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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
JAEA-Review-2017-002.pdf:9.41MB
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
JNC-TN4200-2004-001.pdf:24.97MB
None
Kitabata, Takuya; Yamato, Yoshiaki; Hochin, Koji; Morita, Satoru
JNC TN4410 2003-011, 39 Pages, 2003/09
JNC-TN4410-2003-011.pdf:3.14MB
None
Kitabata, Takuya; Shimono, Kimihiro; sekiguchi, mineo; Matsushima, Akira
JNC TN4410 2003-004, 42 Pages, 2003/03
JNC-TN4410-2003-004.pdf:11.33MB
None
O upgrader in FugenKiyota, 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
Kitabata, Takuya
Fusion Science and Technology, 41(3, Part 2), p.356 - 360, 2001/05
None
Kitabata, Takuya*; Ueda, Shiho*; Takahashi, Hidetaka; Kanesaki, Takuno*; Iwai, Masaki*
PNC TN3410 88-011, 22 Pages, 1988/04
Long term trends in water chemistry have been appeared in the Fugen after more than two years' hydrogen water chemistry: an increase of soluble Co-60 concentration and cyclic concentration change of Cr-51 in reactor water, an increase of soluble iron concentration in condensate, and acceleration of radioactivity buildup on pipeworks in the reactor cooling system. The hydrogen addition has been carried out using hydrogen produced by a water electrolysis system on the site. Protective effect of hydrogen addition on mitigating the IGSCC susceptibility of type 304 stainless steel is maintained. Hydrogen uptake by zircaloy-2 is not accelerated with the hydrogen addition.
; Kitabata, Takuya*
PNC TN341 83-15, 18 Pages, 1983/10
Experience of the heavy water and primary coolantchemistry of the Fugen is described. Deterioration has beenobserved in the weak basic ion exchange resins used in theheavy water purification system. Extensive studies to pro-long the life of resins are now going on. Amount of iron inthe feed water has been reduced by means of oxygen injection,operational improvement of condensate demineralizers,hotdrain-off of the feed water circuit,and sufficient flushingprior to operations.
Kitabata, Takuya
no journal, ,
The restart of Monju after 14 year 5 month lay down at May 6, 2010, progress of the system start-up test (SST) and long term R&D program will be presented at the 30th Anniversary of the BN600, a prototype of the fast breeder reactor in Russia. Monju is now conducting the Core Confirmation Test (CCT) as the first step of the SST. The tentative evaluation of the CCT will be reported. The Monju is conducting the 40 % power confirmation test and power raising test in 2011 and 2012, respectively as a part of the SST. Monju aims to realize 1.5 GWd/t of burn-up as a plutonium using fast reactor and minor actinide burning as a long term R&D plan. For shorter range, Monju will be used to validate the core analysis and fluid dynamics codes, to develop in-service inspection devices, to analyze the behavior of radioactive materials and others.
Katsumura, Soichiro; Suzuki, Mitsutoshi; Hashimoto, Yu; Inoue, Naoko; Kitabata, Takuya; Irie, Tsutomu; Rochau, G.*; Cleary, V.*; Mcfadden, K.*; Mendez, C.*
no journal, ,
no abstracts in English
Kitabata, Takuya; Inoue, Naoko; Irie, Tsutomu; Rochau, G.*; Cleary, V.*; York, D.*
no journal, ,
An experimental system of "Transparency Framework" was completed connecting the output signal of the fuel handling training model of the Prototype Fast Breeder Reactor, "Monju" and server computers in the Sandia National Laboratory. The system determines a proliferation risk of the model on a real-time basis using a risk evaluation method. A prospect for application of the "Transparency Framework" to future nuclear systems is discussed.
