DOI: 10.55176/2414-1038-2021-4-63-71
Authors & Affiliations
Trofimchuk V.V., Nasonov V.A., Pesnya Y.E., Glyva K.I.
National Research Center “Kurchatov Institute”, Russia, Moscow
Trofimchuk V.V. – Research Engineer. Contacts: 1, Academician Kurchatov pl., Moscow, Russia, 123182. Tel.: +7 (917) 574-13-08; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Nasonov V.A. – Deputy Head of Department.
Pesnya Y.E. – Head of Laboratory.
Glyva K.I. – Junior Researcher.
Abstract
The paper considers the possibility of achieving the required neutron-physical parameters during irradiation of experimental fuel elements circumfluent with a SCW parameters coolant in the RR IR-8 in order to study the behavior of fuel element cladding under the influence of reactor radiation and coolant with SCW parameters under conditions closest to real operation in nuclear power plant. The possibility of carrying out such experiments in the RR IR-8 will make it possible to contribute to the development of new generation IV nuclear power plants, one of the areas of which is a reactor with supercritical parameters coolant. This direction is promising, as the use of the SCW coolant technology will increase the efficiency of the reactors by 10–12 %. Irradiation experiments in RR IR-8 are carried out using experimental ampoule rigs. During developing the design of an ampoule rig with experimental fuel elements, it is required to provide the necessary heat transfer from the fuel element to the water of the reactor pool, and to maintain the pressure of the SCW coolant by the structure of the ampoule rig vessel. The calculations of heat release in the experimental fuel elements and the accumulation of fluence in the cladding were carried out using the MCU-PTR code with the MDBPT-50 database, which implements the Monte Carlo method. The assessment of heat release in fuel elements during irradiation of an ampoule rig in the cells of the IR-8 core and reflector was carried out. The calculation results of heat release in experimental fuel elements and fast neutron fluxes in the cladding during irradiation in the central channels of fuel assemblies and special blocks made of aluminum, stainless steel, as well as water are presented. An assessment of the contribution of heat release from gamma heating of the ampoule rig structure elements was carried out, which showed that the amount of heat release can be comparable with the energy release due to the fuel fission reaction in an experimental fuel element, which must be taken into account when calculating the temperature irradiation regimes of experimental fuel elements. Obtained results showed the principle possibility of achievement the parameters of the SCW coolant in the ampoule rig on the outer surface of the experimental fuel elements cladding in the RR IR 8.
Keywords
RR, IR-8, reactor, parameters of the SCW coolant, irradiation experiments, experimental fuel elements, ampoule rig (AR), fuel enrichment, heat release, neutron flux, gamma radiation
Article Text (PDF, in Russian)
References
- Gen IV International Forum (GIF). Annual report 2020.
- Ryazantsev E.P., Nasonov V.A., Egorenkov P.M., Yakovlev V.V., Yashin A.F., Kuznetsov I.A., Rozhnov V.N. Eksperimental'nyye vozmozhnosti i perspektivy ispol'zovaniya reaktora IR-8 RNTS “KI” dlya fundamental'nykh i prikladnykh issledovaniy [Experimental possibilities and prospects of using the IR-8 reactor of the RRC “KI” for fundamental and applied research]. Preprint-IAE-6411/4, 2006.
- Nasonov V.A., Pesnya Y.E. Spektry neytronov v eksperimental'nykh kanalakh reaktora IR-8 [Neutron spectra in experimental channels of the IR-8 reactor]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors. 2017, no. 3, pp. 65–70.
- Nasonov V.A., Pesnya Y.E., Kruglikov A.E., Glyva K.I., Trofimchuk V.V. Optimization of FA Reloading in the IR-8 Reactor. Atomic Energy, 2019, vol. 126, issue 1, p. 7–11.
- Yakovlev V.V., Erak D.Y., Abramov A.N., Buslaev V.S., Kochkin V.N., Mikhin O.V., Mozhaev A.A., Murashov V.N., Nasonov V.A., Nichiporenko Y.B., Pesnya Y.E., Khmyzov N.V., Yashin A.F. Tekhnika i metody ispytaniy konstruktsionnykh materialov na issledovatel'skom reaktore IR-8 [Technique and methods of testing structural materials at the IR-8 research reactor]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2017, no. 3, pp. 58–64.
- 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.
- 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 energe-ticheskim ustanovkam [Materials of the XXI International Conference of Young Specialists on Nuclear Power Plants]. Podolsk, 2019, pp. 200–204.
- Makhin V.M., Churkin A.N. Kontseptual'nyye predlozheniya po vodookhlazhdayemomu reaktoru so sverkhkriticheskimi parametrami (obzor zarubezhnykh i rossiyskikh razrabotok SCWR) [Conceptual proposals for a water-cooled supercritical reactor (review of foreign and Russian SCWR developments)]. Trudy nauchno-tekhnicheskoy konferentsii “Teplofizika reaktorov novogo pokoleniya, Teplofizika-2018” [Report of the scientific and technical conference “Thermophysics of new generation reactors, Teplophisika-2018”]. Obninsk, 2018, pp. 6–21. Available at: https://www.ippe.ru/images/publications/thesis/tf-2018-tezis.pdf (accessed 29.10.2021).
- Makhin V.M., Vasilchenko I.N., Vyalitsyn V.V., Kushmanov S.A., Kurakin K.Yu., Churkin A.N., Lapin A.V., Semiglazov S.V. Kontseptsiya aktivnykh zon VVER SKD: usloviya ekspluatatsii tvelov, konstruktsiya TVS i kandidatnyye materialy [The concept of WWER SKD cores: fuel rod operating conditions, fuel assembly design and candidate materials]. Materialy VII Mezhdunarodnoy nauchno-tekhnicheskoy konferentsii “Obespecheniye bezopasnosti AES s VVER” [Materials of the VII International Scientific and Technical Conference “Ensuring the Safety of NPP with WWER”]. Podolsk, 2011. Available at: http://www.gidropress.podolsk.ru/files/proceedings/mntk2011/documents/mntk2011-120.pdf (accessed 29.10.2021).
- Alekseev N.I., Gomin E.A., Marin S.V., Nasonov V.A., Shkarovsky D.A., Yudkevich M.S. MCU-PTR program for high-precision calculations of pool and tank type research reactors. Atomic Energy, 2011, vol. 109, issue 3, pp. 149–156.
UDC 621.039.5
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, issue 4, 4:6
