EDN: HOKYGW
Authors & Affiliations
Bednyakov S.M., Bezborodov А.А., Doolin V.A., Izotov V.V., Мikhailov G.М., Prishchepa V.V.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Bednyakov S.M. – Leading Researcher, Cand. Sci. (Tech.).
Bezborodov А.А. – Senior Researcher, Cand. Sci. (Phys.-Math.). Contacts: 1, Bondarenko sq., Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-70-00 (56-46); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Doolin V.A. – Chief Researcher, Professor, Dr. Sci. (Phys.-Math.).
Izotov V.V. – Senior Researcher.
Mikhailov G.M. – Head of the Laboratory, Cand. Sci. (Tech.).
Prishchepa V.V. – Senior Researcher.
Abstract
BFS-2 is the largest physical stand in the World, the dimensions (tank height 3 m, diameter 5 m) and reactor materials of which allow for full-scale modeling of active zones and screens of fast reactors with a capacity of up to 3000 MW (EL), as well as in-hull protections and in-reactor storages. Including fast neutron power reactors cooled with liquid lead. Manufactured new reactor materials in hermetic shells make it possible to carry out a wide range of studies of the BREST-OD-300 reactor core on dense mixed nitride uranium-plutonium fuel (MNUP). The program of experiments on the BREST-OD-300 reactor model was started up with a set of critical mass of a given configuration – assembly of the BFS-88. The sensitivity of the KNT-54-1 fission chamber (potentially the BREST-OD-300 launch chamber) was assessed when it was irradiated with neutrons of different spectra. The paper presents the results of experiments important for the safety of the BREST-OD-300 reactor. The lead void reactivity effect (LVRE) was measured by the method of inverse multiplication in a trapezoid-shaped region extending from the central permanent reactivity compensator to the boundary with the lead reflector. The passive feedback system (PFS) was modeled by an area of 120 rods of a lead reflector adjacent directly to the core, and its effectiveness was also determined by the method of inverse multiplication with the partial removal of lead in height in groups of rods included in it. The results of the above experiments are considered in the article.
Keywords
BFS Stand, approached source multiplication method, ASM method, MNUP fuel, critical mass, passive feedback system, void reactivity effect, fission ionization chamber, spatial distributions, fission reactions rates, small-sized fission chamber, project codes verification
Article Text (PDF, in Russian)
References
- Gulevich A.V., Dvuchsherstnov V.G., Eliseev V.A., Klinov D.A, Matveenko I.P., Mikhailov G.M., Semenov M.Yu. BFS – unikal'nyy instrument dlya obosnovaniya neytronno-fizicheskikh kharakteristik aktivnykh zon bystrykh reaktorov novogo pokoleniya. Izbrannye trudy AO “GNTs RF – FEI”. Otv. red. A.A. Goverdovskiy [BFS is a unique tool for substantiating the neutron-physical characteristics of the cores of new generation fast reactors. Selected works of IPPE. Ed. A.A. Goverdovsky]. Obninsk, 2021. 464 p.
- Bednyakov S.M., Gulevich A.V., Dvuchsherstnov V.G., Zhookov A.M., Klinov D.A, Mikhailov G.M., Semenov M.Yu. BFS – unikal'nyy instrument dlya obosnovaniya neytronno-fizicheskikh kharakteristik aktivnykh zon bystrykh reaktorov novogo pokoleniya. Nauchnyy godovoy otchet AO “GNTs RF – FEI” – 2021: sb. statey. Pod red. V.M. Troyanova [BFS is a unique tool for substantiating the neutron-physical characteristics of the cores of new generation fast reactors. Scientific and Technical Annual Report of IPPE. Ed. by V.M. Troyanov]. Obninsk, 2022. Pp. 18–24.
- Adamov E.O., Kaplienko A.V., Orlov V.V., Smirnov V.S., Lopatkin A.V., Lemekhov V.V., Moiseev A.V. Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation. At Energy, 2021, vol. 129, issue 4, pp. 179–187. DOI: https://doi.org/10.1007/s10512-021-00731-w. Available at: https://link.springer.com/article/10.1007/s10512-021-00731-w#citeasciteas (accessed 14.05.2024).
- Davidov V.K., Zhirnov A.P., Lamanov S.A., Moiseev A.V., Yufereva V.A. Polnomasshtabnoe modelirovanie reaktora BREST-OD-300 na kriticheskom stende BFS-2 [Full-scale simulation of the BREST-OD-300 reactor on the BFS-2 critical stand]. 32-ya Vserossiyskaya nauchno-tekhnicheskaya konferentsiya “Neytronno-fizicheskie problemy atomnoy energetiki” (“Neytronika-2024”) [32d All-Russian Scientific and Technical Conference “Neutronic problems of nuclear energy” (“Neutronica-2024”)]. Obninsk, IPPE, May 28–31, 2024. Available at: https://www.ippe.ru/images/science_info/conference/neutron2024/presentation/pl-5.pdf (accessed 17.07.2024).
- Bednyakov S.M., Bezborodov А.А., Izotov V.V., Mikhailov G.M., Prishchepa V.V., Semenov M.Yu. Fast reactor start-up reproduction on BFS. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear Reactor Constants, 2022, issue 3, pp. 39–48. Available at: https://vant.ippe.ru/year2022/3/neutron-constants/2200-4.html (accessed 15.05.2024).
- Dmitriev A.B., Malishev E.K. Neytronnye ionizatsionnye kamery dlya reaktornoy tekhniki [Neutron ionization chambers for reactor equipment]. Moscow, Atomizdat Publ., 1975. 96 p.
- Safety Related Terms for Advanced Nuclear Plants. IAEA-TECDOC-626. Vienna: IAEA, 1991.
- Leonov V.N., Rodina E.A., Chernetsov N.G., Chernobrovkin Yu.V., Shevchenko A.B. Passive Negative-Reactivity Injector for a Lead-Cooled Fast Reactor. At Energy, 2017, vol. 122, issue 1, pp. 9–14. DOI: https://doi.org/10.1007/s10512-017-0228-x. Available at: https://link.springer.com/article/10.1007/s10512-017-0228-x#citeas (accessed 14.05.2024).
- IAEA Safety Glossary: 2007 Edition. Vienna, IAEA, 2007. 295 p.
- Bednyakov S.M., Bezborodov А.А., Doolin V.A., Izotov V.V., Koozin E.N., Mikhailov G.M., Prishchepa V.V. Provedenie eksperimental'nykh issledovaniy neytronno-fizicheskikh kharakteristik modeli aktivnoy zony reaktora BREST-OD-300 na sborke BFS-88-2. Nauchnyy godovoy otchet AO “GNTs RF – FEI” – 2022: sb. statey. Pod red. V.M. Troyanova [Conducting experimental studies of the neutron-physical characteristics of the BREST-OD-300 reactor core model on the BFS-88-2 assembly. Scientific and Technical Annual Report of IPPE. Ed. V.M. Troyanov]. Obninsk, 2023. Pp. 14–17.
UDC 621.039.58
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 4, 4:3
