EDN: ALOVZA
Authors & Affiliations
Aksenova A.E., Isakov A.B., Kiselev A S., Koltashev D.A., Pervichko V.A., Chudanov V.V., Shurygin R.E.
Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
Aksenova A.E. – Senior Researcher, Cand. Sci. (Phys.-Math.).
Isakov A.B. – Head of the Service Software Development laboratory, Cand. Sci. (Phys.-Math.).
Kiselev A.S. – Leading Researcher, Dr. Sci. (Tech.).
Koltashev D.A. – Head of the Department of Modeling Physical Processes, Cand. Sci. (Tech.).
Pervichko V.A. – Senior Researcher.
Chudanov V.V. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Shurygin R.E. – Engineer, Nuclear Safety Institute of the Russian Academy of Sciences. Contacts: 52, Bolshaya Tulskaya st., Moscow, Russia, 115191. Tel.: +7 (495) 955-23-96; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
This paper presents the actual state of the coupled 3D code being developed at IBRAE RAN within the project “New Generation Codes” of the “PRORYV” (“Breakthrough”) project based on neutron, thermal-hydraulic and thermomechanical codes. The coupled 3D code is designed to simulate normal and abnormal operation modes of fast neutron reactors with liquid metal coolants. The actual problems that can be solved by the coupled 3D code include calculations of the modes: reactor start-up, reaching a steady-state, shutdown, introduction of positive reactivity, operation under conditions of deteriorated heat exchange (for example, in case of malfunctions of the main pump) and other modes. Currently, the coupled 3D code includes neutron modules based on Monte Carlo methods and discrete ordinate approximation, a precision scalable DNS and LES CFD code and a three-dimensional thermomechanical code for strength calculations. The paper presents information on the modules included in the coupled code is provided, and the created computational tools are described. Calculation for the experimental assembly, containing three lead ampoules with experimental SNUP fuel elements and fuel elements with vibration-compacted fuel, in the BOR-60 reactor was performed to demonstrate the coupled code use. 3D distributions calculated by codes MCU-FR-CONV-3D-TERMA and CORNER-CONV-3D-TERMA are presented. The assembly contains three lead ampoules with prototype fuel rods with SNP fuel and heating fuel rods with vibration-compacted fuel. In both cases good agreement between the calculated and experimental values of the prototype fuel rod cladding temperature demonstrated. Information on plans for further improvements of the 3D coupled code is provided.
Keywords
couples 3D code, couples calculations, MCU-FR, CORNER, TERMA, CONV-3D, OU-AS
Article Text (PDF, in Russian)
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UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 3, 3:1
