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.
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Translated from Atomnaya Énergiya, Vol. 120, No. 6, pp. 303–312, June, 2016.
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Bol’shov, L.A., Mosunova, N.A., Strizhov, V.F. et al. Next Generation Design Codes for a New Technological Platform for Nuclear Power. At Energy 120, 369–379 (2016). https://doi.org/10.1007/s10512-016-0145-4
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DOI: https://doi.org/10.1007/s10512-016-0145-4