Egorov M.Yu., Isanov K.A.
Saint-Petersburg State University of Aerospace Instrumentation, Saint Petersburg, Russia
The concept of a heavy-water thorium-uranium breeder reactor on thermal neutrons is considered. A neutron-physical calculation is carried out for a model of a fuel assembly of infinite dimensions of a conventional design and with a grid of displacers. A one-dimensional diffusion calculation method has been implemented in a twenty-six group approximation, constants have been prepared taking into account heterogeneous resonance effects, using the NJOY software package. The intermediate results are compared with the Serpent-2 precision software package, which is based on the Monte-Carlo method. The effective multiplication coefficient, the reproduction coefficient, as well as the operating spectrum in the reactor are calculated. Neutron fluxes and their corresponding thermal capacities are determined for the given sizes of the core. The nuclide dynamics is calculated for neutron fluxes normalized to the corresponding power levels. The change in the effective multiplication coefficient during the campaign for different levels of neutron power is determined. The protactinium effect characteristic of the thorium-uranium cycle with an increased reproduction coefficient is analyzed. The relationship between the protactinium effect and the neutron power level has been established and analyzed. The paper considers the general concept of spectral regulation. Possible methods of spectral regulation implementation are analyzed. The optimal method of introducing a grid of displacers has been established. The multiplication coefficient is calculated at the beginning of the campaign with the grid of displacers introduced to the full depth. The total compensating capacity of the displacer grid is determined. The integral compensating ability from the depth of immersion of the displacer grid into the core is determined. Based on the integral compensating ability of the displacer grid, the rate of lattice rise during the campaign is determined by the calculated equality of the reactivity increment due to burnout and release due to lattice rise. The multiplication coefficients were recalculated during the campaign in cases with spectral maneuvering. The effects of increasing the duration of the campaign are determined. The dependence of the effect of increasing the duration of the campaign with spectral regulation on the neutron power is estimated.
1. Uranium 2020: Resources, Production and Demand. Nuclear Energy Agency, 2020. 484 p.
2. Zverev D.L., Samoilov O.B., Romanov A.I., Panov V.A., Fal’kov A.A., Sholin E.V., Zotov S.A. Fuel for VVER and PWR: current status and prospects. Atomic Energy, 2020, vol. 129, issue 2, pp. 51–53.
3. Blank M.O., Egorova O.V., Liventsova N.V., Liventsov S.N., Schmidt O.V. Mathematical model of carbothermal synthesis mixed nitride uranium-plutonium fuel. Atomic Energy, 2021, vol. 129, issue 6, pp. 331–336.
4. Goryunov A.G., Egorova O.V., Kozin K.A., Liventsov S.N., Liventsova N.V., Shmidt O.V. Optimization and Diagnostics Code for Technological Processes: Radiochemical Production Simulator. Atomic Energy, 2018, vol. 124, issue 5, pp. 321–325.
5. Calculation of the Isotopic Composition, Cross Sections and Fluxes for a Typical PWR-Cell Loaded mith (PU-Th) O2-Fuel, as a Function о f the Fuel Burnup. International Atomic Energy Agency, 1996. 192 p.
6. Marshalkin V.Ye., Povyshev V.M. Breeding of 233U in the Thorium–Uranium Fuel Cycle in VVER Reactors Using Heavy Water. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2015, vol. 78, issue 11, pp. 1274–1286.
7. Marshalkin V.Ye., Povyshev V.M. Utilization of Non-Weapon Plutonium and Highenriched Uranium with 233U Isotope Production in VVER Type Reactors Using Thorium and Heavy Water. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2014, vol. 78, issue 11, pp. 1287–1300.
8. Yurova L.N., Polyakov A.A., Rukhlo V.P., Titarenko Yu.E., Bobrov S.A. Investigation into the Possibilities of 233U Accumulation in the WWER Type Reactors at Minimal Production of 232U. Atomic Energy, 1978, vol. 45, issue 1, pp. 21–24.
9. Marshalkin V.E. The Concept of Closed Thorium-Uranium-Plutonium Fuel. Physics of Atomic Nuclei, 2019, vol. 82, issue 8, pp. 1131–1148.
10. Reda S.M., Gomaa I.M., Bashter I.I., Amin E.A. Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library. Science and Technology of Nuclear Installations, 2021, no. 8838097.
11. Marshalkin V.Ye., Povyshev V.M. Sposob ekspluatatsii yadernogo reaktora v toriyevom toplivnom tsikle s rasshirennym vosproizvodstvom izotopa 233U [A method for operating a nuclear reactor in a thorium fuel cycle with expanded reproduction of the 233U isotope]. Patent RU, no.&bnbsp;2541516, 2015.
12. Marshalkin V.Ye., Povyshev V.M. Sposob ekspluatatsii yadernogo reaktora v urantoriyevom toplivnom tsikle s narabotkoy izotopa 233U [Method for operating a nuclear reactor in the uranium-thorium fuel cycle with the production of the 233U isotope]. Patent RU, no.&bnbsp;2619599, 2017.
13. Marshalkin V.Ye., Povyshev V.M. On Equilibrium Isotop Composition of Thorium-Uranium-Plutonium Fuel Cycle. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2016, no.&bnbsp;79, pp. 1290–1297.
14. Ponomarev-Stepnoi N.N., Lunin G.L., Ryazantsev E.P., Morozov A.G., Kuznetsov V.V., Kevrolev V.V., Kuznetsov V.F. Light-Water Thorium Reactor VVER-T. Atomic Energy, 1998, vol. 85, issue 4, pp. 685–699.
15. Marshalkin V.Ye., Povyshev V.M. Natural Transmutation of Actinides via the Fission Reaction in the Closed Thorium-Uranium-Plutonium Fuel Cycle. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2017, vol. 80, issue 8, pp. 1433–1442.
16. Marshalkin V.Ye., Povyshev V.M. The Second-Generation Fissile Materials in the Nuclear Power Industry. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2018, vol. 81, issue 8, pp. 1211–1226.
17. Marshalkin V.Ye., Povyshev V.M. Sposob ekspluatatsii yadernogo reaktora v toriyevom toplivnom tsikle s narabotkoy izotopa urana 233U [A method for operating a nuclear reactor in a thorium fuel cycle with the production of the uranium isotope 233U]. Patent RU, no.&bnbsp;2634476, 2017.
18. Thorium-Based Nuclear Fuel: Current Status and Perspectives. Vienna: International Atomic Energy Agency, 1987. 158 p.
19. Abagyan L.P., Bazazyants N.O., Nikolayev M.N., Tsibulya A.M. Gruppovyye konstanty dlya rascheta reaktorov i zashchity [Group constants for the calculation of reactors and protection]. Moscow, Energoizdat Publ., 1981. 232 p.
20. Manturov G.N., Nikolaev M.N., Koshcheev V.N. Nuclear Data for Reactor Neutronics Calculations – ROSFOND Data Library and ABBN-RF Group Data System. Voprosy Atomnoy Nauki i Tekhniki. Seriya: Yaderno-reaktornye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, no.&bnbsp;2, pp. 5–24.
21. Shamanin I.V., Chertkov Yu.B., Bedenko S.V. Toriyevaya reaktornaya ustanovka maloy moshchnosti, rabotayushchaya v sverkhdlinnoy kampanii. Izvestiya vuzov. Yadernaya energetika, 2016, no.&bnbsp;2, pp. 121–132.
22. Lebedev V.M. Yadernyy toplivnyy tsikl: Tekhnologii, bezopasnost’, ekonomika [Nuclear fuel cycle: Technology, safety, economics.]. Moscow, Energoatomizdat Publ., 2005. 316 p.
23. Sylvain D., Elisabeth H., Hervé N. Revisiting the Thorium-Uranium Nuclear Fuel Cycle. Europhysics News, 2007, vol. 38, no.&bnbsp;2, pp. 24–27.
