Comparison of Simple Design of Sodium and Lead Cooled Fast Reactor Cores

Piotr Mazgaj, Piotr Darnowski, Sebastian Gurgacz, Maciej Lipka, Karolina Dziubanii


Abstract The purpose of this report was to present the results of a numerical simulation of thermal hydraulics processes in the liquid metal cooled fast reactor core, combined with the simple neutron population computing for infinite pin cell lattice. Two types of the coolant have been studied: liquid sodium and the liquid lead, with all requirements regarded to safety conditions. Temperature distributions along the cooling channel and distributions in radial direction have been prepared and in the next step the criticality calculations using MCNP Monte Carlo code for MOX fuel have been conducted.


lead fast reactor; sodium fast reactor; pin design; MCNP

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Bunn, M., Fetter, S., Holdren, J., van der Zwaan, B., 2005. The economics of reprocessing versus direct disposal of spent nuclear fuel. Nuclear Technology 150.

Buongiorno, J., Larson, C., Czerwinski, K., 2003. Speciation of polonium re- leased from molten lead bismuth. Radiochimica Acta 91 (3), 153–158.

Cheon, J. S., Lee, C., Lee, B. O., Raison, J., Mizuno, T., Delage, F., Carmack, J., 2009. Sodium fast reactor evaluation: Core materials. Journal of Nuclear Materials (392), 324–330.

Fanning, T., 2007. Sodium as a fast reactor coolant. Tech. rep., U.S. Department of Energy, U.S. Nuclear Regulatory Commission, Topical Seminar Series on Sodium Fast Reactors.

Goorley, T., 2004. Criticality calculations with MCNP5: A primer. Tech. Rep. LA-UR-04-0294, Los Alamos National Laboratories X-5.

IAEA, 2012a. International status and prospects for nuclear power 2012. Tech. rep., IAEA.

IAEA, 2012b. Uranium 2011: Resources, Production and Demand. A Joint Report by the OECD Nuclear Energy Agency and the International Atomic Energy Agency.

Jimenez, D., Lopez, D., Mazgaj, P., 2009. of a sub-critical reactor for transmu- tation of higher actinides. Tech. rep., Department of Reactor Physics, Royal Institute of Technology, Stockholm.

Kiełkiewicz, M., 1987. Teoria Reaktorów Jądrowych. Oficyna Wydawnicza Po- litechniki Warszawskiej.

Lipinski, P., Swirski, K. (Eds.), 2012. Towards Modern Collaborative Knowledge Sharing Systems. Springer.

Mazgaj, P., 2010. Conceptual neutronic design of a 300 MWth lead fast reactor core. Master’s thesis, Warsaw University of Technology.

Pfrang, W., Struwe, D., 2007. Assessment of Correlations for Heat Transfer to the Coolant for Heavy Liquid Metal Cooled Core Designs. Forschungszentrum Karlsruhe Gmbh.

SNETP, 2010. Esnii concept paper. Tech. rep., Sustainable Nuclear Energy Technology Platform,

Sobolev, V., Malambu, E., Abderrahim, H. A., 2009. Design of a fuel element for a lead-cooled fast reactor. Journal of Nuclear Materials (385), 392–399.

Todreas, N., Kazimi, M. S., 1990. Nuclear Systems: Vol. I, Thermal Hydraulic Fundamentals. Taylor & Francis.

Tucek, K., 2004. Neutronic and burnup studies of accelerator-driven systems dedicated to nuclear waste transmutation. Ph.D. thesis, Royal Institute of Technology, Stockholm.

Tucek, K., Carlsson, J., Wider, H., 2006. Comparison of sodium and lead-cooled fasr reactors reagarding physics aspects, svere safety and economical issues. Nuclear Engineering and Design (236), 1589–1598.

USGS, 2012. Mineral commodity summaries 2012. Tech. rep., U.S. Department of the Interior, U.S Geological Survey.

Wallenius, J., 2010. Transmutation of nuclear waste. Royal University of Technology, Stockholm,

Waltar, A., Reynolds, A., 1981. Fast Breeder Reactors. Pergamon Press.

Williams, R., Graves, R., McElroy, D., 1984. Thermal and electrical conductivi- ties of an improved 9 Cr-1 Mo steel from 360 to 1000 K. International Journal of Thermophysics 5 (3), 301–313.

Zhang, H., Zhao, H., Mousseau, V., do Szilard, R., 2009. Design considerations for economically competitive sodium cooled fast reactors. In: ICAPP.

Zrodnikov, A., Toshinsky, G., Komlev, O., Dragunov, Y., Stepanow, V., Klimov, N., Generalov, V., Kopytov, I., Krushelnitsky, V., 2008. Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors. Progress in Energy 50 (2-6), 170–178.


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