Fabrication and characterization of Li3TaO4 ceramic pebbles by wet process |
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| Authors: | Deqiong Zhu Shuming Peng Xiaojun Chen Xiaoling Gao Tongzai Yang |
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| Affiliation: | 1. Breeding Functional Materials Development Group, Department of Blanket Systems Research, Rokkasho Fusion Institute, Sector of Fusion Research and Development, Japan Atomic Energy Agency, 2-166 Obuch, Omotedate, Rokkasho-mura, Kamikita-gun, Aomori 039-3212, Japan;2. Tritium Technology Group, Department of Blanket Systems Research, Rokkasho Fusion Institute, Sector of Fusion Research and Development, Japan Atomic Energy Agency, 2-4 Shirakata, Shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan;3. Blanket Technology Group, Department of Blanket Systems Research, Rokkasho Fusion Institute, Sector of Fusion Research and Development, Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193, Japan;4. BA Project Coordination Group, Department of Fusion Power Systems Research, Rokkasho Fusion Institute, Sector of Fusion Research and Development, Japan Atomic Energy Agency, 2-166 Obuch, Omotedate, Rokkasho-mura, Kamikita-gun, Aomori 039-3212, Japan;1. Karlsruhe Institute of Technology, IAM-WPT, 76021 Karlsruhe, Germany;2. Institute for Plasma Research, Bhat, Gandhinagar 382428, Gujarat, India;3. Southwestern Institute of Physics, Chengdu 610041, PR China;4. Japan Atomic Energy Agency, Rokkasho-mura, Aomori 039-3212, Japan;5. ITER Korea, National Fusion Research Institute, Yuseong-gu, Daejeon 305-333, Republic of Korea;1. College of Physical Science and Technology, Sichuan University, Chengdu 610064, China;2. Key Laboratory of Radiation Physics and Technology of Ministry of Education, Sichuan University, Chengdu 610064, China;3. Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Box 919-214, Mianyang 621900, China;4. School of Materials Science and Engineering, Xi’an University of Technology, Xi’an 710048, China;1. Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China;2. State Key Laboratory of Porous Metal Materials, Northwest Institute for Non-ferrous Metal Research, Xi’an, 710016, China;3. Shenzhen Institutes of Advanced Technology, Chinese Academy of Sciences, Shenzhen, 518055, PR China |
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| Abstract: | Lithium-containing ceramics have long been recognized as the tritium breeding materials in the fusion–fission or fusion reactor blanket. Li3TaO4 (lithium orthotantalate) pebbles, with high melting point (～1406 °C), good thermal stability, and high thermal conductivity, were fabricated by wet process (freeze–drying) as a new potential candidate of tritium breeder. The diameter of ceramic pebbles is 0.7–1.0 mm, density is over 90% (TD), pore diameter is 1.86 μm (a.v), grain size is 15 μm (a.v), crush load is up to 46.7 N (a.v). |
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