Books on the topic 'Steam and product piping'

Tanrikut, A. In-tube steam condensation in the presence of air. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

Tanrikut, A. In-tube steam condensation in the presence of air. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

Kalmbach, Steve. Piping for high-pressure boilers: The installation and inspection of high-pressure boiler piping for code compliance with the ASME and National Board Code Requirements. Wheatmark, 2013.

Clark, R. A. Compendium and comparison of international practice for plugging, repair, and inspection of steam generator tubing. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Clark, R. A. Compendium and comparison of international practice for plugging, repair, and inspection of steam generator tubing. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

The industrialization of design: A history from the steam age to today. McFarland, 2011.

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.

Basdekas, D. Regulatory analysis for the resolution of Generic issue 125.II.7, "Reevaluate provision to automatically isolate feedwater from steam generator during a line break". Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

E, MacDonald Philip, U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs., Idaho National Engineering Laboratory, and Lockheed Idaho Technologies Company, eds. Steam generator tube failures. Safety Programs Division, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission, 1996.

G, Heasler P., Anderson C. M, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Pacific Northwest National Laboratory (U.S.), eds. Performance demonstration tests for eddy current inspection of steam generator tubing. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996.

Eichenberg, Thomas William. Numerical analysis of condensation induced water-hammer in horizontal piping systems. 1990.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering, ed. Circumferential cracking of steam generator tubes. U.S. Nuclear Regulatory Commission, 1997.

M, Tenore Frank, and Technical Association of the Pulp and Paper Industry. Steam and Power Committee., eds. Power piping data: A project of the Steam and Power Committee of the Engineering Division. TAPPI Press, 1985.

Companion Guide ASME BPVC: Criteria & Commentary Select Aspects ASME Boiler, Press Vesl & Piping Codes. American Society of Mechanical Engineers, 2001.

Rao, K. R. Companion Guide ASME BPVC: Criteria & Commentary Select Aspects ASME Boiler, Press Vesl & Piping Codes. American Society of Mechanical Engineers, 2001.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering. and Oak Ridge National Laboratory, eds. Effects of aging and service wear on main steam isolation valves and valve operators. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996.

A, Gorman J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Argonne National Laboratory, eds. Estimating probable flaw distributions in PWR steam generator tubes. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

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.

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.

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.

1933-, Rao K. R., ed. Companion guide to the ASME boiler & pressure vessel code: Criteria and commentary on select aspects of the boiler & pressure vessel and piping codes. ASME Press, 2002.

1933-, Rao K. R., and American Society of Mechanical Engineers. Boiler and Pressure Vessel Committee., eds. Companion guide to the ASME boiler & pressure vessel code: Criteria and commentary on select aspects of the Boiler & pressure vessel and piping codes. 3rd ed. ASME Press, 2009.

Companion guide to the ASME boiler & pressure vessel code: Criteria and commentary on select aspects of the Boiler & pressure vessel and piping codes. 3rd ed. ASME Press, 2009.

The role of time-dependent deformation in intergranular crack initiation of alloy 600 steam generator tubing material. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

K, Lian, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. The role of time-dependent deformation in intergranular crack initiation of alloy 600 steam generator tubing material. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

K, Lian, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. The role of time-dependent deformation in intergranular crack initiation of alloy 600 steam generator tubing material. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

U.S. Nuclear Regulatory Commission., ed. Screening Reactor Steam/Water Piping Systems For Water Hammer... Nureg/CR-6519... U.S. Nuclear Regulatory Commission... 1997. s.n., 1997.

Tenore, Frank M. Power Piping Data: A Project of the Steam and Power Committee of the Engineering Division, Ca 4993. 2nd ed. Tappi, 1997.

M, Tenore Frank, Smeal Keith W. 1949-, Lunde Jeffrey S. 1947-, and Technical Association of the Pulp and Paper Industry. Steam and Power Committee., eds. Power piping data: A project of the Steam and Power Committee of the Engineering Division, CA 4993. 2nd ed. TAPPI, 1992.

1935-, Sjöberg Anders, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Consejo de Seguridad Nuclear (Spain), and Studsvik energiteknik AB, eds. Assessment of TRAC-PF1/MOD1 against an inadvertent steam line isolation valve closure in the Ringhals 2 power plant. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

1935-, Sjöberg Anders, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Consejo de Seguridad Nuclear (Spain), and Studsvik energiteknik AB, eds. Assessment of TRAC-PF1/MOD1 against an inadvertent steam line isolation valve closure in the Ringhals 2 power plant. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

1935-, Sjöberg Anders, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Consejo de Seguridad Nuclear (Spain), and Studsvik energiteknik AB, eds. Assessment of TRAC-PF1/MOD1 against an inadvertent steam line isolation valve closure in the Ringhals 2 power plant. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

1935-, Sjöberg Anders, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Consejo de Seguridad Nuclear (Spain), and Studsvik energiteknik AB, eds. Assessment of TRAC-PF1/MOD1 against an inadvertent steam line isolation valve closure in the Ringhals 2 power plant. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

Agency, Property Services. Thermally Insulated Underground Piping Systems for the Conveyance of Steam, Hot and Chilled Water (Property Services Agency Standard Specification (M & E)). Stationery Office Books, 1990.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. and Argonne National Laboratory, eds. Bases for predicting the earliest penetrations due to SCC for alloy 600 on the secondary side of PWR steam generators. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Tennessee Valley Authority. Combustion By-product Marketing and Management Section., ed. Environmental assessment development of by-product disposal facilities: Cumberland Fossil Plant, flue gas desulfurization gypsum and fly ash. Tennessee Valley Authority], Fossil Fuels Combustion By-Product Marketing and Management Section, 1992.

Raitz, Karl. Making Bourbon. University Press of Kentucky, 2020. http://dx.doi.org/10.5810/kentucky/9780813178752.001.0001.

Pool, Robert. Beyond Engineering. Oxford University Press, 1997. http://dx.doi.org/10.1093/oso/9780195107722.001.0001.