2001 Fiscal Year Final Research Report Summary
Development of Actinide Hydride Target for High Efficiency Rad-Waste Annihilation
| Project/Area Number |
12480136
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| Research Category |
Grant-in-Aid for Scientific Research (B)
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| Allocation Type | Single-year Grants |
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| Section | 一般 |
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| Research Field |
Nuclear engineering
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| Research Institution | The University of Tokyo |
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Principal Investigator |
YAMAWAKI Michio Graduate School of Engineering, The University of Tokyo, Professor, 大学院・工学系研究科, 教授 (30011076)
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| Co-Investigator(Kenkyū-buntansha) |
KONASHI Kenji Tohoku University, Oarai Branch, Institute for Materials Research, Associate Professor, 金属材料研究所, 助教授 (10250812)
ONO Futaba Graduate School of Engineering, The University of Tokyo, Research Associate, 大学院・工学系研究科, 助手 (00011198)
TERAI Takayuki Graduate School of Engineering, The University of Tokyo, Professor, 大学院・工学系研究科, 教授 (90175472)
ITAGAKI Noboru Nuclear Fuel Industry Co., BWR Fuel Engineering Department, Senior Researcher, BWR燃料事業部, 研究員
YAMAGUCHI Kenji Japan Atomic Energy Research Institute, Department of Materials Science, Senior Engineer, 物質科学研究部, 副主任研究員 (50210357)
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| Project Period (FY) |
2000 – 2001
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| Keywords | Rad-waste / Annihilation Treatment / Actinide / Hydride / U-Zr Alloy / U-Th-Zr Alloy / Thermophysical Properties / Thermal Analysis |
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| Research Abstract |
Thermophysical properties of ThZr_2H_x specimens prepared in this study have been measured by means of a differential scanning calorimeter (DSC) purchased in this project as well as a TG-DTA apparatus and a laser flash thermal diffusivity apparatus formerly procured. Thermal conductivity of ThZr_2H_x was evaluated by combining the measured thermal diffusivity and heat capacity data. The evaluated thermal conductivity revealed a unique feature change from electronic conduction dominating to lattice conduction dominating with the increase of hydrogen content x. Thermal conductivity of ThZr_2H_x has been confirmed to be two times better than that of UO_2. Based on the TG-DTA results, the occupancies of the hydrogen sites 96g and 32e were estimated to be in ratio of 2:1, which is maintained with the change of x. With regard to the compatibility investigation between hydride fuel and zircaloy cladding, an oxide layer of ZrO_2 3-4 μm thick was observed to form an effective barrier against hydrogen permeation.
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