Результаты поиска по 'liquid-metal cooled reactor':
Найдено статей: 1
  1. Didenko D.V., Nikanorov O.L., Rogozhkin S.A.
    Analytical study of rod lifting margin of fuel assembly of fast sodium reactor
    Computer Research and Modeling, 2020, v. 12, no. 6, pp. 1307-1321

    The paper describes an analytical study of hydrodynamic processes taking place in the course of coolant flow through a fuel assembly of the core of a fast neutron sodium-cooled reactor. Within the framework of the study, a procedure and an analytical model were developed based on program complex FlowVision of computational fluid dynamics, which, using proved simplifications, permits to obtain a coefficient of rod lifting margin of a fuel assembly and to study hydrodynamic characteristics of processes taking place in the course of simulation of different initial events influencing motion of a reactor core fuel assembly.

    For analytical justification a fuel assembly model was developed, which is equivalent by hydraulic resistance values and permits not to simulate explicitly a complicated full-scale fuel assembly design, thus, decreasing a number of computational cells in the model and, as a result, reducing computational and time resources.

    Hydraulic parameters of the equivalent fuel assembly model in program complex FlowVision were analyzed in two stages. At the first stage, to determine the minimum rod lifting margin coefficient of a fuel assembly, steady-state analyses were performed, where various flowrate values were assigned at the model inlet and forces acting upon the assembly were analyzed. A series of dynamic mode analyses was performed at the second stage. Jump-like pressure increase being the initial event which could occur hypothetically in the fast neutron sodium cooled reactor plant was assigned in these modes. Hydrodynamic parameters and forces acting upon the fuel assembly were determined.

    The results of the first stage of the analytical study proved the minimum coefficient of rod lifting margin of a fuel assembly of the fast neutron reactor justified in reactor plant design documentation. As a result of the second stage of the study, conclusions were made on impossibility for the fuel assembly to move at the initial event associated with jump-like pressure increase in the reactor pressure chamber.

    Keywords: core, liquid-metal cooled reactor, fuel assembly, hydrodynamics, analytical model, FlowVision.

Indexed in Scopus

Full-text version of the journal is also available on the web site of the scientific electronic library eLIBRARY.RU

The journal is included in the Russian Science Citation Index

The journal is included in the RSCI

International Interdisciplinary Conference "Mathematics. Computing. Education"

Copyright © 2009–2024 Institute of Computer Science