Neutronic calculation of fast reactors by the EUCLID/V1 integrated code

International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016

Koltashev, D.A.^1 ; Stakhanova, A.A.^1

Nuclear Safety Institute of the Russia Academy of Sciences, 52 Bolshaya Tulskaya, Moscow

115191, Russia^1

关键词: Abnormal operating conditions;    Development and applications;    Diffusion approximations;    Full scale simulation;    Neutron transport equation;    Neutronic calculations;    Nuclear power plant safeties;    Russian Academy of Sciences;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012003/pdf
DOI  :  10.1088/1742-6596/781/1/012003

来源: IOP

【 摘 要 】

This article considers neutronic calculation of a fast-neutron lead-cooled reactor BREST-OD-300 by the EUCLID/V1 integrated code. The main goal of development and application of integrated codes is a nuclear power plant safety justification. EUCLID/V1 is integrated code designed for coupled neutronics, thermomechanical and thermohydraulic fast reactor calculations under normal and abnormal operating conditions. EUCLID/V1 code is being developed in the Nuclear Safety Institute of the Russian Academy of Sciences. The integrated code has a modular structure and consists of three main modules: thermohydraulic module HYDRA-IBRAE/LM/V1, thermomechanical module BERKUT and neutronic module DN3D. In addition, the integrated code includes databases with fuel, coolant and structural materials properties. Neutronic module DN3D provides full-scale simulation of neutronic processes in fast reactors. Heat sources distribution, control rods movement, reactivity level changes and other processes can be simulated. Neutron transport equation in multigroup diffusion approximation is solved. This paper contains some calculations implemented as a part of EUCLID/V1 code validation. A fast-neutron lead-cooled reactor BREST-OD-300 transient simulation (fuel assembly floating, decompression of passive feedback system channel) and cross-validation with MCU-FR code results are presented in this paper. The calculations demonstrate EUCLID/V1 code application for BREST-OD-300 simulating and safety justification.