Search Results - "Shirasu, Noriko"
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The solubility and diffusion coefficient of helium in uranium dioxide
Published in Journal of nuclear materials (01-12-2011)“…► The solubility and diffusivity of He in single-crystal UO 2 were determined. ► The determined He solubility lay within the scatter of the available data. ►…”
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2
Variation in the surface morphology of polycrystalline UO2 powder induced by helium precipitation
Published in Journal of Asian Ceramic Societies (01-09-2013)“…This report addresses the precipitation of helium in polycrystalline UO2, which deforms the morphology of the grains and their surfaces. The formation of…”
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3
Characterization of solidified melt among materials of UO2 fuel and B4C control blade
Published in Journal of nuclear science and technology (03-08-2014)“…To predict the fundamental phase relationships in the solidified core melt of the Fukushima Daiichi Nuclear Power Plant, solidified melt samples of the various…”
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Extraction Behavior of Metal Ions by TODGA, DOODA, MIDOA, and NTAamide Extractants from HNO3 to n-Dodecane
Published in Solvent extraction and ion exchange (01-07-2013)“…Four novel diamide and triamide extractants developed in our group, TODGA, DOODA, MIDOA, and NTAamide, were examined to see the extractability trends of up to…”
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5
A new method of measuring ruthenium activity in ruthenium-containing alloys by using thermogravimetric analysis
Published in Journal of nuclear science and technology (03-04-2022)“…A new method named thermogravimetric calibration curve method was developed in this study using thermogravimetric analysis to determine Ru activity (a Ru ) in…”
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Novel Extractant, NTAamide, and its Combination with TEDGA for Mutual Separation of Am/Cm/Ln
Published in Solvent extraction and ion exchange (23-02-2014)“…A novel extractant, N,N,N′,N′,N′′,N′′-hexaalkyl-nitrilotriacetamide (NTAamide), was developed for the extraction and separation of actinides (An) and…”
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7
Fundamental experiments on phase stabilities of Fe-B-C ternary systems
Published in Journal of nuclear science and technology (03-10-2015)“…To understanding the control blade degradation mechanism of a boiling-water reactor (BWR), a thermodynamic database for the fuel assembly materials is a useful…”
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8
Characterization of solidified melt among materials of UO 2 fuel and B 4 C control blade
Published in Journal of nuclear science and technology (03-08-2014)Get full text
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9
Extraction Behavior of Metal Ions by TODGA, DOODA, MIDOA, and NTAamide Extractants from HNO 3 to n -Dodecane
Published in Solvent extraction and ion exchange (01-07-2013)Get full text
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10
Variation in the surface morphology of polycrystalline UO 2 powder induced by helium precipitation
Published in Journal of Asian Ceramic Societies (01-09-2013)Get full text
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