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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
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 consumption reaction previously found in the simulated solution proceeded equally well in the actual solution.
Sekine, Keiji*; Fujita, Kunio*; Kodama, Takashi*; Tamauchi, Yoshikazu*; Uchiyama, Gunzo; Yoshida, Kazuo; Yamane, Yuichi; Ueda, Yoshinori*; Takanashi, Mitsuhiro*
no journal, ,
A study on the release and transport of aerial radioactive materials in reprocessing plants was started. The cooling system of high active liquid waste in reprocessing plants and the release and transport of aerial radioactive materials in reprocessing plants at loss of cooling events were surveyed.
Tomiyama, Masahiro; Yasuda, Takeshi; Tsutagi, Koichi; Yoshino, Yasuyuki; Shirato, Yoji; Nakamura, Yoshinobu; Kinuhata, Hiroshi*; Kodama, Takashi*; Nakano, Masanao*; Tamauchi, Yoshikazu*; et al.
no journal, ,
no abstracts in English
Kinuhata, Hiroshi*; Kodama, Takashi*; Nakano, Masanao*; Tamauchi, Yoshikazu*; Matsuoka, Shingo*; Tomiyama, Masahiro; Yasuda, Takeshi; Tsutagi, Koichi; Yoshino, Yasuyuki; Shirato, Yoji; et al.
no journal, ,
no abstracts in English
Yamamoto, Masahiko; Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kinuhata, Hiroshi*; Tamauchi, Yoshikazu*; Shibata, Yuki*; Kodama, Takashi*; Matsuoka, Shingo*
no journal, ,
no abstracts in English
Kinuhata, Hiroshi*; Tamauchi, Yoshikazu*; Shibata, Yuki*; Kodama, Takashi*; Matsuoka, Shingo*; Yamamoto, Masahiko; Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi
no journal, ,
no abstracts in English
in Reprocessing Solutions, 5; Experimental apparatus and its validation test for measuring radiolytic H production from aqueous plutonium nitrate solutionKumagai, Yuta; Oyama, Kanichi*; Sato, Tomonori; Ishijima, Yasuhiro; Taguchi, Mitsumasa*; Watanabe, Masayuki; Abe, Yuma; Nakano, Masanao*; Tamauchi, Yoshikazu*
no journal, ,
Radiolysis of water generates H gas. The radiolytic H production inevitably goes on when an aqueous solution contains radioactive nuclides such as plutonium nitrate solution in the nuclear fuel reprocessing. In order to obtain experimental data for the H safety assessment, we carried our measurements of H production from the aqueous plutonium nitrate solution at elevated temperatures. In this presentation, we will talk about experimental apparatus and results of a validation test of the apparatus using Co-60 gamma source.
in Reprocessing solutions, 6; Consideration on the temperature dependence of G value of H in plutonium nitrate solutionAbe, Yuma; Kumagai, Yuta; Hotoku, Shinobu; Inoue, Masao*; Suzuki, Sachiko*; Toigawa, Tomohiro; Watanabe, Masayuki; Nakano, Masanao*; Oyama, Kanichi*; Tamauchi, Yoshikazu*
no journal, ,
Hydrogen is generated from aqueous solutions containing radioactive materials through radiolysis of water. Because of the wide variety of solution properties treated in reprocessing plants and the difficulty of conducting experiments with radioactive materials, few studies have taken into account the properties of the solutions actually used. In particular, there are very few studies on the effects of agitation by bubbling, etc. and on temperature dependence. In this study, hydrogen generation was measured in Pu nitrate solution with and without agitation and at different temperatures, and G-values were calculated. Under the test conditions where the solution was agitated (bubbling agitation or boiling), the G-value increased by about 20 to 30% compared to that under static conditions at room temperature. Under the stirring condition, there was no clear trend of increase/decrease of G-values with increasing temperature. From these results, it is considered that the G-value of Pu nitrate solution increases with stirring and that there is no significant temperature dependence in the stirred condition. The reason for the observed temperature dependence of the hydrogen G-values in this study, which gives different from that of the nitric acid solution in the validation experiment, may be due to the difference in the composition and reaction behavior of the radicals produced by radiolysis between Co-60 gamma-rays and alpha-rays from Pu due to the difference in LET.
in Reprocessing Solutions, 7; Measurement of hydrogen generation test using high active liquid wasteHotoku, Shinobu; Fukaya, Hiroyuki; Kumagai, Yuta; Inoue, Masao*; Suzuki, Sachiko*; Ban, Yasutoshi; Kida, Takashi; Watanabe, Masayuki; Abe, Yuma*; Tamauchi, Yoshikazu*
no journal, ,
In order to evaluate the amount of hydrogen generated by radiolysis of water from the high active liquid waste in the reprocessing process, In this study a spent fuel solution was used and tests were conducted under the conditions of the solution temperature and the presence or absence of agitation and analyzed of the components in spent fuel solution. In this presentation, it is report on the outline of the test and the results obtained in the test.
in Reprocessing solutions, 8; Consideration on the temperature dependence and evaluation of the absorbed dose of G value of H in High active liquid wastes.Abe, Yuma*; Kumagai, Yuta; Toigawa, Tomohiro; Hotoku, Shinobu; Fukaya, Hiroyuki; Watanabe, Masayuki; Oyama, Kanichi*; Hasegawa, Satoshi*; Nakano, Masanao*; Tamauchi, Yoshikazu*
no journal, ,
We evaluated hydrogen production G-value in high-level liquid waste from the results of hydrogen production test at elevated temperatures and the absorbed dose of the solution calculated by using an ionizing radiation transport code. The temperature effect on the radiolytic hydrogen production was discussed based on the evaluated G-values.
