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spp.Uyama, Yoshihide*; Oya, Hirotaka*; Amano, Yoshinori*; Kashimoto, Koichi*; Hatano, Shoji*; Nozawa, Shigeki; Yoshihara, Ryohei*; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2012-046, JAEA Takasaki Annual Report 2011, P. 102, 2013/01
Okubo, Tadatsune*; Tsukuda, Yoshiaki*; Kamimura, Katsuichiro*; Murai, Kenji*; Goto, Ken*; Doi, Soichi*; Senda, Yasuhide*; Kosaka, Yuji*; Kido, Toshiya*; Murata, Tamotsu*; et al.
Nihon Genshiryoku Gakkai-Shi, 43(9), p.906 - 915, 2001/09
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Toi, Kazuo*; Fukuda, Takeshi; Wakatani, Masahiro*; Ogawa, Yuichi*; Takizuka, Tomonori; Miura, Yukitoshi; Ide, Shunsuke; Takase, Yuichi*; Tobita, Kenji; Fukuyama, Atsushi*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 77(2), p.184 - 191, 2001/02
no abstracts in English
Uyama, Yoshihide*; Furukawa, Hiroaki*; Nishijima, Tomoko*; Amano, Yoshinori*; Kashimoto, Koichi*; Hase, Yoshihiro; Yoshihara, Ryohei; Nozawa, Shigeki; Narumi, Issei
no journal, ,
no abstracts in English
Tashiro, Shinsuke; Matsumoto, Tetsuya; Kataoka, Osamu; Amano, Yuki; Abe, Hitoshi; Yamane, Yuichi; Yoshida, Kazuo; Ishikawa, Jun; Uchiyama, Gunzo; Ueda, Yoshinori*; et al.
no journal, ,
Measurements on the release ratios of aerial radioactive materials from mocked fuel reprocessing liquid waste under its boiling to dryness process were performed using labo-scaled experiments. Test sample, dissolved 27 elements into nitric acid and arranged to 2M acidity, was heated up to 300 
C under the constant air ventilation. Steam, gaseous and airborne materials were collected or absorbed at the condenser, the air filter and the washing bottles. The accumulated release ratios of mocked FP elements from samples were determined using ICP-MS. From the accumulated release ratios determined from the condensed samples, the major release of Cs and Ru could be involved the release of mist and gaseous RuO
, respectively. Besides, accumulated release ratios of Ru was about 10 to 1000 times higher than Cs, differed from the literature using fuel reprocessing liquid waste. Its differences could be influenced the nitrous acid, which was reduced the generation of RuO.
Tashiro, Shinsuke; Matsumoto, Tetsuya; Kataoka, Osamu; Amano, Yuki; Abe, Hitoshi; Yamane, Yuichi; Yoshida, Kazuo; Ishikawa, Jun; Uchiyama, Gunzo; Ueda, Yoshinori*; et al.
no journal, ,
The release behavior of radioactive materials from high-level radioactive liquid wastes (HLW) from reprocessing plants under an accidents of boiling to dryness of HLW condition has been studied. The influences of FP concentration in the simulated HLW on the release ratio of FP from the waste were measured in the laboratory-scaled experiments using non-radioactive simulated HLW which was prepared by dissolving 27 FP elements into nitric acid and adjusted to 2 M acidity. The simulated HLW was heated up to 300C under the constant air ventilation condition. The accumulated release ratios of FP elements from samples were determined using ICP-MS analysis. It was found that the accumulated release ratio of Ru was decreased with the increase of the initial Ru concentration in the simulated HLW. However, those of Cs and Nd were not influenced by the initial concentrations of them.
Yamane, Yuichi; Amano, Yuki; Yanagida, Yoshinori; Kawasaki, Yasushi; Sato, Makoto; Hayasaka, Hiromi; Tashiro, Shinsuke; Abe, Hitoshi; Uchiyama, Gunzo; Ueda, Yoshinori*; et al.
no journal, ,
The release and transport characteristics of radioactive materials at a boiling accident of the high active liquid waste (HALW) in a reprocessing plant have been studied for improving experimental data of source terms of the boiling accident. This paper describes an experiment using a small test device having an electric furnace, in which 100 mL of the HALW was heated from room temperature to 300C and the amount of materials released during heating was measured. The amount of materials as a function of its initial concentration in the HALW is reported.
Abe, Hitoshi; Masaki, Tomoo; Watanabe, Koji; Suzuki, Shinya; Tashiro, Shinsuke; Amano, Yuki; Yamane, Yuichi; Yoshida, Kazuo; Uchiyama, Gunzo; Ueda, Yoshinori*; et al.
no journal, ,
The release and transport characteristics of radioactive materials under the boiling and desiccating accident of the high active liquid waste in a reprocessing plant have been studied. Ruthenium is one of the important nuclides for evaluating public dose from the volatile viewpoint. By using apparatus which can control the experimental condition of temperature and atmosphere composition in the gas phase, the transport characteristics data of RuO which is chemical form of Ru with volatility was acquired. As the results, it was found that RuO would transport in the gas phase without thermal decomposition and deposition onto the inner wall of glass under the experimental condition with nitric acid vapor.
