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Maekawa, Kazuhiko*; Yoshimura, Tadahiro*; Kikuchi, Toshiaki*; Hoshino, Yasushi*; Munekata, Hideki*; Shimizu, Makoto*
JNC TJ9420 2005-004, 284 Pages, 2005/02
JNC-TJ9420-2005-004.pdf:11.56MB
In feasibility studies on commercialized FBR cycle system, comprehensive system investigation and properties evaluation for candidate FBR cycle systems have been implemented through view point of safety, economics, environmental burden reduction, non-proliferation resistivity, etc. As part of these studies, an investigation of small scale sphere-pac fuel fabrication plant with external gelation process was conducted. Until last fiscal year, equipment layout in cells and overall layout design of the 200t-HM/y scale fuel fabrication plant were conducted as well as schematical design studies on main equipments in gelation and reagent recovery processes of the plant. System property data concerning economics and environmental burden reduction of fuel fabrication plant was also acquired. In this fiscal year, the processes from vibropacking to fuel assemblies storage were added to the investigation range, and a conceptual design of whole fuel fabrication plant was studied as well as deepening the design study on main equipments. The conceptual design study was mainly conducted for small 50t-HM/y scale plant and a revising investigation was done for 200t-HM/y scale Plant. Taking the planed comparative evaluation with pellet fuel fabrication system into account, design of equipments which should be equivalent with pellet system, especially in post-vibropacking processes, were standardized in each system. Based on these design studies, system properties data concerning economics and environmental burden reduction of the plant was also acquired. In comparison with existing design, the cell height was lowered on condition that plug type pneumatic system was adopted and fuel fabrication building was downsized by applying rationalized layout design of pellet system to post-vibropacking processes. Reduction of reagent usage at gelation process and rationalization of sintering and O/M controlling processes etc., are foremost tasks.
; kasahara, Naoto; ; ; Kamide, Hideki
JNC TN9400 2000-010, 168 Pages, 2000/02
JNC-TN9400-2000-010.pdf:8.78MB
Thermal striping is significant issue of the structural integrity, where the hot and cold fluids give high cycle fatigue to the structure through the thermal stress resulted from the time change of temperatur distibution in the structure. In the sodium cooled fast reactor, temperature change in fluid easily transfers to the structure because of the high thermal conductivity of the sodium. It means that we have to take care of thermal striping, The thermal striping is complex phenomena between the fluid and structure engineering fields. The investigations of thermal striping are not enough to evaluate the integrity directly. That is the fluctuation intensity at the structure surface is assumed to be temperature difference between source fluids (upstream to the mixing region) as the maximum value in the design. 0therwise, the design conditions are defined by using a mockup experiment and large margin of temperature fluctuation intensity. Furthermore, such evaluation manners have not yet been considered as a design rule. Transfer mechanism of temperature fluctuation from fluid to structure has been investigated by the authors on the view points of the fluid and structure. Attenuation of temperature fluctuation was recognized as a dominant factor of thermal fatigue. We have devdoped a numerical analysis system which can evaluate thermal fatigue and crack growth with consideration of the attenuation of temperature fluctuation in fluid, heat transfer, and structure. This system was applied to a real reactor and the applicability was confirmed. Further verification is planned to generalize the system. For the higher cost performance of the fast reactor, an evaluation rule is needed, which can estimate thermal loading with attenuation and can be applied to the design. An idea of the rule is proposed here. Two methods should be prepared; one is a precise evaluation method where mechanism of attenuation is modeled, and the other is simple evaluation method where ...
Suzuki, Kazuyuki; Kikuchi, Hideki; Hata, Katsuro; Tanaka, Ken; Miyamoto, Masanori; Nakamura, Yoshinobu; Hayashi, Shinichiro
no journal, ,
no abstracts in English
Hata, Katsuro; Suzuki, Kazuyuki; Kikuchi, Hideki; Kogawa, Takayuki; Nakamura, Yoshinobu; Hayashi, Shinichiro
no journal, ,
no abstracts in English
Terunuma, Hirotaka; Shimoyamada, Tetsuya; Kogawa, Takayuki; Kikuchi, Hideki; Miyoshi, Ryuta; Yokota, Satoru; Nakamura, Yoshinobu; Hayashi, Shinichiro
no journal, ,
We have developed dissolver cleaning device which can clean up sludge inside dissolver with high pressure water spray. The device has been applied to TRP dissolvers and the sludge has been cleaned up successfully. This allowed smooth solution transfer and stable operation of the dissolvers.
Kikuchi, Hideki; Suzuki, Kazuyuki; Sugai, Eiji; Hikita, Keiichi; Otani, Takehisa; Samoto, Hirotaka; Hayashi, Shinichiro
no journal, ,
About 6t the Fugen MOX type B fuels, whose Pu content rate is about 1.7%, were reprocessed on Tokai Reprosessing Plant(TRP) to the present. It was required to control plutonium(Pu) concentration of dissolution liquor because of the higher Pu content of the MOX fuels. There operational method to control Pu concentration by dilution has be established. And the amount of Pu, which was transferred to the highly radioactive liquid waste system with the residue from the clarification process, was investigated.
Sugai, Eiji; Kikuchi, Hideki; Hatanaka, Akira; Otani, Takehisa; Suzuki, Kazuyuki; Taguchi, Katsuya
no journal, ,
no abstracts in English
Sugai, Eiji; Hata, Katsuro; Kikuchi, Hideki; Terunuma, Hirotaka; Uchida, Naoki; Taguchi, Katsuya
no journal, ,
no abstracts in English
Otani, Takehisa; Suzuki, Kazuyuki; Hata, Katsuro; Kikuchi, Hideki; Nakamura, Daishi; Samoto, Hirotaka; Tanaka, Yukiyoshi
no journal, ,
The investigation of the behavior of krypton gas arising due to reprocessing of spent fuels has been performed at TRP. The whole amount of Kr gas transfers to the off-gas system through shearing and dissolution process, so it is applicable as an indicator to determine the progress of fuel dissolution. It is thought that the behavior of gaseous fission product, including Kr, in the spent fuels depends on burn-up and the type of spent fuels. In the reprocessing process, these deference are reflected to the migration rate of krypton gas between shearing off-gas system (SOG) and dissolver off-gas system (DOG). At TRP, four types of spent fuels (LWR; PWR, BWR and ATR; UO
, MOX) were treated and examined about their release characteristics of krypton gas in order to understand the effect on burn-up and type of spent fuels. In this report, the results concerning the ATR-UO fuel and ATR-MOX fuel are discussed compared with the results of LWR fuel.
Nakamura, Daishi; Kikuchi, Hideki; Terunuma, Hirotaka; Uchida, Naoki; Tanaka, Yukiyoshi
no journal, ,
Sludge generated in the dissolution vessel deposit on storage vessel and caused translation pipe to be choked. It is difficult to remove sludge from vessel and translation piping for few of accessible point in this line and high radioactive environment. In this report, we report on the blockage removal device and method in translation piping adapted on existing machine in order to establish sludge removal technique.
Kikuchi, Hideki; Numata, Shinji; Suzuki, Kazuyuki; Wakimoto, Fumitsugu; Tanaka, Yukiyoshi
no journal, ,
Tokai Reprocess Plant (TRP) has reprocessed about 1140 tU spent nuclear fuel for 35 years. In clarification process, there are 2 kinds of valves that used under spent fuel dissolving solution environment. These valves operation data are very valuable in process handling dissolving solution because the valves are rarely used in this process. In this report, we summarize malfunctions of the valves that we have experienced until now, and explain the method of maintenance and operation management.