Published date: May 06 2018

Journal Title: KnE Materials Science

Issue title: 15th International School-Conference "New Materials – Materials of Innovative Energy" (MIE)

Pages: 32–43

DOI: 10.18502/kms.v4i1.2125

M Ternovykh

I SaldikovISSaldikov@mephi.ru

G Tikhomirov

A Gerasimov

The purpose of neutron-physical calculations is typically isotopic composition of the fuel elements. However, in solving materials science problems related to nuclear fuel, researchers are usually interested in elemental composition of the fuel pellets, because the chemical and thermal physic properties are the same for different
isotopes of one chemical element. Nevertheless, for modeling of the elemental composition one should perform calculation of the isotopic composition and carry out the summation over all isotopes of a given chemical element. The development of computational tools allows the use of improved methods and codes, which held the consequent solution of tasks of heat conduction, neutron transport, and kinetics of
nuclides transformation. Thus the calculations take into account the dependence of the thermal conductivity from the changing isotopic composition and fuel burnup. This allows to perform neutron-physical and thermal-physical calculations of the reactor with detailed temperature distribution, taking into account temperature dependence of thermal conductivity and other characteristics. This approach was applied to calculations of the fuel pellet of the VVER type reactor and calculation of its elemental composition.

Keywords: materials science, elemental composition, fuel pellet.

[1] Kurina I.S., Popov V.V., Rumyantsev V.N. Investigation of the properties of modified uranium dioxide. Atomic Energy. 2006. V. 101. No 5. pp. 802-808.


[2] Fink J.K., Chazanov M.G, Leibovitz L.J. Thermophysical properties of uranium dioxide. J. Nucl. Mater. 1981, V. 102, pp.17-25.


[3] Likhansky V. V., Aliev T. N., Evdokimov I. A. Modeling of the behavior of UO2 fuel for operating conditions in light water reactors. Nuclear physics and engineering, 2010, V. 1, No 2, pp. 104–122.


[4] Alyushin V.M., Baranov V.G., Kudryashov N.A., et al. Numerical modeling of the temperature distribution in a VVER fuel element. Atomic Energy, 2010, V.108, pp.184-193.


[5] J. Piron, B. Bordin, G. Geoffroy, et al., Proc. of the International Topical Meeting on Light Water Reactor Fuel Performance. Florida, USA, April 17-21, 321-327 (1994)


[6] A. Shcheglov, V. Sidorenko, V. Proselkov, S. Boi’shagin. Atomic Energy, 1996, V.80, pp.222-224


[7] Saldikov I., Tikhomirov G., Ternovykh M., and Gerasimov A. Computation methods and techniques for solution of coupled multiohysics roblems in precision calculations of VVER type reactors. Proceedings of the VII International Conference on Computational Methods for Coupled Problems in Science and Engineering COUPLED PROBLEMS 2017. Rhodes Islad, Greece, June 12 - 14, 2017. P. 1031-1041.


[8] G.Tikhomirov, I.Saldikov, M.Ternovykh, A.Gerasimov. Consistent neutron-physical and thermal-physical calculations of fuel rods of VVER type reactors. EPJ Web of Conferences 153, 07036 (2017). https://doi.org/10.1051/epjconf/201715307036


[9] F.De Lillo, F.Cecconi, G.Lacorata, A.Vulpiani, EPL, 84 (2008) V. Davidenko, V. Tsibulsky. Proc. of the Int. Conf. on the Physics of Nuclear Science and Technology, Oct. 5–8, Long Island, New York, 1755-1760 (1998).


[10] K. Childs, HEATING 7.0 User’s Manual, K/CSD/INF/90-32 (Martin Marietta Energy Systems, Inc., July 1990).


[11] SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Version 5, ORNL/TM-2005/39, I-III, ORNL (2005).


[12] Andrianov A.N., Baranov V.G., Tikhomirov G.V., Khlunov A.V. Simulation of neutronphysical processes in the surface layer of a fuel kernel. Atomic Energy. 2008. Т. 104. № 6. С. 463-469.


[13] Baranov V.G., Ternovykh M.Yu., Tikhomirov G.V., Khlunov A.V. Simulation of nuclearphysical processes in the surface layer of a fuel kernel with a consumable absorber. Atomic Energy. 2008. Т. 105. № 6. С. 391-396.


[14] I S Saldikov, M Yu Ternovykh, P A Fomichenko, A S Gerasimov, The scheme for evaluation of isotopic composition of fast reactor core in closed nuclear fuel cycle, IOP Conf. Series: Journal of Physics: Conference Series, Volume 781 (2017), Number 1