Диссертация (781854), страница 42
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1960.232. Kaiser A., Peppler W., Will H. SIMBATH 1976-1992, seventeen years of experimental investigation of key issues concerned with severe reactor accidents.–In:IAEA/IWGFR Techn. Com. Meeting on Material-Coolant Interactions and MaterialMovement and Relocation in Liquid Metal Fast Reactors. Japan, 1994, pp. 349−383.233. Kampf H., Karsten G.
Effects of Different Types of Void Volumes on the Radial Temperature Distribution of Fuel Pins // Nuclear Applications and Technology. –1970. – Vol. 9. – No. 3. – pp. 288−300.234. Kascheev M.V., Kuznetsov I.A. Computation Analysis of Fuel Melt Confinement Processes in Fast Reactors // International Conference on Fifty Years of NuclearPower - the Next Fifty Years, 27 June - 2 July 2004, Obninsk/Moscow, Russian Federation.
Book of Extended Synopses. IAEA – CN - 114/35p, pp. 209,210.235. Kascheev M.V., Kuznetsov I.A. Analytical studies on a severe accident in theBN-800 reactor // The 20th International Conference on Transport Theory (ICТT-20),22-28 July 2007, Obninsk, Russia. Book of Abstracts, pp. 150,151.236. King L.D.P. Safety Neutronics for Rover Reactors, LA-3358-MS, 1965.237.
King L.D.P. et. al. Description of the Kiwi-TNT Excursion and Related Experiments, LA-3350-MS, 1966.238. Kolsky H.G. A Method for the Numerical Solution of Transient HydrodynamicsShock Problems in Two Space Dimensions, LA-1867, 1955.239. Kuznetsov I.A., Shvetsov Yu.E. Computational efficiency for analysis of fuelpin damage registration and fuel assembly damage location by means of a sector fuelfailure detection and location system // International Conference of Fast Reactors and298Related Fuel Cycles: Challenges and Opportunities, FR09, 7−11 December 2009,Kyoto, Japan. Book of Extended Synopses, p. 370, IAEA-CN-176/03-15P.240.
Kymalainen O. et. al. COPO: Experiments for Heat Flux Distribution froma Volumetrically Heated Corium Pool // 20th Water Reactor Safety InformationMeeting, Bethesda, Maryland, 21-23 Oct. 1992.241. Kymalainen O. et. al. Heat Flux Distribution from a Volumetrically HeatedPool with High Rayleigh Number // Proceedings of 6 th International Topical Meeting on Reactor Thermal - Hydraulics, Grenoble, France, 5-8 Oct. 1993, Vol. l,pp.47–53.242. Lipinski R.J., Gronager J.E., Schwarz M. Particle Bed Heat Removal withSubcooled Sodium: D4 Results and Analysis // Nuclear Technology. – 1982.
–Vol. 58. – No. 3. – pp. 369−378.243. McDonald J.S. and Connolly T.J. Investigation of natural convection heat transfer in liquid sodium // Nuclear Science and Engineering. – 1960. − Vol. 8. – No. 5. −pp. 369–377.244. Meyer R.A., Wolfe B. and Friedman N.F. A Parameter Study of Large Fast Reactor Meltdown Accidents // Proc. of the Conf. on Safety, Fuels and Core Design inLarge Fast Power Reactors, ANL-7120, Argonne National Laboratory, October11−14, 1965.245. Meyer-Heine A., Kayser G., Moxon D. et. al.
The SCARABEE Program and thePHYSURA-GRAPPE Code – a Phenomenological Approach for Subassembly Accidents // Science and Technology of FAST REACTOR SAFETY: Proc. of an international conference held in Guernsey on 12-16 May 1986. – BNES, London,1987. –Vol.
1. – pp. 251−256.246. Moor K., Brealey J. Modelling of Sodium-Cooled Debris Beds // Science andTechnology of Fast Reactor Safety: Proc. of an Int. Conf. held in Guernsey on 12–16May 1986. – BNES, London, 1987. − Vol. 1. − pp. 165–170.247. Morita K., Tobita Y., Kondo Sa. Multiphase, Multicomponent Heat-and MassTransfer Modelling in SIMMER-III // Sodium Cooled Fast Reactor Safety: Proc. of299an International Topical Meeting. – Obninsk, Russia, October 3−7, 1994.
– Obninsk.1994. – Vol. 2. – pp. 2/290 – 2/299.248. Morita K., Fischer E. A., Thurnay K. Thermodynamic properties and equationsof state for fast reactor safety analysis. Part II: Properties of fast reactor materials //Nuclear Engineering and Design. – 1998.
– Vol. 183. – pp. 193–211.249. Moxon D., Camous F. A New Cavity Model for SAS4A // Proc. IAEA/IWGFRTechn. Committee Meet. on Material-Coolant Interactions and Material Movementand Relocation in LMFR’S, O-arai, Ibaraki, Japan, June 6-9, 1994. – O-arai Engineering Center, PNC, 1994. – pp. 257−280.250.
Nicholson R. B. Methods for Determining the Energy Release in HypotheticalFast-Reactor Meltdown Accidents // Nuclear Science and Engineering. – 1964. – Vol.18. – No. 2. − pp. 207–219.251. Nijsing R., Schwalm D. A One-dimensional Computation Method for Predictingthe Asymptotic Heat Transfer Behaviour of Sodium-Saturated Fuel Particle Bedswith Top and Bottom Cooling // Nuclear Engineering and Design. – 1981. – Vol. 66.– pp.
151−170.252. Okrent D. e.a. AX-1. Computing Program for Coupled NeutronicHydrodynamics Calculations on the IBM-704, USAEC Report ANL-5977, 1959.253. Peddie W. Note on the Cooling of a Sphere in a mass of well-stirred Liquid //Proc. Edin. Math. Soc. – 1901. – Vol. 19. – pp. 34,35.254. Plassmann E.A.
et. al. Some Neutronics Results of the Kiwi-B-4E Newada Test,LA-3327-MS, 1965.255. Poplavsky V.M., Kuznetsov I.A.,Shvetsov Yu.E., Volkov A.V., Ashurko Yu.M.,Kashcheev M.V., Shchekotova L.A., Kuntsio G.A.. Computational software packagefor analyzing the fast neutron reactor safety, its improvement and development prospects // International Conference of Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, FR09, 7−11 December 2009, Kyoto, Japan. Book of Extended Synopses, p. 232, IAEA-CN-176/06-10P.300256.
Pourcheresse C., Gouez J.M. Le, Anzieu P. Application of the SURFASS Codeto a Reactor Calculation and Comparison with SCARABEE Experiments // Scienceand Technology of FAST REACTOR SAFETY: Proc. of an international conferenceheld in Guernsey on 12-16 May 1986. – BNES, London,1987. – Vol. 1. –pp. 451−455.257. Richtmyer R.D. and Morton K.W.
Difference Methods for Initial Value Problems. – New York: Interscience Publishers, 1957.258. Rivard J.B. In-reactor experiments on the cooling of fast reactor debris // Nuclear Technology. – 1979. − Vol. 46. − No 2. − pp. 344–349.259. Rutge T., Wickens L.M. FRAX-4: a Whole Core Accident Analysis Code forthe Fast Reactor // Science and Technology of FAST REACTOR SAFETY: Proc. ofan international conference held in Guernsey on 12-16 May 1986. – BNES, London,1987.
– Vol. 2. – pp. 13−18.260. Schmuck P., Jacobs G., Arnecke G. KADIS: ein Computerprogram zur AnalysederKernzerlegungsphasebeihypothetischenStörfälleninschnellen,natriumgekühlten Brutreaktoren, Karlsruhe, KFK 2497, 1977.261. Schwarz M., Gronager J.E., Lipinski R.J. Particle-Bed Heat Removal withSubcooled Sodium: D4 Analysis // Transactions of the ANS.
– 1980. – Vol. 35. – pp.357,358.262. Scriven L.E. On the dynamics of phase growth // Chem. Engng Sci. – 1959. –No. 1. – pp. 1–13.263. Sha W.T. and Hughes T.H. VENUS: A Two-dimensional Coupled NeutronicsHydrodynamics Computer Program for Fast-reactor Power Excursions, ANL-7701,Oct. 1970.264. Shins H.A., Gunnerson F.S. Boiling and Fragmentation Behavior duringFuel-Sodium Interactions // Nuclear Engineering and Design. – 1986. – Vol. 91. −No. 3.
– pp. 221−235.265. Shvetsov Yu.E., Kuznetsov I.A. Calculation of the thermohydraulic parametersof a fast neutron reactor with account of inter-fuel assembly space influence // Inter-301national Conference of Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, FR09, 7−11 December 2009, Kyoto, Japan. Book of Extended Synopses,p. 370, IAEA-CN-176/06-29P.266. Shvetsov Yu.E., Kouznetsov I.A. Analytical Studies on Thermal-Hydraulic Parameters of Fast Reactor Taking into Account Effect of Inter-wrapper Space // Journal of Materials Science and Engineering B. – 2011.
– Vol. 1. − No. 7. – pp.938−946.267. Smets H. B. Reactor dynamics at low power. − In: ”Proc. Geneva Conf.”, 1958.− Vol. 11. − p. 237.268. Struve D., Royl P., Wirtz P., Angerer G., Fischer E. CAPRI – A Computer Codefor Analysis of Hypothetical Core Disruptive Accidents in the Predissassembly Phase/ Proc. of the Int. Meeting on Fast Reactor Safety and Related Physics, CONF740401-P1, April 2-4, 1974, Beverly Hills, CA, p. 1525.269. Tentner A.M., Miles K.J., Kalimullah, D.J. Hill. Fuel Relocation Modelling inthe SAS4A Accident Analysis Core System // Science and Technology of FASTREACTOR SAFETY: Proc.
of an international conference held in Guernsey on 1216 May 1986. – BNES, London,1987. – Vol. 2. – pp. 85-90.270. Tosello A., Anzieu P., Camaro P,Y. Hexcan Failure Modelling for SubassemblyMeltdown in the SURFASS Code // Sodium Cooled Fast Reactor Safety: Proc. of anInternational Topical Meeting. – Obninsk, Russia, October 3−7, 1994. – Obninsk:SSC RF – IPPE, 1994. – Vol. 2. – pp. 2/221 – 2/227.271. Von Neumann J., Richtmyer R.D. A Method for the Numerical Calculation ofHydrodynamics Shocks // J. of Appl. Phys. – 1950. – Vol. 21. – No.