Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 26

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Remote maintenance technologies of equipment and analyzing apparatus in hot cell of Tokai Vitrification Facility, Tokai Reprocessing Plant

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.

Journal Articles

Treatment technology of highly radioactive solid waste generated by experimental tests and sample analysis in reprocessing facilities

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.

Journal Articles

Physical property evaluation of valve seal material at analytical radioactive liquid waste storage tanks in reprocessing facility

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.

Journal Articles

Replacement of the glove port equipped with glove box in Nuclear Fuel Reprocessing Facility

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

Journal Articles

Design and application of greenhouse on the maintenance of analytical machineries in Tokai Reprocessing Plant

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.

JAEA Reports

Report on analytical activities in potentially hazardous materials mitigation measures at the Plutonium Conversion Development Facility; 2015.12 $$sim$$ 2016.10

Horigome, 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.

JAEA Reports

Report on analytical activities in potentially hazardous materials mitigation measures at the Plutonium Conversion Development Facility; 2014.4 $$sim$$ 2015.12

Horigome, 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.

Journal Articles

Radionuclide release to stagnant water in the Fukushima-1 Nuclear Power Plant

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:15 Percentile:81.43(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.

Journal Articles

Restoration of the corrosion department of the reprocessing facilities analysis waste fluid plumbing

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

Journal Articles

Radionuclide release to stagnant water in Fukushima-1 Nuclear Power Plant

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.

JAEA Reports

Operation and management data for the JRR-3 CNS Facility

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.

Oral presentation

Simultaneous determination of U(IV) and U(VI) in uranium nitrate solutions by differential pulse voltammetry

Masui, Kenji; Kitao, Takahiko; Inada, Satoshi; Yamada, Keiji; Watahiki, Masaru

no journal, , 

no abstracts in English

Oral presentation

Simultaneous determination of U(IV) and U(VI) in nitrate solutions by differential pulse voltammetry

Masui, Kenji; Suzuki, Yasaka*; Kitao, Takahiko; Inada, Satoshi; Yamada, Keiji; Watahiki, Masaru

no journal, , 

no abstracts in English

Oral presentation

Development of the solid scintillator for the determination of trace amount of plutonium

Ogura, Hiroshi; Inada, Satoshi; Igarashi, Kazuto*; Yamada, Keiji; Watahiki, Masaru

no journal, , 

no abstracts in English

Oral presentation

Determination of plutonium by using microchip separation/alpha liquid scintillation counter

Yamamoto, Masahiko; Taguchi, Shigeo; Do, V. K.; Inada, Satoshi; Kuno, Takehiko

no journal, , 

Microchip is a glass plate that has a microchannel typically below 100 $$mu$$m. Various chemical process can be performed in flow by introducing sample solution through this microchannel. One of the application of microchip is solvent extraction. If microchip can be applied to Pu analysis, it is possible to reduce waste generation, radiation exposure of laboratory staff and simplify the analytical operation. In this study, we have developed an online alpha liquid scintillation measurement system coupled with microchip application to the separation field of analysis pretreatment. Quantitative analysis of plutonium has been performed by using the developed system. In the conference, we present these experimental results.

Oral presentation

Development of analytical method for metal elements in reprocessing solution by optical emission spectrometry based on liquid electrode plasma, 2; Determination of cesium and technetium in highly active liquid waste

Do, V. K.; Yamamoto, Masahiko; Taguchi, Shigeo; Inada, Satoshi; Takamura, Yuzuru*; Kuno, Takehiko

no journal, , 

A simple and rapid method for determination of Cs and Tc in highly radioactive liquid waste (HALW) using liquid electrode plasma (LEP) has been developed. Effects of pulsed voltage sequence and nitric acid concentration on emissions of these elements are investigated. The method is applied to the quantitative analysis of Cs and Tc in HALW samples at Tokai reprocessing plant.

Oral presentation

Development of analytical method for metal elements in reprocessing solution by optical emission spectrometry based on liquid electrode plasma, 1; Liquid electrode plasma optical emission spectra of reprocessing solution

Taguchi, Shigeo; Do, V. K.; Yamamoto, Masahiko; Inada, Satoshi; Takamura, Yuzuru*; Kuno, Takehiko

no journal, , 

Optical emission peaks of main FP such as Tc and Cs, and Fe were observed in spectra of simulated highly active liquid waste based on liquid electrode plasma. It was found that this optical emission spectrometry based on liquid electrode plasma could be applied to analysis for reprocessing solution.

Oral presentation

Analysis of iodine 129 in gaseous radioactive waste at Tokai Reprocessing Plant

Saegusa, Yu; Yamamoto, Masahiko; Nishida, Naoki; Taguchi, Shigeo; Watanabe, Nobuhisa; Inada, Satoshi; Kuno, Takehiko

no journal, , 

Iodine in gaseous radioactive waste at the reprocessing facility is collected on an activated charcoal filter. Iodine129 is measured by radioactive analysis using a Ge semiconductor detector. In this research, the correction method for the influence of self-absorption and iodine recovery is proposed. The influence of self-absorption is evaluated by determining the linear attenuation coefficient of activated charcoal filter. Iodine recovery on the activated charcoal filter is also evaluated by measuring $$gamma$$-ray intensity from both side of the filter.

Oral presentation

Development of analytical methods for metal elements in reprocessing solution by optical emission spectrometry based on liquid electrode plasma, 3; Determination of technetium in reprocessing process solution

Yamamoto, Masahiko; Do, V. K.; Taguchi, Shigeo; Inada, Satoshi; Takamura, Yuzuru*; Kuno, Takehiko

no journal, , 

In this research, we focused on liquid electrode plasma optical emission spectrometry(LEP-OES), which is effective method to minimize the analytical device, to determine technetium (Tc) in reprocessing solution. Measurement conditions such as applied voltage, output pulse sequence and nitric acid concentration were optimized. Consequently, measurement condition at voltage of 1000V, pulse width of 2ms, pulse interval of 8ms, pulse number of 50 and nitric acid concentration of 0.4M offers the high peak intensity with good reproducibility. Also, interference of coexisting elements in sample from reprocessing steam was investigated for Tc peak at 254.3nm, 261.0nm, 264.7nm. The spectral interference of iron was observed at Tc peak of 254.3nm and 261.0nm although no spectral interference were observed at 264.7nm peak. It was found that determination of Tc by LEP-OES can be possible using this peak.

Oral presentation

Development of analytical methods for metal elements in reprocessing solution by optical emission spectrometry based on liquid electrode plasma, 4; Determination of strontium in highly active liquid waste

Do, V. K.; Yamamoto, Masahiko; Taguchi, Shigeo; Inada, Satoshi; Takamura, Yuzuru*; Kuno, Takehiko

no journal, , 

An analytical technique for determination of elemental strontium in highly radioactive liquid waste (HALW) using liquid electrode plasma optical emission spectrometry (LEP-OES) has been developed. We use the LEP-OES instrument that is installed recently. Measurement condition including voltage and sample acidity is optimized. The method is validated using simulated HALW and comparing with inductively coupled plasma spectrometry (ICP-OES). The measurement of real HALW is being carried out.

26 (Records 1-20 displayed on this page)