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Proceedings of the 22nd International Workshop on the Ceramic Breeder Blanket Interactions 6−8th October 2025 Kyoto University Uji campus, Japan Keisuke Mukai (ed.) National Institute for Fusion Science DOI: 10.5281/zenodo.17685909
https://doi.org/10.5281/zenodo.17685909 1 Contents Introduction ................................................................................................................................... 2 List of participants .......................................................................................................... 4 Photo .............................................................................................................................. 6 Program .......................................................................................................................... 8 Presentations on 6 th Oct. 2025 ..................................................................................... 16 Presentations on 7 th Oct. 2025 ................................................................................... 132 Presentations on 8 th Oct. 2025 ................................................................................... 233 Acknowledgement ...................................................................................................... 293 Workshop website: https://indico.nifs.ac.jp/e/CBBI22 DOI: 10.5281/zenodo.17685909 Published: November 24, 2025
https://doi.org/10.5281/zenodo.17685909 2 Introduction The 22 nd International Workshop on the Ceramic Breeder Blanket Interactions (CBBI-22) was held from 6th to 8th October 2025 at Obaku plaza at Kyoto University in Japan under the auspices of the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and in conjunction with the International Conference on Fusion Materials (ICFRM-22) held in Shizuoka, Japan. The CBBI-22 was held jointly with the 17th International Workshop on Beryllium Technology (BeWS-17), and the joint sessions took place. The workshop provided a forum for the researchers, engineers and technologists, involved in the development of the fusion ceramic breeding blanket concepts for ITER/DEMO/FPP, to exchange the latest progress in the design, fabrication, modeling, materials, isotope separation, and tritium breeding/extraction. Group photo after the CBBI/BeWS joint session on 6 th October 2025
https://doi.org/10.5281/zenodo.17685909 3 Program Advisory Board M. Abdou (UCLA) M-Y. Ahn (KFE) L. V. Boccaccini (KIT) P. Chaudhuri (IPR) X. Chen (CAEP) K. Feng (SWIP) A. Ibarra(CIEMAT & IFMIF-DONES España) Y. Kawamura (QST) R. Knitter (KIT) T. Terai (IAE) Local organization Keisuke Mukai (Workshop Chair): National Institute for Fusion Science Jae-Hwan Kim: National Institutes for Quantum Science and Technology Juro Yagi: Kyoto University Takumi Chikada: Shizuoka University Editor Keisuke Mukai (National Institute for Fusion Science)
https://doi.org/10.5281/zenodo.17685909 4 List of participants No. Name Affiliation 1 Arturs Zarins University of Latvia, Faculty of Science and Technology, Instute of Chemical Physics 2 Asset Shaimerdenov The Instute of Nuclear Physics 3 Axel Dr. Klix Karlsruhe Instute of Technology 4 Chase Taylor Idaho Naonal Laboratory 5 Daigo Kanamori The Graduate University for Advanced Studies 6 Daniel Wilkinson University of Oxford, Materials Department 7 Dario Passafiume KIT, Instute for Applied Materials (IAM) 8 Dirk Radloff Karlsruhe Instute of Technology (KIT) 9 Donggyu Lee Seoul Naonal University 10 Harsh Patel Instute for plasma research, India 11 Hazel Gardner UKAEA 12 Hiroyasu Tanigawa Naonal Instutes for Quantum Science and Technology 13 Hitoshi Kuma Idemitsu Kosan Co., Ltd. 14 Inesh Kenzhina Satbayev University 15 Jaehwan Kim Naonal Instutes for Quantum Science and Technology 16 Julia Leys Karlsruhe Instute of Technology 17 Kazunari MEGURO Mitsui Mining & Smelng Co.,Ltd. 18 Kazuya Sasaki Hirosaki University 19 Keisuke Mukai Naonal Instute for Fusion Science 20 Kenji Morita Naonal Instutes for Quantum Science and Technology, Rokkasho Instute for Fusion Energy 21 Lee Auco UK Industrial Fusion Soluons Ltd (STEP) 22 Long Wang No.5 Huangjing Road Baijia County Shuangliu Chengdu, Sichuan 23 Magzhan Aitkulov Instute of Nuclear Physics 24 Marta Dias Instuto de Plasmas e Fusão Nuclear, Instuto Superior Técnico, Universidade de Lisboa 25 Maulik Panchal Instute for plasma research, India 26 Michael Moorehead Idaho Naonal Laboratory 27 Milan Zmitko Fusion for Energy (F4E)
https://doi.org/10.5281/zenodo.17685909 5 28 Mu-Young Ahn Korea Instute of Fusion Energy 29 Oliver Leys Karlsruhe Instute of Technology 30 Pedr Charlesworth University of Oxford 31 Qilai Zhou Wuhan University of Technology 32 Regina Knier Karlsruhe Instute of Technology 33 Roman Afanasenko Karlsruhe Instute of Technology 34 ruijie zhang Department of Nuclear Engineering, Seoul Naonal University, Seoul 35 Saulet Askerbekov Instute of Nuclear Physics 36 Shumpei Iwasaki Hirosaki university 37 Shurui Shang Instute of Plasma Physics, HFIPS, Chinese Academy of Sciences, Hefei, China 38 Takayuki Terai Instute of Applied Energy 39 Xiao-Ying Yu Oak Ridge Naonal Laboratory 40 Xiaoyong Wang Southwestern Instute of Physics 41 Xinghua Wu Southwestern Instute of Physics 42 Yi-Hyun PARK Korea Instute of Fusion Energy 43 Yonghee Lee Korea Instute of Fusion Energy 44 Young Ah Park Korea Instute of Fusion Energy 45 Yuriy Ponkratov Satbayev Kazakh Naonal Research Technical University 46 Zhanar Bugybay The Instute of Nuclear Physics Number of participants at CBBI-22 from each country/region
https://doi.org/10.5281/zenodo.17685909 6 Photo CBBI/BeWS joint session on 6 th October 2025 Tritium transport session on 6 th October 2025
https://doi.org/10.5281/zenodo.17685909 7 Technical tour at Heliotron-J on 8 th October 2025 Group photo after the technical tour at Heliotron-J on 8 th October 2025
https://doi.org/10.5281/zenodo.17685909 8 Program
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https://doi.org/10.5281/zenodo.17685909 16 Presentations on 6 th Oct. 2025
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https://doi.org/10.5281/zenodo.17685909 88 A new perspective on hydrogen isotope permeation behavior of LiAlO 2 layer Long Wang, Fantao Meng, Zhihao Hong, Baoping Gong, Fengchao Zhao, Qixiang Cao Southwestern Institute of Physics, Chengdu 610225, P.R. China Formation of a LiAlO2 layer is inevitable once solid-state reaction occurred between Al2O3 tritium permeation barrier and lithium ceramics. In this study, effect of LiAlO2 layer on the hydrogen isotope permeation behavior was first investigated. LiAlO2 coating were prepared on CLF-1 steel substrates by high-temperature lithium infiltration. The formation process and hydrogen isotope permeation behavior of LiAlO2 coatings were systematically analyzed through experimental and simulation approaches. The results demonstrate that LiAlO2 exhibits inward growth over time, forming a stable LiAlO2 -Al interface after 7 days. Deuterium permeation tests revealed that the LiAlO2 coating effectively resists deuterium permeation and diffusion. Notably, as the LiAlO2 coatings thickens, both the permeability and diffusion rates decrease progressively. Computational simulations further corroborated these findings, attributing the resistance to the low H₂ adsorption energy and high dissociation barrier of the LiAlO2 surface. Keywords: LiAlO2 coating, Gas-driven permeation, Hydrogen isotope behavior
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https://doi.org/10.5281/zenodo.17685909 97 Tritium Transfer Behavior from Neutron-Irradiated LiAlO 2 to Zirconium by Heating in a Sealed Quartz Tube Hiroki Isogawaa, Kazunari Katayamaa, Rin Ganahab, Hideaki Matsuurac aDepartment of Advanced Energy Engineering Science, Kyushu University, 6-1 Kasugakouen Kasuga-shi Fukuoka, 816-0811, Japan bSchool of Engineering, Kyushu University, 744 Motooka Nishi-ku Fukuoka-shi Fukuoka, 319-0395, Japan bcDepartment of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka Nishi-ku Fukuoka-shi Fukuoka, 319-0395, Japan To ensure sufficient tritium inventory for the start-up phase of D-T fusion reactors, we have proposed a method of tritium production by the ⁶Li(n, α)T reaction in high-temperature gas-cooled reactors (HTGR). A key challenge is minimizing tritium loss under high-temperature conditions. While Li₂TiO₃ and Li₄SiO₄ are promising materials for blankets in fusion reactors, LiAlO₂—known for its excellent chemical stability at high temperatures—has been selected as a primary candidate for tritium production in HTGRs. A potential solution involves encapsulating LiAlO₂ with zirconium (Zr) in an Al₂O₃ container, but the tritium behavior in such composite systems is not yet fully understood. In this study, we investigated tritium transfer behavior from LiAlO2 to Zr under heating conditions. LiAlO2 and Ni coated Zr were sealed in a quartz tube and irradiated by neutrons in the JRR-3 reactor. After irradiation, the following 3 experiments were conducted to evaluate the extent of tritium transfer from LiAlO2 to Zr. ・Run 1: LiAlO₂ powder + Ni-coated Zr spheres, heated to effectively 700 °C ・Run 2: LiAlO₂ pebble + Ni-coated Zr spheres, heated to 900 °C ・Run 3: LiAlO₂ powder + Ni-coated Zr spheres, heated to 1000 °C The sealed samples were pre-heated to the target temperature at 30 °C/min and held for 60 minutes. In an Ar-filled glovebox, Zr spheres and LiAlO₂ were separated, and then individually reheated to either 900 °C or 1000 °C at 5 °C/min. Tritium release rates over time were quantified using sequential water bubblers: tritiated water vapor (HTO) was collected in the first bubbler, and gaseous tritium (HT), after oxidation, in the second. The tritium retention ratios in LiAlO₂, Zr, and other components were as follows: ・Run 1: LiAlO₂ powder: Ni-coated Zr : others = 94.0 : 4.3 : 1.7 ・Run 2: LiAlO₂ pebble : Ni-coated Zr : others = 89.0 : 9.9 : 1.1 ・Run 3: LiAlO₂ powder : Ni-coated Zr : others = 95.0 : 4.7 : 0.3
https://doi.org/10.5281/zenodo.17685909 98 These results indicate that more than 90% of the tritium was retained within the LiAlO₂-Zr system after heating above 700 °C. The slightly lower retention in Run 2 may be attributed to the sintering of LiAlO₂ pebbles, which likely led to crystal grain growth and reduced tritium diffusivity. The "others" category represents tritium lost via permeation through the quartz tube during pre-heating and tritium released into the Ar atmosphere during the post-heating quartz breakage process. Keywords: Tritium release, LiAlO2, Zr, neutron irradiation
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https://doi.org/10.5281/zenodo.17685909 293 Acknowledgement The 22 nd International Workshop on the Ceramic Breeder Blanket Interactions (CBBI22) is co-organized and supported by the Joint Usage/Research Program on ZeroEmission Energy Research, Institute of Advanced Energy, Kyoto University (ZE2025D04). Prof. Shigeru Inagaki and Assistant Prof. Fumiyoshi Kin at Institute of Advanced Energy, Kyoto University are thanked for arranging and guiding the technical tour at Heliotron J.