Kaoru Otsuka - Presentations

Examination of stabilization treatment method of radioactive aluminum waste, 2; Removal properties of impurities in the stabilization treatment process

Seki Misaki, Ishikawa Koji*, Fujihara Yasuyuki*, Sano Tadafumi*, Nagata Hiroshi, Otsuka Kaoru, Omori Takazumi, Ide Hiroshi, Hori Junichi*, Tsuchiya Kunihiko

日本原子力学会2020年春の年会

Examination of stabilization treatment method of radioactive aluminum waste

Seki Misaki, Ishikawa Koji*, Nagata Hiroshi, Otsuka Kaoru, Omori Takazumi, Suzuki Yumi*, Tanaka Atsushi*, Kawakami Tomohiko*, Ide Hiroshi, Tsuchiya Kunihiko

日本原子力学会2019年秋の大会

Effect of dissolved oxygen and hydrogen on mechanical property of AISI 316 stainless steels in a simulated PWR water conditions

Takeuchi Tomoaki, Nakano Hiroko, Otsuka Kaoru, Hirota Noriaki, Tsuchiya Kunihiko

Nuclear Materials Conference 2018 (NuMat 2018)

Corrosion properties of PCV equivalent materal for simulated severe accident

Nakano Hiroko, Takeuchi Tomoaki, Otsuka Kaoru, Hirota Noriaki, Tsuchiya Kunihiko

Nuclear Materials Conference 2018 (NuMat 2018)

Renewal of JMTR of facility, 2; Renewal of cooling system

Kawamata Takanori, Otsuka Kaoru, Sekine Katsunori, Onoue Ryuji, Koike Sumio, Nishiyama Yutaka

日本原子力学会2012年春の年会