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Oral presentation

Current issues in radiation protection in Nuclear Fuel Cycle Engineering Laboratories; Next personal dosimeter and eye lens dosimetry

Uchida, Masahiro; Maeda, Tsuyoshi; Takimoto, Misaki; Takada, Chie; Tsujimura, Norio

no journal, , 

no abstracts in English

Oral presentation

Development of lightweight portable air monitor for emergencies

Tamura, Ken; Takahashi, Akina

no journal, , 

no abstracts in English

Oral presentation

Examination of a new decontamination method for contamination on skin and clothes due to radioactive air pollution

Honda, Fumiya; Isozaki, Kohei; Nabatame, Satoru

no journal, , 

no abstracts in English

Oral presentation

Development of a dust monitor detector reducing radon progeny impact using ZnS (Ag) scintillator, 2; Field test

Sasaki, Kazuki; Okuyama, Shun; Sagawa, Naoki; Hosomi, Kenji; Takada, Chie

no journal, , 

no abstracts in English

Oral presentation

Development of elemental technologies for "in-situ" alpha dust monitors for fuel debris retrieval and decommissioning

Tsubota, Yoichi; Yoshida, Masato; Honda, Fumiya; Tokonami, Shinji*; Nakagawa, Takahiro; Kawasaki, Takashi

no journal, , 

In order to measure the airborne concentration in air in real time, a dust monitor to measure directly the alpha-particle concentration in a flat-type flow path was developed and its performance was evaluated. The performance of the prototype dust monitor was evaluated in a high-humidity environment, and its counting rate was more than ten times higher than that of a conventional dust monitor.

Oral presentation

Development of analytical method for selenium-79 and iodine-129 in sample from reprocessing process by inductively coupled plasma mass spectrometry with collision reaction cell technique, 2

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.

Oral presentation

Acquisition and analysis of alpha-radioactivity data for glove box dismantling

Yoshida, Masato; Kawasaki, Kohei; Aita, Takahiro; Tsubota, Yoichi; Kikuchi, Ryo*; Honda, Fumiya

no journal, , 

no abstracts in English

Oral presentation

Investigation of method for stabilization of contaminated cadmium

Taniguchi, Takumi; Osugi, Takeshi; Sone, Tomoyuki; Kobayashi, Kentaro

no journal, , 

no abstracts in English

Oral presentation

Understanding the elution adsorption behavior of Eu in the column using the resonant neutron imaging method

Sato, Daisuke; Miyazaki, Yasunori; Watanabe, So; Nakamura, Masahiro; Kai, Tetsuya; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Preliminary study of the impact of changing thermal neutron scattering law data on the neutronic calculation for graphite cores

Okita, Shoichiro

no journal, , 

Neutronic calculations are performed for VHTRC core with JENDL-4.0 and the thermal neutron scattering law for graphite in ENDF/B-VIII, and the effective multiplication factor is compared with the experimental data. The calculation accuracy is improved by using the thermal neutron scattering law for graphite in ENDF/B-VIII compared with the previous results based on JENDL-4.0.

Oral presentation

Image analysis on ceramography of MOX fuel pellets by machine learning

Hirooka, Shun; Okumura, Kazuyuki; Makino, Takayoshi

no journal, , 

no abstracts in English

Oral presentation

Evaluation of ultraviolet on fire-retardant sheet for glove box panels

Kawasaki, Kohei

no journal, , 

no abstracts in English

Oral presentation

Measurements of neutron total and capture cross-sections of $$^{181}$$Ta

Endo, Shunsuke; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Rovira Leveroni, G.

no journal, , 

no abstracts in English

Oral presentation

Development of dry suction decontamination method for alpha-activity

Asakawa, Jun; Ono, Yosuke; Shibanuma, Tomohiro; Aita, Takahiro; Nagai, Yuya

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Manufacturing miniature beam window for accelerator driven system by cutting T91 steel

Watanabe, Nao; Sugawara, Takanori; Okubo, Nariaki; Nishihara, Kenji

no journal, , 

no abstracts in English

Oral presentation

Evaluation of an ultra-thin plastic scintillator to detect alpha and betaparticle contamination

Morishita, Yuki; Hoshi, Katsuya; Torii, Tatsuo*

no journal, , 

no abstracts in English

Oral presentation

Development of a Cs getter contained coated fuel particle layer for high temperature gas cooled reactor

Sasaki, Koei

no journal, , 

We are developing a fuel coating material with a Cs capture function in anticipation of reducing the exposure dose of HTGR plants, improving safety in the event of a primary reactor accident, making the plant more compact and reducing construction costs due to the reduction of shielding wall thickness. Bi and Sb were selected as Cs getter materials. Their simulated Cs trap compounds were formed in the carbon structure and high temperature stability at 1500$$^{circ}$$C was evaluated. Although Bi was precipitated in carbon, the formation of Cs compounds could not be seen. Sb formed a Cs compound (Cs$$_{3}$$Sb, etc.) in carbon structure and showed stability at 1500$$^{circ}$$C. Therefore, it was found that Sb has a Cs trap function.

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