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Journal Articles

FaCT Phase-I evaluation on the advanced aqueous reprocessing process, 4; Solvent extraction simplified for FBR fuel reprocessing

Koma, Yoshikazu; Ogino, Hideki; Sakamoto, Atsushi; Nakabayashi, Hiroki; Shibata, Atsuhiro; Nakahara, Masaumi; Washiya, Tadahiro

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12

Journal Articles

Extraction and stripping tests of engineering-scale centrifugal contactors cascade system for spent nuclear fuel reprocessing

Takeuchi, Masayuki; Ogino, Hideki; Nakabayashi, Hiroki; Arai, Yoichi; Washiya, Tadahiro; Kase, Takeshi; Nakajima, Yasuo

Journal of Nuclear Science and Technology, 46(3), p.217 - 225, 2009/03

 Times Cited Count:8 Percentile:53.11(Nuclear Science & Technology)

JAEA Reports

Fast Reactor Cycle Technology Development Project (FaCT Project); A Design study on an engineering-scale hot test facility (Interim report)

Nakamura, Hirofumi; Nagai, Toshihisa; Suto, Toshiyuki; Kosaka, Ichiro; Nakazaki, Katsutoshi; Suto, Shinya; Nakamura, Tomotaka; Nakabayashi, Hiroki; Hayashi, Naoto; Sumida, Daisaku

JAEA-Technology 2008-077, 276 Pages, 2008/12

JAEA-Technology-2008-077.pdf:25.66MB

Japan Atomic Energy Agency (JAEA) has been conducting "Fast Reactor Cycle Technology Development Project (FaCT Project)" for the purposes of researching and developing the technologies for the fast breeder reactor cycle commercialization since Japanese fiscal year (JFY) 2007. Based on the above R&D program for reprocessing system, the engineering-scale hot test would provide demonstration data on the specification, operation and maintenance of the adapted innovative technologies, system and plant. And more, these results would be fed to the design of the demonstration facility planning on the FaCT project road map. This report is the interim report of design studies about the engineering-scale hot test facility and includes not only design of the equipment and facility, but also consideration for design principle, requirements and facility basic planning.

Journal Articles

Development of FR fuel cycle in Japan, 2; Basic design and verification of U-Pu-Np co-recovery flowsheets for engineering scale hot examinations in Japan

Nakabayashi, Hiroki; Nagai, Toshihisa

Proceedings of 2008 International Congress on Advances in Nuclear Power Plants (ICAPP '08) (CD-ROM), p.2029 - 2035, 2008/06

We performed a basic design of the solvent extraction test system with centrifugal contactors for the engineering-scale hot examination facility to ensure the development and commercialization of the advanced aqueous reprocessing technology for fast reactor fuels in Japan. The system was designed to have the ability to operate two different flowsheet, the simplified solvent extraction method and the co-processing method, which we proposed as promising solvent extraction processes. In the design, various engineering issues, such as error of flow rate of reagent pumps and a dissolver solution feeder, error of chemical analyses and environmental temperature fluctuation, were delt with. For the design we modified and used the computer code "MIXSET-X" which was developed to simulate solvent extraction system by JAEA in 1999. The validity of the modified code was benchmarked by comparison with an engineering scale uranium test.

JAEA Reports

Heat evaluation examination of fuel assembly

Suto, Shinya; Nakabayashi, Hiroki; Yao, Kaoru*

JAEA-Technology 2007-029, 73 Pages, 2007/03

JAEA-Technology-2007-029.pdf:11.39MB

The cooling examination was executed by using the simulated fuel assembly to obtain the basic data of the most effective cooling system in the laser disassembling process of the spent fuel assembly of prototype fast breeder reactor "Monju". As a result, the following have been understood. (1) Before the laser disassembling (there is not any duct tube cutting), it is possible to cool enough by the amount of the wind of 20m$$^{3}$$/h or more flowing from the handling head side. (2) After the laser disassembling begins (duct tube is cut), 1kW or more of the heat generation cannot be cooled by ventilation from the handling head side. (3) Cooling by the flow across fuel pin is required during laser disassembling. The basic data of the cooling system was obtained from these examination results. However, for cooling across fuel pin during the laser disassembling, it is necessary to examine shape of the side cooling nozzle, spraying angle, and flow velocity at the nozzle exit, etc. enough.

Journal Articles

Research and development for advanced aqueous reprocessing system in JAEA

Nakabayashi, Hiroki; Koma, Yoshikazu; Nakamura, Hirofumi; Sato, Koji

Dai-4-Kai Saishori Risaikuru Semina Tekisuto, p.142 - 146, 2006/05

no abstracts in English

JAEA Reports

A Study of the criticality safety design for the metal fuel recycle system, 2

Nakabayashi, Hiroki; Kurisaka, Kenichi; Sato, Koji; Niwa, Hajime; Aoki, Kazuo*

JAEA-Technology 2006-027, 119 Pages, 2006/03

JAEA-Technology-2006-027.pdf:9.02MB

This report describes a study about the criticality safety design for the large-scale electrorefiner, which is designed in the activities of "The Design Study of Metal Fuel Recycle System (2002)", under the collaboration with Central Research Institute of Electric Power Industry, and the continuation of "A Study of the Criticality Safety Design for the Metal Fuel Recycle System", which was published at September 2003. The report includes a detail design and quantitative criticality parameter limits based on "the mass control supported with chemical form control" concept which is proposed in "A Study of the Criticality Safety Design for the Metal Fuel Recycle System". Furthermore procedures to determine these limits are presented in the report. Next we studied contingencies anticipated under the critical control and executed quantitative criticality safety analyses of models based on these abnormal conditions. The analytical result shows adequate safety margins are existed in the criticality safety design even if many of these contingencies could occur. Moreover we propose a concept of material transfer and production control system, we call it as "Operation by wire", which all equipment and handling machines are electrified and the control system provides completely automated process control and operation. The control system eliminates human errors and violations like over batching error or transfer error in the commercial scale metal fuel recycle system with complicated operation procedures.

JAEA Reports

Feasibility Study on Commercialization of Fast Breeder Reactor Cycle Systems, Interim Report of Phase2 -Technical Study Report for Nuclear Fuel Cycle Systems-

Sato, Koji; Koma, Yoshikazu; Inoue, Akira; Yonezawa, Shigeaki; Takata, Takeshi; Nakabayashi, Hiroki; Namekawa, Takashi; Kawaguchi, Koichi

JNC TN9400 2004-036, 1051 Pages, 2004/06

JNC-TN9400-2004-036.pdf:90.95MB

The plant concept concerning the fuel cycle systems (combination of the reprocessing and the fuel fabrication )has been constructed to reduce their total cost by the introduction of various innovative techniques and to apply their utmost superior efficiency from such standpoints of a decrease in the environmental burden, better resource utilization and proliferation resistance improvement by the low decontamination transuranium element (TRU) recycle. For economical efficiency, less than 0.8 yen/kWh which is the demand value (total of the reprocessing expense and the fuel fabrication expense) of the fuel cycle expense satisfied each combination case at 200 tHM/y scale provisionally set for large-scale facilities. On the other hand, the combination case with a low breeder reactor core has satisfied the demand value, with improvement of the average burnup by the radial direction blanket fuel deletion contributing to the decrease of the fuel cycle expense at 50 tHM/y scale provisionally set for small-scale facilities.

JAEA Reports

A Study of the Criticality Safety Design for the Metal Fuel Recycle System

Nakabayashi, Hiroki; Fujioka, Tsunaaki; Sato, Koji; Aoki, Kazuo*

JNC TN9400 2003-082, 67 Pages, 2003/09

JNC-TN9400-2003-082.pdf:3.02MB

This report accounts for a study about the criticality safety design for the large-scale electrorefiner, which is designed in the activities of "The Design Study of Metal Fuel Recycle System(2002)", under the collaboration with Central Research Institute od Electric Power Industry.

Journal Articles

Conceptual design on an integrated metal fuel recycle system

Sato, Koji; Fujioka, Tsunaaki; Nakabayashi, Hiroki; Kitajima, Shoichi; Yokoo, Takeshi*; Inoue, Tadashi*

Global 2003; International Conference on Atoms for Prosperity: Upda, 0 Pages, 2003/00

We have been performing the feasibility study on conceptual design for an integrated metallic fuel recycle plant of 38 tHM/y throughput. As a result of this study, the process concept was constructed, and the main equipment and devices were designed considering rationalixation,operationability, reduction of environmental impact and safety for the future commercialization. Furthermore, the image of the whole building included in cells was examined. In particular, the electrorefiner was enlarged from its current size and the cathode processor was improved from the current batch type to the continuation type to increase throughput. The plant was evaluated comprehensively. We confirmed that the major specifications for plant design would be satisfied. The economical cometitiveness of the plant has been evaluated.

Oral presentation

Study on Np behaviors in U-Pu-Np co-extraction process using PARC code

Asakura, Toshihide; Tsubata, Yasuhiro; Morita, Yasuji; Nakabayashi, Hiroki; Nagai, Toshihisa

no journal, , 

To contribute to optimize the simple solvent extraction process of NEXT process, PARC-L code simulation calculations of U-Pu-Np co-extraction process were performed, and the extraction/separation behaviors of Np were examined from the viewpoint of oxidation/reduction reaction rate of Np (V)-Np (VI) in relating to the nitrous acid concentration. The time-dependent change of Np valence state distribution in the feed solution was calculated. Assuming the composition of the feed solution as that obtained from the valence calculation, extraction calculations were performed.

Oral presentation

Study on fire and explosion safety for extraction chromatography process

Koma, Yoshikazu; Sano, Yuichi; Watanabe, So; Nomura, Kazunori; Nakabayashi, Hiroki

no journal, , 

The system of extraction chromatography has been investigated for Am and Cm recovery from highly active reprocessing solutions. The process uses an adsorbent containing organic compounds and hydrogen is generated due to radiation, therefore, safety on fire and explosion has to be considered. A method to assure the safety on fire and explosion was studied.

Oral presentation

Application of probability risk assessment in TRP and its capability to maintenance planning

Takase, Yuki; Miura, Yasushi; Nakabayashi, Hiroki

no journal, , 

Tokai Reprocessing plant (TRP), which temporarily suspended the reprocessing of spent fuel in 2007, moved to decommissioning in 2018 without restarting operations. Under the decommissioning situation, the high-level radioactive liquid waste generated in the past reprocessing operation is the highest potential risk in TRP. These high-level radioactive liquid wastes are stored in High Active Liquid Waste Storage Facility (HAW) and sequentially Vitrified in Tokai Vitrification Facility (TVF). The serious accident risk about evaporation accident of high radioactive liquid waste has been remained in both facilities. In this study, a loss of heat sink (LOHS) frequency of high radioactive liquid waste in HAW and TVF was assessed by Probability Risk Assessment (PRA). The risk information was extracted for the equipment of important of safety related system from the view point of maintaining the facility safety. Its capability to maintenance planning was evaluated.

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