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Watanabe, Takeshi*; Tsushima, Satoru*; Yamamoto, Ichiro*; Tomioka, Osamu; Meguro, Yoshihiro; Nakashima, Mikio; Wada, Ryutaro*; Nagase, Yoshiyuki*; Fukuzato, Ryuichi*
Proceedings of 2nd International Symposium on Supercritical Fluid Technology for Energy and Environment Applications (Super Green 2003), p.363 - 366, 2004/00
Recovery of salts by supercritical fluid leaching (SFL) method using carbon dioxide was experimentally studied. It was confirmed that LiCl was recovered with a mixed fluid of carbon dioxide and methanol, and KCl and SrCl
were recovered with a mixed fluid of carbon dioxide, methanol and crown ether. The influence of crown ether for KCl and SrCl extraction were found to increase in the order of 15-crown-5 (15C5) 
18-crown-6 (18C6) dicychlohexyl-18-crown-6 (DC18C6). It is expected that other salts can be recovered selectively with a mixed fluid of carbon dioxide, methanol and suitable crown ether.
Nagase, Yoshiyuki*; Masuda, Kaoru*; Wada, Ryutaro*; Yamamoto, Ichiro*; Tomioka, Osamu; Meguro, Yoshihiro; Fukuzato, Ryuichi*
Proceedings of 2nd International Symposium on Supercritical Fluid Technology for Energy and Environment Applications (Super Green 2003), p.254 - 257, 2004/00
no abstracts in English
Nagase, Fumihisa; Chuto, Toshinori; Hatakeyama, Yuichi; Fuketa, Toyoshi
no journal, ,
LOCA-simulated experiments were conducted with irradiated PWR and BWR fuel cladding (77 GWd/t) to investigate high burnup effect on LWR fuel behavior under LOCA conditions. In the experiments, MDA, NDA, ZIRLO, M5 and Zircaloy-2 cladding specimens were sampled from the high burnup fuels irradiated at European power plants, and they were oxidized at 1563 to 1480 K and quenched. The cladding specimens oxidized to 18.3 to 27.3% ECR did not fracture during the quench. Consequently, the fracture boundary is not significantly reduced in the examined burnup range. Obvious high burnup effect was not seen also in the ballooning, rupture, fracture behavior.
Yoshida, Masaaki*; Nemoto, Shuhei*; Nagase, Midori*; Arai, Tsuyoshi*; Emori, Tatsuya; Morita, Keisuke; Ban, Yasutoshi; Watanabe, So; Sano, Yuichi; Kunii, Shigeru*
no journal, ,
In this study, we investigated the adsorption characteristics of simulated nuclides of adsorbents carrying various NTA amide extracts. From the results of this test, It has become clear that HONTA-impregnated adsorbent showed a high adsorption distribution coefficient with respect to Ln (III) at a nitric acid concentration of 10
- 10
M. It has also revealed that all elements quickly reached adsorption equilibrium. In addition, the elution of the extractant and Sty / DVB was not occurred from the results of the extractant elution test from the impregnated adsorbent. We discuss the applicability of the extraction chromatography method using various NTA adsorbents.
Sato, Hiromori*; Yoshida, Masaaki*; Nemoto, Shuhei*; Nagase, Midori*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi
no journal, ,
We focused on the extraction chromatography technique using HONTA impregnated adsorbent for MA (III)/Ln (III) separation from high-level radioactive liquid waste. In this study, we had the column test for evaluating the adsorption performance with the improved carrier.
Yoshida, Junya; Ohashi, Masaki*; Goto, Ryosuke*; Nagase, Yuichi*; Murai, Rina*; May, S.*; Aye, M. M. T.*; Kimbara, Shinji*; Yoshimoto, Masahiro*; Nakazawa, Kazuma*
no journal, ,
J-PARC E07 collaboration has been performed K- beam exposure to all the emulsion sheet detector. The analysis for double strangeness nuclei is ongoing. We'll discuss the current status, performance, speed, and future prospects.
Nagase, Midori*; Arai, Tsuyoshi*; Sano, Yuichi; Watanabe, So; Kunii, Shigeru*
no journal, ,
As a separation technology for recovering MA (III) from high-level radioactive liquid waste, we focused on an adsorbent impregnated with an NTA amide extractant. In this study, we synthesized H2EH NTA extractant, which is one of the NTA amide extractants, and investigated the adsorption / elution behavior for rare earth elements.