Development of fundamental numerical simulation system for integrated safety evaluation in various innovative sodium-cooled fast reactor, 1; Overall plan for development of systems

Takata, Takashi*; Nakahara, Hirotaka*; Suzuki, Toru*; Oishi, Yuji*

no journal, , 

A safety evaluation technology which is based on the SPECTRA code for integrated analysis of in- and ex-vessel phenomena during severe accidents in sodium-cooled fast reactors has been developed. The development in the next four years includes an in-vessel lumped mass model, a core damage model, application of SPECTRA for a PRISM-type reactor, a design optimization method by artificial intelligence, a graphical user interface for input data construction, and an automation tool of quality assurance. Furthermore, thermal properties of molten fuels will be measured by a state-of-the-art technology for enlargement of basic database.