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Journal Articles

Study on the behavior of radiolytically produced hydrogen in a high-level liquid waste tank of a reprocessing plant; Comparison between actual and simulated solutions

Kinuhata, Hiroshi*; Yamamoto, Masahiko; Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kodama, Takashi*; Tamauchi, Yoshikazu*; Shibata, Yuki*; Anzai, Kiyoshi*; Matsuoka, Shingo*

Nuclear Technology, 192(2), p.155 - 159, 2015/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Experiments using a small-scale apparatus with 30 ml actual high-level liquid waste from the Tokai Reprocessing Plant were carried out to show that the hydrogen concentration in the gas phase reaches a steady-state value of much less than 4% (lower explosive limit) in the absence of sweeping-air. The H$$_{2}$$ concentration reached a steady-state value as was expected and it was compared with a value predicted from an equation with parameters which had been obtained using the simulated solution. Satisfactory agreement showed that the Pd-ion catalytic H$$_{2}$$ consumption reaction previously found in the simulated solution proceeded equally well in the actual solution.

Oral presentation

Study on release and transport of aerial radioactive materials in reprocessing plant, 7; Hot test

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 300$$^{circ}$$C 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.

Oral presentation

Study on release and transport of aerial radioactive materials in reprocessing plant, 8; Cold large scale test

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$$_{4}$$ which is chemical form of Ru with volatility was acquired. As the results, it was found that RuO$$_{4}$$ 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.

Oral presentation

Measurement of radiolytically generated hydrogen from HALW and analysis of the inhibitory effect on hydrogen release, 1; Measurement of hydrogen concentration and its evaluation

Yamamoto, Masahiko; Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kinuhata, Hiroshi*; Tamauchi, Yoshikazu*; Shibata, Yuki*; Kodama, Takashi*; Matsuoka, Shingo*

no journal, , 

no abstracts in English

Oral presentation

Measurement of radiolytically generated hydrogen from HALW and analysis of the inhibitory effect on hydrogen release, 2; Comparison of measured hydrogen concentration and its estimate

Kinuhata, Hiroshi*; Tamauchi, Yoshikazu*; Shibata, Yuki*; Kodama, Takashi*; Matsuoka, Shingo*; Yamamoto, Masahiko; Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi

no journal, , 

no abstracts in English

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