Books on the topic 'Pressurized water reactors Steam-turbines'

Kurtz, R. J. Steam generator group project: Annual report, 1985. Washington, DC: Division of Engineering Safety, Office of Nuclear Regulatory Researach, U.S. Nuclear Regulatory Commission, 1987.

Zverkov, V. V. I͡A︡dernai͡a︡ paroproizvodi͡a︡shchai͡a︡ ustanovka s VVĖR-440. Moskva: Ėnergoatomizdat, 1987.

Stubbe, E. J. Assessment study of RELAP-5 MOD-2 cycle 36.01: Based on the Doel-2 steam generator tube rupture incident of June 1979. Washington, D.C: U.S. Nuclear Regulatory Commission, 1986.

Yidong, Zhou, and Huang Xingrong, eds. He dian chang he zheng qi gong ying xi tong: Nuclear steam supply system of nuclear power plants. Beijing Shi: Yuan zi neng chu ban she, 2010.

Rogers, J. M. An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2. Washington, DC: U.S. Nuclear Regulatory Commission, 1992.

He dian chang zheng qi dong li zhuan huan xi tong: Steam power conversion system of nuclear power plants. Beijing Shi: Yuan zi neng chu ban she, 2010.

Frank, L. Steam generator operating experience update for 1987-1988. Washington, D.C: Division of Engineering and Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989.

Odar, F. Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: U.S. Nuclear Regulatory Commission, 2001.

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

Wet-steam turbines for nuclear power plants. Tulsa, Okla: PennWell Corp., 2005.

J, Preece R., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., and National Power, Technology, and Environmental Centre (Great Britain), eds. Assessment of PWR steam generator modelling in RELAP5/MOD2. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

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. Washington, DC: Safety Programs Division, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission, 1996.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering, ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. and Siemens Energierzeugung (Firm), eds. RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research and Siemens Energierzeugung (Firm), eds. RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research and Siemens Energierzeugung (Firm), eds. RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

Voltage-based alternative repair criteria: A report to the Advisory Committee on Reactor Safeguards. Washington, DC: Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 2001.

Voltage-based alternative repair criteria: A report to the Advisory Committee on Reactor Safeguards. Washington, DC: Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 2001.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, ed. Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, ed. Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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

G, Oh J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Hanʾguk Chŏllyŏk Kisul Chusik Hoesa, Hanʾguk Wŏnjaryŏk Anjŏn Kisurwŏn, and Nihon Genshiryoku Kenkyūjo, eds. Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. and Argonne National Laboratory, eds. Assessment of current understanding of mechanisms of initiation, arrest, and reinitiation of stress corrosion cracks in PWR steam generator tubing. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

S, Park H., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Hanʾguk Kwahak Kisurwŏn, and Hanʾguk Wŏnjaryŏk Anjŏn Kisurwŏn, eds. Assessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

J, Shack W., and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions: Phase I final report. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2003.

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. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., ed. Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, ed. Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., ed. Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.