EDN: MWOGJQ
Authors & Affiliations
Smykov V.B.1, Alekseev V.V.1, Legkikh K.G.1, Zhdanov V.P.1, Kovrezhkin N.V.2, Guch I.V.2, Nikitin E.M.3, Semenov D.A.3, Rybin A.N.3, Semin S.D.3, Ermakov A.I.3
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Obninsk Engineering Center NIKIMT Branch of “Research and Design Institute of Installation Technology – Atomstroy”, Obninsk, Russia
3 TVEL Fuel Company of Rosatom, Moscow, Russia
Smykov V.B.1 – Head of Department, Decommissioning Department, Cand. Sci. (Tech.).
Alekseev V.V.1 – Chief Researcher, Dr. Sci. (Tech.).
Legkikh K.G.1 – Head of Laboratory of Chemical-Engineering and Radiochemical Research. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga Region, 249033. Tel.: +7 (484) 399-70-00 (add. 88-03), e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Zhdanov V.P.1 – Chief Specialist, Decommissioning Department.
Kovrezhkin N.V.2 – Head of Department.
Guch I.V.2 – Head of Department.
Nikitin E.M.3 – Director of Decommissioning Programs.
Semenov D.A.3 – Head of Decommissioning Department for Scientific and Technical Documentation.
Rybin A.N.3 – Head of Group.
Semin S.D.3 – Head of Department.
Ermakov A.I.3 – Chief Expert, Cand. Sci. (Chem.).
Abstract
By the decision of the Board of the Ministry of Atomic Energy dated 05.03.1997 (announced by Order of the Minister No. 130), the BR-10 research reactor was designated as a technological testing ground for the implementation of the fast reactors with alkaline liquid metal coolants decommissioning program. To solve the problem of conditioning alkaline waste in IPPE JSC, it was proposed to use the dump granulated slag of the furnaces of the copper smelting plant of the Karabash combine, containing iron oxides FeO (35–38 %) and Fe2O3 (12 %), silicon SiO2 (34–36 %), aluminum Al2O3 (5–8 %), calcium CaO and magnesium MgO (6 to 10–15 % in total) are the main components of the slag, the impurities are ZnO oxides (2.0–2.5 %) and CuO (up to 0.5 %).
Experimental studies of the solid-phase technology (SPT) method were carried out on the stands MINERAL-3, MINERAL-30, MINERAL-50. The SPT technology is used for processing radioactive waste of alkaline liquid metal coolants on the BR-10 IR at the MAGMA-SPT module. The results indicate the prospects for the development of this method and the creation on its basis of an optimized technology for processing radioactive waste of alkaline liquid metal coolants.
The construction of pilot production of sufficient productivity on the basis of a fully functional sample of the MINERAL-100/150 series installation being created for its implementation in the decommissioning programs of reactor plants with alkaline liquid metal reactor plants BOR-60, BN-350, BN-600, with preliminary testing of optimized technology on a sample of the MINERAL-100/150 installation on the IR BR-10 of IPPE JSC.
Keywords
solid-phase oxidation, alkaline liquid metal coolant, MINERAL plant, fast reactors with sodium coolant, 137Cs isotope leaching rate
Article Text (PDF, in Russian)
References
- Smykov V.B. Problemy vyvoda iz ekspluatatsii bystrykh reaktorov i puti ikh resheniya na baze issledovatel'skogo reaktora BR-10 [Problems of Decommissioning Fast Reactors and Ways of their Solution on the Basis of the BR-10 Research Reactor]. Izvestiya vuzov. Yadernaya Energetika, 2022, no. 2, pp. 90–102. DOI: https://doi.org/10.26583/npe.2022.2.09.
- Smykov V.B., Kononyuk M.Kh., Lukyanov A.A., Bagdasarov Yu.E., Belinsky I.S., Kryuchkov E.A., Tymosh B.S., Kuzin V.V. Razrabotka tekhnologii pererabotki RAO shchelochnykh teplonositeley metodom tverdofaznogo okisleniya. Izbrannyye trudy FEI [Development of technology for processing RW alkaline coolants by solid phase oxidation. Selected works of IPPE]. Obninsk, FEI Publ., 2001. Pp. 64–67.
- Smykov V.B., Alekseev V.V., Lung K.G., Zhdanov V.P., Kovrezhkin N.V., Guch I.V., Nikitin E.M., Semenov D.A., Rybin A.N., Semin S.D., Ermakov A.I. Optimizatsiya tverdofaznoy tekhnologii pererabotki RAO shchelochnykh teplonositeley na polnomasshtabnom obraztse ustanovki MINERAL-100/150 [Optimization of solid-phase technology for processing RW alkaline coolants on a full-scale sample of the MINERAL-100/150 installation]. Sb. tezisov nauchno-tekhnicheskoy konferentsii “Teplofizicheskiye eksperimental'nyye i raschetno-teoreticheskiye issledovaniya v obosnovaniye kharakteristik i bezopasnosti yadernykh reaktorov (Teplofizika 2024)” [Proc. of the Scientific and Technical Conference “Thermophysical experimental and computational theoretical studies to substantiate the characteristics and safety of nuclear reactors (Thermophysics 2024)”]. Obninsk, AO “GNTS RF – FEI” Publ., 2024, pp. 47–48.
- Legkikh K.G., Smykov V.B. Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation. At Energy, 2024, vol. 137, pp. 129–135. DOI: https://doi.org/10.1007/s10512-025-01186-z.
- Smykov V.B., Kononyuk M.Kh., Lukyanov A.A., Bagdasarov Yu.E., Belinsky V.S., Borisov V.V., Kryuchkov E.A., Kuzin V.V., Poplavsky V.M., Kamaev A.A. Sposob pererabotki shchelochnogo metalla, zagryaznennogo radioaktivnymi primesyami, i ustroystvo dlya yego realizatsii [Method for Processing Alkali Metal Contaminated with Radioactive Impurities and Device for Its Implementation]. Patent RF No. 2200991, 2003.
- Legkikh K.G., Smykov V.B. Otrabotka tekhnologiy immobilizatsii natriyevogo teplonositelya na IR BR-10 i vozmozhnosti primeneniya tekhnologiy bezopasnogo obrashcheniya s natriyem 1-go kontura i yego nedreniruyemymi ostatkami v otdel'nom oborudovanii BN-350 [Development of sodium coolant immobilization technologies at BR-10 reactor and the possibility of using technologies for safe handling of primary circuit sodium and its undrained residues in separate BN-350 equipment]. Sb. dokladov otraslevoy nauchno-tekhnicheskoy konferentsii “Razvitiye tekhnologii reaktorov na bystrykh neytronakh s natriyevym teplonositelem (BN-2023)” [Proc. of the Industry Scientific and Technical Conference “Development of Fast Neutron Reactor Technology With Sodium Coolant (BN-2023)”]. Nizhny Novgorod, OKBM Afrikantov, 2023. Pp. 81–85.
- Smykov V.B., Zhurin A.V., Legkikh K.G., Alekseev V.V., Zhdanov V.P. Pererabotka teplonositelya pervogo i vtorogo konturov pri vyvode iz ekspluatatsii reaktora BN-350 [Reprocessing of Primary and Secondary Coolants During the BN-350 Reactor Decommissioning]. Izvestiya vuzov. Yadernaya Energetika, 2023, no. 3, pp. 164–169. DOI: https://doi.org/10.26583/npe.2023.3.16.
- Smykov V.B., Lung K.G., Trifanova E.M., Raskach O.V. Metod tverdofaznogo okisleniya otrabotavshego SHCHZHMT. Cootvetstviye kriteriyam priyemlemosti dlya zakhoroneniya [Method of solid-phase oxidation of spent sludge. compliance with the criteria of acceptability for burial]. Tezisy dokladov XVI Mezhdunarodnoy konferentsii “Bezopasnost' AES i podgotovka kadrov” [Proc. of the XVI International Conference “NPP Safety and Personnel Training”]. Obninsk, October 26–27, 2023, pp. 225–227.
- Smykov V.B., Legkikh K.G., Trifanova E.M., Grushicheva E.A. Opredeleniye sootvetstviya produkta tverdofaznogo okisleniya otrabotavshego natriyevogo teplonositelya kriteriyam priyemlemosti k dlitel'nomu khraneniyu [Determination of the conformity of the product of solid-phase oxidation of spent sodium coolant with the criteria of acceptability to long-term storage]. Sb. tezisov nauchno-tekhnicheskoy konferentsii “Teplofizicheskiye eksperimental'nyye i raschetno-teoreticheskiye issledovaniya v obosnovaniye kharakteristik i bezopasnosti yadernykh reaktorov (Teplofizika 2024)” [Proc. of the Scientific and Technical Conference “Thermophysical experimental and computational theoretical studies to substantiate the characteristics and safety of nuclear reactors (Thermophysics 2024)”]. Obninsk, AO “GNTS RF – FEI” Publ., pp. 49–50.
- Tazhibayeva I.L., Klepikov A.H., Romanenko O.G., Blynsky A.P. Regulyatornyye aspekty i praktika obrashcheniya s radioaktivnymi otkhodami v respublike Kazakhstan [Regulatory aspects and practice of radioactive waste management in the Republic of Kazakhstan]. Atomic Energy, 2024, vol. 137, issues 1–2, pp. 106–114.
- Tazhibaeva I.L., Pustobaev S.I., Zhantikin T.M. Handling of sodium coolants for the BN-350 fast neutron reactor. Almaty, Izd-vo Glory K ltd Publ., 2010. 320 p.
- Vasiliev I.I., Pleshchenkova L.K., Pugachev G.G., Rovneiko A.V. Ustanovka pererabotki natriyevogo teplonositelya reaktornoy ustanovki BN-350 [Sodium coolant processing unit of the BN reactor unit-350]. 1-ya Mezhdunarodnaya vystavka i konferentsiya “Atomnaya energetika i Promyshlennost'” KazAtomExpo
[1st International Exhibition and Conference “Nuclear Energy and Industry” KazAtomExpo. Astana Kazakhstan, May 19–21, 2010. Available at: https://www.slideserve.com/dorian-bird/350 (accessed 12.05.2025).
- Dolgikh V.P., Zabrodskaya S.V., Lebedeva O.M., Popov E.P., Smykov V.B. Otsenka stoimosti okonchatel'nogo zakhoroneniya radioaktivnykh otkhodov konditsionirovannogo raznymi sposobami natriya pervogo kontura bystrykh reaktorov [Estimation of the cost of the final disposal of radioactive waste from the first circuit of fast reactors/ cables conditioned by various methods of sodium]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology Series: Nuclear and Reactor Constants, 2020, issue 2, pp. 96–103.
- Legkikh K.G., Smykov V.B. Otrabotka tekhnologiy immobilizatsii radioaktivnogo SHCHZHMT (natriy, natriy – kaliy) na IR BR-10 i vozmozhnosti ikh primeneniya dlya bezopasnogo obrashcheniya s SHCHZHMT pervogo kontura i yego nedreniruyemymi ostatkami v otdel'nom oborudovanii RU tipa BN [Development of technologies for the immobilization of radioactive HCMT (sodium, sodium – potassium) on the BR-10 ion and the possibility of their use for the safe handling of primary-circuit HCMT and its non-drainable residues in separate BN-type RC equipment]. Sb. tezisov XII Vserossiyskoy molodezhnoy konferentsii “Nauchnyye issledovaniya i tekhnologicheskiye razrabotki dlya obespecheniya razvitiya yadernykh tekhnologiy novogo pokoleniya” [Proc. of the XII All-Russian Youth Conference “Scientific Research and Technological Developments to Ensure the Development of New Generation Nuclear Technologies”]. Dimitrovgrad, 2025, pp. 14–16.
- Tykleeva K.V., Ulyakhin S.M., Grabezhnoy V.N., Zabrodskaya S.V., Legkikh K.G., Smykov V.B. Raschetnoye modelirovaniye ustroystva dlya utilizatsii natriya bystrykh reaktorov [Computational modeling of a device for the utilization of sodium in fast reactors]. Sb. tezisov nauchno-tekhnicheskoy konferentsii “Neytronno-fizicheskiye problemy atomnoy energetiki (Neytronika-2024)” [Proc. of the Scientific and Technical Conference “Neutron Physics problems of nuclear energy (Neutronics-2024)”]. Obninsk, IPPE, 2024, pp. 46–47.
UDC 621.181.6
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