Development of fundamental numerical simulation system for integrated safety evaluation in various innovative sodium-cooled fast reactor, 11; Improvement of simulation system applicability and user convenience

Uchibori, Akihiro ; Sonehara, Masateru ; Aoyagi, Mitsuhiro ; Okano, Yasushi; Takata, Takashi  

A new computational code, SPECTRA, has been developed as a base simulation system for integrated safety evaluation of advanced sodium-cooled fast reactors. In this study, a lumped mass module for in-vessel coolant behavior and user convenience improvement tool were constructed. The lumped mass module was validated through the analysis of a compressible gas-liquid two-phase flow experiment by using the computational domain connected with a multidimensional mesh. As user convenience improvement, the AI-driven design tool successfully found an optimum solution in a single parameter problem. The GUI tool supporting creation of a input data and quality assurance of analysis work was also constructed.