The basic regularities in the transmutation Np, Am, and Cm in a molten-salt burner reactor are examined on the basis of the results of neutronic calculations of an idealized infinite homogeneous medium consisting of metal halogenides with low atomic mass. It is shown that an optimal equilibrium regime for the transmutation of Np, Am, and Cm in a molten-salt burner reactor could exist. In this regime, makeup fuel consists of the actinides of the spent nuclear fuel of power reactors; only fission products are extracted. The optimal regime obtains at a definite concentration of actinide fluorides in the fuel composition. The concentration is determined by the size of the reactor and depends relatively weakly on the composition of the spent nuclear fuel, type of salt solvent, and frequency of fuel reprocessing during a run.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
A. M. Degtyarev, A. A. Myasnikov, O. E. Kolyaskin, et al., “Molten-Salt subcritical transplutonium actinide incinerator,” At. Energ., No. 4, 183–188 (2013); Atomic Energy, 114, No. 4, 225–232 (2013).
V. Ignatiev and O. Feynberg, “Progress in development of Li, Be, Na/F molten-salt actinide recycler and transmuter concept,” in: Int. Congr. on Advanced in Nuclear Power Plants, France, May 13–18, 2007, Paper 7548.
V. Ignatiev, O. Feynberg, I. Gnidoi, et al., “Molten salt actinide recycler and transforming system without and with Th–U support. Fuel cycle fl exibility and key material properties,” Ann. Nucl. Energy, 64, 408–420 (2014).
Status of Minor Actinide Fuel Development, IAEA Atomic Energy Ser. No. NF-T-4.6, IAEA, Vienna (2009).
Advanced Reactor Technology Options for Utilization and Transmutation Actinides in Spent Nuclear Fuel, TECDOC- 1626, IAEA, Vienna (2009), pp. 170–301.
L. I. Ponomarev, M. N. Belonogov, I. A. Volkov, et al., “LiF–NaF– KF eutectic based fast molten-salt reactor as Np, Am, Cm transmuter,” At. Energ., 126, No. 3, 123–132 (2019); Atomic Energy, 126, No. 3, 139–149 (2019).
J. Vergnes and D. Lecarpentier, “The AMSTER concept (actinides molten salt transmuter),” Nucl. Eng. Design, 216, 43–67 (2002).
R. Hill, T. Taiwo, J. Stillman, et al., “Multiple TIER fuel cycle studies for waste transmutation,” in: Proc. ICONE-10: 10th Int. Conf. on Nuclear Engineering, USA (2002), Paper 22575.
J. Uhlíř and V. Juříček, “Current Czech R&D in thorium Molten Salt Reactor (MSR) technology and future directions,” in: Proc. ThEC13 Conf. Thorium Energy for the World, CERN, Geneva, Switzerland (2013), pp. 139–144.
5th National Report of the Russian Federation on the Fulfillment of Obligations Arising from the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Moscow (2017), www.gosnadzor.ru/activity/international/national%20 reports/Russian_Federation_rus.pdf, acc. March 4, 2020.
L. I. Ponomarev, M. N. Belonogov, I. A. Volkov, et al., “Transmutation of Np, Am, Cm in different types of reactors,” At. Energ., 126, No. 3, 132–137 (2019); Atomic Energy, 126, No. 3, 150–155 (2019).
Ya. Z. Kandiev, A. A. Malakhov, E. V. Serova, and S. G. Spirina, “Evaluation of the effect of small perturbations in multivariate calculations using the Prizma-D Computer Program,” Atomic Energy, 99, No. 3, 203–210 (2005); Atomic Energy, 99, No. 3, 639–645 (2005).
D. G. Modestov, Computer Program for Solving the Problems of Nuclear Kinetics RISK-2014, Preprint No. 243, RFNC–VNIITF (2014).
A. Trkov, M. Herman, and D. A. Browm, ENDF-6 Formats Manual, Rep. BNL-90365-2009 Rev. 2 (2012).
V. V. Ignatiev, O. S. Feinberg, A. V. Zagnitko, et al., “Molten-salt reactors: new possibilities, problems and solutions,” At. Energ., 112, No. 3, 135–143 (2012); Atomic Energy, 112, No. 3, 157–165 (2012).
A. A. Lizin and S. V. Tomilin, “Selection of carrier salt for molten salt fast reactor,” in:. Abstr. Int. Conf. on Fast Reactors and Related Fuel Cycles. Next Generation Nuclear Systems for Sustainable Development, Russia, June 26–29, 2017, Paper IAEA-CN245-394.
L. I. Ponomarev, M. B. Seregin, A. P. Parshin, et al., “Fuel salt for the molten-salt reactor,” At. Energ., 115, No. 1, 6– 11 (2013); Atomic Energy, 115, No. 1, 5– 10 (2013).
A. A. Lizin, S. V. Tomilin, O. E. Gnevashov, et al., “PuF3, AmF3, CeF3, and NdF3 solubility in LiF–NaF–KF melt,” At. Energ., 115, No. 1, 11–16 (2013); Atomic Energy, 115, No. 1, 11–17 (2013).
E. R. Petrov, B. A. Bibichev, V. D. Domkin, et al., “The results of measurements of the radionuclide composition and burnup of high-burnup VVER-1000 fuel by destructive methods,” Radiokhimiya, 54, No. 4, 348–351 (2012); Radiochemistry, 54, No. 4, 379–382 (2012).
E. R. Petrov, B. A. Bibichev, V. D. Domkin, et al., “Results of measurements of the content of actinide, neodymium, and cerium isotopes and the burnup in a sample of high-burnup VVER-100 fuel by destructive methods,” Radiokhimiya, 55, No. 5, 437–439 (2013); Radiochemistry, 55, No. 5, 517–520 (2013).
M. Sohal, M. Ebner, P. Sabharwall, et al, Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties, INL/EXT-10-18297 (2010).
Author information
Authors and Affiliations
Corresponding author
Additional information
Translated from Atomnaya Énergiya, Vol. 128, No. 3, pp. 135–142, March, 2020
Rights and permissions
About this article
Cite this article
Belonogov, M.N., Volkov, I.A., Modestov, D.G. et al. On an Optimal Minor-Actinide Transmutation Regime in a Molten-Salt Reactor. At Energy 128, 143–150 (2020). https://doi.org/10.1007/s10512-020-00665-9
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-020-00665-9