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Arai, Yoichi; Watanabe, So; Hasegawa, Kenta; Okamura, Nobuo; Watanabe, Masayuki; Takeda, Keisuke*; Fukumoto, Hiroki*; Ago, Tomohiro*; Hagura, Naoto*; Tsukahara, Takehiko*
Nuclear Instruments and Methods in Physics Research B, 542, p.206 - 213, 2023/09
Times Cited Count:1 Percentile:0.02(Instruments & Instrumentation)Kusaka, Ryoji; Watanabe, Masayuki
Journal of Physical Chemistry B, 125(24), p.6727 - 6731, 2021/06
Times Cited Count:8 Percentile:44.55(Chemistry, Physical)Okamoto, Yoshihiro; Kobayashi, Hidekazu; Shiwaku, Hideaki; Sasage, Kenichi; Hatakeyama, Kiyoshi*; Nagai, Takayuki
Journal of Non-Crystalline Solids, 551, p.120393_1 - 120393_8, 2021/01
Times Cited Count:5 Percentile:30.89(Materials Science, Ceramics)The chemical state of ruthenium in simulated iron phosphate radioactive waste glass was investigated by conventional X-ray absorption fine structure (XAFS) and imaging XAFS analyses. The EXAFS analysis suggested that ruthenium was contained as glass phase when content of the waste components was less than 10wt.% in 30 mol%FeO-PO base glass. In other samples, crystalline RuO was predominant. According to the imaging XAFS analysis, RuO particles in all samples had length smaller than 50m. Aggregations of RuO, which are found in nuclear waste borosilicate glass, were not seen in any of the iron phosphate glass samples.
Ueda, Yuki; Kikuchi, Kei*; Tokunaga, Kohei; Sugita, Tsuyoshi; Aoyagi, Noboru; Tanaka, Kazuya; Okamura, Hiroyuki
Solvent Extraction and Ion Exchange, 39(5-6), p.491 - 511, 2021/00
Times Cited Count:0 Percentile:0(Chemistry, Multidisciplinary)no abstracts in English
Ueda, Yuki; Kikuchi, Kei; Sugita, Tsuyoshi; Motokawa, Ryuhei
Solvent Extraction and Ion Exchange, 37(5), p.347 - 359, 2019/07
Times Cited Count:8 Percentile:34.18(Chemistry, Multidisciplinary)We have newly-designed fluorous phosphate(TFP) for the effective Zr(IV) ion extractant as an alternative extractant against the conventional organic phosphate, tri--butyl phosphate(TBP). Zr(IV) ion extraction system using the TBP has many problems such as the formation of the third phase during liquid-liquid extraction. Here, we develop the fluorous extraction system based on the TFP-perfluorohexane for the Zr(IV) ion extraction to improve the Zr(IV) ion extraction system with an effective extractability and without the third phase formation. Our main findings were that the significant high extraction performance of the TFP for Zr(IV) ion as compared with TBP, and the origins of the high extraction performance of the TFP are related to the water and HNO contents in the fluorous phase and the stability of the complex, Zr(No)(TFP).
Irisawa, Keita; Kudo, Isamu*; Taniguchi, Takumi; Namiki, Masahiro*; Osugi, Takeshi; Nakazawa, Osamu
QST-M-16; QST Takasaki Annual Report 2017, P. 63, 2019/03
no abstracts in English
Irisawa, Keita; Kudo, Isamu*; Taniguchi, Takumi; Namiki, Masahiro*; Osugi, Takeshi; Nakazawa, Osamu
QST-M-8; QST Takasaki Annual Report 2016, P. 63, 2018/03
A solidification technique with minimized water content is being developed using a phosphate cement for safe storage of secondary radioactive wastes in the Fukushima Daiichi Nuclear Power Plant. To understand the applicability of the solidification technique for the actual secondary wastes, phosphate cement during dehydration was irradiated by Co -ray. The G(H) for the phosphate cement decreased with time during dehydration, and was not detected after 7 days. Moreover, the Co -ray irradiation during dehydration did not change the crystalline and amorphous phases of the phosphate cement.
Amamoto, Ippei
Journal of the Society of Inorganic Materials, Japan, 24(391), p.393 - 401, 2017/11
Glass is a non-crystalline solid, as such, it is relatively easy to change its composition to control its characteristics. The borosilicate glass, which is produced by the addition of boron oxide into sodium-lime glass, possesses excellent heat-resistant properties and mechanical strength. It has a wide variety of uses. The borosilicate glass is applied as the vitrified medium for radioactive wastes to immobilize and stabilize them for long term. The glass form which is loaded with high-level radioactive waste is called the vitrified waste. This paper classified the radioactive waste and describes treatment and production methods of vitrified waste, its characteristics, disposal method and also introduces alternative vitrified medium.
Onishi, Takashi; Tanaka, Kosuke; Koyama, Shinichi; Ou, L. Y.*; Mimura, Hitoshi*
NEA/NSC/R(2017)3, p.463 - 469, 2017/11
no abstracts in English
Nagai, Takayuki; Kobayashi, Hidekazu; Okamoto, Yoshihiro
Photon Factory Activity Report 2016, 2 Pages, 2017/00
To estimate the valence state of iron in the preparation process of iron phosphate glass frit, mixtures of ferric oxide and phosphoric acid was heated and XANES spectra of Fe-K edge was measured in this study. This report described the situation of high temperature XAFS measurement and results of this study.
Motokawa, Ryuhei; Endo, Hitoshi*; Nagao, Michihiro*; Heller, W. T.*
Solvent Extraction and Ion Exchange, 34(5), p.399 - 406, 2016/07
Times Cited Count:5 Percentile:19.64(Chemistry, Multidisciplinary)Mu, J.*; Motokawa, Ryuhei; Williams, C. D.*; Akutsu, Kazuhiro*; Nishitsuji, Shotaro*; Masters, A. J.*
Journal of Physical Chemistry B, 120(23), p.5183 - 5193, 2016/06
Times Cited Count:27 Percentile:60.26(Chemistry, Physical)Ueda, Ryoshiro*; Sato, Katsuya; Hayashi, Hidenori*; Narumi, Issey*; Ono, Yutaka
JAEA-Review 2015-022, JAEA Takasaki Annual Report 2014, P. 101, 2016/02
Ueda, Ryoshiro; Sato, Katsuya; Hayashi, Hidenori*; Narumi, Issey*; Ono, Yutaka
JAEA-Review 2014-050, JAEA Takasaki Annual Report 2013, P. 118, 2015/03
Tsuzuki, Tatsuya*; Mitamura, Naoki*; Amamoto, Ippei
Shakai, Kankyo Hokokusho 2014 (Internet), p.6 - 7, 2014/10
no abstracts in English
Abe, Hitoshi; Tashiro, Shinsuke; Miyoshi, Yoshinori
Nihon Genshiryoku Gakkai Wabun Rombunshi, 6(1), p.10 - 21, 2007/03
In MOX fuel fabrication facility, zinc stearate will be added into the MOX powder as addition material. If the material is added in large excess by miss operation, criticality characteristics of the MOX fuel would be influenced because it has neutron moderation effect. If criticality condition should be induced by the excess addition, physical variations, such as melting and pyrolysis of the material, must be caused by the fission energy and dynamic characteristics of the MOX fuel must be affected. To contribute quantitative evaluation of the dynamic characteristics, thermal properties data such as exo/endothermic calorific values, reaction rates, etc. with the respective physical variations and release behavior of pyrolysis gas were measured. It was found the exo/endothermic behavior with rinsing temperature of the material could be divided into six regions and rapid pressure rise caused by the pyrolysis reaction over about 400 C. Furthermore, on the basis of the results, evaluation model for the thermal properties under the criticality condition was also investigated.
Onuki, Toshihiko; Ozaki, Takuo; Yoshida, Takahiro*; Sakamoto, Fuminori; Kozai, Naofumi; Wakai, Eiichi; Francis, A. J.; Iefuji, Haruyuki*
Geochimica et Cosmochimica Acta, 69(22), p.5307 - 5316, 2005/11
Times Cited Count:48 Percentile:68.3(Geochemistry & Geophysics)no abstracts in English
Seko, Noriaki; Tamada, Masao; Yoshii, Fumio
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.340 - 345, 2004/12
Fibrous adsorbents having chelate agent such as amidoxime (AN/MAA-ad), iminodiacetic acid (IDA-ad), and phosphoric acid (HMPA-ad) were prepared by radiation-induced graft polymerization. AN/MAA-ad was synthesized by co-grafting of acrylonitrile and methacrylic acid. Then the introduced functional group of CN was converted to the amidoxime with chemical treatment. Grafting of glycidyl methacrylate and chemically introducing the IDA group synthesized IDA-ad. HMPA-ad was directly synthesized by grafting of phosphoric acid monomer. The densities of the chelate agency were 3.5 mol/kg for AN/MAA-ad, 2.0 mol/kg for IDA-ad and 2.0 mol/kg for HMPA-ad after the grafting time of 2, 1.5 and 8 hours, respectively. HMPA-ad had 200 times higher distribution coefficient for uranium than that of a commercial adsorbent (Diaion-PK216) at pH 0.5. The distribution coefficient for AN/MAA-ad became 500 times higher than that of Diaion-CR11 more than pH 8. These chelate adsorbents are promising materials for removal of uranium from acid or alkali treated waste sludge contaminated uranium.
Hashimoto, Kazuyuki; Matsuoka, Hiromitsu
Radiochimica Acta, 92(4-6), p.285 - 290, 2004/07
Times Cited Count:1 Percentile:10.03(Chemistry, Inorganic & Nuclear)no abstracts in English
Basuki, F.*; Seko, Noriaki; Tamada, Masao; Sugo, Takanobu; Kume, Tamikazu
Nihon Ion Kokan Gakkai-Shi, 14(Suppl.), p.209 - 212, 2003/00
Radiation induced graftpolymerization is a sophisticated tool for introducing the aiming functional group into the conventional polymer. Adsorbent having phosphoric acid was directly synthesized by grafting methacrylate monomer having phosphoric acid onto polyethylene nonwoven fabric. Degree of grafting, which was estimated by increment weight after grafting, reached 185 % when the 10 % monomer in the mixture of 10 % methanol and 90 % water was reacted with 200 kGy-irradiated polyethylene nonwoven fabric. The resulting adsorbent revealed that adsorption capacities were 3 mmol/g-adsorbent for Pb and Cd. The removal of these metals could be performed with space velocity of 250 h.