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O
with electrochemical Li
intercalationMurase, Satoshi*; Yoshikawa, Yumi*; Fujiwara, Kosuke*; Fukada, Yukimasa*; Teranishi, Takashi*; Kano, Jun*; Fujii, Tatsuo*; Inada, Yasuhiro*; Katayama, Misaki*; Yoshii, Kenji; et al.
Journal of Physics and Chemistry of Solids, 162, p.110468_1 - 110468_6, 2022/03
Times Cited Count：0 Percentile：0.00(Chemistry, Multidisciplinary)We report a trial of the valence control for mixed valence iron triangular oxide YbFeO in order to develop an effective technique to control the frustration of charges in strongly correlated electron systems. The electro-chemical doping of Li into YbFeO was examined on the cell type sample similar to the Li-ion secondary battery cell. Systematic change of the lattice constant, Fe-Fe and Fe-Yb distance were observed with Li doping. Maximum value of the doping was over 300 mAh/g. An EXAFS experiment indicated that Li positioned between Yb octahedron layer (U-layer) and Fe-bipyramidal layer (W-layer). However, detailed change of iron valence state of YbFeO was not clearly observed because of the superimpose of the signal from iron metal nano particles in XANES observation. The results indicate that the electrochemical method might be one of the potential technique to control the frustration of charges in YbFeO.
Aoya, Juri; Miyata, Katsuhiko*; Terakado, Akihito*; Otsuzumi, Yoji*; Kurosawa, Daiki*; Sunaba, Takanobu*; Oyama, Yuto*; Inada, Satoshi
Nihon Hozen Gakkai Dai-17-Kai Gakujutsu Koenkai Yoshishu, p.507 - 512, 2021/07
The high level radioactive liquid waste is analyzed for the vitrification process control and the vitrified waste quality in the hot cell of Tokai Vitrification Facility, Tokai Reprocessing Plant. There are 8 Master-slave manipulators, 7 lighting equipment, an electronic balance, and an inductively coupled plasma-optical emission spectrometer used for remote operation, securing visibility, total oxide analysis, and elemental analysis in the analytical hot cell. These equipment and analytical apparatus must be secured with the integrity all the time because the vitrification process cannot be proceeded without analysis of the high level radioactive liquid waste. We constructed the self-remote-maintenance technologies of these equipment and analytical apparatus which reduce the risks of radioactive contamination, radiation exposure, and injury of an operator and also were optimized with respect to a labor, time, and cost, based on the operation of approximately 20 years.
Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko; Mori, Eito*
Nihon Hozen Gakkai Dai-16-Kai Gakujutsu Koenkai Yoshishu, p.221 - 224, 2019/07
Test equipment, containers, and analytical wastes, generated by experiments using spent fuel pieces in hot cell of Operation Testing Laboratory and by analysis of highly active liquid wastes in hot analytical cell line of Tokai Reprocessing Plant, are treated as highly radioactive solid wastes. These wastes are stored in specific shielded containers called waste cask and then transport to the storage facility. The treatment of these highly radioactive solid wastes have been carried out for 40 years with upgrading waste taking out system and transportation device. As a results, automation of several procedures have been achieved utilizing conventional equipment, and work efficiency and safety have been improved.
Goto, Yuichi; Yamamoto, Masahiko; Kuno, Takehiko; Inada, Satoshi
Nihon Hozen Gakkai Dai-15-Kai Gakujutsu Koenkai Yoshishu, p.489 - 492, 2018/07
Radioactive liquid waste from the Tokai Reprocessing Facility Analytical Laboratory is temporarily stored in intermediate waste storage tank by using receiving valves. Then, the liquid waste is transferred to liquid treatment facility by using liquid feed valves. The deterioration of the gasket part of these valves (leakage of waste liquid) was confirmed in 2004. Since then, the material of gaskets was changed from polyethylene to Teflon. In 2016, the gaskets were replaced by periodical update. Therefore, physical properties of used gaskets were investigated, and the relevance between radioactive level and degradation degree was evaluated.
Horigome, Kazushi; Taguchi, Shigeo; Nishida, Naoki; Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko
Nihon Hozen Gakkai Dai-14-Kai Gakujutsu Koenkai Yoshishu, p.381 - 384, 2017/08
no abstracts in English
Suzuki, Yoshimasa; Tanaka, Naoki; Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko
Nihon Hozen Gakkai Dai-14-Kai Gakujutsu Koenkai Yoshishu, p.385 - 389, 2017/08
Greenhouse is used in order to prevent diffusion of radioactive materials on the maintenance of machineries and decomposition of the analytical equipment such as glove box in Tokai Reprocessing Plant (TRP). The specifications of the greenhouse change depending on a risk of the radiation exposure, operation and environment. Design and application of original greenhouses in the analytical laboratory of TRP is summarized.
2016.10Horigome, Kazushi; Taguchi, Shigeo; Ishibashi, Atsushi; Inada, Satoshi; Kuno, Takehiko; Surugaya, Naoki
JAEA-Technology 2017-008, 14 Pages, 2017/05
JAEA-Technology-2017-008.pdf:1.15MB
The plutonium solution had been converted into MOX powder to mitigate the potential hazards of storage plutonium solution such as hydrogen generation at the Plutonium Conversion Development Facility. The plutonium conversion operations had been started in April, 2014, and had been finished in July, 2016. With respect to the samples taken from the conversion process, about 2,200 items of plutonium/uranium solutions and MOX powders had been analyzed for the operation control in the related analytical laboratories at the Tokai Reprocessing Plant. This paper describes the reports on analytical activities and related maintenance works in the analytical laboratories conducted from December, 2015 to October, 2016.
2015.12Horigome, Kazushi; Suzuki, Hisanori; Suzuki, Yoshimasa; Ishibashi, Atsushi; Taguchi, Shigeo; Inada, Satoshi; Kuno, Takehiko; Surugaya, Naoki
JAEA-Technology 2016-026, 21 Pages, 2016/12
JAEA-Technology-2016-026.pdf:1.14MB
In order to mitigate potential hazards of storage plutonium in solution such as hydrogen generation, conversion of plutonium solution into MOX powder has been carried out since 2014 in the Plutonium Conversion Development Facility. With respect to the samples taken from the conversion process, about 3500 items of plutonium/uranium solutions and MOX powders have been analyzed for the operation control in the related analytical laboratories at the Tokai Reprocessing Plant. This paper describes the reports on analytical activities and related maintenance works in the analytical laboratories conducted from April 2014 to December 2015.
Nishihara, Kenji; Yamagishi, Isao; Yasuda, Kenichiro; Ishimori, Kenichiro; Tanaka, Kiwamu; Kuno, Takehiko; Inada, Satoshi; Goto, Yuichi
Journal of Nuclear Science and Technology, 52(3), p.301 - 307, 2015/03
Times Cited Count：17 Percentile：80.66(Nuclear Science & Technology)After the severe accident at the Fukushima-1 nuclear power plant, large amounts of contaminated stagnant water have accumulated in turbine buildings and their surroundings. This rapid communication reports calculation of the radionuclide inventory in the core, collection of measured inventory in the stagnant water, and estimation of radionuclide release ratios from the core to the stagnant water. This evaluation is based on data obtained before June 3, 2011. The release ratios of tritium, iodine, and cesium were several tens of percent, whereas those of strontium and barium were smaller by one or two orders of magnitude. The release ratios in the Fukushima accident were equivalent to those in the TMI-2 accident.
Nishida, Naoki; Suwa, Toshio; Tanaka, Naoki; Inada, Satoshi; Kuno, Takehiko
Nihon Hozen Gakkai Dai-11-Kai Gakujutsu Koenkai Yoshishu, p.121 - 126, 2014/07
Corroded pore was found at stainless pipe for liquid waste solution from the analytical laboratory. Part of the pipe was cut for preparing samples to investigate the cause of the corrosion. The same size of stainless pipe was welded to recover it, under the strict radiation control. The restoration work was done inside of the vinyl house, as it is called "greenhouse", which was the small room completely separated by vinyl sheet. All the works, cutting, decontamination, digging groove and welding with back seal gas, were done inside of the greenhouse. We report the work method for recovery of corroded pipe containing radioactive materials
Nishihara, Kenji; Yamagishi, Isao; Yasuda, Kenichiro; Ishimori, Kenichiro; Tanaka, Kiwamu; Kuno, Takehiko; Inada, Satoshi; Goto, Yuichi
Nihon Genshiryoku Gakkai Wabun Rombunshi, 11(1), p.13 - 19, 2012/03
After the severe accident in the Fukushima-1 Nuclear Power Plant, large amount of contaminated stagnant water has been produced in turbine buildings and those surroundings. This rapid communication reports calculation of radionuclide inventory in the core, collection of measured inventory in the stagnant water, and estimation of radionuclide release ratios from the core to the stagnant water. The present evaluation is based on data obtained before June 3, 2011.
Suzuki, Masatoshi; Hazawa, Tomoya; Ishizaki, Yoichi*; Obara, Michio*; Inada, Katsutoshi*; Yonekawa, Mitsunori*; Wakita, Hiroshi*
JAERI-Tech 2004-060, 153 Pages, 2004/09
JAERI-Tech-2004-060.pdf:9.78MB
The cold neutron source (CNS) at JRR-3 was constructed for the purpose of improving the utilization performance of the reactor along the lines of upgrade program. There are two methods for extracting cold neutrons from a reactor, one is to filter a small fraction of cold neutrons in the Maxwellian spectrum of reactor neutrons while the other is to increase the fraction of cold neutron by inserting a cryogenic moderator. The latter is adopted as CNS facilities at almost all cases, and liquid hydrogen and its cooling system are equipped with a cold neutron source at many neutron facilities just like JRR-3. Cold neutrons generated in a cold source are extracted through a neutron guide tube, and are utilized for the purpose of neutron beam experiments such as neutron scattering which study the structures of atoms and molecules in the materials and life science fields. This report summarizes the operation data and the main technical issues which were recorded in the whole operation period from commencement date in 1989 to March 2004.
Saegusa, Yu; Kodaka, Noriyasu; Yamamoto, Masahiko; Horigome, Kazushi; Inada, Satoshi; Kuno, Takehiko
no journal, ,
Determination of iodine-129, in sample of reprocessing process has high priority to evaluate the environmental impact at treatment and disposal of radioactive solid wastes. In this study, we have been developed analytical method for iodine-129 by ICP-MS with collision reaction cell technique. Oxygen gas has been introduced into the collision reaction cell and isobaric ion, xenon-129, has been eliminated. In this presentation, optimized oxygen gas flow rate, analytical performance, and the measurement results of iodine-129 in the iodine adsorption filter collected from the liquid waste treatment facility in Tokai Reprocessing Plant are reported.
Saegusa, Yu; Yamamoto, Masahiko; Inada, Satoshi; Kuno, Takehiko
no journal, ,
Selenium-79 is a long half-life nuclide and emits low energy beta ray. Although it is difficult to analyze by radioactivity method, selenium-79 has high analytical needs for dose assessment due to the high occupancy rate of public exposure in the geological disposal of vitrified solids accompanying reprocessing of spent fuel. Selenium-79 can be measured by inductively coupled plasma mass spectrometry, however, accurate analysis is difficult due to the isobaric interference. In this study, we investigated analytical method for selenium-79 by inductively coupled plasma mass spectrometry with collision reaction cell technique. Selenium-79 can be measured after reaction with oxygen gas the cell and shift higher mass number. We will report the basic experiment results to measure selenium by collision reaction cell typed ICP-MS in this presentation.
Saegusa, Yu; Kodaka, Noriyasu; Yamamoto, Masahiko; Horigome, Kazushi; Inada, Satoshi; Kuno, Takehiko
no journal, ,
Iodine-129 (
I), which is a long-lived radionuclide, has high analytical needs for trace concentrations in gaseous and liquid radioactive waste to evaluate the environmental impact of treatment and disposal. However, conventional analytical methods such as gamma ray spectrometry, liquid scintillation counter, and inductively coupled plasma mass spectrometry (ICP-MS) are difficult to apply due to measurement sensitivity and isobaric interference. In this study, we have been developed analytical method for I by ICP-MS with collision reaction cell technique. Reaction gas has been introduced into the collision reaction cell and isobaric ion has been eliminated. In this presentation, the measurement results of I in the iodine adsorption filter collected from the liquid waste treatment facility of Tokai Reprocessing Plant is reported.
Saegusa, Yu; Yamamoto, Masahiko; Inada, Satoshi; Kuno, Takehiko
no journal, ,
Selenium-79 in highly active liquid waste (HAW) is important nuclides due to abundance and dose evaluation in regards to treatment and disposal of vitrified glass. Iodine-129 shifts to shearing and dissolver off-gas so it is not included in HAW. However there are few analysis report of iodine in HAW. These are difficult to be analyzed by radioactivity method due to a long half-life nuclide and emits low energy beta ray. Accurate analysis by inductively coupled plasma mass spectrometry is difficult due to the isobaric interference. In this study, we investigated analytical method for selenium-79 and iodine-129 by inductively coupled plasma mass spectrometry with collision reaction cell technique. Reaction gas can be introduced into the cell and isobaric ion can be eliminated. We will report the fundamental experiment results to determine selenium-79 and iodine-129 by collision reaction cell typed ICP-MS in this presentation.
Aoya, Juri; Kono, Soma; Yamamoto, Masahiko; Inada, Satoshi; Kuno, Takehiko
no journal, ,
Vitrification of high active liquid waste (HALW) is a top priority toward the decommissioning of Tokai Reprocessing Plant. Concentration of Sodium (Na) in HALW is required to be analyzed accurately and quickly for the vitrification process control, because it affects viscosity of molten glass and element leaching rate from the vitrified waste. An inductively coupled plasma optical emission spectrometer (ICP-OES), which is modified for remote operation by manipulator in the hot cell, is used for determination of Na in HALW. However, the trouble of the ICP-OES generally requires long recovery time and causes possibility of the vitrification process delay. Therefore, for alternative determination method to prevent the vitrification process delay, Na determination method in HALW using Na-ion selective electrode, which measures electromotive force generated in accordance with ion concentration in solution sample is developed. In this study, influences by hydrogen ion (H) and the other coexistent elements on analytical performance, and measurement results of Na in HALW by the ion selective electrode are reported.
Saegusa, Yu; Yamamoto, Masahiko; Inada, Satoshi; Kuno, Takehiko
no journal, ,
Determination of iodine-129 in sample from reprocessing process has high priority to evaluate the environmental impact at treatment and disposal of radioactive wastes. In this study, we have been developed analytical method for iodine-129 by ICP-MS with collision reaction cell technique. Oxygen gas has been introduced into the collision reaction cell and isobaric ion has been eliminated. In this presentation, measurement target is low level radioactive liquid waste (LLW). Effect of coexisting element in sample and the quantitative results of iodine-129 in the LLW in Tokai Reprocessing Plant are reported.
Masui, Kenji; Suzuki, Yasaka*; Kitao, Takahiko; Inada, Satoshi; Yamada, Keiji; Watahiki, Masaru
no journal, ,
no abstracts in English
Masui, Kenji; Kitao, Takahiko; Inada, Satoshi; Yamada, Keiji; Watahiki, Masaru
no journal, ,
no abstracts in English
