The issues of Np, Am, Cm recycling in a BZhSR molten-salt reactor with a fast neutron spectrum based on LiF–NaF–KF eutectic are examined. The results of a comparative analysis of the efficacy of transmutation for different BZhSR fuel compositions and core volume are reported. It is shown that BZhSR with an initial load of enriched uranium and Np, Am, Cm fl uorides makes it possible to transmute ~1 ton/yr Np, Am, Cm on average over 50 years of operation at 1650 MW(t). The advantage of the chosen arrangement is the capability of Np, Am, Cm replenishment without adding additional enriched uranium even after the first run with duration 300 EFPD.
Similar content being viewed by others
References
Status and Trends in Spent Fuel and Radioactive Waste Management, IAEA Nuclear Energy Ser. No. NW-T-1.14, IAEA, Vienna (2018).
Status of Minor Actinide Fuel Development, IAEA Nuclear Energy Ser. No. NF-T-4.6, IAEA, Vienna (2009).
E. O. Adam (ed.), White Book of Nuclear Power, NIKIET, Moscow (2001).
U. F. Sheremetyeva, N. D. Dyrda, V. A. Simonenko, et al., “VVER-type reactor in the uranium-plutonium fuel cycle,” Innovative Nuclear Technology. CNFC Technologies and Hydrogen Safety: Abstracts, Snezhinsk (2016), pp. 32–33.
Advanced Reactor Technology Options for Utilization and Transmutation of Actinides in Spent Nuclear Fuel, TECDOC-1626, IAEA, Vienna (2009).
A. A. Lizin, S. V. Tomilin, O. E. Gnevashov, et al., “Solubility of PuF3, AmF3, CeF3, NdF3 in LiF–NaF–KF melt,” At. Energ., 115, No. 1, 11–16 (2013).
A. A. Lizin, S. V. Tomilin, O. E. Gnevashov, et al., “UF4 and ThF4 solubility in the LiF–NaF–KF melt,” ibid., 20–22.
M. V. Volozhin, R.Ya. Zakirov, P. N. Mushnikov, et al., “CeF3 and PuF3 solubility in the LiF–NaF–KF melt,” ibid., 17–19.
L. I. Ponomarev, M. B. Seregin, A.P. Parshin, et al., “Salt choice for a molten-salt reactor,” ibid., 6–11.
A. M. Degtyarev and L. I. Ponomarev, “LiF–NaF–KF based molten-salt reactor with a fast neutron spectrum,” At. Energ., 112, No. 6, 367–368 (2012).
A. Degtyarev, A. Myasnikov, and L. Ponomarev, “Molten salt fast reactor with U–Pu fuel cycle,” Progr. Nucl. Energy, 82, 33–36 (2015).
A. M. Degtyarev, A. A. Myasnikov, O. E. Kolyaskin, et al., “Molten-salt subcritical reactor-burner of transplutonium isotopes,” At. Energ., 114, No. 4, 225–232 (2013).
V. V. Ignatiev, O. S. Feinberg, A. V. Zagnitko, et al., “Molten salt reactors: new opportunities, problems and solutions,” At. Energ., 112, No. 3, 135–143 (2012).
V. L. Blinkin and V. M. Novikov Molten Salt Nuclear Reactors, Atomizdat, Moscow (1978).
Ya. Z. Kandiev, A. A. Malakhov, E. V. Serova, and S. G. Spirina, “Evaluation of the effects of small perturbations in multivariate calculations using the PRIZMA-D code,” At. Energ., 99, No. 3, 203–210 (2005).
D. G. Modestov, RISK-2014: Code for Solving Problems of Nuclear Kinetics, Preprint VNIITF, No. 243 (2014).
A. Trkov, M. Herman, and D. A. Brown, ENDF-6 Formats Manual, Rep. BNL-90365-2009 Rev. 2 (2012).
I. Kh. Ganev, A. V. Lopatkin, and V. V. Orlov, “Homogeneous transmutation of Am, Cm, Np in the BREST reactor core,” At. Energ., 89, No. 5, 355–361 (2000).
L. I. Ponomarev, M. N. Belonogov, I. A. Volkov, et al., “Np, Am, Cm transmutation in different types of reactors,” At. Energ., 126, No. 3, 132–137 (2019).
Author information
Authors and Affiliations
Corresponding author
Additional information
L. I. Ponomarev is Deceased.
Translated from Atomnaya Énergiya, Vol. 126, No. 3, pp. 123–132, March, 2019.
Rights and permissions
About this article
Cite this article
Ponomarev, L.I., Belonogov, M.N., Volkov, I.A. et al. LiF–NaF–KF Eutectic Based Fast Molten-Salt Reactor as Np, Am, Cm Transmuter. At Energy 126, 139–149 (2019). https://doi.org/10.1007/s10512-019-00528-y
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-019-00528-y