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Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka
JAERI-Tech 2004-071, 85 Pages, 2005/02
JAERI-Tech-2004-071.pdf:4.81MB
To facilitate easy maintainability, the ITER divertor is divided into 60 cassettes, which are transported for replacement using the remote equipments. The cassette of 25 tons has to be transported and installed with a positioning accuracy less than 2 mm in the limited space under the intense gamma radiation field. Based on these requirements, the following design and tests were performed. (1) Link mechanism was studied to apply to the transportation. A compact mechanism with links is designed through the optimization of the link angle taking account of space requirement and force efficiency. The lifting capacity of 30 tons has been demonstrated. (2) Compact link mechanism was also studied to apply for locking of the cassette. The final positioning accuracy of 0.03 mm for installation from the initial positioning error of 5 mm has been demonstrated. (3) Sensor-based control of the remote equipment was tested using simple sensors. It is found that the positioning accuracy of 0.16 mm has been achieved and this value is sufficient.
Tamaki, Hitoshi; Yoshida, Kazuo; Watanabe, Norio; Muramatsu, Ken
Proceedings of International Topical Meeting on Probabilistic Safety Analysis (PSA '05) (CD-ROM), 11 Pages, 2005/00
A probabilistic safety assessment (PSA) procedure for Mixed Oxide (MOX) fuel fabrication facilities is being developed applicable to nuclear facilities at Japan Atomic Energy Research Institute (JAERI). As part of the PSA procedure, the approach to hazard analysis was established, which consists of two analysis steps: Functional Failure Modes and Effects Analysis (Functional FMEA) and Risk Matrix Analysis. In the Functional FMEA, a variety of functions of equipment composing the facility are analyzed to identify potential abnormal events exhaustively. In the second step, these potential events are screened to select abnormal events as candidate events to be analyzed for frequency and consequence by using two-dimensional matrix based on the rough estimation of likelihood and maximum unmitigated release of radioactive material. The applicability of the hazard analysis approach established was demonstrated through the trial application of the PSA procedure being developed to model plant of MOX fuel fabrication facility.
F.Bianchi*; L.Burgazzi*; ; Katsuta, Hiroji; Konishi, Satoshi; Takeuchi, Hiroshi; Martone, M.*
Proc. of 2nd Int. Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98), p.556 - 561, 1998/00
no abstracts in English
Konishi, Satoshi; Yamaki, Daiju; Katsuta, Hiroji; M
slang, A.*; R.Jameson*; Martone, M.*; Shannon, T. E.*
JAERI-Tech 97-056, 9 Pages, 1997/11
no abstracts in English
Enoeda, Mikio; *
Purazuma, Kaku Yugo Gakkai-Shi, 73(8), p.786 - 789, 1997/08
no abstracts in English
Enoeda, Mikio; D.F.Holland*; Matsuda, Yuji; Ohira, Shigeru; Okuno, Kenji; *; Hirata, Shingo*
JAERI-Tech 95-050, 90 Pages, 1995/11
no abstracts in English
JAERI-M 7964, 161 Pages, 1978/12
no abstracts in English
