Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Yamaguchi, Mika; Hidaka, Akihide; Ikuta, Yuko; Murakami, Kenta*; Tomita, Akira*; Hirose, Hiroya*; Watanebe, Masanori*; Ueda, Kinichi*; Namaizawa, Ken*; Onose, Takatoshi*; et al.
JAEA-Review 2017-002, 60 Pages, 2017/03
Since 2010, IAEA has held the NEM School to develop future leaders who plan and manage nuclear energy utilization in their county. Since 2012, JAEA together with Japan Nuclear HRD Network, University of Tokyo, Japan Atomic Industrial Forum and JAIF International Cooperation Center have cohosted the school in Japan in cooperation with IAEA. Since then, the school has been held in Japan every year. In 2006, Japanese nuclear technology and experience, such as lessons learned from the Fukushima Daiichi Nuclear Power Plant accident, were provided to offer a unique opportunity for the participants to learn about particular cases in Japan. Through the school, we contributed to the internationalization of Japanese young nuclear professionals, development of nuclear human resource of other countries including nuclear newcomers, and enhanced cooperative relationship with IAEA. Additionally, collaborative relationship within the network was strengthened by organizing the school in Japan.
Kitabata, Takuya
Nihon Anzengaku Kyoiku Kenkyu Kaishi, 3, p.65 - 71, 2010/08
Authors have given lectures on "Nuclear Safety" at the Tsuruga College to educate the students to obtain knowledge to judge the safety and values of nuclear power generation as a kind of literacy since 2003. This paper describes the contents of the final lecture of the "Nuclear Safety" on the "Safety of Fast Breeder Reactors (FBRs)". The paper explains the possibility of the positive void reactivity of FBRs and re-criticality in the unprotected loss of flow (ULOF) condition. As additional issues, sodium-water reaction and sodium leakage are also described. The risk communication booklet on the "Safety of Monju" as an activity for public relations is also explained.
Katsumura, Soichiro; Kitabata, Takuya; Irie, Tsutomu; Suzuki, Mitsutoshi; Hashimoto, Yu; Kato, Keiji*
Transactions of the American Nuclear Society, 99(1), P. 780, 2008/11
Sakakibara, Yasuhide; IKEDA, Hiroshi; Yokota, Yoshio; Kitabata, Takuya; Yamaguchi, Toshihiko
JNC TN4200 2004-001, 317 Pages, 2004/08
None
Kitabata, Takuya; Yamato, Yoshiaki; Hochin, Koji; Morita, Satoru
JNC TN4410 2003-011, 39 Pages, 2003/09
None
Kitabata, Takuya; Shimono, Kimihiro; sekiguchi, mineo; Matsushima, Akira
JNC TN4410 2003-004, 42 Pages, 2003/03
None
Kiyota, Shiko; Kitabata, Takuya; Ninomiya, Ryuji*; Senrui, Shiro*; Isomura, Shohei*
Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 7 Pages, 2003/00
no abstracts in English
; Kitabata, Takuya; Kiyota, Shiko; Iguchi, Yukihiro; Tajiri, Tsuyoshi
Saikuru Kiko Giho, (20), 151 Pages, 2003/00
Based on the report titled "Activities of Fugen NPS after permanent shutdown" , Fugen has been preparing for the project, including necessary development of technologies. The development of decommissioning for Fugen is divided into two areas.
Kitamura, Koichi; Kitabata, Takuya; Matsushima, Akira
Purazuma, Kaku Yugo Gakkai-Shi, 78(12), p.1313 - 1318, 2002/12
None
; Kitabata, Takuya; ; Takagi, Hisatsugu; ;
Dai-13-Kai Kantaiheiyo Genshiryoku Kaigi 2002, 0 Pages, 2002/00
None
Kitabata, Takuya
Proceedings of 6th International Conference on Tritium Science and Technology (TRITIUM 2001), 3(2), 0 Pages, 2002/00
None
Matsushima, Akira; ; ; ; ; ;
Saikuru Kiko Giho, (11), p.81 - 91, 2001/06
None
Kitabata, Takuya
Fusion Science and Technology, 41(3, Part 2), p.356 - 360, 2001/05
None
; ; ;
PNC TN9410 97-023, 186 Pages, 1997/02
Zinc addition to the coolant of the reactor core of ATR "Fugen" is being planned for the purpose of reducing the radiation exposures. In order to confirm the integrity of the materials used in the reactor coolant system, a matrerial corrosion test with zinc addition (10 ppb) and that without zinc addition were performed for 2,000 h under the condition simulating the reactor core of "Fugen". Main results obtained from these tests are as follows : (1)For Zr-2.5%Nb alloy used for the pressure tubes, weight gain during the corrosion test tended to be large by zinc addition. It was concluded that this weight gain would not affect the integrity the pressure tube, because the reduction of the thickness of the base metal was estimated around 1 m during the corrosion test (extrapolated value for 100,000 h was about 10m). The hydrogen absorption during the test was not observed. (2)Some specimens of stainless steels showed weight loss caused by metal release from corroded surface without zinc addition. This weight loss is clearly observed for less corrosion resistance steels. Since all of the specimens tested with zinc addition showed slight gain of the weight, it is confirmed that zinc addition suppressed the corrosion of stainless steels. (3)From surface analyses after the corrosion test, it was clarified that zinc was concentrated in the surface oxide film, and that the morphology was changed. It was considered that the difference of weight changes between the specimens corroded with zinc addition and that without zinc addition was attributed to the difference of the composition and the morphology of the surface oxide films.
; ; ; ;
Nihon Genshiryoku Gakkai-Shi, 38(6), p.511 - 520, 1996/00
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)None