Books on the topic 'Reactor system code'
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Paratte, Jean Marie. Elcos: The PSI code system for LWR core analysis. Paul Scherrer Institut (PSI), 1996.
Find full textRao, D. V. GSI-191: Thermal-hydraulic response of PWR reactor coolant system and containments to selected accident sequences. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.
Find full textWard, L. W. Consequences of the loss of the residual heat removal systems in pressurized water reactors. Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1992.
Find full textWard, L. W. Consequences of the loss of the residual heat removal systems in pressurized water reactors. Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1992.
Find full textHall, P. C. Analysis of semiscale test S-LH-1 using RELAP5/MOD2. U.S. Nuclear Regulatory Commission, 1992.
Find full textRogers, J. M. An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2. U.S. Nuclear Regulatory Commission, 1992.
Find full textTaler, Jan. Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =: Symulacja awaryjnego schładzania zbiorników reaktorów wodnociśnieniowych. Politechnika Krakowska im. Tadeusza Kościuszki, 1993.
Find full textChristie, Robert F. Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system. Tennessee Valley Authority, 1985.
Find full textNatesan, K. Knowledge base report on emergency core cooling sump performance in operating light water reactors. United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2014.
Find full textCramond, Wallis R. Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor: Case study. Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987.
Find full textSerkiz, A. W. Containment emergency sump performance: Technical findings related to unresolved safety issue A-43. Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985.
Find full textSerkiz, A. W. USI A-43 regulatory analysis. Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985.
Find full textSerkiz, A. W. USI A-43 regulatory analysis. Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985.
Find full textSerkiz, A. W. USI A-43 regulatory analysis. Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985.
Find full textSerkiz, A. W. USI A-43 regulatory analysis. Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985.
Find full textSerkiz, A. W. USI A-43 regulatory analysis. Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985.
Find full textUnited States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment. Safety aspects of the Yankee Rowe Nuclear Powerplant: Oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, One Hundred Second Congress, first session ... hearing held in Washington, DC, August 1, 1991. U.S. G.P.O., 1992.
Find full textS, Rohatgi Upendra, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., and Brookhaven National Laboratory, eds. RAMONA-4B, a computer code with three-dimensional neutron kinetics for BWR and SBWR system transients. Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.
Find full textW, Ross K., Ashbaugh S. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Los Alamos National Laboratory, eds. GSI-191: Thermal-hydraulic response of PWR reactor coolant system and containments to selected accident sequences. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.
Find full textComparison of thermal-hydraulic safety codes for PWR systems. Graham & Trotman for the Commission of the European Communities, 1988.
Find full textD, Kahook S., Diaz N. J, and United States. National Aeronautics and Space Administration., eds. A burst mode, ultrahigh temperature UF4 vvapor core reactor rankine cycle space power system concept. National Aeronautics and Space Administration, 1996.
Find full textAbdul-hamid, Shahab A. Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system. 1993.
Find full textReliability study: auxiliary/emergency feedwater system, 1987-1995. The Commission, 1998.
Find full textJ, 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. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2003.
Find full textU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research and AEA Technology (Firm), eds. RELAP/MOD3 analysis of BETHSY test 6.9c: Loss of RHRS, SG manway open. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.
Find full textColpo, Sarah E. Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown. 1999.
Find full textUse of Computational Fluid Dynamics Codes for Safety Analysis of Nuclear Reactor Systems (Iaea Tecdoc Series). International Atomic Energy Agency, 2004.
Find full textU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. and Siemens AG-KWU Group, eds. Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg). Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Find full textDraft regulatory guide DG-1107: Water sources for long-term recirculation cooling following a loss-of-coolant accident : (proposed revision 3 to Regulatory Guide 1.82). U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2003.
Find full textDraft regulatory guide DG-1107: Water sources for long-term recirculation cooling following a loss-of-coolant accident : (proposed revision 3 to Regulatory Guide 1.82). U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2003.
Find full textDraft regulatory guide DG-1107: Water sources for long-term recirculation cooling following a loss-of-coolant accident : (proposed revision 3 to Regulatory Guide 1.82). U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2003.
Find full textCompendium of ECCS research for realistic LOCA analysis: Final report. Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
Find full textU.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs., U.S. Nuclear Regulatory Commission. Division of Risk Analysis and Applications., and Idaho National Engineering and Environmental Laboratory., eds. Reliability study. Safety Programs Division, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission, 1998.
Find full textWetherel, Mark A., and Kav Vedhara. The measurement of physiological outcomes in health and clinical psychology. Oxford University Press, 2015. http://dx.doi.org/10.1093/med:psych/9780198527565.003.0005.
Full textWaechter, Matthias, and Hartmut Marhold, eds. Europe - Against the Tide. Nomos Verlagsgesellschaft mbH & Co. KG, 2019. http://dx.doi.org/10.5771/9783845292762.
Full textSchultz, Richard R. Validation of Systems Transients Analysis Codes: Presented at the 1995 Asme/Jsme Fluids Engineering and Laser Anemometry Conference and Exhibition, Au (Ne). American Society of Mechanical Engineers, 1995.
Find full textHitlin, Steven, and Sarah K. Harkness. The Theory of Inequality and Moral Emotions. Oxford University Press, 2017. http://dx.doi.org/10.1093/oso/9780190465407.003.0006.
Full textRaff, Lionel, Ranga Komanduri, Martin Hagan, and Satish Bukkapatnam. Neural Networks in Chemical Reaction Dynamics. Oxford University Press, 2012. http://dx.doi.org/10.1093/oso/9780199765652.001.0001.
Full textValidation of systems transients analysis codes: Presented at the 1995 ASME/JSME Fluids Engineering and Laser Anemometry Conference and Exhibition, August 13-18, 1995, Hilton Head, South Carolina. American Society of Mechanical Engineers, 1995.
Find full textFox, Raymond. The Use of Self. Oxford University Press, 2011. http://dx.doi.org/10.1093/oso/9780190616144.001.0001.
Full textUnger, Brigitte, Lucia Rossel, and Joras Ferwerda, eds. Combating Fiscal Fraud and Empowering Regulators. Oxford University Press, 2021. http://dx.doi.org/10.1093/oso/9780198854722.001.0001.
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