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Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Nakamichi, Masaru; Katsuyama, Kozo; Iwamatsu, Shigemi; Hasegawa, Teiji; Kodaka, Hideo; Takatsu, Hideyuki; et al.
JAEA-Technology 2009-007, 168 Pages, 2009/03
JAEA-Technology-2009-007.pdf:31.88MB
In-pile functional tests of breeding blankets have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in the International Thermonuclear Experimental Reactor (ITER). In preparation for the in-pile functional tests, JAEA has been being performed irradiation experiments of lithium titanate (Li
TiO
), which is the first candidate of solid breeder materials for the blanket of the demonstration reactor (DEMO) under designing in Japan. The present report describes (1) results of a detailed design and trial fabrication tests of a dismantling apparatus for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA, and (2) results of a preliminary investigation of a glove box facility for post-irradiation examinations (PIEs). In the detailed design of the dismantling apparatus, datailed specifications and the installation methods were examined, based on results of a conceptual design and basic design. In the trial fabrication, cutting tests were curried out by making a mockup of a cutting component. Furthermore, a preliminary investigation of a glove box facility was carried out in order to secure a facility for PIE work after the capsule dismantling, which revealed a technical feasibility.
Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Kodaka, Hideo; Katsuyama, Kozo; Kitajima, Toshio; Takahashi, Kozo; Tsuchiya, Kunihiko; Nakamichi, Masaru; et al.
JAEA-Technology 2008-010, 68 Pages, 2008/03
JAEA-Technology-2008-010.pdf:11.31MB
In-pile functional tests of breeding blankets for fusion reactors have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in ITER. The present report describes a conceptual investigation and a basic design of the dismantling process for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA. In the present design, the irradiation capsule is cut by a band saw; the released tritium is recovered safely by a purge-gas system, and is consolidated into a radioactive waste form. Furthermore, adoption of the inner-box enclosing the dismantling apparatus has brought a prospect to be able to utilize an existing hot cell (beta-
cell) equipped with usual wall material permeable to tritium, without extensive refurbishing of the cell. Thus, the present study has indicated the feasibility of the present dismantling process for the irradiated JMTR capsules containing tritium.
Kodaka, Hideo; Nakamura, Yasuo
PNC TN9470 96-001, 79 Pages, 1995/11
Three different kinds of In-Cell Crane Equipment were designed from 1989 to March 1990, manufactured, and installed in the Fuel Monitoring Facility (FMF) Extension in 1994. These equipments consists of an in cell crane, a power manipulator, and a repair hoist. Their outline is shown as follows. (1)The in cell crane was designed to handle and transfer the reactor components such as irradiated fuel subassemblies, and/or heavy equipments in the examination cell. Its basic function and structure is similar to an industrial ceiling run way crane, except for its design for hot lob. use. Namely, this is also designed specially to permit their remote dismantling and assembling in the cell, because workers have impossible access to the crane due to high radioactivity and nitrogen atmosphere in the cell, when a trouble occurs on the in cell crane itself. (2)The power manipulator has various function such as transferring specimens lighter than a few ten kilograms within the cell, and/or helping operation and maintenance of other equipments. This manipulator is operated by a computer, so that it is able to transfer a rack filled with irradiated fuel pins automatically by changing its manipulator arm to specially designed tool. It has remote dismantling and assembling capability as same as the in cell crane. (3)The repair hoist was designed to hoist a bridge, a carriage and trolley of the in cell crane and the power manipulator up and down, in case of their maintenance. It was installed in the third floor of the FMF Extension and reach the crane and the manipulator through ceil of the examination cell. This enable complete remote maintenance of these equipments.
; Kodaka, Hideo;
BNES conference fuel management and handling, 0 Pages, 1995/00
None
Kodaka, Hideo*; ; Ogata, Yoshiaki; Matsushima, Hideya*
PNC TN9410 85-141, 85 Pages, 1985/07
None
Kodaka, Hideo*; ; Ogata, Yoshiaki
PNC TN9410 84-126, 78 Pages, 1984/10
Nondestructive Examination of Subassembly and its fuel elements of the "JOYO" MK-I Core Fuel Subassembly (Fab. No. PPJX12, average burnup 38,900 MWD/KTM) has been performed. The purposes of the Examination were for the first time to obtain the detailed irradiation data on this Subassembly which had reached to the next highest burnup throughout the "JOYO" MI-I project, and to investigate the influence of sodium corrosion on the subassembly for which the sodium removal washing had been intentionally net enough performed. The results of the examination are summarized below. (1)The subassembly and its fuel elements showed no failure. (2)In general the irradiation characteristics of the subassembly in each item of PIE were nearly the same as those of the subassembly (Fab. No. PPJX13). (3)No extrarrdinal behaviors have not been found. (4)Sodium corrosion on material surface has not been observed in the present nondestructive examination.
Isozaki, Ryosuke; Mizukoshi, Yasutaka; Katsuyama, Kozo; Kodaka, Hideo
no journal, ,
no abstracts in English
Ishimi, Akihiro; Kodaka, Hideo; Katsuyama, Kozo; Furuya, Hirotaka
no journal, ,
In order to observe the structural change in the interior of irradiated fuel assembly, the non-destructive post irradiation examination technique using X-ray computer tomography (X-ray CT) was developed. In this X-ray CT system, the 12 MeV X-ray pulses were used in synchronization with the switch-in of the detector to minimize the effects of the ray emissions from the irradiated fuel assembly. This method was applied to a fuel assembly irradiated in the experimental fast reactor JOYO, and images were successfully obtained of transverse cross sections at different heights of fuel assembly along its axis for the first time in the world. This X-ray CT technique can substitute non-destructive PIEs for a number of destructive PIEs. This has a great advantage to enhance efficiency of PIE and greatly reduces radioactive wastes generated during PIE.
Sasaki, Shinji; Soga, Tomonori; Maeda, Koji; Katsuyama, Kozo; Kodaka, Hideo
no journal, ,
no abstracts in English
