Model and real solutions are used to study and monitor the dissolution and extraction operations in the reprocessing of spent fuel AM(B) based on uranium oxide or uranium-molybdenum alloy (alloy OM-9, 9% molybdenum) with a sublayer of mass 12% comprised of Ca, Mg or the alloy Cu–Mg individually and in a batch with VVER-440. Batching of different types of spent fuel or their solutions should be done for in order to clarify them.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
Yu. V. Glagolenko, E. G. Dzekun, and S. I. Rovnyi, “Reprocessing of spent nuclear fuel on the RT-1 complex: history, problems and prospects,” Vopr. Radiats. Bezop. (PO Mayak, Ozersk), No. 2, 3–12 (1997).
M. Schmid, Analyse des Residus de Dissolution Primaires et Secondaires, These de l’Univer. Technique de Munich (1986).
M. Lloyd, “Instabilities and solids formation in LWR reprocessing solutions,” Trans. Am. Nucl. Soc., No. 24, 238–242 (1976).
B. Ya. Zilberman, “Development of the purex process for reprocessing high-burnup NPP fuel in a closed NFC from the standpoint of localization of long-lived radionuclides,” Radiokhim., 42, No. 1, 3–15 (2000).
P. I. Protsenko, O. N. Razumovskaya, and N. A. Brykova, Handbook of the Solubility of Nitrite and Nitrate Salt Systems, Khimiya, Leningrad (1971).
V. B. Shevchenko, N. S. Povitskii, and A. S. Solovkin, “Some particulars of reprocessing of spent irradiated fuel elements from the first nuclear power plant in the USSR,” in: Proc. 2nd Int. Conf. Peaceful Use of Atomic Energy, Geneva, 1958:Works of Soviet Scientists,Vol. 4, Chemistry of Radioelements, Atomizdat, Moscow (1959), pp. 28–33.
S. N. Kirillov, D. N. Kolupaev, M. V. Logunov, et al., “Possibility of various types SNF reprocessing at the PA Mayak exampled with AMB SNF,” in: Proc. Int. Conf. Atalante 2012 (2012), Paper F 057.
O. G. Darenskikh, V. M. Sandratskii, M. V. Tret’yakov, et al., Submersible Gamma-Absorption Probe, RF Patent No. 2334218, Byull. Izobret.. Polezn. Modeli, No. 26, Pt. IV, 782 (2008).
Yu. V. Baranov, N. D. Goletskii, F. E. Gofman, et al., “KVGK remote-service chamber conductivity meter,” in: Sci.-Techn. Conf. Handling Spent Nuclear Fuel in Russia, Polikor, Krasnoyarsk (2012), pp. 174–178.
B. Ya. Zilberman, A. N. Mashkin, A. K. Nardova, et al., Method for Reprocessing Spent NPP Fuel, RF Patent No. 2012075, Byull. Izobret., No. 8, 163 (1994).
I. V. Pyatnitskii and V. V. Sukhan, Masking and De-Masking in Analytical Chemistry, Nauka, Moscow (1990).
K. A. Bolshakov (ed.), Chemistry and Technology of Rare and Abundant Elements: Pt. III, Vys. Shkola, Moscow (1976).
N. D. Goletsky, L. G. Mashirov, B. Ya. Zilberman, et al., “Molybdenum extraction by solutions of tributyl phosphate from supersaturated nitric-acid solutions,” Radiokhim., 52, No. 2, 156–161 (2010).
W. Schulz, R. Burns, and E. Duke, “Nitric acid dissolution of uranium-molybdenum alloy reactor fuels,” Industr. Engin. Chem., Ser. Process Design and Development, 1, No. 2, 156–160 (1962).
Yu. S. Fedorov, B. Ya. Zilberman, N. D. Goletsky, et al., Method for Reprocessing Spent Nuclear Fuel from NPP, Patent RU 2454742, Byull. Izobret. (patenty), No. 18, Pt. II, 348 (2012).
L. V. Sytnik, B. Ya. Zilberman, I. V. Blazheva, et al., Method for Reprocessing Spent Nuclear Fuel from Nuclear Power Plants, Patent RU 2454741, ibid., pp. 347–348.
C. Bernard, P. Miquel, and M. Viala, “Advanced purex process for the new reprocessing plants in France and Japan,” in: Proc. 3rd Int. Conf. RECOD’91, Japan, Sendai (1991), Vol. 1, pp. 83–86.
B. Ya. Zilberman, Yu. S. Fedorov, E. N. Mishin, et al., Method for Reprocessing Spent Nuclear Fuel from Nuclear Power Plants, Patent RU 2132578, Byull. Izobret. (zayavki i patenty), No. 8, Pt. II, 445–446 (1999).
O. P. Anisimov, A. S. Aloi, V. I. Besnosyuk, et al., “Particulars of technology for handling high-burnup spent nuclear fuel from NPP,” in: 6th Int. Nucl. Forum, St. Petersburg, Sept. 26–30, 2011, pp. 180–190.
B. Ya. Zilberman,Yu. S. Fedorov, E. A. Puzikov, and I. V. Blazheva, Development of a Database and Adaptation of a Mathematical Model of the Purex Process to the Conditions for Reprocessing High-Burnup Spent Nuclear Fuel from NPP, Preprint Khlopin Radium Institute, No. RI-264 (2009).
B. Ya. Zilberman, V. A. Borovinskii, L. M. Ramazanov, et al., Method for Reductive Separation of Neptunium and Plutonium, Patent RU 2066489, Byull. Izobret., No. 25, 222 (1996).
M. V. Gladyshev, E. G. Dzekun, B. Ya. Zilberman, et al., “Single-cycle scheme for extractive reprocessing of spent fuel from NPP with addition sorption purification of uranium re-extract,” Vopr. Radiats. Bezop. (PO Mayak, Ozersk), No. 4, 27–32 (1998).
N. E. Mishina, A. A. Akhmatov, B. Ya. Zilberman, et al., “Solubility and co-precipitation of barium and strontium nitrates in HNO3 solutions and multicomponent systems,” Radiokhim., 52, No. 5, 442–447 (2010).
E. G. Dzekun, D. Kh. Kopeliovich, V. I. Rodionov, et al., “Evaporation procedures in spent fuel reprocessing,” in: Proc. Int. Conf. Nucl. Fuel Reproc. Waste Manag. RECOD’91, Sendai, Japan (1991), Vol. 1, pp. 433–436.
B. Ya. Zilberman, M. N. Makarychev-Mikhailov, D. N. Ryabkov, et al., Method of Evaporating High-Activity Raffinate from Reprocessing of Spent Nuclear Fuel from Nuclear Power Plants, RF Patent 2 303 306, Byull. Izobret. Polezn. Modeli, No. 20, Pt. II, 534 (2007).
B. Ya. Zilberman,V. F. Saprykin, and M. N. Makarychev-Mikhailov, “Management of high level wastes (HLW) from nuclear power plant spent fuel reprocessing in terms of tritium localization and nitric acid regeneration,” in: Proc. Int. Conf. Nucl. Waste Manag. and Environ. Remediation, Prague (1993); in: Am. Soc. Mech. Engineers, 1, 375–378 (1993).
B. Ya. Zilberman, S. Ya. Trukhanov, E. G. Dzekun, et al., Method of Processing High-Activity Nitric-Acid Raffinates, Patent RU 1739784, Byull. Izobret., No. 1, 200 (1994).
Author information
Authors and Affiliations
Additional information
Translated from Atomnaya Énergiya, Vol. 114, No. 5, pp. 276–285, May, 2013.
Rights and permissions
About this article
Cite this article
Kudinov, A.S., Goletsky, N.D., Zilberman, B.Y. et al. Batching of spent AMB nuclear fuel for reprocessing at the industrial association mayak. At Energy 114, 344–354 (2013). https://doi.org/10.1007/s10512-013-9722-y
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-013-9722-y