Preliminary analysis of the possibility of using REMIX fuel in VVER-1200 reactors of the Belarusian NPP
https://doi.org/10.29235/1561-8358-2022-67-1-57-64
Abstract
The transition from conventional uranium to regenerated fuel, which uses reprocessed spent fuel and enriched natural uranium, improves fuel efficiency and reduces the amount of spent nuclear fuel (SNF). Based on the analysis of published materials concerning mainly the fuel cycles of the VVER-1000 reactor, it was concluded that the most suitable in the conditions of the Republic of Belarus is the use of REMIX fuel. To confirm this conclusion in relation to the VVER-1200 reactors of the Belarusian NPP, computational studies were carried out within the framework of the State program “Scienceintensive technologies and equipment” for 2021–2025, subprogram 3 “Scientific support for the effective and safe operation of the Belarusian nuclear power plant and promising directions for the development of nuclear energy”. The characteristics of a 12-month fuel cycle with multiple recycling (reuse of fuel) according to the REMIX technology with 19.75 % enrichment of added uranium and maintaining the design capacity and duration of the campaign have been obtained. The share of SNF that is not returned to the reactor is 12.8 % (for a cycle with uranium fuel – 100 %); the fraction of waste intended for disposal or long-term storage, respectively, decreases by 8 times, and the specific consumption of natural uranium is reduced from 202 g/(MW·day) for uranium fuel to 159 g/(MW·day) for REMIX fuel. The results obtained can be taken into account when developing a fuel use strategy at the Belarusian NPP.
About the Authors
V. T. KazazyanBelarus
Vagan T. Kazazyan – Ph. D. (Engineering), Associate Professor, Head of Laboratory
47/17, Prilesye village, 223063, Lugovoslobodskaya village, Minsk District, Minsk Region
A. P. Malykhin
Belarus
Aliy P. Malykhin – Ph. D. (Engineering), Associate Professor, Leading Researcher
47/17, Prilesye village, 223063, Lugovoslobodskaya village, Minsk District, Minsk Region
E. F. Vaitsetskaya
Belarus
Elena F. Vaitsetskaya – Researcher of the Laboratory of Neutron Physics
47/17, Prilesye village, 223063, Lugovoslobodskaya village, Minsk District, Minsk Region
N. M. Dneprovskaya
Belarus
Nina M. Dneprovskaya – Researcher at the Laboratory of Neutron Physics
47/17, Prilesye village, 223063, Lugovoslobodskaya village, Minsk District, Minsk Region
I. E. Rubin
Belarus
Isaak E. Rubin – Senior Researcher at the Laboratory of Neutron Physics
47/17, Prilesye village, 223063, Lugovoslobodskaya village, Minsk District, Minsk Region
N. A. Tetereva
Belarus
Natalia A. Tetereva – Researcher at the Laboratory of Neutron Physics
47/17, Prilesye village, 223063, Lugovoslobodskaya village, Minsk District, Minsk Region
References
1. Adamov E.O., Mochalov Yu. S., Rachkov V.I. Spent Nuclear Fuel Reprocessing and Nuclear Materials Recycling in Two-Component Nuclear Energy. Atomic Energy, 2021, vol. 130, no. 1, pp. 29–35. https://doi.org/10.1007/s10512-021-00769-w
2. Matveenko A.V., Kharitonov V. V., Pavlov Yu. G., Ul’yanin Yu. A. Competitiveness Assessment of Regenerated Uranium-Plutonium Remix Fuel in Thermal Reactors. Atomic Energy, 2021, vol. 130, no. 1, pp. 57–62. http://doi.org/10.1007/s10512-021-00774-z
3. Kuz’min A. V., Kazazyan V.T., Kuz’mina N.D., Malykhin A.P., Kovalevich V. G. Analysis of promising directions for the use of reprocessed uranium and plutonium in the fuel cycle of the BelNPP. Energeticheskaya strategiya [Energy Strategy], 2020, no. 2 (74), pp. 34–38 (in Russian).
4. Proselkov V.N., Aleshin S.S., Popov S.G., Sidorenko V.D., Slavyagin P.D., Tataurov A.L., Milovanov O.V., Mikheev E.N., Anan’ev Yu.A., Pytkin Yu.N., Pimenov Yu.V. Analysis of the Possibility of Using Fuel Based on Reclaimed Uranium in VVÉR Reactors. Atomic Energy, 2003, vol. 95, no. 6, pp. 829–834. http://doi.org/10.1023/b:aten.0000018995.09337.b5
5. Fedorov Yu. S., Bibichev B.A., Zil’berman B.Ya., Kudryavtsev E. G. Use of regenerated uranium and plutonium in thermal reactors. Atomnaya energiya [Atomic Energy], 2005, vol. 99, iss. 2, pp. 136–141 (in Russian).
6. Maslennikov I.A., Fedorov Yu. S., Shadrin A.Yu., Zil’berman B.Ya., Babain V. A., Bibichev B. A. Processing of irradiated fuel: new requirements and innovative approaches. Bezopasnost’ okruzhayushchei sredy [Environmental Safety], 2010, no. 1, pp. 90–93 (in Russian).
7. Makovskii S.V., Kuryndin A.V., Kirkin A. M., Sinegribov S.V. Analysis of the radiation and thermophysical characteristics of the spent REMIX fuel. Voprosy atomnoi nauki i tekhniki. Ser. Yaderno-reaktornye konstanty [Questions of Atomic Science and Technology. Ser. Nuclear Reactor Constants], 2017, iss. 4, pp. 134–143 (in Russian).
8. Fedorov M. I., D’yachenko A.I., Balagurov N.A., Artisyuk V.V. Formation of supplies of protected nuclear fuel based on reprocessed uranium for recipient countries of Russian nuclear technologies. Izvestiya vuzov. Yadernaya energetika [News of Higher Educational Institutions. Nuclear Energy], 2015, no. 1, pp. 128–135 (in Russian).
9. Pavlovichev A.M., Pavlov V.I., Semchenkov Yu. M., Kudryavtsev E.G., Fedorov Yu. S., Bibichev E.A. Neutronphysical characteristics of a VVÉR core with 100% load of reprocessed uranium and plutonium fuel. Atomic Energy, 2006, vol. 101, no. 6, pp. 863–868. http://dx.doi.org/10.1007/s10512-006-0182-5
10. Dekusar V. M., Kagramanyan V. S., Kalashnikov A.G., Kapranova E. N., Korobitsyn V. E., Puzakov A. Yu. Analysis of the characteristics of REMIX fuel with multiple recycle in VVER reactors. Izvestiya vuzov. Yadernaya energetika [News of Higher Educational Institutions. Nuclear Energy], 2013, no. 4, pp. 109–117 (in Russian).
11. Postovarova D.V., Kovalev N. V., Onegin M. S., Bibichev B. A. Radiation characteristics of REMIX fuel during multiple recycle in VVER-1000 reactors. Izvestiya vuzov. Yadernaya energetika [News of Higher Educational Institutions. Nuclear Energy], 2016, no. 1, pp. 100–110 (in Russian).