[3E05-09] Accident Analysis, In-service Inspection, Spent Fuel Pool

10:50 AM - 11:05 AM JST(1:50 AM - 2:05 AM UTC)

[3E06] Applicability assessment of Transient Reactor Analysis Code Toshiba version (TRACT^TM) to Loss-of-Coolant-Accident analysesBreak area effect assessments on cladding surface temperature etc.

*Hideki Horie¹, Fumie Sebe¹, Shin Goto¹ (1. TOSHIBA ESS)

Keywords:

TRACT,LOCA,ROSA-III,validation analysis

Toshiba Energy Systems & Solutions Corporation have been enhancing Transient Reactor Analysis code Toshiba version (TRACT^TM) for application to a licensing analysis code for transient and accident analysis in Boiling Water Reactors (BWR) in Japan. To achieve the goal, TRACT^TM needs to extend its applicable range to Design Basis Accident including Loss of Coolant Accident (LOCA) in addition to transient which is traditional one. Then, some physical models in TRACT^TM were improved, and validation analyses were carried out to confirm the applicability of TRACT^TM to LOCA. This report presents the results of the validation analyses conducted for the ROSA-III test, which is LOCA-simulated test of BWR, to confirm LOCA applicability based on integral effect test.