Development of program modules with space-time kinetics for calculating unanticipated accidents in fast reactors

The first version of the complex computer code COREMELT-2D for calculating in a two-dimensional geometry the nonstationary neutron-physical and thermohydraulic processes taking account of coolant boiling, melting of fuel elements and mixing of melted components of a fast-reactor core has been develo...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2013-06, Vol.114 (2), p.77-82
Main Authors: Ashurko, Yu. M., Volkov, A. V., Raskach, K. F.
Format: Article
Language:English
Subjects:
Accidents
Analysis
Approximation
Boron
Computer programming
Geometry
Hadrons
Heat
Heavy Ions
Kinetics
Mathematical analysis
Mathematical models
Modules
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear Physics
Nuclear reactors
Physics
Physics and Astronomy
Radar
Radar systems
Reaction kinetics
Reactors
Sodium
Spacetime
Studies
Thermodynamics
Thermohydraulics
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Summary:The first version of the complex computer code COREMELT-2D for calculating in a two-dimensional geometry the nonstationary neutron-physical and thermohydraulic processes taking account of coolant boiling, melting of fuel elements and mixing of melted components of a fast-reactor core has been developed. The code consists of a thermohydraulic module COREMELT and the neutron-physical module RADAR. COREMELT implements a multicomponent and multiphase thermohydraulics model in R–Z geometry in the porous body approximation. RADAR solves a multigroup neutron diffusion equation in R–Z and X–Y geometry. In the RADAR module, a modified TRIGEX program with a built-in CONSYST module, associated with the BNAB-93 group-constants library, is used to prepare the dynamical neutron constants. A test calculation of a serious accident due to loss of system and reliable power with all emergency protection organs of the reactor failing simultaneously is performed for the BN-1200 design using the complex program developed. The results are compared with previous calculations of the same accident performed using a COREMELT version with a point model of neutron kinetics.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-013-9675-1