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JAEA Reports

Japan - IAEA Joint Nuclear Energy Management School 2016

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.

Journal Articles

Safety of fast breeder reactor; A Lecture at the Tsuruga College

Kitabata, Takuya

Nippon 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.

Journal Articles

Extrinsic sensors and external signal generator for advanced transparency framework

Katsumura, Soichiro; Kitabata, Takuya; Irie, Tsutomu; Suzuki, Mitsutoshi; Hashimoto, Yu; Kato, Keiji*

Transactions of the American Nuclear Society, 99(1), P. 780, 2008/11

JAEA Reports

Proceedings 4th Tsuruga International Energy Forum

Sakakibara, Yasuhide; IKEDA, Hiroshi; Yokota, Yoshio; Kitabata, Takuya; YAMAGUCHI, Tomohiko

JNC-TN4200 2004-001, 317 Pages, 2004/08

JNC-TN4200-2004-001.pdf:24.97MB

None

JAEA Reports

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

JAEA Reports

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

Journal Articles

Design and Operating Experience of CECE D$$_{2}$$O Upgrader in Fugen

Kitabata, Takuya; Kiyota, Shiko; *; Senrui, Shiro*; *

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 1152 Pages, 2003/00

None

Journal Articles

Activities for the Fugen Decommissioning Project in the Future

; ; 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.

Journal Articles

Development and Experience of Tritium Control in Heavy Water Reactor "FUGEN"

Kitamura, Koichi; Kitabata, Takuya; Matsushima, Akira

Purazuma, Kaku Yugo Gakkai-Shi, 78(12), p.1313 - 1318, 2002/12

None

Journal Articles

TWENTY FOUR YEAR'S EXPERIENCE OF WATER CHEMISTRY IN THE FUGEN NUCLEAR POWER STATION

; Kitabata, Takuya; ; ; ;

Dai-13-Kai Kantaiheiyo Genshiryoku Kaigi 2002, 0 Pages, 2002/00

None

Journal Articles

Tritium handling in a 165MW power generating heavy water reactor, Fugen

Kitabata, Takuya

Proceedings of 6th International Conference on Tritium Science and Technology (TRITIUM 2001), 3(2), 0 Pages, 2002/00

None

Journal Articles

Tritium Handling Experience in 165 MWE Power Generating Station, Fugen

Kitabata, Takuya

Fusion Science and Technology, 41(3, Part.2), p.356 - 360, 2001/05

None

JAEA Reports

None

*; *; Kitabata, Takuya*; 8 of others*

PNC-TN3410 89-011, 617 Pages, 1989/07

PNC-TN3410-89-011.pdf:18.87MB

None

JAEA Reports

Experience with hydrogen addition water chemistry in the Fugen nuclear power station

Kitabata, Takuya*; Ueda, Shiho*; Takahashi, Hidetaka; Kanesaki, Takuno*; Iwai, Masaki*

PNC-TN3410 88-011, 22 Pages, 1988/04

PNC-TN3410-88-011.pdf:0.43MB

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.

JAEA Reports

Experience of water chemistry in HWR

*; Kitabata, Takuya*

PNC-TN341 83-15, 18 Pages, 1983/10

PNC-TN341-83-15.pdf:0.45MB

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.

Journal Articles

None

; Kitabata, Takuya; ; Okubo, Seishiro

Donen Giho, 58 Pages, 

Journal Articles

None

; ; Kitabata, Takuya

Hoken Butsuri, 19(3), 239 Pages, 

Oral presentation

A Demonstration of advanced nuclear fuel cycle transparency concepts

Inoue, Naoko; Irie, Tsutomu; Kitabata, Takuya; Rochau, G.*; York, D.*; Mendez, C.*

no journal, , 

Japan Atomic Energy Agency (JAEA) and Sandia National Laboratories (SNL) have entered cooperative program, in 2005, to demonstrate a methodology capable assessing proliferation risk in support of overall plant transparency. Earlier, both organizations have preliminary discussion to develop the methodology. The Advanced Fuel Cycle Transparency Framework Concept is being implemented at the Fuel Handling Training Model designed for "Monju", prototype Fast Reactor at the International Nuclear Information and Training Center (ITC) of Tsuruga Head Office, the Japan Atomic Energy Agency (JAEA). "Monju" is fully automated facility and the training model reproducts the entire Monju fuel handling process. The training model is used to generate and transmit information to a secure database at ITC located by Monju site. A computer syncronized to the visible movements in the model mimicking process data supply data. The database is accessible to analyst at SNL via encryption and virtual private network (VPN). The data stream is fed into the "Transparency Software" for real time analysis when the model is being exeicised. "Transparency Software" is expected to monitor the information from the model and to calcurate the prolifearation risk by compared with expected values. This concept will be able to expamd the ability to enable effective transparency system in the aspect of safety and lagitmate use of nuclear material and technology, to contribute the transparency concept among international communities or between a state and IAEA, for the future nuclear fuel cycles. This paper will describe the concept, implememtation plan and status of the demonstration project, and progress toward the first demonstration of the system.

Oral presentation

Development of transparency framework using Monju; Demo study using fuel handling training model

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.

Oral presentation

Development of transparency framework concept using Monju fuel handling model

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

22 (Records 1-20 displayed on this page)