2 steel in pressurized, high temperature water (The Commission, 1983), also by W. H. Cullen, Inc ENSA, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Fracture evaluation of surface cracks embedded in reactor vessel cladding : unirradiated bend specimen results (Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by D. E. McCabe and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering (page images at HathiTrust)
• Materials Engineering Associates: J-R curve characterization of irradiated low upper shelf welds (Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984., 1984), also by A. L. Hiser, B. H. Menke, F. J. Loss, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Light water reactor pressure vessel surveillance dosimetry improvement program (The Division, 1984), also by J. R. Hawthorne, A. L. Hiser, B. H. Menke, Inc ENSA, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Plan for experimental characterization of clad vessel steel after irradiation (Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), also by D. E. McCabe and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety (page images at HathiTrust)
• Materials Engineering Associates: Proceedings of the Second International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth, held at Sendai, Japan, May 15-17, 1985 (U.S Nuclear Regulatory Commission :, 1986), also by Japan) International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth (2nd : (1985 : Sendai, W. H. Cullen, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Tōhoku Daigaku. Zairyō Kyōdo Kenkyū Shisetsu, and International Atomic Energy Agency (page images at HathiTrust)
• Materials Engineering Associates: Significance of nickel and copper content to radiation sensitivity and postirradiation heat treatment recovery of reactor vessel steels (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1982., 1982), also by J. R. Hawthorne and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Structural integrity of light water reactor pressure boundary components : four-year plan 1984-1988 (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1984., 1984), also by U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Structural integrity of water reactor pressure boundary components (Washington, D. C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983-., 1984), also by F. J. Loss, Inc ENSA, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Structural integrity of water reactor pressure boundary components : annual report for 1982 (Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983., 1983), also by U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Structural integrity of water reactor pressure boundary components : annual report for 1984 (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1985), also by F. J. Loss and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Structural integrity of water reactro pressure boundary components : annual report for 1986 (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by F. J. Loss and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: Surface spectroscopy of pressure vessel steel fatigue fracture surface films formed in PWR environments (Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by H. E. Hanninen, W. H. Cullen, M. Vulli, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering (page images at HathiTrust)
• Materials Engineering Associates: The Temperature dependence of fatigue crack growth rates of A 351 CF8A cast stainlss steel in LWR environment (Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984., 1984), also by W. H. Cullen, M. Kemppainen, Kari T©·orr©·onen, R. E. Taylor, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Materials Engineering Associates: A user's guide to the NRC's Piping Fracture Mechanics Data Base (PIFRAC) (Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by A. L. Hiser, G. M. Callahan, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering (page images at HathiTrust)

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