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Kondo, Satoru; Deshimaru, Takehide; Konomura, Mamoru
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Safe Technologies and Sustainable Scenarios (FR-13) (USB Flash Drive), 6 Pages, 2013/03
Monju, a 280-MWe prototype sodium-cooled fast reactor of, restarted its test operation in 2010. The zero-power tests were successfully conducted. It's major achievement was accurate prediction of reactor physics parameters with a core including americium-rich fuel. The reactor, however, has been put into a stand-by mode again since the 3.11 Fukushima-Daiichi accident. The roles shall not change: demonstrating stable power generation and actinide burning; providing technology and knowledge base for future SFRs; and using the plant as an international research facility.
Deshimaru, Takehide
Genshiryoku eye, 57(3), p.30 - 35, 2011/03
The prototype fast breeder reactor (FBR) MONJU resumed the system startup test (SST) on May 6th 2010 after five months and fourteen years shutdown since the sodium leakage of the secondary heat transport system on December 1995. Core confirmation test (CCT) is the first step of SST which consists of three steps, and finished on July 22nd after 78 days test. CCT is composed 20 test items including confirmation of the safety criteria and measurement of several core performance data. Through CCT, were demonstrated the stable operation and the accuracy of the prediction on the core performance after long-term shutdown and refueling. The several core physics characteristic data especially by accumulated minor actinide americium-241 will be contributed to the research and development of FBR. And the operation and maintenance experiences gained in CCT are also very variable to development next FBR power plant.
Morizono, Koji; Takeuchi, Norihiko; Takayama, Koichi; Deshimaru, Takehide; Mukai, Kazuo
Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 5 Pages, 2008/10
Prototype fast breeder reactor Monju is the first power generating FBR in Japan which is a plant for research & development to demonstrate reliability of fast breeder reactor as a power plant and establish sodium handling technology etc. Monju started construction in 1985, achieved initial criticality in 1994 and attained 40% output in 1995, however the sodium leak accident occurred during the test operation at the end of that year. Since then, the plant remained shut down for 12 years. In this subject, our efforts for the restart of this long term shut down plant will be presented.
Usami, Shin; Suzuoki, Zenro; Deshimaru, Takehide; Hikichi, T.*; Nakashima, F.*
Proceedings of 11th International Symposium on Reactor Dosimetry (ISRD-11), p.389 - 396, 2003/00
None
Okawachi, Yasushi; Kitano, Akihiro; Suzuki, Takayuki; Okimoto, Yutaka; Usami, Shin; Deshimaru, Takehide
no journal, ,
no abstracts in English
Okawachi, Yasushi; Kitano, Akihiro; Suzuki, Takayuki; Okimoto, Yutaka; Usami, Shin; Deshimaru, Takehide
no journal, ,
no abstracts in English
Deshimaru, Takehide
no journal, ,
In Tsuruga Summer Institute on Nuclear Energy 2010, the restart, system start-up test(SST) of MONJU and it's use for the research and development of fast breeder reactor system. Monju restarted on May 6 in 2010 after 14 years and 5 month shutdown and the core confirmation test, the first step of SST, was competed on schedule's consists of three steps: Core Confirmation Test, 40%-output Confirmation Test, and Power Rising Test. After finishing these steps, the full power operation will start. Based on the experiences of SST and the full power operation, there are several R&D plans: validation of the reliability of the power generating plant's operational safety, establishment of sodium handling technology. The plans include the validations of codes concerning of core analysis or thermo-hydraulic analysis, the developing in-service inspection devices and etc.
Deshimaru, Takehide
no journal, ,
The prototype fast breeder reactor (FBR) MONJU resumed the system startup test (SST) on May 6th 2010 after five months and fourteen years shutdown since the sodium leakage of the secondary heat transport system on December 1995. Core confirmation test (CCT) is the first step of SST which consists of tree steps, and finished on July 22nd after 78days test. CCT is composed 20 test items including confirmation of the safety criteria and measurement of several core performance data. Through CCT, were demonstrated the stable operation and the accuracy of the prediction on the core performance after long-term shutdown and refueling. The several core physics characteristic data especially by accumulated minor actinide amerisiumu-241 will be contributed to the research and development of FBR.
