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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

Detailed analysis of individual uranium particles in environmental sample by SIMS and pre-screening measurement introduced into the analysis procedure

Tomita, Ryohei; Esaka, Fumitaka; Miyamoto, Yutaka

no journal, , 

In the previous study, we developed a combination method of individual uranium particle manipulation in scanning electron microscope (SEM) and secondary ion mass spectrometry (SIMS) for removing the interferences from other elements in other particles. Since the particles were selected randomly and manipulated, it caused the problem not to cover the range of $$^{235}$$U/$$^{238}$$U isotope ratio in the sample. In this study, we introduced pre-screening measurement into the procedure of analyzing uranium isotope ratios in individual particles by SIMS to cover the range of $$^{235}$$U/$$^{238}$$U in the sample.

Oral presentation

Application of the rapid analytical method for $$^{90}$$Sr to environmental samples with online solid phase extraction/ICP-MS

Hagiwara, Hiroki; Yanagisawa, Kayo*; Kuwata, Haruka*; Tanabe, Tsutomu; Uezu, Yasuhiro

no journal, , 

no abstracts in English

Oral presentation

Urea-substituted ionic liquid for the extraction and separation of Pd(II) and Pt(IV)

Ueda, Yuki; Sugita, Tsuyoshi; Okamura, Hiroyuki; Naganawa, Hirochika; Shimojo, Kojiro

no journal, , 

The separation and recovery of PGM is carried out by a hydrometallurgy process mainly based on a solvent extraction method. In recent years, development of alternative solvents for such volatile organic solvents has been advanced. Ionic liquids (IL) has attracted substantial interest in many fields as a green alternative solvent due to their non-volatile, non-flammable, and thermally stable properties. Task-specific ionic liquids (TSIL) that functionalized by incorporating ligating group can give the extraction ability for metal ions. Many extraction systems using IL and TSIL aimed at separating PGM have been reported so far, however there is no extraction system that achieves individual separation of Pd and Pt by one type of TSIL. In this study, imidazolium bis(trifluoromethanesulfonyl) imide type TSIL incorporating a urea group was synthesized and its extraction ability for Pd and Pt was evaluated from a viewpoint the individual separation of Pd and Pt.

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