The Online Books Page

Books by W. H. Cullen:

Books in the extended shelves:

• Cullen, W. H.: 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 A. L. Hiser, Materials Engineering Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Cullen, W. H.: 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 M. Kemppainen, Kari Torronen, Inc ENSA, Valtion teknillinen tutkimuslaitos (Finland), Materials Engineering Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Cullen, W. H.: Fatigue crack growth of A508 steel in high-temperature, pressurized reactor grade water (Washington, D. C. : Naval Research Laboratory : Available from U.S. Nuclear Regulatory Commission, 1979., 1979), also by F. L. Loss, H. E. Watson, K. J. Torronen, V. Provenzano, U.S. Nuclear Regulatory Commission, and Naval Research Laboratory (U.S.). Thermostructural Materials Branch (page images at HathiTrust)
• Cullen, W. H.: 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 U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology and Materials Engineering Associates (page images at HathiTrust)
• Cullen, W. H.: Fatigue crack growth rates of A 508-2 steel in pressurized, high temperature water (The Commission, 1983), also by Inc ENSA, Materials Engineering Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Cullen, W. H.: 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, Materials Engineering Associates, 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)
• Cullen, W. H.: A review of fatigue crack growth of pressure vessel and piping steels in high-temperature, pressurized reactor-grade water (Washington, D. C. : Naval Research Laboratory, 1980., 1980), also by Kari Torronen, Naval Research Laboratory (U.S.). Thermostructural Materials Branch, U.S. Nuclear Regulatory Commission, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Naval Research Laboratory (U.S.) (page images at HathiTrust)
• Cullen, W. H.: 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, M. Vulli, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and Materials Engineering Associates (page images at HathiTrust)
• Cullen, W. H.: 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 M. Kemppainen, Kari T©·orr©·onen, R. E. Taylor, Materials Engineering Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)

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