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*; Yumoto, Ryozo; *; *; *
JNC TJ9440 99-019, 106 Pages, 1999/03
Problems were picked up by investigating how to strengthen JNC's competitive position of the fuel cycle technologies (reprocessing and MOX fabrication) in world markets. Market needs in mainly Asian countries were also investigated about plutonium utilization in light water reactors (LWRs). Legal regulations were surveyed on import, export and transport of nuclear fuels. Foreign enterprises involved in fuel reprocessing and MOX fabrication businesses were surveyed on their activities and company histories. Fundamental conditions required to a company which is going to commence and run a fuel reprocessing and MOX fuel fabrication were discussed. Technical problems were picked up concerning strengthening JNC's competitive position of reprocessing technologies by making an image of 400tons / year model plant. Cost reduction and improvement of safety are two basic indexes for pick up technical problems other indexes are simplification of process, cutting down of radioactive waste generation and so on. Accumulated amount and generation rate of spent fuels discharged from LWRs in some Asian countries were analyzed from the date of electric power consumption and share of nuclear power plant generation. Latent reprocessing demand which is caused by the pressure of big accumulations of spent fuel storage were also estimated. Then timing of commencing fuel reprocessing and MOX fuel utilizing were forecasted for Korea, Taiwan and China based on the above results.
Yumoto, Ryozo*; Yokochi, Yoji*; Koizumi, Masumichi*; Seki, Sadao*
PNC TJ9409 96-002, 93 Pages, 1996/03
The state of development of pyrometallurgical partitioning and extracting technology of irradiated fuel is investigated. Also in case of perfoming the test at O-arai engineering center, the contents of the test, equipments, structure and arragement of cells that equipments are installed, are studied. The purpose of the test is to confirm the realization of the process and behavior of FP and TRU elements, and off-gass that cannot be made dear by cold test. In this study it is assumed that 
100g monju fuel (94,000MWd/t B.U, cooled for 550 days) per batch is treated. Four processes are picked up except for pin sectioning and powdering, as important subjects. They are as follows. (1)reduction of oxide fuel (2)electrorefining (3)cathode processing (4)extraction of TRU elements. And the outline of the test, blocked flow chart and the outline of equipment are clarified. And the outline of chart is drawn. Moreover, the specification of analitical equipments which are necessary to analyze the product is shown. From spent chloride, TRU and a part of FP elements are extracted and they are recycled for electrorefining and so on. The salt-waste including residual FP elements is kept in a receptacle after being absorbed into Zeorite and soldified. As the disposition of these tests, modified test cell in the existing FMF, modified concrete cell in AGF, new cell at B2F in the existing FMF and new cell at second auxiliary room in FMF extension are studied. As result of considering the disposition for equipment, the difficulty of reconstucting new cell including of equipments, method of mentenance, and equipments of ventilazion (Ar circumstance) including of management of off gas, and the plan of disposition, it is concluded that constructing iron cell into the second auxiliary room of FMF extension is best, because it is easy to construct safely, and the occurance of radioactive waste and the influence to other tests is little, and it is possible to examine more efficiently.
; Yokochi, Yoji; *; ; Aoyama, Takafumi; ; Yatabe, Toshio
PNC TN9520 91-006, 861 Pages, 1991/07
None
Shikakura, Sakae*; Matsushima, Hideya*; Shibahara, Itaru*; *; *
PNC TN9420 89-004, 124 Pages, 1989/10
None
*; *; Koizumi, Masumichi
PNC TN9410 89-037, 32 Pages, 1989/03
New type fuels (metal, nitride and carbide) are expected to be superior to MOX fuel in future. Here, informations about the new fuels are investigated and evaluated for comparing with these of MOX (Mix Oxide) fuel. It is believed that this evaluation can contribute to the decision of policy how they are chosen. In Japan and Europe, the MOX fuel has been developed as the main FBE fuel. However, the research and development of MC (Mix Carbide) and MN (Mix Nitride) fuel in Europe, which includes the manufacturing process, properties of physical-chemistry, and irradiation behavior, has been continued on a labo-scale since before. In France, U.K., Switzerland, and West Germany, they have a plan of development which puts stress on MN fuel more than MC fuel. In the united States, DOE had developed MOX fuel as the favorite like Japan, but they decided to advance the development of Metal fuel and small-sized reactor in 1985. If they can't have anticipated results, it is thought to secure the option of being able to access to data of MOX fueled large scale FBR in Japan.
Yamaguchi, Takashi; *
PNC TN9410 88-138, 94 Pages, 1988/10
The second subco㎜ittee of the planning and coordinating committee on the Long-Term Program for Development and utilization of nuclear Energy in 1987 has discussed plutonium utilization strategy aside from FBR, and also utilizatlon possibility in HCLWR. Meanwhile, HCLWR development has made considerable progress in Japan, France and West Germany. From its characteristic advantage, it will have the possibility of affecting the plan of FBR development. Therefore, in the discussion of the next Program, HCLWR can be an option of strategical candidates next to LWR. HCLWR has a tight pitched MOX fuel sub-assembly. PNC will be able to estimate HCLWR exactly, because PNC has been conducting R&D on ATR, FBR, MOX fuel fabrication and reprocessing for a long time. For the estimation of the possibility of HCLWR as interium reactor, this report summarized the characteristics and status of development of HCLWR, and discussed activities that PNC is able to carry out.
Shikakura, Sakae*; Tobita, Noriyuki; Seki, Masayuki; Tsutagi, Koichi; *
PNC TN8420 87-003, 88 Pages, 1987/05
None
Komatsu, Junji*; *; Seki, Masayuki; *; Tobita, Noriyuki
PNC TN845 85-09, 57 Pages, 1985/09
Halden IFA-554/555 irradiation test is planned to examine the fuel behavier of ATR type fuel under load follow reactor operation. Eight fuel rods for this irradiation test were fabricated in Plutonium Fuel Div. in Tokai Works PNC. These fuel rods install instruments for the measurement of fuel columnelongation, cladding elongation, plenum pressure and fuel center temperature. The fuel pellets were made from one type of PuO2 raw materials. It was obtained by precipitation directde nitration process . The fuel compositionis 4.4% PuO2-UO2(natural), and the pellet nominal dimension is 12.40 mm diameter and 13 mm height.
*; *; *; *; *; ; *; Yamamoto, Kazuya*
PNC TN841 85-25, 125 Pages, 1985/03
no abstracts in English
*; Kamimura, Katsuichiro; Kodato, Kazuo; Yamaguchi, Toshihiro; *
PNC TN841 84-23, 190 Pages, 1984/05
no abstracts in English
*; Seki, Masayuki; Kaya, Akira; *; *; Tsutagi, Koichi; *; *
PNC TN843 84-05, 168 Pages, 1984/04
None
*; Kawata, Tomio*; Kaneda, Kenichiro; *; Goto, Tatsuro*; *
PNC TN841 84-67, 187 Pages, 1984/04
no abstracts in English
; ; *; *; *; Seino, Takeshi*; ; *; *; *
JAERI-M 84-031, 285 Pages, 1984/02
no abstracts in English
