Neutronics Calculation of Fast Reactor Using Modern Computing Systems

The possibility of using the LUCKY-A three-dimensional multiprocessor transport code as a neutronics module for the COREMELT integrated non-stationary code for performing safety analysis, which is used for fast sodium reactor safety validation, is discussed. In this application, more stringent requi...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2018-06, Vol.124 (2), p.75-81
Main Authors: Kovalishin, A. A., Moryakov, A. V., Raskach, K. F.
Format: Article
Language:English
Subjects:
Analysis
ARRAY PROCESSORS
Computation
Computer applications
Energy industry
FAST REACTORS
GENERAL STUDIES OF NUCLEAR REACTORS
Hadrons
Heavy Ions
Mathematical analysis
Multiprocessing
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear Physics
Nuclear power plants
Nuclear reactors
Nuclear safety
Parallel processing
Physics
Physics and Astronomy
REACTOR SAFETY
Reactors
SAFETY ANALYSIS
Sodium
SODIUM COOLED REACTORS
THREE-DIMENSIONAL LATTICES
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Summary:The possibility of using the LUCKY-A three-dimensional multiprocessor transport code as a neutronics module for the COREMELT integrated non-stationary code for performing safety analysis, which is used for fast sodium reactor safety validation, is discussed. In this application, more stringent requirements are imposed on the computing speed of the LUCKY-A code. To test LUCKY-A possibilities, a typical computational problem is examined in a formulation characteristic for the proposed use of the code. The possibilities of the code for parallelized calculations are shown, and a comparison is made with calculations performed with the MMKKENO and TRIGEX codes. The efficacy of a parallel computational process is investigated as a function of the number of computing kernels used.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-018-0378-5