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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
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:12 Percentile:61.17(Nuclear Science & Technology)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
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.
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.
Suto, Shinya; Nakabayashi, Hiroki; Yao, Kaoru*
JAEA-Technology 2007-029, 73 Pages, 2007/03
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/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.
Nakabayashi, Hiroki; Koma, Yoshikazu; Nakamura, Hirofumi; Sato, Koji
Dai-4-Kai Saishori Risaikuru Semina Tekisuto, p.142 - 146, 2006/05
no abstracts in English
Nakabayashi, Hiroki; Kurisaka, Kenichi; Sato, Koji; Niwa, Hajime; Aoki, Kazuo*
JAEA-Technology 2006-027, 119 Pages, 2006/03
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.
Sato, Koji; Koma, Yoshikazu; Inoue, Akira; Yonezawa, Shigeaki; Takata, Takeshi; Nakabayashi, Hiroki; Namekawa, Takashi; Kawaguchi, Koichi
JNC TN9400 2004-036, 1051 Pages, 2004/06
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.
Nakabayashi, Hiroki; Fujioka, Tsunaaki; Sato, Koji; Aoki, Kazuo*
JNC TN9400 2003-082, 67 Pages, 2003/09
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.
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.
Nakabayashi, Hiroki;
JNC TN9400 2001-072, 107 Pages, 2001/06
Pyrochemical reprocessing systems, which are based on the different physical principles from the existing aqueous reprocessing systems, are expected to be the more economical, more reductible of environmental impact and higher proliferation-resistant. Though many researches and experiments for the development of those systems have been done in many countries there are few studies on the criticality safety design. In this study, the criticality safety design are performed for three pyrochemical reprocessing systems, the metal electrorefining process which has been developed by the Argonne National Labolatory (ANL) in the U.S, the oxide electrowinning process which has been developed by the Research Institute of Atomic Reactors (RIAR) in Russia and the fluoride volatility process which has been developed by the ANL in the U.S, the Japan Atomic Energy Reserch Institute (JAERI) in Japan, etc. As a result of this study, the ordinal criticality safety management methods can directly be applied both to the electrowinning process and to the fluoride volatility process. However, for the electrorefiner vessel used in the metal-electrorefining process, the ordinal methods, in which the only one chemical state is supposed for the all fissile nuclide in the individual unit, cannot be applied directly because the different chemical states co-exist in the electrorefiner by the operation. It is proposed the different idea for this case in the study. And these results are useful to design any pyrochemical reprocessing plants. Because subcritical limits are determined by criticality data of simple models in this study, these limits should be reevaluated based on the detailed hardware design. Futhermore, the criticality safety evaluation with the contingency analysis must be performed to certify that the design has an adequate safety clearance to the anticipated anomaly events.
Kakehi, Isao; Nakabayashi, Hiroki
JNC TN9400 2000-051, 237 Pages, 2000/04
In this study, we have proposed the concept of safety systems (solutions of safety problems) in pyrochemical reprocessing systems (lt consists of pyrochemical reprocessing methods and the injection casting process for the metal fuel fabrication, or vibro-packing process for the oxide fuel fabrication.) which has different concept from the existing PUREX reprocessing method and pellet fuel fabrication process. And we performed its safety evaluations. FoIlowing the present Japanese safety regulations for reprocessing facilities, we pointed out functions, design requirements and equipments relating to its safety systems and picked up subjects. For the survey of safety evaluations, we first selected anticipated events and accident events, and second by evaluated 6the correspondence of the limitation of the public exposure to the accidents above, by using two parameters, the safety design parameter (the filter performance to confine radioactive matelials) and the leak inventory of radioactivities, and last by picked up its problems. ln addition to the above evaluations we performed basic criticality analyses for its systems to utilize these results for the design and evaluation of the criticality safety management system. Thus this study specified the concept of safety systems for pyrochemical reprocessing processes and then issues in order to establish safety design policies (matters which must consider for the safety design) and guides and to advance more definite safety design.
Taguchi, Katsuya; Nakabayashi, Hiroki; Nakano, Takafumi
no journal, ,
The Tokai Reprocessing Plant (TRP) was taken out of service of spent fuel reprocessing operation and the first decommissioning plan was authorized by the Nuclear Regulatory Agency (NRA) at June 2018. Due to the complexity, numerousness of facilities and various condition of contamination, it would be expected the decommissioning plan requires over 70 years. In the view of maintenance following three major issues were arisen at this time, temporary increase of maintenance and testing works with additional equipment for safety enhancement to the storage of HAW, the ageing management for over 70 years decommissioning period and optimizing the replacement strategy for existing equipment considering of the risk level reduction with progress of the decommissioning plan. The presentation shows our perspective and conceptual procedures to take up these issues.
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.
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.
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.