抄録
Validation study of numerical analysis tools has been underway in the Japan Atomic Energy Agency in order to establish a safety evaluation method for sodium leak and fire accident postulated in sodium-cooled fast reactor plants. This paper describes briefly the current status of sodium fire analysis codes development and validation activities, emphasizing that the code validation is performed with focusing on important phenomena and dominant factors for accident consequence. It is also demonstrated from a numerical experiment that one of the important evaluating issues of large-scale sodium spray leak and fire would be predicted more realistically and precisely by a three-dimensional sodium fire analysis code since it would enable the estimation of local effect; i.e. the oxygen deficiency behavior in the spray fire region.
