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Nagai, Takayuki; Hasegawa, Takehiko*
JAEA-Research 2023-008, 41 Pages, 2023/12
JAEA-Research-2023-008.pdf:7.52MB
To reduce the risks posed by stored the high-level radioactive liquid waste (HAW), Tokai Vitrification Facility (TVF) is working to produce the HAW into vitrified bodies. With the aim of steady vitrification of HAW in TVF, the vitrification technology section has manufactured a new 3rd melter with an improved bottom structure and is working to verify the performance of this melter. In this study, solidified glass samples were taken from simulated vitrified bodies produced by flowing molten glass during the bottom drain-out test in the operation confirmation of the TVF 3rd melter. And the properties of the surface layer and fracture surface of the vitrified bodies were evaluated by using Raman spectroscopy, synchrotron radiation XAFS measurement, and laser ablation inductively coupled plasma atomic emission spectroscopy (LA ICP-AES) analysis. As a result of measuring the surface layer and fracture surface of the solidified samples produced on an actual scale, a slight difference was confirmed between the properties of the surface layer and those of the fracture surface. Since the chemical composition of these simulated vitrified bodies does not contain platinum group elements, it is expected that the glass structure of solidified glass samples is different from that of the actual vitrified body. However, this sample measuring was a valuable opportunity to evaluate samples produced by using the direct energized joule heating method. The properties of cullet used the operation confirmation of the TVF 3rd melter and the cullet of another production lot were measured and analyzed in the same manner under the measuring conditions of solidified glass samples. As a result, it was confirmed that cullet with different producing histories have different glass structures even with the same chemical composition, and that differences in glass structures remain in the glass samples after melting these cullet.
Nagai, Takayuki
JAEA-Research 2022-014, 84 Pages, 2023/02
JAEA-Research-2022-014.pdf:22.26MB
Most of the simulated waste glasses used for physical property evaluation are processed into a shape suitable for the measurement method from glass gob obtained by slowly cooling molten glass to room temperature. However, the actual vitrified waste glass material is obtained by cooling and being coagulated the glass drained from the bottom of glass melter into the canister. In this study, Raman spectroscopy was performed on the coagulated surface of molten simulated waste glass in the depth direction to evaluate the state of the Si-O bridging structure near the coagulated glass surface. The Raman spectra measured from the surface to the depth direction near the surface of the glasses produced by several melting and coagulation conditions of molten simulated waste glass cullet in the air atmosphere, and it was confirmed that there were changes in these spectra. On the other hand, the raw material glass cullet and the surface of the glass solidified in argon gas atmosphere showed little change in the spectrum in the depth direction, and the Si-O bridging structure near the glass surface was similar. It was also confirmed that the spectrum change in the depth direction measurement was small for the cut surface of the glass, and that the change in the spectrum for the broken glass fracture surface was also small. For glasses with a large change in Raman spectra in the depth direction near the coagulated surface, the molten glass was cooled from the molten state to room temperature in a muffle furnace with air atmosphere. That is, the magnitude of the spectral change with respect to the depth direction depends on the time from the molten state to coagulation. In order to confirm the reason why the number of bridging oxygen in the Si-O bridging structure is small on the coagulated surface of glass, the XANES spectra of Si-K edge and Ce-L3 edge were measured by XAFS on the coagulated surface and the cutting face. As a result, the Si-K edge peak on the coagulated surface is
Nakashio, Nobuyuki; Osugi, Takeshi; Iseda, Hirokatsu; Tohei, Toshio; Sudo, Tomoyuki; Ishikawa, Joji; Mitsuda, Motoyuki; Yokobori, Tomohiko; Kozawa, Kazushige; Momma, Toshiyuki; et al.
Journal of Nuclear Science and Technology, 53(1), p.139 - 145, 2016/01
Times Cited Count：1 Percentile：10.6(Nuclear Science & Technology)no abstracts in English
Meguro, Yoshihiro; Tomioka, Osamu; Imai, Tomoki*; Fujimoto, Shigeyuki*; Nakashima, Mikio; Yoshida, Zenko; Honda, Tadashi*; Koya, Fumio*; Kitamura, Nobu*; Wada, Ryutaro*; et al.
Proceedings of International Waste Management Symposium 2004 (WM '04) (CD-ROM), 8 Pages, 2004/03
Supercritical CO
fluid leaching (SFL) method using supercritical CO fluid containing a complex of HNO
- tri-n-butyl phosphate (TBP) was applied to removal of uranium from radioactive solid wastes. Sea sands, incineration ashes and porous alumina bricks were employed as matrixes of simulated solid wastes. Real radioactive incineration ash wastes and firebrick wastes were also subjected to the SFL treatment. It was found that uranium could be efficiently removed from both of the simulated wastes and real wastes by the SFL method. The removal efficiency of uranium from the real waste was lower than that from the corresponding artificial waste. About 1 g and 35 mg of uranium were recovered from 10 g of the real ash waste and 37 g of the real firebrick waste, respectively.
O-stabilized zirconia in air;
Journal of Nuclear Materials, 137, p.227 - 235, 1986/00
Times Cited Count：7 Percentile：62.96(Materials Science, Multidisciplinary)no abstracts in English
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JAERI-M 84-220, 23 Pages, 1984/12
no abstracts in English
; ; ;
JAERI-M 82-088, 19 Pages, 1982/07
no abstracts in English
; ; ; ; Araki, Kunio;
JAERI-M 9387, 13 Pages, 1981/02
no abstracts in English
Nagai, Takayuki; Kobayashi, Hidekazu; Okamoto, Yoshihiro; Seki, Katsumi*; Kobayashi, Hiromi*; Homma, Masanobu*; Hatakeyama, Kiyoshi*
no journal, ,
It is expected by bubbling operation of molten glass that glass composition becomes uniform. Air or Ar gas was purged into the molten simulated waste glass, and the drained glass was investigated by Raman spectrophotometry and synchrotron XAFS measurement. As a result, the Si-O bridging structure with a small number of non-bridging oxygen increases by Ar gas purging into the molten glass and also valence of Ce included in the simulated waste glass reduces.
Yamanaka, Keisuke*; Nagai, Takayuki; Ota, Toshiaki*
no journal, ,
For understanding the fundamental knowledge in the vitrification process of radioactive waste, the local structure of boron of simulated waste glass was investigated by using the XAFS measurement in BL-11 of Ritsumeikan University SR Center.
Nagai, Takayuki; Kobayashi, Hidekazu; Okamoto, Yoshihiro; Seki, Katsumi*; Kobayashi, Hiromi*; Homma, Masanobu*; Hatakeyama, Kiyoshi*
no journal, ,
no abstracts in English
Nagai, Takayuki; Sasage, Kenichi; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*
no journal, ,
no abstracts in English
