Neutronics Calculation of Fast Reactor Using Modern Computing Systems
- Авторлар: Kovalishin A.A.1, Moryakov A.V.1, Raskach K.F.2
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Мекемелер:
- National Research Center Kurchatov Institute
- State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)
- Шығарылым: Том 124, № 2 (2018)
- Беттер: 75-81
- Бөлім: Articles
- URL: https://journal-vniispk.ru/1063-4258/article/view/248894
- DOI: https://doi.org/10.1007/s10512-018-0378-5
- ID: 248894
Дәйексөз келтіру
Аннотация
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.
Авторлар туралы
A. Kovalishin
National Research Center Kurchatov Institute
Email: j-atomicenergy@yandex.ru
Ресей, Moscow
A. Moryakov
National Research Center Kurchatov Institute
Email: j-atomicenergy@yandex.ru
Ресей, Moscow
K. Raskach
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)
Email: j-atomicenergy@yandex.ru
Ресей, Obninsk
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