Neutronics Calculation of Fast Reactor Using Modern Computing Systems
- Authors: Kovalishin A.A.1, Moryakov A.V.1, Raskach K.F.2
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Affiliations:
- National Research Center Kurchatov Institute
- State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)
- Issue: Vol 124, No 2 (2018)
- Pages: 75-81
- Section: Articles
- URL: https://journal-vniispk.ru/1063-4258/article/view/248894
- DOI: https://doi.org/10.1007/s10512-018-0378-5
- ID: 248894
Cite item
Abstract
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.
About the authors
A. A. Kovalishin
National Research Center Kurchatov Institute
Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow
A. V. Moryakov
National Research Center Kurchatov Institute
Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow
K. F. Raskach
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
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