Development of numerical analysis technologies in an integrated evaluation system, ARKADIA, for plant system thermal-hydraulics related issues in advanced sodium-cooled fast reactors

Tanaka, Masaaki ; Doda, Norihiro  ; Hamase, Erina ; Mori, Takero ; Yoshimura, Kazuo ; Yoshikawa, Ryuji ; Kikuchi, Norihiro ; Matsushita, Kentaro  ; Mochinaga, Shota  ; Ezure, Toshiki 

This paper presents the outline of the evaluation support program on the evaluations of the thermal-hydraulics related issues in the conceptual design study of the sodium-cooled fast reactor for demonstration in Japan, utilizing the technical basis on the simulations and evaluations configured in the integrated evaluation system named ARKADIA that has been developed with experiences through the development of the SFRs and related R&Ds in Japan Atomic Energy Agency. Moreover, as the extension of the function of the ARKADIA, the possible framework for SFR lifecycle development introducing the Digital-Twin for the MBD with ARKADIA is presented with an example of a whole plant coupled analysis model developed in ARKADIA.