Yuya Imaizumi - Presentations - researchmap

Presentations

11

Entries per page

Visualization of gas-liquid two-phase flow in a packed bed of spheres

Fujitsu Akito*, Odaira Naoya*, Ito Daisuke*, Ito Kei*, Saito Yasushi*, Imaizumi Yuya, Matsuba Kenichi, Kamiyama Kenji

日本機械学会第98期流体工学部門講演会
Study on coolant behavior in damaged core of sodium-cooled fast reactor, 5; Effect of pipe and particle sizes on pressure drop in simulated debris bed

Ishiguro Akinari*, Ito Daisuke*, Ito Kei*, Saito Yasushi*, Imaizumi Yuya, Matsuba Kenichi, Kamiyama Kenji

日本原子力学会2019年秋の大会
Study on coolant behavior in damaged core of sodium-cooled fast reactor, 4; Evaluation of pressure drop through simulated debris bed in consideration of porosity distribution

Kurisaki Tatsuya*, Ito Daisuke*, Ito Kei*, Saito Yasushi*, Imaizumi Yuya, Matsuba Kenichi, Kamiyama Kenji

日本原子力学会2018年秋の大会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 6; Effectiveness evaluations of countermeasures against anticipated transient without scram

Imaizumi Yuya, Yamada Fumiaki, Nishimura Masahiro, Mori Takero, Fukano Yoshitaka

日本原子力学会2018年春の年会
Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors, 4; Effects of test conditions on dispersion and sedimentation of molten-material in a shallow water pool

Emura Yuki, Matsuba Kenichi, Isozaki Mikio, Imaizumi Yuya, Kamiyama Kenji

日本原子力学会2017年秋の大会
Safety evaluations for MONJU during decommissioning phase, 2; Conservative thermal evaluations on fuel integrity

Mori Takero, Sotsu Masutake, Imaizumi Yuya, Yoshimura Kazuo, Fukano Yoshitaka

日本原子力学会2017年秋の大会
Validation of an analysis code on initiating phase of core disruptive accident in sodium-cooled fast reactors by CABRI in-pile experiments

Imaizumi Yuya, Fukano Yoshitaka

原子力関係科学技術の基礎的研究の動向調査委員会
Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors, 1; Overall plan

Kamiyama Kenji, Matsuba Kenichi, Isozaki Mikio, Imaizumi Yuya, Suzuki Toru, Emura Yuki

日本原子力学会2016年秋の大会
Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors, 2; Experimental study on molten-metal discharge into a shallow water pool

Imaizumi Yuya, Kamiyama Kenji, Matsuba Kenichi, Isozaki Mikio, Suzuki Toru, Emura Yuki

日本原子力学会2016年秋の大会
Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors, 4 Analysis of EFM1 test

Imaizumi Yuya, Fukano Yoshitaka

日本原子力学会2016年春の年会
Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors,1; Summary of SAS4A code and CABRI in-pile experiments

Fukano Yoshitaka, Imaizumi Yuya, Yoshioka Naonori*, Akahori Hisashi*

日本原子力学会2016年春の年会