EDN: MEZRMW
Authors & Affiliations
Arefinkina S.E., Gerstle A.D., Dmitrieva N.A., Erak D.Yu., Efremov P.K., Kruglikov A.E., Mikhin O.V., Murashov V.N., Papina V.B., Pesnya Yu.E., Trofimchuk V.V., Yakovlev V.V.
National Research Centre “Kurchatov Institute”, Moscow, Russia
Arefinkina S.E. – Researcher. Contacts: 1, Academician Kurchatov pl., Moscow, Russia, 123182. Tel.: +7 (903) 783-36-31; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Gerstle A.D. – Senior Researcher.
Dmitrieva N.A. – Leading Researcher.
Erak D.Yu. – Head of Department, Dr. Sci. (Tech.).
Efremov P.K. – Engineer.
Kruglikov A.E. – Senior Researcher.
Mikhin O.V. – Head of Laboratory.
Murashov V.N. – Leading Researcher, Cand. Sci. (Tech.).
Papina V.B. – Senior Researcher.
Pesnya Yu.E. – Head of Laboratory, Cand. Sci. (Tech.).
Trofimchuk V.V. – Researcher.
Yakovlev V.V. – Deputy Head of Department, Cand. Sci. (Tech.).
Abstract
Creating supercritical water cooled reactors (SCWR) is one of the promising directions of VVER-type reactor development.
The article considers the stages of the SOTAR program development, that could be used to estimate the processes in the fuel rods with UO2 and with candidate fuel rods claddings for advanced nuclear power plants.
The possibilities of the IR-8 research reactor of the NRC “Kurchatov Institute” to test experimental fuel rods for the designed SCWR reactor with special ampoule devices are shown. The importance of performing calculations for the processes inside the fuel rod during its irradiation is discussed. The interrelation of fuel rod process evaluations with other design calculations required in planning reactor experiments is demonstrated.
The data of modeling tests at the IR-8 reactor of fuel rods for SCWR in the ampoule device of a selected design are presented. Comparison of calculations for fuel rods with different parameters was performed. Modeling was carried out for fuel rods with uranium dioxide core and steel cladding CHS-68-ID cd. The prospects for the SOTAR program are also being reviewed.
Keywords
SCWR, experimental fuel rods, IR-8 research reactor, ampoule device, natural convection, fuel rod performance under irradiation, SOTAR program, reactor experiment modeling, MCU-PTR, cladding materials, fuel rod instrumentation
Article Text (PDF, in Russian)
References
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UDC 621.039.5
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:8
