Bücher zum Thema „Plantar pressure“
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Wily violets & underground orchids: Revelations of a botanist. New York: Vintage, 1990.
Den vollen Inhalt der Quelle findenWily violets & underground orchids: Revelations of a botanist. New York: Morrow, 1989.
Den vollen Inhalt der Quelle findenEarth, Friends of the, Hrsg. Sizewell B: Under pressure. London: Friends of the Earth, 1986.
Den vollen Inhalt der Quelle findenJ, Elliot B., und U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering, Hrsg. Reactor pressure vessel status report. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1996.
Den vollen Inhalt der Quelle findenM, Hashemian H., Analysis and Measurement Services Corporation. und U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., Hrsg. Assessment of fiber optic pressure sensors. Washington, DC: U.S. Nuclear Regulatory Commission, 1995.
Den vollen Inhalt der Quelle finden1954-, Johnson Mary, Boone Steven, University of California, Los Angeles. Dept. of Chemistry and Biochemistry. und United States. National Aeronautics and Space Administration., Hrsg. High pressure cosmochemistry applied to major planetary interiors: Experimental studies : status report. Los Angeles, CA: Dept. of Chemistry and Biochemistry, University of California, 1985.
Den vollen Inhalt der Quelle findenSofronas, Anthony. Analytical Troubleshooting of Process Machinery and Pressure Vessels. New York: John Wiley & Sons, Ltd., 2006.
Den vollen Inhalt der Quelle findenAmerican Institute of Chemical Engineers. Center for Chemical Process Safety., Hrsg. Guidelines for pressure relief and effluent handling systems. New York, N.Y: The Institute, 1998.
Den vollen Inhalt der Quelle findenG, DeWall K., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Idaho National Engineering and Environmental Laboratory. und Lockheed Idaho Technologies Company, Hrsg. Results of pressure locking and thermal binding tests of gate valves. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.
Den vollen Inhalt der Quelle findenThomas, Kenneth Glyndwr. Research, engineering design and operation of a pressure hydrometallurgy facility for gold extraction. Toronto, Ont: Thomas, 1994.
Den vollen Inhalt der Quelle findenS, Dean R., Hennick A, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Operational Events Assessment. und Parameter Inc, Hrsg. Closeout of IE bulletin 86-02: Static "O" ring differential pressure switches. Washington, DC: Division of Operational Events Assessment, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989.
Den vollen Inhalt der Quelle findenWong, S. High pressure coolant injection (HPCI) system risk-based inspection guide for Browns Ferry Nuclear Power Station. Washington, DC: Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.
Den vollen Inhalt der Quelle findenT, Kisisel I., American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und ASME Pressure Vessels and Piping Conference (1999 : Boston, Massachusetts), Hrsg. Operations, applications, and components, 1999 : presented at the 1999 ASME Pressure Vessels and Piping Conference, Boston, Massachusetts, August 1-5, 1999. New York, N.Y: American Society of Mechanical Engineers, 1999.
Den vollen Inhalt der Quelle findenT, Kisisel I., Ezekoye L. I, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (2001 : Atlanta, Ga.), Hrsg. Operations, applications, and components, 2001: Presented at the 2001 ASME Pressure Vessels and Piping Conference, Atlanta, Georgia, July 23-26, 2001. New York, N.Y: American Society of Mechanical Engineers, 2001.
Den vollen Inhalt der Quelle findenSafety, American Institute of Chemical Engineers Center for Chemical Process. Guidelines for vapor cloud explosion, pressure vessel burst, BLEVE, and flash fire hazards. 2. Aufl. New York, NY: Wiley, 2010.
Den vollen Inhalt der Quelle findenC, Holston William, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., U.S. Nuclear Regulatory Commission. und Pressure Vessels and Piping Conference (2001 : Atlanta, Georgia), Hrsg. NRC/ASME Boiler and Pressure Vessel code, section XI, 2001 : presented at the 2001 ASME Pressure Vessels and Piping Conference, Atlanta, Georgia, July 23-26, 2001. New York, N.Y: American Society of Mechanical Engineers, 2001.
Den vollen Inhalt der Quelle findenN, Pangborn R., Narayanan T. V, Means K. H, Bond C. B, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., American Society of Mechanical Engineers. NDE Engineering Division. und Pressure Vessels and Piping Conference (1990 : Nashville, Tenn.), Hrsg. Damage assessment, reliability, and life prediction of power plant components: Presented at the 1990 Pressure Vessels and Piping Conference, Nashville, Tennessee, June 17-21, 1990. New York, N.Y: American Society of Mechanical Engineers, 1990.
Den vollen Inhalt der Quelle findenH, Bamford W., American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (1993 : Denver, Colo.), Hrsg. Service experience and life management: Nuclear, fossil, and petrochemical plants : presented at the 1993 Pressure Vessels and Piping Conference, Denver, Colorado, July 25-29, 1993. New York: American Society of Mechanical Engineers, 1993.
Den vollen Inhalt der Quelle findenW, Shier, U.S. Nuclear Regulatory Commission. Division of Systems Safety and Analysis. und Brookhaven National Laboratory, Hrsg. High pressure coolant injection system risk-based inspection guide for Hope Creek. Washington, DC: Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1992.
Den vollen Inhalt der Quelle findenD, Naus, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. und Oak Ridge National Laboratory, Hrsg. A survey of repair practices for nuclear power plant containment metallic pressure boundaries. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.
Den vollen Inhalt der Quelle findenKorth, G. E. Metallographic and hardness examinations of TMI-2 lower pressure vessel head samples. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.
Den vollen Inhalt der Quelle findenSofronas, Anthony. Analytical troubleshooting of process machinery and pressure vessels: Including real-world case studies. Hoboken, N.J: John Wiley & Sons, 2005.
Den vollen Inhalt der Quelle findenSofronas, Anthony. Analytical troubleshooting of process machinery and pressure vessels: Including real-world case studies. Hoboken, NJ: John Wiley & Sons, 2006.
Den vollen Inhalt der Quelle findenFouad, Fanous, Bluhm Delwyn, Ames Laboratory und U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., Hrsg. Crack propagation in high strain regions of Sequoyah containment. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.
Den vollen Inhalt der Quelle findenA, Dermenjian Artin, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (1996 : Montréal, Québec), Hrsg. Pressure vessels and piping design, analysis, and severe accidents: Presented at the 1996 ASME Pressure Vessels and Piping Conference, Montreal, Quebec, Canada, July 21-26, 1996. New York, N.Y: American Society of Mechanical Engineers, 1996.
Den vollen Inhalt der Quelle findenInternational, Conference on NDE in the Nuclear and Pressure Vessel Industries (13th 1995 Kyoto Japan). NDE in the nuclear and pressure vessel industries: Proceedings of the 13th International Conference on NDE in the Nuclear and Pressure Vessel Industries : 22-25 May 1995, Kyoto International Conference Hall, Kyoto, Japan. Materials Park, Ohio: ASM International, 1995.
Den vollen Inhalt der Quelle findenInternational Conference on NDE in the Nuclear and Pressure Vessel Industries (14th 1996 Stockholm, Sweden). NDE in the nuclear and pressure vessel industries: Proceedings of the 14th International Conference on NDE in the Nuclear and Pressure Vessel Industries, 24-26 September 1996, Stockholm, Sweden. Materials Park, OH: ASM International, 1997.
Den vollen Inhalt der Quelle findenK, Kasza, Franklin J, Argonne National Laboratory und U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Hrsg. Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.
Den vollen Inhalt der Quelle findenH, Bamford W., Cipolla R. C, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (1994 : Minneapolis, Minn.), Hrsg. Service experience and reliability improvement: Nuclear, fossil, and petrochemical plants : presented at the 1994 Pressure Vessels and Piping Conference, Minneapolis, Minnesota, June 19-23, 1994. New York: American Society of Mechanical Engineers, 1994.
Den vollen Inhalt der Quelle findenK, Kasza, Franklin J, Argonne National Laboratory und U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Hrsg. Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.
Den vollen Inhalt der Quelle findenOesterle, R. G. Design provisions for tangential shear in containment walls. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
Den vollen Inhalt der Quelle findenK, Kasza, Franklin J, Argonne National Laboratory und U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Hrsg. Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.
Den vollen Inhalt der Quelle findenSikora, Richard A., Johan Desaeger und Leendert Molendijk, Hrsg. Integrated nematode management: state-of-the-art and visions for the future. Wallingford: CABI, 2021. http://dx.doi.org/10.1079/9781789247541.0000.
Der volle Inhalt der QuelleBoilers, ASME Boiler and Pressure Vessel Committee Subcommittee on Heating. 2007 ASME boiler & pressure vessel code: An international code : Materials. New York, N.Y: American Society of Mechanical Engineers, 2007.
Den vollen Inhalt der Quelle findenD, Rodery Clay, Takagi Yoshio, Miura Naoki, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (2004 : San Diego, Calif.), Hrsg. Fitness for service, life extension, remediation, repair, and erosion/corrosion issues for pressure vessels and components--2004: Presented at the 2004 ASME/JSME Pressure Vessels and Piping Conference : San Diego, California, USA, July 25-29, 2004. New York: American Society of Mechanical Engineers, 2004.
Den vollen Inhalt der Quelle findenU.S. Nuclear Regulatory Commission. Division of Systems Safety and Analysis. und Brookhaven National Laboratory, Hrsg. High pressure coolant injection system risk-based inspection guide for Hatch Nuclear Power Station. Washington, DC: Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.
Den vollen Inhalt der Quelle findenJ, Shack W., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. und Argonne National Laboratory, Hrsg. Environmental effects on fatigue crack initiation in piping and pressure vessel steels. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.
Den vollen Inhalt der Quelle findenChristie, Robert F. Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system. [Washington, D.C.?: Tennessee Valley Authority, 1985.
Den vollen Inhalt der Quelle findenChŏng, Yong-mu. Wŏnjŏn paegwan kyetʻong ŭi chŏnjagi chʻoŭmpʻa kŏmsa, kamsi kisul kaebal =: Development of electromagnetic ultrasonic testing, monitoring technology for piping in nuclear power plant. [Seoul]: Chisik Kyŏngjebu, 2008.
Den vollen Inhalt der Quelle findenWesley, D. A. Screening methods for developing internal pressure capacities for components in systems interfacing with nuclear power plant reactor coolant systems. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
Den vollen Inhalt der Quelle findenChi-Wen, Lin, Wang C. Y, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (1994 : Minneapolis, Minn.), Hrsg. Natural hazard phenomena and mitigation: Presented at the 1994 Pressure Vessels and Piping Conference, Minneapolis, Minnesota, June 19-23, 1994. New York, N.Y: American Society of Mechanical Engineers, 1994.
Den vollen Inhalt der Quelle findenASME Pressure Vessels and Piping Conference--JSME Co-Sponsorship (1989 Honolulu, Hawaii). Design and analysis of piping and components, 1989: Presented at the 1989 ASME Pressure Vessels and Piping Conference - JSME Co-Sponsorship, Honolulu, Hawaii, July 23-27, 1989. Herausgegeben von Truong Q. N, Goodling Evans C, Balaschak J. J, Widera G. E. O und American Society of Mechanical Engineers. Pressure Vessels and Piping Division. New York, N.Y. (345 E. 47th St., New York 10017): American Society of Mechanical Engineers, 1989.
Den vollen Inhalt der Quelle findenChŏng, Yong-mu. Wŏnjŏn paegwan kyetʻong ŭi chŏnjagi chʻoŭmpʻa kŏmsa, kamsi kisul kaebal =: Development of electromagnetic ultrasonic testing, monitoring technology for piping in nuclear power plant. [Seoul]: Chisik Kyŏngjebu, 2008.
Den vollen Inhalt der Quelle findenH, Bamford W., Cipolla R. C, Jaske C. E, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (1991 : San Diego, Calif.), Hrsg. Service experience in operating plants, 1991: Presented at the 1991 Pressure Vessels and Piping Conference, San Diego, California, June 23-27, 1991. New York, N.Y: American Society of Mechanical Engineers, 1991.
Den vollen Inhalt der Quelle findenUnited States. National Aeronautics and Space Administration., Hrsg. Asteroid entry in Venusian atmosphere: Pressure and density fields effect on crater formation : final report. [Seattle, Wash.]: Boeing Defense & Space Group, 1995.
Den vollen Inhalt der Quelle findenAgency, OECD Nuclear Energy, und U.S. Nuclear Regulatory Commission., Hrsg. 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. Paris: Organisation for Economic Co-operation and Development, 1994.
Den vollen Inhalt der Quelle findenGraves, C. C. Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure". Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
Den vollen Inhalt der Quelle findenL, Cho F., Badie Navid, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (2000 : Seattle, Wash.), Hrsg. Emerging technologies: Risk assessment, computational mechanics, and advanced engineering topics : presented at the 2000 ASME Pressure Vessels and Piping Conference, Seattle, Washington, July 23-27, 2000. New York, N.Y: American Society of Mechanical Engineers, 2000.
Den vollen Inhalt der Quelle findenChi-Wen, Lin, Wang C. Y, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. und Pressure Vessels and Piping Conference (1995 : Honolulu, Hawaii), Hrsg. Natural hazard phenomena and mitigation, 1995: DOE facilities programs/design criteria and methods for--impact, wave, high frequency, and seismic loads : presented at the 1995 Joint ASME/JSME Pressure Vessels and Piping Conference, Honolulu, Hawaii, July 23-27, 1995. New York: American Society of Mechanical Engineers, 1995.
Den vollen Inhalt der Quelle findenMaerker, R. E. Analysis of the VENUS-3 experiments. Washington, D.C: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Den vollen Inhalt der Quelle finden