Enviar artigo por via de e-mail Next Generation Design Codes for a New Technological Platform for Nuclear Power
- Autores: Bol’shov L.A.1, Mosunova N.A.1, Strizhov V.F.1, Shmidt O.V.2
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Afiliações:
- Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
- Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM)
- Edição: Volume 120, Nº 6 (2016)
- Páginas: 369-379
- Seção: Dedicated to the 60th Anniversaryof the Journal Atomnaya Énergiya
- URL: https://journal-vniispk.ru/1063-4258/article/view/247757
- DOI: https://doi.org/10.1007/s10512-016-0145-4
- ID: 247757
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Resumo
Information is presented on the status of next generation codes for a new technological platform for nuclear power based on fast reactors and fuel cycle closure. The composition of the system of next generation codes and information on the status of individual codes are presented. The approaches to verification and validation of the codes as well as the collective development of software are described.
Sobre autores
L. Bol’shov
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Rússia, Moscow
N. Mosunova
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Rússia, Moscow
V. Strizhov
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Rússia, Moscow
O. Shmidt
Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM)
Email: j-atomicenergy@yandex.ru
Rússia, Moscow
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