Toshio Koya - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101020520026392
researchmap Member ID: R000021769

Research Areas

Other / Other /

Papers

Effects of silicon, carbon and molybdenum additions on IASCC of neutron irradiated austenitic stainless steels

Nakano Junichi, Miwa Yukio, Koya Toshio, Tsukada Takashi

Journal of Nuclear Materials, 329-333(Part1) 643-647, Aug, 2004 Peer-reviewed
Integrity confirmation tests and post-irradiation test plan of the HTTR first-loading fuel

Sawa Kazuhiro, Sumita Junya, Ueta Shohei, Suzuki Shuichi*, Tobita Tsutomu*, Saito Takashi, Minato Kazuo, Koya Toshio, Sekino Hajime

Journal of Nuclear Science and Technology, 38(6) 403-410, Jun, 2001 Peer-reviewed
Fission product release behavior from individual coated fuel particles for high-temperature gas-cooled reactors

Minato Kazuo, Sawa Kazuhiro, Koya Toshio, Tomita Takeshi, Ishikawa Akiyoshi, Baldwin C. A.*, Gabbard W. A.*, Malone C. M.*

Nuclear Technology, 131(1) 36-47, Jul, 2000 Peer-reviewed

Misc.

Decommissioning program and future plan for Research Hot Laboratory, 2

Koya Toshio, Nozawa Yukio, Hanada Yasushi, Ono Katsuto, Kanazawa Hiroyuki, Nihei Yasuo, Owada Isao

Dekomisshoningu Giho, (42) 41-48, Sep, 2010
Decommissioning of the Research Hot Laboratory; Dismantlement works of lead cells 1

Nozawa Yukio, Koya Toshio, Sekino Hajime

JAEA-Technology 2007-019, 23, Mar, 2007
Decommissioning program and future plan for research hot laboratory

Umino Akira, Saito Mitsuo, Kanazawa Hiroyuki, Koya Toshio, Okamoto Hisato, Sekino Hajime*, Nishino Yasuharu

Dekomisshoningu Giho, (32) 2-12, Sep, 2005
Development of facility for in-situ observation during slow strain rate test for irradiated materials

Nakano Junichi, Tsukada Takashi, Tsuji Hirokazu, Terakado Shogo, Koya Toshio, Endo Shinya

JAERI-Tech 2003-092, 54, Jan, 2004
Development of corrosion testing equipment to evaluate corrosion resistance in fuel dissolved solution (Contract research)

Motooka Takafumi, Terakado Shogo, Koya Toshio, Kiuchi Kiyoshi

JAERI-Tech 2001-089, 52, Jan, 2002
Selection of dissolution process for spent fuels and preparation of corrosion test solution simulated to dissolver (Contract research)

Motooka Takafumi, Terakado Shogo, Koya Toshio, Hamada Shozo, Kiuchi Kiyoshi

JAERI-Tech 2001-023, 29, Mar, 2001
Retention of fission product cesium in ZrC coated fuel particles for high-temperature gas-cooled reactors

Minato Kazuo, Ogawa Toru, Koya Toshio, Sekino Hajime, Tomita Takeshi

Journal of Nuclear Materials, 279(2-3) 181-188, Jun, 2000
ZrC-coated particle fuel for high temperature gas-cooled reactors

Minato Kazuo, Ogawa Toru, Sawa Kazuhiro, Sekino Hajime, Koya Toshio, Kitagawa Isamu, Ishikawa Akiyoshi, Tomita Takeshi

Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 8, Jan, 1999

Presentations

Decommissioning program of research hot laboratory in JAEA; Technical review of dismantling works for the lead cells

Shiina Hidenori, Nozawa Yukio, Ono Katsuto, Nishi Masahiro, Koya Toshio, Ishikawa Akiyoshi

50 Years of HOTLAB; Preparing for Tomorrow

Industrial Property Rights

1664508 放射性試料用切断機の砥石固定装置

園部清美, 高橋五志生, 石川明義, 高野利夫, not registered