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Takeuchi, Masayuki; Nakajima, Yasuo; Hoshino, Kuniyoshi*; Kawamura, Fumio*
Journal of Alloys and Compounds, 506(1), p.194 - 200, 2010/09
Times Cited Count:10 Percentile:49.21(Chemistry, Physical)Kawamura, Fumio*; Aoi, Masakatsu*; Hoshino, Kuniyoshi*
JNC TJ9420 2003-006, 436 Pages, 2004/02
The stratagem feasibility studies for aim of commercialization of FBR cycle system have been researched in JNC. In these studies economy, load suppression for environmentality, non-proliferation and et. al. have been evaluated for several kinds of systems. In series of these researches, we had researched the vibration packing fuel manufacturing system of wet fuel recycle plant for FBR's fuel, and investigated the concepts of main equipments for the fuel pin fabrication system. In 2002 we had achieved the conceptual design of main equipments and assignment of those in cells from reception process of fuel particles material to storage process of fuel assemblies concerning the production scale about 50t-HM/y manufacturing system, and estimated the applicability of fabrication system in cell. In this study, we have researched the conceptual design and assignment in cells of main equipments of the vibration packing fuel manufacturing system, quality control, and maintenance of equipments concerning the production scale about 200t-HM/y manufacturing system. The building is constructed independently near here the recycle facility building and fuel particle fabrication building. And then the technical matching and economical evaluation of manufacturing system have been investigated. Resulting these investigations, we have got the basic conceptual design of main equipments for the fuel pin fabrication system in the scale of 200t-HM/y, assignment of main procedure cell and auxiliary equipments, and also the ability of 200 days operation per year based on the quality control and maintenance of equipments. And then we have got the aspect of technical matching to the plant and the reasonable economical evaluation of manufacturing system. It is cleared that this manufacturing method is the suitable one of systems concerning of wet fuel recycle plant for FBR's fuel manufacturing system.
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JNC TN9420 2001-002, 47 Pages, 2001/06
Several kinds of advanced fuel cycle systems have been developed as a link in the strategy investigation study to put FBR Cycle to practical use. In this study, survey and evaluation have been carried out on the hybrid fuel reprocessing systems in which developed fuel reprocessing systems are combined. For the survey of hybrid fuel reprocessing systems, three systems were surveyed such as combination system with fluoride volatility and wet reprocessing method, fuel cycle system in which fluoride volatility method, molten fluoride salt extraction method and long life nuclide transmuter are combined, and an application of dry reprocessing technology before and/or after wet reprocessing process. Contents of the systems are investigated and evaluation was made on peculiarities of the systems. As for the proposal and evaluation of the hybrid fuel reprocessing systems, fluoride volatility method, molten salt extraction method (oxide electrowinning method etc.) were combined with wet reprocessing method etc. to propose hybrid fuel reprocessing systems. For proposed hybrid system, system validity, MA/FP recovery method, nuclear proliferation resistance and system safety were investigated and comparison were made to the original systems from the standpoint of cost, produced fuel purity and amount of the waste.
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Proceedings of International Conference on; Back-End of the Fuel Cycle; From Research to Solutions (GLOBAL 2001), 0 Pages, 2001/00
None
; Kakehi, Isao; Moro, Satoshi; ; ; ;
JNC TN9400 98-003, 422 Pages, 1998/10
Advanced recycle system engineering group of OEC has being carried out a design study of the advanced nuclear fuel recycle system using molten salt (electro-metallurgical process). This system is aiming for improvements of fuel cycle economy and reduction of environmental burden (MA recycles, Mimmum of radioactive waste disposal), and also improvement of safety and nuclear non-proliferation. This report describes results of the design study that has been continued since December 1996. (1)A design concept of the advanced nuclear fuel recycle system, that is a module type recycle system of pyrochemical reprocessing and fuel re-fabrication was studied. The module system has advantage in balance of Pu recycle where modules are constructed in coincidence with the construction plan of nuclear power plants, and also has flexibility for technology progress. A demonstration system, minimum size of the above module, was studied. This system has capacity of 10 tHM/y and is able to demonstrate recycle technology of MOX fuel, metal fuel and nitride fuel. (2)Each process of the system, which are pyrochemical electrorefining system, cathode processor, de-cladding system, waste disposal system, etc., were studied. In this study, capacity of an electrorefiner was discussed, and vitrification experiment of molten salt using lead-boric acid glass was conducted. (3)A hot cell system and material handling system of the demonstration system was studied. A robot driven by linear motor was studied for the handling system, and an arrangement plan of the cell system was made. Criticality analysis in the cell system and investigation of material accountancy system of the recycle plant were also made. This design study will be continued in coincidence with design study of reactor and fuel, aiming to establish the concept of FBR recycle system.
; Moro, Satoshi; ; Kakehi, Isao; ;
PNC TN9410 98-033, 284 Pages, 1998/03
System engineering division of OEC has being carried out a design study of the advanced nuclear fuel recycle system using electro-metallurgical process, aiming for improvements in safety, reliability, economy and a1so in environmental burden and nuclear non-proliferation. But the public criticism against nuclear power is more severe recently, and the situation is changing as seeing in the conclusion of the round-table conference on FBR. The researcher's meetings, in which researchers in PNC and from other organizations attended, were held during December, 1997 and March, 1998 in order to discuss on the advanced nuclear fuel recycle system and technology for FBR to be aimed in the future, and how to execute its research & development, etc. The conclusions of this meeting are as follows: (1)The future advanced FBR fuel cycle system shall be the system which has high potential for maximum utilization of uranium resources, and also for revolutionary improvements of economy, safety, environmental burden, etc. so as to be accepted in the society. (2)Regarding to the process of the future fuel eycle system, electro-metallurgical process that is able to apply for reprocessing of different types of fuel (oxide, metal and nitride) and is flexible for technical progress is recommended. Research & development of this system and technology shall be carried out. (3)The mission of PNC (new organization) is to select the most appropriate advanced FBR fuel cycle system from the viewpoint of the long-term FBR age in the future, and to conduct development of its system. It is expected for the new organization to execute its research and development steadily in cooperation with other research institutes, etc. under the nation-wide assessment and agreement. According to the above conclusions, the system engineering division will enhance the design study of the advanced FBR fuel cycle system and establish the definite concept of the system in cooperation with concerned in and ...
Kakehi, Isao; ; ; ; ; Kajitani, Yukio;
PNC TN9410 97-015, 382 Pages, 1996/12
For the purpose of developing the future nuclear fuel recycle system, the design study of the advanced nuclear fuel recycle system is being conducted. This report describes intermediate accomplishments in the conceptual system study of the advanced nuclear fuel recycle system. Fundamental concepts of this system is the recycle system using molten salt which intend to break through the conventional concepts of purex and pellet fuel system. Contents of studies in this period are as follows, (1)feasibility study of the process by Cd-cathode for nitride fuel (2)application study for the molten salt of low melting point (AlCl+organic salt)(3)research for decladding (advantage of decladding by heat treatment)(4)behavior of FPs in electrorefinning (behavior of iodine and volatile FP chlorides, FPs behavior in chlorination) (5)criticaliy analysis in electrorefiner (6)drawing of off-gas flow diagram (7)drawing of process machinery concept (cathode processor, vibration packing) (8)evaluation for the amounts of the high level radioactive wastes (9)quality of the recycle fuels (FPs contamination of recycle fuel) (10)conceptual study of in-cell handling system (11)meaning of the advanced nuclear fuelrecycle system. The conceptual system study will be completed in describing concepts of the system and discussing issues for the developments.
Kihara, Takehiro; *; Fujine, Sachio; Maeda, Mitsuru; *; *
JAERI-M 93-234, 47 Pages, 1993/12
no abstracts in English
; ; ; Kawamura, Hiroshi; ; Ooka, Norikazu; Saito, Minoru
JAERI-M 88-156, 57 Pages, 1988/08
no abstracts in English
Kawamura, Hiroshi; ; ; ;
JAERI-M 85-211, 50 Pages, 1985/12
no abstracts in English
; Kawamura, Hiroshi; ; ; ; ;
JAERI-M 85-087, 23 Pages, 1985/07
no abstracts in English
Kawamura, Hiroshi; ; ; ; ; ; ; ;
JAERI-M 84-228, 61 Pages, 1984/12
no abstracts in English
Yamashita, Junichi*; Fukasawa, Tetsuo*; Kawamura, Fumio*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Sato, Seichi*; Minato, Kazuo
no journal, ,
no abstracts in English
Yamashita, Junichi*; Fukasawa, Tetsuo*; Kawamura, Fumio*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Minato, Kazuo; Akabori, Mitsuo; Arai, Yasuo
no journal, ,
no abstracts in English
Yamashita, Junichi*; Fukasawa, Tetsuo*; Kawamura, Fumio*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Sato, Seichi*; Minato, Kazuo
no journal, ,
no abstracts in English
Sato, Nobuaki*; Takenaka, Toshihide*; Hayashi, Hirokazu; Amano, Osamu*; Kawamura, Fumio*
no journal, ,
no abstracts in English
Takeuchi, Masayuki; Koizumi, Tsutomu; Hoshino, Kuniyoshi*; Kawamura, Fumio*
no journal, ,
no abstracts in English
Takeuchi, Masayuki; Koizumi, Tsutomu; Hoshino, Kuniyoshi*; Kawamura, Fumio*
no journal, ,
no abstracts in English