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Senzaki, Tatsuya; Arai, Yoichi; Yano, Kimihiko; Sato, Daisuke; Tada, Kohei; Ogi, Hiromichi*; Kawanobe, Takayuki*; Ono, Shimpei; Nakamura, Masahiro; Kitawaki, Shinichi; et al.
JAEA-Testing 2022-001, 28 Pages, 2022/05
JAEA-Testing-2022-001.pdf:2.33MB
In preparation for the decommissioning of Laboratory B of the Nuclear Fuel Cycle Engineering Laboratory, the nuclear fuel material that had been stored in the glove box for a long time was moved to the Chemical Processing Facility (CPF). This nuclear fuel material was stored with sealed by a polyvinyl chloride (PVC) bag in the storage. Since it was confirmed that the PVC bag swelled during storage, it seems that any gas was generated by radiolysis of the some components contained in the nuclear fuel material. In order to avoid breakage of the PVC bag and keep it safety for long time, we began the study on the stabilization treatment of the nuclear fuel material. First, in order to clarify the properties of nuclear fuel material, radioactivity analysis, component analysis, and thermal analysis were carried out. From the results of thermal analysis, the existence of organic matter was clarified. Then, ion exchange resin with similar thermal characteristics was selected and the thermal decomposition conditions were investigated. From the results of these analyzes and examinations, the conditions for thermal decomposition of the nuclear fuel material contained with organic matter was established. Performing a heat treatment of a small amount of nuclear fuel material in order to confirm the safety, after which the treatment amount was scaled up. It was confirmed by the weight change after the heat treatment that the nuclear fuel material contained with organic matter was completely decomposed.
Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nomura, Kazunori; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Hagura, Naoto*; Kubota, Toshio*
Nuclear Instruments and Methods in Physics Research B, 477, p.54 - 59, 2020/08
Times Cited Count：5 Percentile：45.45(Instruments & Instrumentation)Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nomura, Kazunori; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Kubota, Toshio*
QST-M-23; QST Takasaki Annual Report 2018, P. 59, 2020/03
Otaka, Toshiki*; Sato, Tatsumi*; Ono, Shimpei; Nagoshi, Kohei; Abe, Ryoji*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Takeuchi, Masayuki; Nakatani, Kiyoharu*
Analytical Sciences, 35(10), p.1129 - 1133, 2019/10
Times Cited Count：9 Percentile：40.49(Chemistry, Analytical)Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nakamura, Masahiro; Shibata, Atsuhiro; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Hagura, Naoto*; et al.
International Journal of PIXE, 29(1&2), p.17 - 31, 2019/00
The spent PUREX solvent containing U and Pu is generated from the reprocessing process of spent nuclear fuel. The nuclear material removal is important for the safe storage or disposal of the spent solvent. Our previous study revealed that the adsorbent with the iminodiacetic acid (IDA) functional group is one of the most promising materials for designing the nuclear material recovery process. Accordingly, an IDA-type adsorbent was synthesized by using graft polymerization technology or a chemical reaction to improve the adsorption rate and capacity. The synthesized IDA-type adsorbent was characterized by micro particle-induced X-ray emission (PIXE) and extended X-ray absorption fine structure (EXAFS) analyses. The micro-PIXE analysis revealed that Zr was adsorbed on the whole synthesized adsorbents and quantified the microamount of adsorbed Zr. Moreover, EXAFS suggested that Zr in the aqueous solution and solvent can be trapped by the IDA group with different mechanisms.
Watanabe, So; Sano, Yuichi; Shiwaku, Hideaki; Yaita, Tsuyoshi; Ono, Shimpei*; Arai, Tsuyoshi*; Matsuura, Haruaki*; Koka, Masashi*; Sato, Takahiro*
Nuclear Instruments and Methods in Physics Research B, 404, p.202 - 206, 2017/08
Times Cited Count：3 Percentile：28.82(Instruments & Instrumentation)Ono, Shimpei*; Arai, Tsuyoshi*; Sano, Kyohei*; Watanabe, So; Sano, Yuichi; Nakamura, Masahiro; Nomura, Kazunori
no journal, ,
To improve the adsorption ability, the synergic extraction effect was investigated on porous SiO
particles and confirmed.
Ono, Shimpei*; Sano, Kyohei*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Nakamura, Masahiro; Nomura, Kazunori
no journal, ,
The effect of synergism on the adsorption behavior was evaluated and confirmed in the system with porous SiO particles in which extractants were impregnated.
Watanabe, So; Nakamura, Masahiro; Nomura, Kazunori; Nakajima, Yasuo; Arai, Tsuyoshi*; Ono, Shimpei*
no journal, ,
no abstracts in English
Ono, Shimpei*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Takeuchi, Masayuki
no journal, ,
no abstracts in English
carrier"Nagoshi, Kohei*; Arai, Tsuyoshi*; Ono, Shimpei*; Watanabe, So; Sano, Yuichi; Takeuchi, Masayuki
no journal, ,
no abstracts in English
Chiba, Yusuke; Ichikawa, Shoichi; Ono, Shimpei; Hatori, Masakazu; Kobayashi, Takanori; Uekura, Ryoichi; Hashiri, Nobuo*; Inuzuka, Taisuke*; Abe, Hisashi*; Kitano, Hiroshi*
no journal, ,
The lithium chloride-type dew point detector was used for reactor containment vessel the entire leak rate test (CV-LRT) in fast-breeder reactor Monju (Monju) which needs the maintenance every three months. But when the plant process is considered, it's desirable for the maintenance periods beyond 12 months. Thereupon the capacitance-type dew point detector made in VAISALA Corporation was nominated as the alternative lithium chloride-type dew point detector in Monju. The lithium chloride-type dew point detector, when it's adopted, for, to have to be satisfied a request of the regulations, it's necessary to estimate the performance of the lithium chloride-type dew point detector. In the condition of the CV-LRT, the dew point data were measured by the capacitance-type dew point detector and the lithium chloride-type dew point detector for 24 hours. These data were compared and the performance of the capacitance-type dew point detector was estimated. Furthermore, the dew point data of Monju under the atmosphere ware continuously measured by the capacitance-type dew point detector and the mirror surface-type dew point detector for 2 years. These data were compared and the performance of the capacitance-type dew point detector was estimated. As a result, the capacitance-type dew point detector was confirmed that had the instrument precision that JEAC4203-2008 required.
Matsuura, Haruaki*; Nezu, Atsushi*; Arai, Tsuyoshi*; Ono, Shimpei*; Sano, Yuichi; Watanabe, So
no journal, ,
no abstracts in English
Ono, Shimpei; Kawanobe, Takayuki*; Watahiki, Hiromi; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Ono, Shimpei; Arai, Yoichi; Watanabe, So; Seko, Noriaki*; Kasai, Noboru*; Hoshina, Hiroyuki*; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Ono, Shimpei; Arai, Yoichi; Watanabe, So; Seko, Noriaki*; Kasai, Noboru*; Hoshina, Hiroyuki*; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nomura, Kazunori; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Kubota, Toshio*
no journal, ,
no abstracts in English
Ono, Shimpei; Ichige, Yoshiaki; Shibata, Atsuhiro; Sato, Takehiko; Takeuchi, Masayuki
no journal, ,
no abstracts in English
大野 真平; 渡部 創; 佐野 雄一; 小藤 博英; 竹内 正行
新井 剛*; 松浦 治明*; 中谷 清治*
JP, 2017-016011 Patent licensing information Patent publication (In Japanese)
【課題】様々な金属元素を含む酸性溶液から抽出剤を含浸させてなる含浸吸着材を用いて特定の金属元素を効率的に分離する方法を提供することを課題とする。 【解決手段】表面をポリマーで被覆された粒子に2種以上の抽出剤を含浸させてなる含浸吸着材を準備する含浸吸着材の準備工程、特定の金属元素を含む酸性溶液を前記含浸吸着材に接触させ、前記金属元素を前記含浸吸着材に吸着させる吸着工程、を含む、酸性溶液中から特定の金属元素を選択的に分離する方法。
