Books on the topic 'Nuclear fuels – Computer programs'

Klein, M. E. Simulation of in-reactor experiments with the ELOCA.Mk5 code. Chalk River, Ont: Chalk River Laboratories, 1994.

Kikō, Genshiryoku Anzen Kiban. Kakunenryō shisetsu hibaku hyōka shien shisutemu no seibi. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Chan, M. K. User's manual for FIRIN: A computer code to estimate accidental fire and radioactive airborne releases in nuclear fuel cycle facilities. Washington, DC: Division of Fuel Cycle and Material Safety, Office of Nuclear Materials Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1989.

Klein, M. E. Simulation of in-reactor experiments with the ELOCA.Mk5 code. Chalk River, Ont: Fuel Engineering Branch, Chalk River Laboratories, 1994.

Bilanovic, Z. Neutron-photon energy deposition in CANDU reactor fuel channels: A comparison of modelling techniques using ANISN and MCNP computer codes. Chalk River, Ont: System Chemistry and Corrosion Branch, Chalk River Laboratories, 1994.

LeNeveu, D. M. Analysis specifications for the CC3 vault model. Pinawa, Man: AECL Research, 1994.

Commission, Canadian Nuclear Safety. Security programs for category I or II nuclear material or certain nuclear facilities. [Ottawa]: Canadian Nuclear Safety Commission, 2003.

Azmy, Yousry. Nuclear computational science: A century in review. Dordrecht: Springer, 2010.

Dougan, Kenneth D. Programmer's guide for the CC3 computer models of the concept for disposal of Canada's nuclear fuel waste. Pinawa, Man: Environmental and Safety Assessment Branch, Whiteshell Laboratories, 1996.

Dougan, K. D. User's manual for the CC3 computer models of the concept for disposal of Canada's nuclear fuel waste. Pinawa, Man: Environmental and Safety Assessment Branch, Whiteshell Laboratories, 1995.

Modak, R. S. Transport synthetic acceleration scheme for multi-dimensional neutron transport problems. Mumbai: Bhabha Atomic Research Centre, 2005.

Kikō, Genshiryoku Anzen Kiban. CASMO-4/SIMULATE-3 kōdo shisutemu no PWR torikae roshin sekkei e no tekiyōsei no hyōka ni tsuite. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Nagashima, Yasuo. SHINE, tajū tajigen dēta shūshū kaiseki shisutemu. Ibaraki-ken Tsukuba-shi: Tsukuba Daigaku Kasokuki Sentā, 1992.

Mysenkov, I. A. Rasschetnai͡a︡ programma MOST7-CS. Řež: Ústav jaderného výzkumu,Infomačni strĕdisko, 1990.

Turnbull, J. Anthony. Review of nuclear fuel experimental data: Fuel behaviour data available from IFE-OCDE Halden Project for development and validation of computer codes. Paris: Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 1995.

Bayless, Paul D. Analysis of natural circulation during a Surry Station blackout using SCDAP/RELAP5. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Sirola, Miki. Strategy generator in computerized accident management support system. Espoo: Technical Research Centre of Finland, 1994.

Kikō, Genshiryoku Anzen Kiban. Nenryō kakō shisetsu no jikoji kankikei kyodō kaiseki no shuhō seibi. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Kenkyūjo, Mitsubishi Sōgō. Kaiseki kōdo no shinraisei kōjō kōdoka no tame no puroguramingu gengo no kashika kenkyū: Heisei 22-23-nendo genshiryoku anzen kiban chōsa kenkyū (Heisei 22-nendo). [Tokyo]: Mitsubishi Sōgō Kenkyūjo, 2011.

Lee, Guy. Results of a survey on accident and safety analylsis codes, benchmarks, verification and validation methods. Pinawa, Man: Whiteshell Laboratories, 1996.

Brünger, Axel T. X-PLOR, Version 3.1: A system for X-ray crystallography and NMR. New Haven: Yale University Press, 1992.

West, Douglas Brent. User's guide for the TACT5 computer code. Washington, D.C: Division of Radiation Protection and Emergency Preparedness, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1988.

Berar, Ovidiu-Adrian. Assessment against ACHILLES reflood experiment with TRACE V5.0 Patch3. Washington, DC: U.S. Nuclear Regulatory Commission, 2014.

Mayya, Y. S. Containment aerosol behaviour simulation studies in the BARC nuclear aerosol test facility. Mumbai: Bhabha Atomic Research Centre, 2005.

Elks, Carl R. Development of a fault injection-based dependability assessment methodology for digital I & C systems. Washington, D.C: United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2012.

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

K, Mehta M., and Schmidt J. J. 1931-, eds. Workshop on Computation and Analysis of Nuclear Data Relevant to Nuclear Energy and Safety: 10 February-13 March 1992, Trieste, Italy. Singapore: World Scientific, 1993.

Board, United States Nuclear Waste Technical Review. Survey of national programs for managing high-level radioactive waste and spent nuclear fuel: A report to Congress and the Secretary of Energy. Arlington, VA: United States Nuclear Waste Technical Review Board, 2009.

Kikō, Genshiryoku Anzen Kiban. Anzen shinsa kankei dētabēsu no kairyō seibi ni kansuru hōkokusho. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Kikō, Genshiryoku Anzen Kiban. TRACE kōdo ni yoru PWR puranto no LOCA kaiseki shuhō no seibi. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2011.

Kikō, Genshiryoku Anzen Kiban. Taishin kaiseki kōdo no hoshu ni kansuru hōkokusho: SANWAV, SANFALT. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Commission, Canadian Nuclear Safety. Computer programs used in design and safety analyses of nuclear power plants and research reactors. [Ottawa]: The Commission, 2000.

Spindler, B. Assessment of TRAC-PF1/MOD1 version 14.3 using separate effects critical flow and blowdown experiments. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Spindler, B. Assessment of TRAC-PF1/MOD1 version 14.3 using separate effects critical flow and blowdown experiments. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Spindler, B. Assessment of TRAC-PF1/MOD1 version 14.3 using separate effects critical flow and blowdown experiments. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Spindler, B. Assessment of TRAC-PF1/MOD1 version 14.3 using separate effects critical flow and blowdown experiments. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Spindler, B. Assessment of TRAC-PF1/MOD1 version 14.3 using separate effects critical flow and blowdown experiments. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Experience gained from programs to manage high-level radioactive waste and spent nuclear fuel in the United States and other countries. Arlington, VA: U.S. Nuclear Waste Technical Review Board, 2011.

Valdez, G. D. Review and assessment of thermodynamic and transport properties for the CONTAIN code. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Valdez, G. D. Review and assessment of thermodynamic and transport properties for the CONTAIN code. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Corcuera, P. Nowadays tools for graphical post-processing of TRAC-BF1 results. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.

Kimura, Hiromi. BASS dēta shūshū shisutemu. Ibaraki-ken Tsukuba-shi: Tsukuba Daigaku Kasokuki Sentā, 1997.

Stallmann, Friedemann. PR-EDB, power reactor embrittlement data base, version 1: Program description. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Meininger, Richard D. Development of a testing and analysis methodology to determine the functional condition of solenoid operated valves. Washington, DC: Divison of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987.

Kikō, Genshiryoku Anzen Kiban. Kakunenryō shisetsu anzen kaiseki kōdo kairyō seibi kakuritsuronteki kankyō eikyō hyōka shisutemu no kairyō seibi ni kansuru hōkokusho. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Corcuera, P. Nowadays tools for graphical post-processing of TRAC-BF1 results. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.

F, Young Michael, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Sandia National Laboratories, eds. Integrated fuel-coolant interaction (IFCI 6.0) code: User's manual. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

F, Young Michael, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Sandia National Laboratories, eds. Integrated fuel-coolant interaction (IFCI 6.0) code: User's manual. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

F, Young Michael, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Sandia National Laboratories, eds. Integrated fuel-coolant interaction (IFCI 6.0) code: User's manual. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

K, Mikitiouk, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Institut I︠A︡dernykh Reaktorov (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), and Institut problem bezopasnogo ispolʹzovanii︠a︡ i︠a︡dernoĭ ėnergii (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), eds. Modification of IPSN's SCANAIR fuel rod transient code for high burnup VVER fuel. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.