Oral presentation

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

[2J01-04] Loss of Coolant Accident

Thu. Sep 8, 2022 9:45 AM - 10:50 AM Room J (E1 Bildg.4F No.42)

Chair:Keita Goto(TOSHIBA ESS)

9:45 AM - 10:00 AM

[2J01] Study of downstream effect of the sump screen for post LOCA long term core cooling

(6) Core inlet flow pass test and alternative flow pass test for feeding coolant

*Tomoaki Ogata¹, Kei Higashi¹, Ryo Fukuda¹, Hideyuki Sakata¹, Tetsuya Teramae¹, Yugen Shiratsuchi¹, Hamano Junji² (1. MHI, 2. KEPCO)

10:00 AM - 10:15 AM

[2J02] Study of downstream effect of the sump screen for post LOCA long term core cooling

（7）化学デブリ析出時間に関する基礎試験

*Koudai Inoue¹, Nobuyuki ukai¹, Ryo Fukuda¹, Tetsuya Teramae¹, Tomoaki Ogata¹, Yugen Shiratsuchi¹, Takeshi Enomoto ¹, Hideyuki Sakata¹, Kei Higashi¹, Junji Hamano² (1. Mitsubishi Heavy Industries, 2. Kansai Electric Power Co., Inc.)

10:15 AM - 10:30 AM

[2J03] Study of downstream effect of the sump screen for post LOCA long term core cooling

Thermal-hydraulic analysis of core inlet blockage reflect results of several core blockage tests

*Tetsuya Teramae¹, Ryo Fukuda¹, Tomoaki Ogata¹, Yugen Shiratsuchi¹, Kei Higashi¹, Hideyuki Sakata¹, Tomokazu Aoyagi², Junji Hamano³ (1. MHI, 2. MHI NSE, 3. KEPCO)

10:30 AM - 10:45 AM

[2J04] Development of out of pile test equipment to simulate the dispersal and accumulation behavior of fuel fragments under FFRD condition

*Yuki Shimizu¹, Koichi Ogata¹, Yasunari Shinohara¹, Masaaki Yamato² (1. NDC, 2. MHI)

Time reserved for Chair (10:45 AM - 10:50 AM)

Session information