Session Details
[2H09-15]Fast Reactor 2
Thu. Sep 11, 2025 2:45 PM - 4:45 PM JST
Thu. Sep 11, 2025 5:45 AM - 7:45 AM UTC
Thu. Sep 11, 2025 5:45 AM - 7:45 AM UTC
Room H(AIM3F Exhibition Hall D)
Chair:Koji Morita(Kyushu Univ.)
[2H09]Study on Core Disruptive Accidents of Metal-Fueled Sodium-Cooled Fast Reactors(1) Project Overview
*Hidemasa Yamano1, Yoshitaka Fukano1, Kennichi Matsuba1, Takanari Ogata2, Koichi Ohta2, Yuji Ohishi3, Koji Morita4, Yumi Yamada5, Sadae Shimada5, Saishun Yamazaki6 (1. JAEA, 2. CRIEPI, 3. Osaka Univ., 4. Kyushu Univ., 5. MFBR, 6. NFD)
[2H10]Study on Core Disruptive Accidents of Metal-Fueled Sodium-Cooled Fast Reactors(2) Thermophysical Property Evaluation of U-10wt%Zr and U-10wt%Zr-20wt%Fe Melts
*Yuji Ohishi1, Ryu Yano1 (1. Osaka Univ.)
[2H11]Study on Core Disruptive Accidents of Metal-Fueled Sodium-Cooled Fast Reactors(3) Measurement for eutectic reaction rate between U-Zr alloys and Fe/stainless steel
*Saishun YAMAZAKI1, Atsushi OHUCHI1, Kan SAKAMOTO1, Takumi SATO2, Takanari OGATA2, Hidemasa YAMANO2 (1. NFD, 2. JAEA)
[2H12]Study on Core Disruptive Accidents of Metal-Fueled Sodium-Cooled Fast Reactors(4) Plan of the measurement for eutectic reaction rate between U-Pu-Zr alloys and stainless steel
*Takumi Sato1, Takashi Onishi1, Shinji Sasaki1, Yoshihiro Sekio1, Yoko Akutsu1, Koji Maeda1, takanari Ogata1,2, Hidemasa Yamano1 (1. JAEA, 2. CRIEPI)
[2H13]Study on Core Disruptive Accidents of Metal-Fueled Sodium-Cooled Fast Reactors(5) PIRT analysis for initiating phase in the ULOF high power scenario
*Yoshitaka Fukano1, Sadae Shimada2, Yamada Yumi2, Ogata Takanari1,3, Hirokazu Ohta3, Shinya Ishida1, Hidemasa Yamano1, Shigenobu Kubo1 (1. JAEA, 2. MFBR, 3. CRIEPI)
[2H14]Study on Core Disruptive Accidents of Metal-Fueled Sodium-Cooled Fast Reactors(6) Validation of a metal fuel core disruptive accident analysis code by using loss-of-flow accident test data
*Hirokazu Ohta1, Takanari Ogata1, Hidemasa Yamano2, Sadae Shimada3, Yumi Yamada3 (1. CRIEPI, 2. JAEA, 3. MFBR)
[2H15]Study on Core Disruptive Accidents of Metal-Fueled Sodium-Cooled Fast Reactors(7) Development of the SIMMER code metal fuel version and preliminary reactor analysis
*Shinya Ishida1, Kenichi Matsuba1, Hidemasa Yamano1 (1. JAEA)