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Journal Articles

Study of treatment scenarios for fuel debris removed from Fukushima Daiichi NPS

Washiya, Tadahiro; Yano, Kimihiko; Kaji, Naoya; Yamada, Seiya*; Kamiya, Masayoshi

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

On March 11, 2011, a severe nuclear accident occurred at Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Plant (hereinafter called as F1). After the accident, the Council for the Decommissioning was established, mainly by the government and TEPCO, and a road map for the F1 decommissioning was drawn up. In the road map, the fuel debris removal from the reactors is scheduled to launch around 2020. In this study, the characteristics and technological issues of each potential treatment scenario were extracted, and the scenarios were prioritized in advance of formal evaluations in the future. The preliminary evaluation results show that long term storage and direct disposal have more positive aspects in terms of economic efficiency and radioactive waste generation. On the other hand, stabilizing processing, aqueous processing, and pyrochemical processing have been estimated to have more disadvantages in such aspects.

JAEA Reports

Research on Plant of Metal Fuel Fabrication using Casting Process(2)

Senda, Yasuhide*; Yamada, Seiya*

JNC TJ9420 2005-005, 117 Pages, 2005/02

JNC-TJ9420-2005-005.pdf:5.36MB

In this research work for the metal fuel fabrication system (38tHM/y), the studies of the concept of the main process equipments were performed based on the previous studies on the process design and the quality control system design. In this study the handling equipment of the products were also designed, according to these designs the handling periods were evaluated. Consequently the numbers of the equipments were assessed taking into account for the method of the blending the fuel composition.(1)Structural concept design of the major equipments, the fuel handling machine and the gravimetries in the main fabrication process The structural concept were designed for the fuel composition blending equipment, the fuel pin assembling equipment, the sodium bonding equipment, the handling equipment for fuel slug palettes, the handling equipment for fuel pins and the gravimetries.(2)Re-assessment of the numbers of the equipments taking account of the handling periods Based on the results of item (1) the periods were evaluated for the fuel slug and pin handling. Accordingly the numbers of the equipments were optimized.(3)Design of the buffer storages The buffer storages among the equipments were designed through the comparison of the process speed between the equipments taking into account for the handling periods. The required amount of the structural parts (for example cladding materials) was assessed for the buffer in the same manner and the amount of the buffer facilities were optimized.

Journal Articles

Development of New Decladding System in the Reprocessing Process for FBR Fuel

Yamada, Seiya; Washiya, Tadahiro; Takeuchi, Masayuki; Koizumi, Tsutomu; Aose, Shinichi

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(2), p.156 - 166, 2005/00

The application of the fluoride volatility process in the reprocessing of fuel from the fast breeder reactor is regarded as one of the economical methods. Plutonium hexafluoride (PuF6), however, reacting with fluorine (F2) and plutonium dioxide (PuO2) as the raw material, is in an unstable condition and tends to remain as a solid compound in the process after decomposing into plutonium tetrafluoride (PuF4). Suitable conditions should be established for the practical use of this process. One of them is to enhance the stability of PuF6. The behaviour of plutonium fluorination and relevant chemical reactions were investigated by referring to sundry literature and by thermodynamic calculation. It was then compared with recent data from laboratory scale experiments for this paper. Results from the theoretical analysis agreed with experimental observation that PuF6 could be formed stably under a high temperature condition (approx.1000 K) with over supply of figher concentration of F2.

Journal Articles

New Decladding System in the Reprocessing Process for Fast Reactor Fuel

Yamada, Seiya; Washiya, Tadahiro; Takeuchi, Masayuki; Suganuma, Takashi; Aose, Shinichi

Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 8 Pages, 2004/00

As a part of the feasibility study on commercialized fast reactor cycle systems, Japan Nuclear Cycle Development Institute (JNC) has been developing the fuel decladding technology for the dry reprocessing process (oxide electrowinning process) and aqueous reprocessing process. Particularly, in the oxide electrowinning process, the spent fuel should be reduced to powder for quick dissolution in the molten salt at electrolyzer. Heat treatment method such as a voloxidation might not be applicable in the decladding process, because of the high plutonium content as fast reactor fuel. Therefore, JNC proposes new decladding system with innovative mechanical decradding devices. The decladding system consists of fuel crushing stage, hull separation stage and hull rinsing stage. In this paper, the outline of this new decladding system and its innovative devices will be descried.

Journal Articles

The Effect of unbalance flow on the performance of compact heat exchanger for HTGR-GT system

Ishiyama, Shintaro; Muto, Yasushi; Ogata, Hiroshi*; Yamada, Seiya*

Nihon Genshiryoku Gakkai-Shi, 43(11), p.1136 - 1148, 2001/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Design study of helium turbine for the 300MW HTGR-GT power plant

Muto, Yasushi; Ishiyama, Shintaro; Fukuyama, Yoshitaka*; Okumoto, Junji*; Kishibe, Tadaharu*; Yamada, Seiya*

Proceedings of 45th ASME International Gas Turbine & Aeroengine Technical Congress, Exposition and Users Symposium (CD-ROM), 8 Pages, 2000/00

no abstracts in English

Journal Articles

Nuclear heat application systems for arresting CO$$_{2}$$ emission

Fumizawa, Motoo; *; Yamada, Seiya*

Enerugi, Shigen, 20(1), p.87 - 92, 1999/01

no abstracts in English

Journal Articles

Nuclear power cogeneration systems using gas turbine

Fumizawa, Motoo; *; Yamada, Seiya*

Enerugi, Shigen, 18(5), p.73 - 78, 1997/09

no abstracts in English

JAEA Reports

Preliminary design of steam reformer in out-pile demonstration test facility for HTTR heat utilization system

Haga, Katsuhiro; Hino, Ryutaro; Inagaki, Yoshiyuki; Hada, Kazuhiko; ; ; Nishihara, Tetsuo; Yamada, Seiya*; Sudo, Yukio

JAERI-Tech 96-053, 71 Pages, 1996/11

JAERI-Tech-96-053.pdf:2.22MB

no abstracts in English

JAEA Reports

Study of nuclear heat application systems for arresting CO$$_{2}$$ emission

Fumizawa, Motoo; Inaba, Yoshitomo; Hishida, Makoto; *; Yamada, Seiya*

JAERI-Tech 96-045, 97 Pages, 1996/11

JAERI-Tech-96-045.pdf:3.34MB

no abstracts in English

JAEA Reports

Conceptual study of methonal production system using nuclear heat and coal

Fumizawa, Motoo; Inaba, Yoshitomo; Hishida, Makoto; Ogawa, Masuro; *; Yamada, Seiya*

JAERI-Tech 96-002, 107 Pages, 1996/02

JAERI-Tech-96-002.pdf:2.97MB

no abstracts in English

JAEA Reports

Preliminary study of nuclear power cogeneration system using gas turbine process

Fumizawa, Motoo; Inaba, Yoshitomo; Hishida, Makoto; Ogawa, Masuro; *; Yamada, Seiya*

JAERI-Tech 95-055, 125 Pages, 1995/12

JAERI-Tech-95-055.pdf:3.53MB

no abstracts in English

JAEA Reports

Thermal efficiency of the GT-HTGR combined cycle power generation plant

Yamada, Seiya*; ;

JAERI-M 87-071, 107 Pages, 1987/05

JAERI-M-87-071.pdf:2.75MB

no abstracts in English

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 10; Direct extraction test of unirradiated MOX fuel under supercritical condition

Kaji, Naoya; Kamiya, Masayoshi; Koma, Yoshikazu; Koizumi, Tsutomu; Koyama, Tomozo; Aoki, Kazuo*; Yamada, Seiya*

no journal, , 

no abstracts in English

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 12; The Outline of the other results of development

Kamiya, Masayoshi; Kaji, Naoya; Koyama, Tomozo; Aoki, Kazuo*; Yamada, Seiya*

no journal, , 

It is shown in this presentation that the outline "development of actinides co-extraction system with direct extraction process using supercritical fluid" and future schedule.

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fruid, 14; Direct extraction test of unirradiated MOX fuel

Kaji, Naoya; Kamiya, Masayoshi; Takahatake, Yoko; Oyama, Koichi; Miura, Sachiko; Koyama, Tomozo; Aoki, Kazuo*; Yamada, Seiya*

no journal, , 

A battery of tests using MOX fuel were performed for development of actinides co-extraction system with direct extraction process using supercritical fluid. The condition that was set up based on consideration of the results of the tests under ordinary pressure, and then was made fine adjusted based on the tests with supercritical fruid. As a result, U, Pu and Am were extracted simultaneously. Comparative test confirmed that U, Pu and Am could be also extracted simultaneously with dodecane as a diluent. While the extraction test of unirradiated MOX fuel with simulated FP, U, Pu was extracted with U and Am, and the Pu residue, that was found at the extraction test of irradiated fuel, was not found. As the result of scrubbing and stripping test, it was showed that traditional extraction process design method could be applied to design scrubbing and stripping process with supercritical fluid.

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 13; Scope

Koyama, Tomozo; Kamiya, Masayoshi; Kaji, Naoya; Aoki, Kazuo*; Yamada, Seiya*

no journal, , 

The summary of development of actinides co-extraction system with direct extraction process using supercritical fluid which was started at 2005 is reported here.

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 16; Integrated evaluation

Kamiya, Masayoshi; Kaji, Naoya; Koyama, Tomozo; Aoki, Kazuo*; Yamada, Seiya*

no journal, , 

Main process of actinides co-extraction system with direct extraction process using supercritical fluid was designed. The improvement effect of the cost performance was small because multiple lines were needed about main process. But we got the evaluation result that it is possible to reduce substantially about waste liquid treatment. Based on the result, the improvement which uses supercritical fluid for partitioning was gathered.

Oral presentation

Characterization of fuel debris (27'A), 10; R&D plan of treatment technology for fuel debris

Ogino, Hideki; Nakayoshi, Akira; Yamada, Seiya*

no journal, , 

R&D plan of the characteristics of fuel debris related to package, transportation and storage was devised through the information exchange with the developers' project team of such technology.

Oral presentation

Characterization of fuel debris (27'A), 11; Evaluation of moisture and drying characterization for fuel debris

Nakayoshi, Akira; Kano, Yoshiharu; Okamura, Nobuo; Koizumi, Kenji; Watanabe, Masayuki; Yamada, Seiya*

no journal, , 

no abstracts in English

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