The developers of fast sodium reactors are studying nitride fuel for use soon after oxide fuel. Together with a significant increase in the total BR, dense nitride fuel also permits improving a characteristic that is important for reactor safety – significantly decreasing the reactivity excess on burnup. The results of physical calculations of a BN-1200 reactor core, using fuel elements with gas or sodium sublayer on nitride fuel, are presented.
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References
V. I. Rachkov,V. M. Poplavskii, A. M. Tsibulya, et al., “Concept for a prospective power-generating unit with a sodium-cooled fast reactor BN-1200,” At. Énerg., 108, No. 4, 201–206 (2010).
V. M. Poplavskii, A. M. Tsibulya, Yu. S. Khomyakov, et al., “Core and fuel cycle for a prospective sodium-cooled fast reactor,” ibid, pp. 206–211.
V. M. Poplavskii, V. I. Matveev (ed.), V. A. Rogov, et al., Physical and Engineering Problems of Increasing Safety and Effectiveness of Burning Actinides in a Prospective Fast Reactor, FEI, Obninsk (2001).
V. A. Eliseev, I. V. Malyshev, and V. I. Matveev, Cores Fueled with Nitride Fuel in the Prospective Sodium-Cooled Fast Reactor of the Type BN-1200, Preprint FEI-3203 (2011).
H. Blank, “Specification and characterization of dense LMFBR fuels,” J. Nucl. Mater., 153, 7–13 (1988).
B. D. Rogozkin, N. M. Stepennova,Yu. E. Fedorov, et al., “Results of tests of mixed mononitride fuel (45% PuN + 55% UN and 60% PuN + 40% UN) in the BOR-60 reactor for burnup 12% h.a.,” At. Énerg., 110, No. 6, 332–346 (2010).
L. M. Zaboudko and L. I. Moseev, Investigation of the Thermal Dissociation of Uranium Nitride and Mixed Uranium-Plutonium Nitride, Preprint FEI-3006 (2002).
A. A. Bauer, P. Cybulskis, and J. L. Green, “Mixed-nitride performance in EBR II,” in: Proc. Int. Meeting on Advanced LMFBR Fuels, Tucson, Oct. 10–13, 1977, pp. 299–312.
A. S. Seregin, “Annotation of the TRIGEX program for a low-group calculation of a reactor in a three-dimensional hexagonal geometry,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 4(33), 59–60 (1983).
G. N. Manturov, M. N. Nikolaev, and A. M. Tsibulya, “BNAB-93 system of group constants. Pt. 1: Nuclear constants for calculating neutron and photon radiation fields,” Vopr. At. Nauki Tekhn. Ser. Yad. Konst., No. 1, 59–98 (1996).
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Translated from Atomnaya Énergiya, Vol. 114, No. 5, pp. 266–271, May, 2013.
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Eliseev, V.A., Zaboudko, L.M., Malysheva, I.V. et al. Nitride Fuel for a Prospective BN-1200 Type Fast Sodium Reactor. At Energy 114, 331–336 (2013). https://doi.org/10.1007/s10512-013-9720-0
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DOI: https://doi.org/10.1007/s10512-013-9720-0