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Journal Articles

Situation of MONJU/Research and development of MONJU

Takayama, Koichi

Genshiryoku Nenkan 2009, p.48 - 54, 2008/10

The cycle of FBR will be rapidly improved by constructing the recycling system of the energy.

Journal Articles

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.

JAEA Reports

Study of ageing effect of long-term storage fuel in prototype fast breeder reactor Monju

Kato, Yuko; Umebayashi, Eiji; Okimoto, Yutaka; Okuda, Eiichi; Takayama, Koichi; Ozawa, Takayuki; Maeda, Seiichiro; Matsuzaki, Masaaki; Yoshida, Eiichi; Maeda, Koji; et al.

JAEA-Research 2007-019, 56 Pages, 2007/03

JAEA-Research-2007-019.pdf:6.79MB

In order to resume the System Startup Test (SST) of Monju, replacement fuel have to be loaded in exchange for some of initial fuel now loaded in the core to compensate core reactivity lost by decay of Pu-241 in them. The replacement fuel were being stored either in sodium in an ex-vessel storage tank or in air in a storage rack for about 10 years since their fabrication. The initial fuel were irradiated during the SST which was suspended in the end of 1995 and then stayed being loaded in the sodium-circulated core. As this long-term storage and loading may deteriorate mechanical integrity of the assemblies, a study has been made thoroughly on its thermal-hydraulic, structural and material effects on them that might be caused by irradiation in the core, sodium and mechanical environment. The study has shown that the mechanical integrity of them is well maintained even with this long-term storage and loading.

Journal Articles

The Pressure tube inspection and integrity evalution in Fugen

Ishizuka, Nobuo; Takayama, Koichi; Nakai, Kozo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 0 Pages, 2003/00

None

Oral presentation

Keeping situation and use of the fuel of prototype FBR MONJU

Ito, Kazumoto; Ikeda, Hiroshi; Takayama, Koichi; Okuda, Eiichi

no journal, , 

no abstracts in English

Oral presentation

Reflection from the experience of trouble cases etc. in fast reactors of foreign countries

Ito, Kazumoto; Ikeda, Hiroshi; Takayama, Koichi; Tomobe, Katsuma; Usami, Shin

no journal, , 

no abstracts in English

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