EDN: OBJVCG
Authors & Affiliations
Arefinkina S.E., Gerstle A.D., Erak D.Yu., Efremov P.K., Kruglikov A.E., Mikhin O.V., Murashov V.N., Nasonov V.A., Pesnya Yu.E., Trofimchuk V.V., Yakovlev V.V.
National Research Centre "Kurchatov Institute" Moscow, Russia
Arefinkina S.E. – Researcher. Contacts: 1, pl. Academician Kurchatov, Moscow, Russia, 123182. Tel.: +7 (903) 783-36-31; e-mail: Arefinkina_SE@nrcki.
Gerstle A.D. – Senior Researcher.
Erak D.Yu. – Head of Department.
Efremov P.K. – Engineer.
Kruglikov A.E. – Senior Researcher.
Mikhin O.V. – Head of Laboratory.
Murashov V.N. – Lead Researcher.
Nasonov V.A. – Deputy Head of Department.
Pesnya Yu.E. – Head of Laboratory.
Trofimchuk V.V. – Researcher.
Yakovlev V.V. – Deputy Head of Department.
Abstract
In Russia and other countries for light water nuclear power reactor facilities takes place elaboration of accident tolerant fuel resistant to the occurrence of design and beyond-design accidents, including accidents with parocirconium reaction.
This article presents the possibilities of IR-8 research reactor at NRC "Kurchatov Institute" to carry out experimental tolerant fuel rods investigations. Here we considered the scheme of ampoule device design, that can be used for this irradiation, and instrumented by thermocouples to receive data about the temperature changes in real time.
Importance to carry out estimations of fuel rod performance under irradiation at the planning stage of the reactor experiments are discussed. We demonstrate how to use the SOTAR program developed on the basis of PIN series codes for such estimations. Short program description and examples of calculations are presented. Current version of SOTAR program can be used to estimate performance of fuel rods with UO2 and with tolerant fuel rods candidate claddings. The obtained results of modeling experimental tolerant fuel rods irradiation in IR-8 reactor in ampoule device with selected design are presented. Fuel rod performance calculations, as an example, were carried out for fuel rod with UO2 and with FeCrAl cladding.
Keywords
accident tolerant fuel, experimental fuel rods, IR-8 research reactor, ampoule device, fuel rod performance under irradiation, SOTAR program, reactor experiment modeling, MCU-PTR, cladding materials, FeCrAl, fuel rod instrumentation
Article Text (PDF, in Russian)
References
- Arefinkina S.E., Erak D.Y., Mikhin O.V., Yakovlev V.V., Sedov A.A., Trofimchuk V.V., Abramov A.N., Babenko A.V. Obosnovaniye vozmozhnosti issledovaniy na reaktore IR-8 povedeniya opytnykh tolerantnykh tvelov v usloviyakh, maksimal'no priblizhennykh k naturnym [Substantiation of the possibility of investigating the behavior of experimental tolerant fuel elements at the IR-8 reactor under conditions as close as possible to those of full-scale]. Materialy XXI Mezhdunarodnoy konferentsii molodykh spetsialistov po yadernym energeticheskim ustanovkam [Proc. of the XXI International Conference of Young Specialists on Nuclear Power Plants]. Podolsk, 2019, pp. 200–204.
- Kuryndin A.V., Kirkin A.M., Karimov A.Z., Makovskiy S.V. On approaches to regulation of accident tolerant fuel application. Nuclear and Radiation Safety, 2021, no. 4 (102), pp. 13–23. DOI: 10.26277/SECNRS.2021.102.4.002.
- Zinkle S.J., Terrani K.A., Gehin J.C., Ott L.J., Snead L.L. Accident tolerant fuels for LWRs: A perspective. Journal of Nuclear Materials, 2014, vol. 448, pp. 374–379.
- Dolgov A.I., Dreganov O.I., Markelov A.N., Mokeichev M.A., Sychugov M.S. Reaktornyye ispytaniya eksperimental'nykh tvelov tolerantnogo tipa v petlevykh kanalakh reaktora MIR [Reactor investigations of experimental tolerant fuel rods in the loop channels of the MIR reactor]. Tezisy dokladov KHI Vserossiyskoy molodozhnoy konferentsii “Nauchnyye issledovaniya i tekhnologicheskiye razrabotki v obespecheniye razvitiya yadernykh tekhnologiy novogo pokoleniya” [Proc. of the ХI Russian Youth Conference "Scientific researches and technological elaborations to ensure the development of new generation nuclear technologies"]. Dimitrovgrad, 2023, pp. 103–105.
- Yakovlev V.V., Erak D.Y., Goncharov L.A., Kiselev A.S., Kruglikov A.E., Mikhin O.V., Nasonov V.A., Pesnya Y.E., Sedov A.A., Khmyzov N.V., Chabak A.F., Yashin A.F. Tekhnika i metodika issledovaniy v reaktore IR-8 povedeniya opytnykh tvelov s raznymi toplivnymi kompozitsiyami [Technique and methods of research in the IR-8 reactor of the behavior of experimental fuel elements with different fuel compositions]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2017, no. 3, pp. 49–57.
- Erak D.Yu., Arefinkina S.E., Nasonov V.A., Yakovlev V.V., Mikhin O.V., Sedov A.A., Pesnya Yu.E., Trofimchuk V.V., Abramov A.N., Babenko A.V. Possibility substantiation of experimental FE with advanced fuel types behavior investigations at IR-8 reactor in closest to full-scale conditions. Proceedings of the 13th International Conference on WWER Fuel Performance, Modelling and Experimental Support. Nessebar, Bulgaria, 15–21 September 2019, pp. 332–335.
- Blandinsky V.Yu., Kolesov V.V., Nevinitsa V.A., Fomichenko P.A., Sedov A.A., Frolov A.A., Pustovalov S.B., Shchurovskaya M.V., Simonov S.S., Pesnya Yu.E., Trofimchuk V.V., Nasonov V.A., Zhemkov I.Yu. Osobennosti izmeneniya izotopnogo sostava opytnykh tvelov reaktora tipa VVER-SKD pri posledovatel'nom obluchenii v bystrom i teplovom spektre neytronov [Peculiarities of Changes in the Isotopic Composition of Pilot Fuel Elements of a VVER-SKD Reactor under Successive Irradiation in the Fast and Thermal Neutron Spectrum]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2022, no. 2, pp. 90–96.
- Van U.P., Hales J., Li W., Rossiter G., Williamson R. A review of fuel performance modelling. Journal of Nuclear Materials, 2019, vol. 516, pp. 373–412.
- Strijov P.N., Yakovlev V.V., Dubrovin K. P., Pazdera F., Valach M., Barta O. The improved version of the PIN Code and its Verification. IAEA-TC-657/3.4. Preston, England, 19–22 September 1988, pp. 2–7.
- Dubrovin K.P., Ivanov E.G., Strijov P.N., Yakovlev V.V. The results of postirradiations examinations of VVER-1000 and VVER-440 fuel rods. Journal of Nuclear Materials, 1991, vol. 178, pp. 306–311.
- Yakovlev V.V., Strijov P.N., Murashov V.N., Johansson J., Terasvirta R.P., Tiihonen O., Ranta-Puska K. Research carried out on WWER-440 type fuel rods in the MR reactor. IAEA-SM-288/64. Improvements in water reactor fuel technology and utilization. Stockholm, 1986, pp. 191–206.
- Yakovlev V., Strijov P., Murashov V. et al. Qualification and Interpretation of MR Test Reactor Irradiation Data on VVER-440 Type Fuel Rods for Fuel Thermal Model Validation. IAEA-TC-659/1.4. 1987, pp. 50–56.
- Sheglov A.S. Programma rascheta teplofizicheskikh kharakteristik poperechnykh secheniy tvelov VVER-TOPRA-s [Program VVER-TOPRA-s to calculate thermophysical characteristics of fuel rods cross-sections]. Preprint-IAE-6172/4, 2000.
- Analysis and experimental study of fuel for water-cooled reactors with increased resistance to accidents. Final report on the coordinated research project. IAEA-TECDOC-1921. Vienna, IAEA, 2022.
- Qiu B., Jun W., Deng Y., Mingjun W., Yingwei W., Qiu S.Z. A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding. Nuclear Engineering and Technology, 2020, vol. 52, pp. 1–13.
- Pau A., Francisco F., Luis E.H. Modelling FeCrAl cladding thermo-mechanical performance. Part I: Steady-state condition. Progress in Nuclear Energy, 2022, vol. 155, pp. 1–13.
- Yakushkin A.A. O problemakh sozdaniya obolochek TVELov dlya tolerantnogo topliva iz tsirkoniyevykh splavov [On the problems of creating shells of fuel rods from zirconium alloys for tolerant fuel]. Fizika i khimiya obrabotki materialov – Physics and chemistry of materials treatment, 2021, no. 3, pp. 69–78.
- Bul’kanov M.G., Kruglov A.S., Pevchikh Yu.M., Troyanov V.M. In-pile creep studies of structural materials. Atomic Energy, 1996, vol. 80, issue 5, pp. 386–391.
- Alekseev N.I., Gomin E.A., Marin S.V. et al. MCU-PTR program for high-precision calculations of pool and tank type research reactors. Atomic Energy, 2010, vol. 109, issue 3, pp. 123–129.
UDC 621.039.5
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 4, 1:9
