Refine your search:     
Report No.
 - 
Search Results: Records 1-3 displayed on this page of 3
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Decommissioning program and future plan for research hot laboratory

Umino, Akira; Saito, Mitsuo; Kanazawa, Hiroyuki; Koya, Toshio; Okamoto, Hisato; Sekino, Hajime*; Nishino, Yasuharu

Dekomisshoningu Giho, (32), p.2 - 12, 2005/09

The Research Hot Laboratory (RHL) in Japan Atomic Research Institute (JAERI) was constructed in 1961, as the first one in JAPAN, to perform the examinations of irradiated fuels and materials. RHL with two floors and a basement consists of 10 heavy concrete cells, and 38 lead cells (20 lead cells at present). The RHL had been contributed to research program in JAERI. However, RHL is the one of target 'A middle-range decommissioning plan for the facility in Tokai Research Establishment' as the rationalization program for decrepit facilities in JAERI. Therefore, all PIEs had been finished in March 2003 and the dismantling works of hot cells have been started. The 18 lead cells had been dismantled. The examinations performed in RHL will be succeeded to the RFEF and the WASTEF. The partial area of RHL facility will be used for the temporary storage of un-irradiated fuel samples used for our previous research works and radioactive device generated in proton accelerator facility (called J-PARC).

Oral presentation

Reducing the risk of possessing sodium for Monju

Nishino, Yuki; Kuramoto, Shimpei; Naruse, Keiji; Nishino, Hajime; Goto, Takehiro; Takeuchi, Toru

no journal, , 

no abstracts in English

Oral presentation

Status of Monju decommissioning Phase 2, 2; Efforts to reduce sodium risk and rationalize conservation

Fukushima, Tsubasa; Ono, Fumiyasu; Kuramoto, Shimpei; Nishino, Yuki; Nishino, Hajime; Uchihashi, Masaya

no journal, , 

"Monju" is a nuclear reactor facility that uses sodium to cool the reactor core. In order to reduce the risk of decommissioning, all liquid sodium in the cooling system piping was transferred to the tank and solidified in order to reduce the range of liquid sodium that may leak. Since this was the first attempt of this project, we dealt with issues such as the assessment of the impact on related equipment, the formulation of dedicated procedure manuals, and various operational changes, and streamlined equipment maintenance due to the reduction of the range of liquid sodium ownership, and summarized the results.

3 (Records 1-3 displayed on this page)
  • 1