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Ikeuchi, Hirotomo; Koyama, Shinichi; Osaka, Masahiko; Takano, Masahide; Nakamura, Satoshi; Onozawa, Atsushi; Sasaki, Shinji; Onishi, Takashi; Maeda, Koji; Kirishima, Akira*; et al.
JAEA-Technology 2022-021, 224 Pages, 2022/10
A set of technology, including acid dissolving, has to be established for the analysis of content of elements/nuclides in the fuel debris samples. In this project, a blind test was performed for the purpose of clarifying the current level of analytical accuracy and establishing the alternative methods in case that the insoluble residue remains. Overall composition of the simulated fuel debris (homogenized powder having a specific composition) were quantitatively determined in the four analytical institutions in Japan by using their own dissolving and analytical techniques. The merit and drawback for each technique were then evaluated, based on which a tentative flow of the analyses of fuel debris was constructed.
Yamagishi, Isao; Odakura, Makoto; Ichige, Yoshiaki; Kuroha, Mitsuhiko; Takano, Masahide; Akabori, Mitsuo; Yoshioka, Masahiro*
Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1113 - 1119, 2015/09
The characteristics of insoluble residues in fine suspension at the Rokkasho Reprocessing Plant were analyzed. The insoluble residues were washed with oxalic acid solution to dissolve zirconium molybdate residues. XRD profiles of unwashed residues showed the presence of a noble metal alloy, zirconium molybdate, and zirconia, but zirconium molybdate was not found after washing. More than 50% of the Sb-125 and Pu in thee residues was washed out as well. The noble metal alloy composed of Mo, Tc, Ru, Rh, and Pd occupied more than 90% of the total weight of 12 elements (Ca, Cr, Fe, Ni, Zr, Mo, Tc, Ru, Rh, Pd, Te, and U) found in the residues. In consideration of the chemical forms of 12 elements, the alloy-to-residue weight ratio was evaluated to be 64% and 78% with and without 18% of an unknown component, respectively.
Tanigawa, Hiroyasu; Sakasegawa, Hideo*; Zinkle, S. J.*; Klueh, R. L.*; Koyama, Akira*
Fusion Materials Semiannual Progress Report for the Period Ending (DOE/ER-0313/35), p.30 - 32, 2004/04
Extraction residue was made from several HFIR 11J-irradiated RAFs, and the mass change was measured to investigate the irradiation-enhanced change in precipitation. Two different types of filter with coarse and fine pores were used in order to separate the difference of irradiation effects between larger and smaller precipitates. Unirradiated specimens were examined as well. Results suggest that during irradiation the mass of larger precipitates increased in F82H-IEA, Ni-doped F82H, JLF-1 and ORNL9Cr, fine precipitates disappeared in JLF-1, and fine precipitates increased in Ni-doped F82H.
Tanigawa, Hiroyasu; Sakasegawa, Hideo*; Payzant, E. A.*; Zinkle, S. J.*; Klueh, R. L.*; Koyama, Akira*
Fusion Materials Semiannual Progress Report for the Period Ending (DOE/ER-0313/35), p.37 - 40, 2004/04
XRD analyses were performed on the extraction residue of HFIR 11J-irradiated RAFs to investigate the overall precipitate character. Un-irradiated and aged specimens were examined as well. Results suggested that the distinctive peaks of M23C6 (M; Cr, Fe, W) were observed on all specimens. Peaks possibly related to MX (M;Ta,Ti,V : X ; C, N) were observed on the specimens extracted from un-irradiated JLF-1 and ORNL9Cr, but those peaks were not observed on irradiated specimens.
Nakai, Hisaaki*; Seko, Noriaki; Tamada, Masao; Temma, Tsuyoshi*; Oguma, Masaomi*
Nihon Ion Kokan Gakkai-Shi, 15(1), p.10 - 15, 2004/01
Removal of cadmium from the boiled mid-gut gland of the scallop was investigated to utilize the waste of scallop processing for the fertilizer and the livestock feed. Twelve kinds of acid solutions (0.1M) were evaluated on the point of the cadmium elution, toxicity, and price. The selected malic acid could wash out cadmium less than 0.5ppm in the boiled mid-gut gland by optimizing the acid concentration and the repitaion of rinse. It was confirmed that the concentration of the eluted cadmium was reduced to 0.1ppm and less than by the iminodiacetic acid adsorbent synthesized with radiation-induced graftpolymerization.
Mineo, Hideaki; Kihara, Takehiro; *; Kimura, Shigeru; *; ; Uchiyama, Gunzo; Hotoku, Shinobu; Watanabe, Makio; ; et al.
JAERI-Conf 99-004, p.498 - 507, 1999/03
no abstracts in English
Kihara, Takehiro; *; ; *; *; Fujine, Sachio
JAERI-Research 96-070, 23 Pages, 1997/01
no abstracts in English
PNC TN9410 93-226, 109 Pages, 1993/10
Feasibility studies of minor actinide(MA) transmutation in a fast reactor have been performed to achieve the following objectives : (1)Development of a fast reactor core concept loaded with MA fuel which has no serious penalties to core performance in consideration of fuel cycle technology, (2)Conception of an innovative core by utilizing the predominant properties of MA. This paper is summarized the results of the two feasibility studies of MA transmutation in a fast reactor in PNC.
; Yasu, Takami; Kawata, Tomio
PNC TN8410 91-325, 68 Pages, 1991/11
[Purpose] We confirmed modified (6000rpm type) centrifugal clarifier happened unstable vibration in the downward rotation on the condition of including undissolved residue after the clarification operation. This report describes the cause of unstable vibration and the measurement results of vibration characteristic after taking countermeasure for vibration decrease. [Method] It was considered that the cause of unstable vibration was four items in the following. (1)Unbalance between damping force of lower bearing damper and vibration force arisen by rotational bowl (2)Effect of feed condition (3)Effect of self-excited vibration on the free surface (4)Effect of frame strength that be set modified. This test is for take countermeasure to each item (13 item) in the upper items, and for quantitative measure of vibration characteristic (amplitude of rotational bowl and shaft) in the downward rotation on the condition of including undissolved residue after the clarification operation and for select best countermeasure, that is most effective to vibration damping, and does not arise the fall of clarification performance (capture efficiency), the increase of leak rate of feed solution and the fall of sludge washing performance. [Results] (1)We could not confirme vibration damping, compared with spring constant k=9 kgf/cm, damping constant c=20㎏fs/cm and the former condition (k=600 kgf/cm, c=0.3 kgfs/cm). (2)In case of countermeasure that operate as balance ring by sludge cohering height on the inside wall of rotational bowl, we could confirm that the amplitude in the downward rotation is about 1/3, the leak rate of feed solution is about 1/6, compared with the case of feed solution 55㎜ in height from the lower plate of rotational bowl and the former condition (25mm in height from the lower plate of rotational bowl). (3)Compared with the case of setting the side baffle plate 150㎜ in height from the lower plate of rotational bowl for decreasing ...
Sakurai, Tsutomu; ; ; Komaki, Yoshihide
Nuclear Technology, 94, p.99 - 107, 1991/04
Times Cited Count:4 Percentile:47.84(Nuclear Science & Technology)no abstracts in English
JAERI-M 91-010, 187 Pages, 1991/02
no abstracts in English
Sakurai, Tsutomu; ; ; Komaki, Yoshihide; ; Adachi, Takeo
Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management: RECOD91,Vol. 2, p.678 - 681, 1991/00
no abstracts in English
Adachi, Takeo; ; *; ; *; Takeishi, Hideyo; Gunji, Katsubumi; Kimura, Takaumi; ; Nakahara, Yoshinori; et al.
Journal of Nuclear Materials, 174, p.60 - 71, 1990/00
Times Cited Count:40 Percentile:94.49(Materials Science, Multidisciplinary)no abstracts in English
Uchiyama, Gunzo; *; *; Maeda, Mitsuru
JAERI-M 87-101, 17 Pages, 1987/07
no abstracts in English
Nakashio, Nobuyuki; Muraguchi, Yoshinori; Mimura, Ryuji; Nemoto, Koichi; Shiraishi, Kunio
no journal, ,
no abstracts in English
Takeuchi, Masayuki; Miyazaki, Yasunori; Kofuji, Hirohide
no journal, ,
no abstracts in English
Abe, Risako*; Hirasawa, Izumi*; Miyazaki, Yasunori; Takeuchi, Masayuki
no journal, ,
no abstracts in English
松村 達郎; 津幡 靖宏; 佐野 雄一; 小山 真一
山村 朝雄*; 鷹尾 康一郎*; 鈴木 達也*; 可児 祐子*; 高橋 優也*; 小山 直*; 駒嶺 哲*; 藤田 玲子*; 小澤 正基*
【課題】使用済燃料の再処理工程で発生する不溶解性残渣に含まれるジルコニウムやパラジウムを効率よく回収する方法を提供すること。 【解決手段】不溶解性残渣を過酸化水素含有酸性水溶液等で処理し、不溶解性残渣に含まれるジルコニウムとモリブデンを該酸性水溶液に溶解させて分離する。得られたジルコニウムとモリブデンは、抽出剤などを用いて分離され、ジルコニウムに含まれる長寿命放射性核種は偶奇分離によって低減される。また、酸性水溶液に不溶のパラジウムなどを含む白金族合金については、強酸処理、酸化溶解、フッ素化などによりパラジウムを分離し、パラジウムに含まれる長寿命放射性核種も偶奇分離によって低減される。