2022 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[1J04-07] Analysis Technology 2

Wed. Sep 7, 2022 10:50 AM - 12:00 PM Room J (E1 Bildg.4F No.42)

Chair:Koji Morita(Kyushu Univ.)

11:35 AM - 11:50 AM

[1J07] Examination of Transient Reactor Analysis code Toshiba version (TRACTTM) application for Loss-of-Coolant Accident analyses

*Fumie Sebe1, Hideki Horie1, Yutaka Takeuchi1, Takanori Fukunaga1 (1. Toshiba Energy Systems & Solutions Corporation)

Keywords:TRACTTM, LOCA, validation analysis

Transient Reactor Analysis code Toshiba version (TRACTTM) is intended to be adopted as one of licensing analysis codes for BWRs in Japan and its applicable scope is needed to be broadened out to Design Basis Accident like Loss of Coolant Accident (LOCA). To enhance the code so that LOCA phenomena can be evaluated, improvements of incorporated physical models, examination of input conditions and validation analyses to confirm the applicability have been conducted. More than 20 models are extracted as important models in applying to LOCA analyses and they have been investigated in detail. In this report, we report the validation analysis results on ROSA-III studies to confirm the LOCA applicability based on integral effect test.