Książki na temat „Thermal power plants and nuclear power plants”

Drizhi͡us, M. R. Gidrotermicheskiĭ rezhim vodokhranilishch-okhladiteleĭ. Mokslas, 1985.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., ed. Software quality assurance procedures for NRC thermal hydraulic codes. U.S. Nuclear Regulatory Commission, 2000.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, ed. Software quality assurance procedures for NRC thermal hydraulic codes. U.S. Nuclear Regulatory Commission, 2000.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., ed. Software quality assurance procedures for NRC thermal hydraulic codes. U.S. Nuclear Regulatory Commission, 2000.

International Conference Thermal Power India (2nd 2007 New Delhi, India). International Conference, Thermal Power India-2: Coal, gas, oil & nuclear : conference proceedings. Council of Power Utilities, 2007.

Kaczynski, G. M. TPDWR2, thermal power determination for Westinghouse reactors, version 2: User's guide. Division of Emergency Preparedness and Engineering Response, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, 1985.

Tuunanen, Jari. Thermal-hydraulic studies on the safety of VVER-440 type nuclear power plants. Lappeenranta University of Technology, 1994.

Nuclear Thermal Propulsion Workshop (1991 Cleveland, Ohio). Nuclear thermal propulsion: A joint NASA/DOE/DOD workshop : proceedings of the Nuclear Thermal Propulsion Workshop, held at the Holiday Inn Strongsville, Cleveland, Ohio July 10-12, 1990. National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Program, 1991.

Seminar on the Results of the European Communities' Indirect Action Research Programme on Safety of Thermal Water Reactors (1984 Brussels, Belgium). Safety of thermal water reactors: Proceedings of a Seminar on the Results of the European Communities' Indirect Action Research Programme on Safety of Thermal Water Reactors, held in Brussels, 1-3 October 1984. Graham and Trotman, 1985.

Haapalehto, Timo. Validation studies of thermal-hydraulic code for safety analysis of nuclear power plants. Lappeenranta University of Technology, 1995.

G, DeWall K., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Idaho National Engineering and Environmental Laboratory., and Lockheed Idaho Technologies Company, eds. Results of pressure locking and thermal binding tests of gate valves. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

Lee, R. Y. Thermal-hydraulic research plan for Babcock and Wilcox plants. Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Lee, R. Y. Thermal-hydraulic research plan for Babcock and Wilcox plants. Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Lee, R. Y. Thermal-hydraulic research plan for Babcock and Wilcox plants. Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Lee, R. Y. Thermal-hydraulic research plan for Babcock and Wilcox plants. Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Lee, R. Y. Thermal-hydraulic research plan for Babcock and Wilcox plants. Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Sidorov, V. I. Temperaturnye izmerenii͡a︡ na AĖS. Ėnergoatomizdat, 1987.

T, Dugan Edward, and United States. National Aeronautics and Space Administration., eds. Thermal analysis of conceptual designs for GPHS/FPSE power system of 250 We and 500 We: Final report. Dept. of Nuclear Engineering Sciences, University of Florida, 1991.

Makarov, I. I. Modelirovanie gidrotermicheskikh prot͡s︡essov vodokhranilishch-okhladiteleĭ TĖS i AĖS. Ėnergoatomizdat, 1986.

Evans, Marlene S. Zooplankton studies at the Donald C. Cook Nuclear Plant: 1979-1982 investigations, including preoperational (1971-1974) and operational (1975-1982) comparisons. Great Lakes and Marine Waters Center, University of Michigan, 1985.

International Topical Meeting on Safety of Thermal Reactors (1991 Portland, Or.). Proceedings of the International Topical Meeting on Safety of Thermal Reactors: Portland, Oregon, July 21-25, 1991. American Nuclear Society, 1991.

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.

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.

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

Santos, R. H. Development of a computer tool for in-depth analysis and post processing of the RELAP5 thermal hydraulic code. U.S. Nuclear Regulatory Commission, 2011.

Holdup, Edwin D. The history of thermal-electric power generation in Canada, 1891 to 1990: A paper for presentation to the Thermal and Nuclear Power Section, Canadian Electrical Association centennial meeting, May 1991, Toronto, Ontario. The Association, 1991.

Holdup, Edwin D. The history of thermal-electric power generation in Canada 1891-to 1990: A paper for presentation to the Thermal and Nuclear Power Section, Canadian Electrical Association, Centennial Meeting, May, 1991, Toronto, Ontario. The Association, 1992.

S, Kazimi Mujid, ed. Nuclear systems. 2nd ed. Taylor & Francis, 2012.

Saitō, Takeichi. Umi no koe o kiku: Genshiryoku hatsudensho onhaisui no kansoku 25-nen. Nanatsumori Shokan, 2003.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and EG & G Idaho., eds. TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor. Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and EG & G Idaho., eds. TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor. Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and EG & G Idaho., eds. TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor. Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

American Society of Mechanical Engineers. Winter Meeting. Thermal hydraulics of nuclear steam generators/heat exchangers. American Society of Mechanical Engineers, 1988.

Tuomisto, H. Thermal mixing tests in a semiannular downcomer with interacting flows from cold legs. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1986.

R, Olvera J., Ruggles A. E, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., and University of Tennessee, Knoxville. College of Engineering., eds. Bulk temperature measurement in thermally striped pipe flows. Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1995.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Stevenson & Associates., and Oak Ridge National Laboratory, eds. Survey of strong motion earthquake effects on thermal power plants in California with emphasis on piping systems. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1995.

Palmrose, D. Demonstration of pressurized thermal shock thermal-hydraulic analysis with uncertainty: RELAP5/MOD3 and TRAC-PF1/MOD2 calculations in support of regulatory guide 1.154 revisions. Division of Systems Technology, Office of Nuclear Regulatory Commission, U.S. Nuclear Regulatory Commission, 1999.

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.

S, Kazimi Mujid, ed. Nuclear systems. Hemisphere Pub. Corp., 1990.

E, Boyack B., Giguere P. T, Los Alamos National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., eds. A plan for the modification and assessment of TRAC-PF1/MOD2 for use in analyzing CANDU 3 transient thermal-hydraulic phenomena. Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

Sánchez-Espinoza, Victor Hugo. Qualification of the three-dimensional thermal hydraulic model of TRACE using plant data. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2011.

United States. Congress. House. Committee on Science, Space, and Technology. Subcommittee on Investigations and Oversight. The development of nuclear thermal propulsion technology for use in space: Hearing before the Subcommittee on Investigations and Oversight of the Committee on Science, Space, and Technology, U.S. House of Representatives, One Hundred Second Congress, second session, October 1, 1992. U.S. G.P.O., 1993.