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Asahi, Yoshimitsu; Shimamura, Keisuke*; Kobayashi, Hidekazu; Kodaka, Akira
JAEA-Technology 2021-026, 50 Pages, 2022/03
JAEA-Technology-2021-026.pdf:6.29MB
In Tokai Reprocessing Plant, the highly active liquid waste derived from a spent fuel reprocessing is vitrified with a Liquid-Fed Ceramic Melter (LFCM) embedded in Tokai Vitrification Facility (TVF). For an LFCM, the viscosity of melted glass is increased by the deposition of oxidation products of platinum group elements (PGE) and the PGE-containing glass tends to settle to the melter's bottom basin even after draining glass out. Removal of the PGE-containing glass is needed to avoid the Joule heating current from being affected by the glass, it requires time-consuming work to remove. For the early accomplishment of vitrifying the waste, Japan Atomic Energy Agency is planning to replace the current melter with the new one in which the amount of PGE sediments would be reduced. In the past design activities for the next melter, several kinds of shapes in regard to the furnace bottom and the strainer were drawn. Among these designs, the one in which the discharge ratio of PGE-containing glass would be as much as or greater than the current melter and which be able to perform similar operational sequences done in the current melter is selected here. Firstly, an operational sequence to produce one canister of vitrified waste is simulated for three melter designs with a furnace bottom shape, using 3D thermal-hydraulic calculations. The computed temperature distribution and its changes are compared among the candidate structures. After discussions about the technical and structural feasibilities of each design, a cone shape with a 45
slope was selected as the bottom shape of the next melter. Secondly, five strainer designs that fit the bottom shape above mentioned are drawn. For each design, the fluid drag and the discharge ratio of relatively high viscosity fluid resting near the bottom are estimated, using steady or unsteady CFD simulation. By draining silicone oil from acrylic furnace models, it was confirmed experimentally that there are no vortices
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.
Kato, Junya; Nakazaki, Katsutoshi; Takaya, Akikazu; Matsumura, Tadayuki; Niitsuma, Koichi; Kodaka, Akira; Fujiwara, Koji
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Matsumura, Tadayuki; Takaya, Akikazu; Sumi, Hirotaka; Ishii, Kiyonori; Niitsuma, Koichi; Kodaka, Akira; Fujiwara, Koji
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Kuboki, Michikatsu; Naito, Masakazu; Sumi, Hirotaka; Nakayama, Jiro; Kano, Shigeru; Niitsuma, Koichi; Kodaka, Akira; Fujiwara, Koji
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Nakayama, Jiro; Sumi, Hirotaka; Kuboki, Michikatsu; Kodaka, Akira; Fujiwara, Koji
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Sumi, Hirotaka; Nakayama, Jiro; Kuboki, Michikatsu; Kodaka, Akira; Fujiwara, Koji
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Sumi, Hirotaka; Makigaki, Hikaru; Nakayama, Jiro; Niitsuma, Koichi; Kodaka, Akira
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Yamashita, Teruo; Matsumura, Tadayuki; Oyama, Koichi; Harashima, Takero; Ayame, Yasuo; Kodaka, Akira
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Harashima, Takero; Yamashita, Teruo; Matsumura, Tadayuki; Oyama, Koichi; Ayame, Yasuo; Kodaka, Akira
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Matsumura, Tadayuki; Yamashita, Teruo; Oyama, Koichi; Harashima, Takero; Ayame, Yasuo; Kodaka, Akira
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Oyama, Koichi; Matsumura, Tadayuki; Harashima, Takero; Yamashita, Teruo; Ayame, Yasuo; Kodaka, Akira
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Kobayashi, Hidekazu; Kodaka, Akira; Iwabuchi, Hiroki
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In JAEA's Tokai Vitrification Facility (TVF) at Tokai Reprocessing Plant (TRP) site, high level liquid waste (HLLW) generated from reprocessing of spent fuels is vitrified with a liquid-fed joule-heated ceramic melter (LFCM). As noble metals (NMs) in HLLW aren't soluble to the glass, and have low resistivity and higher density, they deposit on bottom of melter and form electrical path and thus disturb melter operation. The first and second TVF melter have square pyramidal shaped bottom and issue that NMs on the bottom are difficult to drain out and have to be removed periodically. To solve this issue, we are developing the third melter with conical shaped bottom. The effect of changing the bottom structure was confirmed by thermo-fluid analysis code. Structural optimization of strainer in the upper part of drain nozzle was carried out by visualization experiment. In this meeting, activity of third melter development including past melter structure will be introduced.
Asahi, Yoshimitsu; Shimamura, Keisuke; Kobayashi, Hidekazu; Kodaka, Akira; Morikawa, Yo
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Shimamura, Keisuke; Asahi, Yoshimitsu; Kobayashi, Hidekazu; Kodaka, Akira; Morikawa, Yo
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