2021 Annual Meeting

Presentation information

Oral presentation

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

[2F01-04] Tool Development for Safety Assessment

Thu. Mar 18, 2021 9:30 AM - 10:45 AM Room F (Zoom room 6)

Chair: Chiaki Kino (IAE)

10:00 AM - 10:15 AM

[2F03] Development of Internal Flooding Propagation Analysis System

(3)High Temperature Steam Propagation Analysis Function

*Mingxi Wei1, Hiroyuki Fujita1, Daisuke Fujiwara1, Tooru Shimano1, Takashi Takeuchi2, Ken Nosaka2, Naoki Takahashi2 (1. TEPCO SYSTEMS CORPORATION, 2. TOKYO ELECTRIC POWER COMPANY Holdings Inc.)

Keywords:internal flooding, steam transfer, GOTHIC

A Function to estimate equipment integrity in reactor building under high temperature and pressure pipe break/leak is implemented in the system. This function utilizes GOTHIC code as an steam propagation analysis engine, which provides room temperature and humidity trend with common graphical user interface with internal flooding analysis function.