Recent progress and status of Monju

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

http://www.iaea.org/nuclearenergy/nuclearpower/Downloadable/Meetings/2013/2013-03-04-03-07-CF-NPTD/T9.1/T9.1.deshimaru.pdf

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.

Efforts toward the restart of fast breeder reactor Monju

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.

Construction experience and renovation plan on MONJU

Russian Forum for Science and Technology, FAST NEU, 0 Pages, 2003/00

Monju

Applicability of the three-dimensional transport code tort to the shielding analysis of the prototype FBR Monju

Shiraki, Takako*; Usami, Shin; Suzuoki, Zenro; ; *; Tada, Keiko*

Proceedings of International Conference on Super Computing In Nuclear Application, 0 Pages, 2002/00

None

Reaction rate distribution measurement and the core performance evaluation in the prototype FBR Monju

Usami, Isao; Suzuoki, Zenro; ; Nakashima, Fumiaki

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Reactor physics measurements at start-up of MONJU

Nakashima, Fumiaki; ; Usami, Isao; ; ; 2 of others*

Proceedings of International Conference on the Physics of Reactors (PHYSOR '96), E-76- Pages, 1996/00

None

Adjustments to the WIMS-ATR nuclear data library

*; *; Fukumura, Nobuo*

PNC TN941 85-167, 66 Pages, 1985/11

PNC-TN941-85-167.pdf:1.37MB

Calculational accuracy of the WIMS-ATR code is analized based on post irradiation examination (PIE) data of Fugen MOX fuel and micro-parameter data of DCA fuel assemblies. In order to minimize discrepancies between calculational results by the WIMS-ATR and experimental ones, the nuclear library data in the WIMS-ATR are adjusted or added. The results are as follows. (1)The errors of heavy nuclide number density ratio by the WIMS-ATR burn-up calculation were max. 0.002% for uranium isotope ratio and max. 2% for isotope ratio at 16 GWd/t burn-up. (2)The error of Pu ratio was much decreased by adding Pu burn-up and product chain to the WIMS-ATR nuclear daTa library. (3)The effects of Pu or U cross section changes were calculated. The adjustments to the WIMS-ATR nuclear data library were proposed to decrease the error of Pu isotopic ratio to max. 1%. (4)The error of micro-parameter calculation was decreased by the adjustments.

Prototype FBR Monju system start up test "zero power reactor physics test", 1; Summary

Okawachi, Yasushi; Kitano, Akihiro; Suzuki, Takayuki; Okimoto, Yutaka; Usami, Shin; Deshimaru, Takehide

no journal, , 

no abstracts in English

MONJU system start-up test and future aspect

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.