Books on the topic 'Plantar pressure'

Safety, American Institute of Chemical Engineers Center for Chemical Process. Guidelines for vapor cloud explosion, pressure vessel burst, BLEVE, and flash fire hazards. 2nd ed. Wiley, 2010.

Wong, S. High pressure coolant injection (HPCI) system risk-based inspection guide for Browns Ferry Nuclear Power Station. Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.

American Society of Mechanical Engineers. Boiler and Pressure Vessel Committee. 2007 ASME boiler & pressure vessel code: An international code : Materials. American Society of Mechanical Engineers, 2008.

Thomas, Kenneth Glyndwr. Research, engineering design and operation of a pressure hydrometallurgy facility for gold extraction. Thomas, 1994.

T, Kisisel I., American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and ASME Pressure Vessels and Piping Conference (1999 : Boston, Massachusetts), eds. Operations, applications, and components, 1999 : presented at the 1999 ASME Pressure Vessels and Piping Conference, Boston, Massachusetts, August 1-5, 1999. American Society of Mechanical Engineers, 1999.

S, Dean R., Hennick A, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Operational Events Assessment., and Parameter Inc, eds. Closeout of IE bulletin 86-02: Static "O" ring differential pressure switches. Division of Operational Events Assessment, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989.

H, Bamford W., American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (1993 : Denver, Colo.), eds. 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. American Society of Mechanical Engineers, 1993.

N, Pangborn R., Narayanan T. V, Means K. H, et al., eds. 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. American Society of Mechanical Engineers, 1990.

C, Holston William, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., U.S. Nuclear Regulatory Commission., and Pressure Vessels and Piping Conference (2001 : Atlanta, Georgia), eds. 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. American Society of Mechanical Engineers, 2001.

Fouad, Fanous, Bluhm Delwyn, Ames Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., eds. Crack propagation in high strain regions of Sequoyah containment. Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.

K, Kasza, Franklin J, Argonne National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes. U.S. Nuclear Regulatory Commission, 2000.

Oesterle, R. G. Design provisions for tangential shear in containment walls. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

K, Kasza, Franklin J, Argonne National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes. U.S. Nuclear Regulatory Commission, 2000.

H, Bamford W., Cipolla R. C, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (1994 : Minneapolis, Minn.), eds. 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. American Society of Mechanical Engineers, 1994.

K, Kasza, Franklin J, Argonne National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes. U.S. Nuclear Regulatory Commission, 2000.

W, Shier, U.S. Nuclear Regulatory Commission. Division of Systems Safety and Analysis., and Brookhaven National Laboratory, eds. High pressure coolant injection system risk-based inspection guide for Hope Creek. Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1992.

D, Naus, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Oak Ridge National Laboratory, eds. A survey of repair practices for nuclear power plant containment metallic pressure boundaries. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

Korth, G. E. Metallographic and hardness examinations of TMI-2 lower pressure vessel head samples. Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

Sofronas, Anthony. Analytical troubleshooting of process machinery and pressure vessels: Including real-world case studies. John Wiley & Sons, 2005.

Sofronas, Anthony. Analytical troubleshooting of process machinery and pressure vessels: Including real-world case studies. John Wiley & Sons, 2006.

International, 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. ASM International, 1995.

A, Dermenjian Artin, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (1996 : Montréal, Québec), eds. 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. American Society of Mechanical Engineers, 1996.

International 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. ASM International, 1997.

Sikora, Richard A., Johan Desaeger, and Leendert Molendijk, eds. Integrated nematode management: state-of-the-art and visions for the future. CABI, 2021. http://dx.doi.org/10.1079/9781789247541.0000.

Chŏng, 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. Chisik Kyŏngjebu, 2008.

Chŏng, 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. Chisik Kyŏngjebu, 2008.

Wesley, D. A. Screening methods for developing internal pressure capacities for components in systems interfacing with nuclear power plant reactor coolant systems. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

Chi-Wen, Lin, Wang C. Y, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (1994 : Minneapolis, Minn.), eds. Natural hazard phenomena and mitigation: Presented at the 1994 Pressure Vessels and Piping Conference, Minneapolis, Minnesota, June 19-23, 1994. American Society of Mechanical Engineers, 1994.

ASME 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. Edited by Truong Q. N, Goodling Evans C, Balaschak J. J, Widera G. E. O, and American Society of Mechanical Engineers. Pressure Vessels and Piping Division. American Society of Mechanical Engineers, 1989.

Boilers, ASME Boiler and Pressure Vessel Committee Subcommittee on Heating. 2007 ASME boiler & pressure vessel code: An international code : Materials. American Society of Mechanical Engineers, 2007.

D, Rodery Clay, Takagi Yoshio, Miura Naoki, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (2004 : San Diego, Calif.), eds. 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. American Society of Mechanical Engineers, 2004.

U.S. Nuclear Regulatory Commission. Division of Systems Safety and Analysis. and Brookhaven National Laboratory, eds. High pressure coolant injection system risk-based inspection guide for Hatch Nuclear Power Station. Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.

J, Shack W., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Argonne National Laboratory, eds. Environmental effects on fatigue crack initiation in piping and pressure vessel steels. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Christie, Robert F. Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system. Tennessee Valley Authority, 1985.

Agency, OECD Nuclear Energy, and U.S. Nuclear Regulatory Commission., eds. 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. Organisation for Economic Co-operation and Development, 1994.

Graves, C. C. Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure". Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

L, Cho F., Badie Navid, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (2000 : Seattle, Wash.), eds. 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. American Society of Mechanical Engineers, 2000.

R, Corwin W., Haggag Fahmy M, Server W. L, and ASTM Committee E-10 on Nuclear Technology and Applications., eds. Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension. ASTM, 1993.

Chi-Wen, Lin, Wang C. Y, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (1995 : Honolulu, Hawaii), eds. 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. American Society of Mechanical Engineers, 1995.

Maerker, R. E. Analysis of the VENUS-3 experiments. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

J, James R., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., ANATECH Corporation, and Sandia National Laboratories, eds. Seismic analysis of a prestressed concrete containment vessel model. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

Maerker, R. E. Analysis of the VENUS-3 experiments. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

H, Bamford W., Cipolla R. C, Jaske C. E, American Society of Mechanical Engineers. Pressure Vessels and Piping Division., and Pressure Vessels and Piping Conference (1991 : San Diego, Calif.), eds. Service experience in operating plants, 1991: Presented at the 1991 Pressure Vessels and Piping Conference, San Diego, California, June 23-27, 1991. American Society of Mechanical Engineers, 1991.

United States. National Aeronautics and Space Administration., ed. Asteroid entry in Venusian atmosphere: Pressure and density fields effect on crater formation : final report. Boeing Defense & Space Group, 1995.