电邮这篇文章 Next Generation Design Codes for a New Technological Platform for Nuclear Power
- 作者: Bol’shov L.A.1, Mosunova N.A.1, Strizhov V.F.1, Shmidt O.V.2
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隶属关系:
- 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)
- 期: 卷 120, 编号 6 (2016)
- 页面: 369-379
- 栏目: Dedicated to the 60th Anniversaryof the Journal Atomnaya Énergiya
- URL: https://journals.rcsi.science/1063-4258/article/view/247757
- DOI: https://doi.org/10.1007/s10512-016-0145-4
- ID: 247757
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详细
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.
作者简介
L. Bol’shov
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow
N. Mosunova
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow
V. Strizhov
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow
O. Shmidt
Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM)
Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow
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