The results of neutron-physical studies of a fast reactor with uranium-plutonium-zirconium metallic fuel at the initial state of the transition to a closed cycle are presented. The characteristics of plutonium breeding and accumulation in the fuel-assembly lattices with uranium-dioxide fuel mixed with oxide and metallic fuel are presented. Variants of one-time fueling of the BN-800 core with metallic fuel with low reactivity excess, average burnup 80 MW·days/kg and plutonium accumulation coefficient 1.05–1.07 are examined.
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References
D. Crawford, D. Porter, and S. Hayes, “Fuel for sodium cooled fast reactors – US perspective,” J. Nucl. Mater., 371, 202–231 (2007).
O. D. Kazachkovskii,V. A. Eliseev,V. I. Matveev, and A. M. Tsibulya, “Prospects for using mixed oxide fuel in sodium-cooled fast reactors,” At. Énerg., 96, No. 5, 361–366 (2004).
Voon H. Chang, “Technical rationale for metal fuel in fast reactor,” Nucl. Eng. Technol., 39, No. 3, 161–170 (2007).
Baldev Raj, “Status of sodium cooled fast reactors with closed fuel cycle in India,” in: Int. Congr. on Advances in Nuclear Power Plants ICAPP’07, Nice, France, May 15–18, 2007, Paper No. 7593.
I. V. Vaganov, G. I. Gadzhiev, N. S. Kosulin, and V. N. Syuzyov, “Results of tests and postirradiation examinations of fuel assemblies UPC-1 with metal U–Pu–Zr fuel,” in: Proc. 6th Conf. on Reactor Material Science, Dimitrovgrad, Russia (2000), Vol. 2, pp. 23–25.
A. A. Maershin,V. A.Tyskanov, G. I. Gadzhiev, et al., “Experience in testing advanced fuel compositions in BOR-60,” At. Énerg., 91, No. 5, 385–389 (2001).
E. F. Mitenkova, N. V. Novikov, G. I. Gadzhiev, and V. N. Syuzyov, “Studies of metal U–Pu–Zr fuel in BOR-60 reactor with focus on its use in high power sodium fast reactors,” in: Proc. PHYSOR’2010, May, 2010, CD-ROM No. 700356.
F. M. Mitenkov, R. A. Peskov, and E. F. Mitenkova, “Neutron-physical characteristics and fuel utilization in a sodium cooled fast reactor and high density fuel at the initial stage of the transition to a closed cycle,” At. Énerg., 106, No. 1, 8–15 (2009).
E. F. Mitenkova and N. V. Novikov, “Particularities of neutron-physical calculations of sodium-cooled fast reactors with mixed oxide fuel,” At. Énerg., 109, No. 5, 253–262 (2010).
F. M. Mitenkov, R. A. Peskov, and E. F. Mitenkova, “Core optimization of a sodium-cooled fast reactor with oxide fuel and improvement of fuel utilization with adoption of a closed fuel cycle,” At. Énerg., 104, No. 2, 94–99 (2008).
E. F. Mitenkova and E. V. Solovieva, “Description of the VAR-GM module for generating computational files in multivariant calculations MCNP–MONTEBURNS–ORIGEN for varying the geometric and materials parameters of a reactor core,” Preprint No. IBRAE-2011-06, IBRAE (2011).
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Translated from Atomnaya Énergiya, Vol. 113, No. 2, pp. 73–79, August, 2012.
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Mitenkov, F.M., Peskov, R.A., Mitenkova, E.F. et al. Analysis of BN-800 fast reactor in an open fuel cycle with metallic fuel at the initial stage of the transition to a closed cycle. At Energy 113, 87–93 (2012). https://doi.org/10.1007/s10512-012-9599-1
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DOI: https://doi.org/10.1007/s10512-012-9599-1