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22nd International Workshop on the Ceramic Breeder Blanket Interactions (CBBI-22)

Oct 6 – 8, 2025
Kyoto University Uji campus
Asia/Tokyo timezone

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Contribution List

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22. [BeWS] Modeling and experimental validation of irradiation defects in HCP materials
Pavel VLADIMIROV
10/6/25, 9:20 AM

Pavel VLADIMIROV
23. [CBBI] Current Plans for the HCCP TBM testing in ITER and Brief Overview of R&D Activities on the European Ceramic Breeder
Milan Zmitko
10/6/25, 9:50 AM

Milan Zmitko1, Italo Ricapito2, Regina Knitter3, Julia Leys3, Salvatore D’Amico4
1 Fusion for Energy (F4E), c/ Josep Pla 2, Barcelona, Spain
2 Fusion for Energy (F4E), Route de Vinon-sur-Verdon, 13115 St Paul lez Durance, France
3 Karlsruhe Institute of Technology (KIT), Institute for Applied Materials (IAM), Karlsruhe, Germany
4 EUROfusion - Programme Management Unit, Boltzmannstrasse 2,...
24. [CBBI] ORNL Status and Progress in Research on Ceramic Breeder Blanket Materials
Xiao-Ying Yu
10/6/25, 10:50 AM

Xiao-Ying Yu*, Yutai Katoh, Takaaki Koyanagi, German Samolyuk, Osetskiy, Yuri, and Weicheng Zhong
Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA

The fusion energy sciences program at the Oak Ridge National Laboratory (ORNL) contributes in a wide range of technical areas to support fusion reactor development. In particular, topics related to the fusion blanket and fuel cycle are...
25. [BeWS] Current R&Ds on advanced breeding functional materials for JA DEMO activities
Jaehwan KIM
10/6/25, 11:20 AM

Jaehwan KIM
26. [CBBI] Overview of Breeding Blanket Technology Development in Korea
Mu-Young Ahn
10/6/25, 11:50 AM

Mu-Young Ahn1*, Seungyon Cho1, Hyoseong Gwon1, NamIl Her1, Hyung Gon Jin2,
Chang-Shuk Kim1, DoHyun Kim1, Myungho Kim1, Sungyu Kim1, Suk-Kwon Kim2,
Woong Chae Kim1, Dong Won Lee2, Yonghee Lee1, Youngmin Lee1, Sungbo Moon1,
Soon Chang Park1, Yi-Hyun Park1, Chang Wook Shin2, Seok-Kwon Son1

1 Korea Institute of Fusion Energy (KFE), Daejeon, Republic of Korea
2 Korea Atomic Energy...
27. Preliminary Study on Tritium Release Properties of Li2TiO3 Pebbles Manufactured by PIM Process
Yi-Hyun Park
10/6/25, 1:30 PM

Yi-Hyun Park1, Young Ah Park1, Mu-Young Ahn1, Haixia Wang2
1KFE, Korea, 2INEST, China

The solid type of tritium breeder is used as a pebble form due to packing phenomena, stress concentration, thermal conductance, purge gas flow, and so on. The important properties of breeder pebbles are not only physical properties but also tritium release property. This study aims at a preliminary...
28. A new perspective on hydrogen isotope permeation behavior of LiAlO2 layer
Long Wang
10/6/25, 1:50 PM

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...
29. Features of experiments to study the generation and release of tritium from lithium-containing ceramics in conditions of vacuum pumping.
I Ye Kenzhina
10/6/25, 2:10 PM

I.Ye. Kenzhina1,2, T.V. Kulsartov1, A.A. Shaimerdenov1,2, Ye.V. Chikhray1, S.K. Askerbekov1,2, M. Aitkulov2, Zh.A. Zaurbekova1
1Satbayev University, Almaty, Kazakhstan
2Institute of Nuclear Physics, Almaty, Kazakhstan
e-mail: kenzhina@physics.kz
The design of future fusion reactors involves the generation of tritium inside a breeder blanket. One of the most promising materials for the...
31. Tritium Transfer Behavior from Neutron-Irradiated LiAlO 2 to Zirconium by Heating in a Sealed Quartz Tube
Hiroki Isogawa
10/6/25, 2:30 PM

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...
47. Effect of Helium Behavior on Hydrogen Isotope Release in Li2TiO3
Shurui Shang
10/6/25, 2:50 PM

Shurui Shang1,2, Qiang Qi1,2*, Shouxi Gu1, Hai-Shan Zhou1,2, Guang-Nan Luo1,2

1Institute of Plasma Physics, Hefei Institutes of Physical Sciences, Chinese Academy of Sciences, Hefei, 230031, China
2Science Island Branch, Graduate School of USTC, Hefei, 230036, China

Lithium-based ceramic tritium breeders serve as critical components in fusion blanket systems. Under neutron irradiation...
32. Investigating the Effect of High Energy Ion Irradiation and High Temperatures on the Mechanical Properties and Phase Stability of the Highly Lithium Dense ‘Octalithium Ceramics’ (Li8MO6, M = Zr, Sn, Pb and Ce) for Tritium Breeding
Pedr Charlesworth
10/6/25, 3:40 PM

Pedr Charlesworth1*, Ben Phoenix2, Samuel Murphy3, Mohamad Abdallah4, David Kingham4,
David Armstrong1, Chris Grovenor1
1Department of Materials, University of Oxford, U.K.
2Department of Physics and Astronomy, University of Birmingham, U.K.
3 Engineering Department, Lancaster University, U.K
4Tokamak Energy, Abingdon, U.K
In order to most efficiently produce tritium from a high energy...
34. Multiple irradiation campaigns for the testing of solid breeder specimens
Chase Taylor
10/6/25, 4:00 PM

Chase Taylor, Pattrick Calderoni, Xiao-Ying Yu
36. Development and Application of Machine Learning Potential for Lithium Titanate for Radiation Damage Simulations
Donggyu Lee
10/6/25, 4:20 PM

Donggyu Lee, Takuji Oda
Seoul National University

Lithium titanate (Li2TiO3) is a promising ceramic-type tritium breeder material for nuclear fusion reactors. While extensive experimental studies have been conducted to investigate its properties, the understanding of its behavior under radiation environments remains limited. Molecular dynamics (MD) simulations provide crucial insights into...
38. [BeWS] Rockland Resources and Beryllium as a Critical Mineral in Clean Energy Research
Chris DORN
10/7/25, 9:10 AM
39. [CBBI] Impact of various HCPB blanket modifications for the new EU-DEMO baseline on tritium breeding ratio and neutron shielding performance
Roman Fanasenko
10/7/25, 9:40 AM

Roman Afanasenko1, D. Leichtle1, F. Hernández1, J.H. Park1, P. Pereslavtsev2, G. Zhou1
1Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Karlsruhe, Germany
2EUROFUSION Programme Management Unit, Fusion Technology Department - DEMO Central Team, Boltzmannstrasse 2, 85748 Garching, Germany

The Helium-Cooled Pebble Bed (HCPB) breeding blanket is one of the leading...
42. [CBBI] Overview of activities at INP to irradiation testing of ceramic breeder
A. Shaimerdenov
10/7/25, 10:40 AM

A.Shaimerdenov, T.Kulsartov, I.Kenzhina, Zh.Zaurbekova, Sh.Gizatulin, S.Askerbekov

The Institute of Nuclear Physics, 1 Ibragimov st., Almaty, Kazakhstan

This article provides an overview of irradiation activities on the WWR-K reactor to test ceramic blanket materials for a fusion reactor. It describes the experimental capabilities of the WWR-K reactor, the tested materials, the...
41. [BeWS] Permeation-against-vacuum extraction of hydrogen isotopes in a forced convection FLiBe loop
Alexander HINZ
10/7/25, 11:10 AM
58. [CBBI] Introduction on Tritium Transport Analysis Platform – THETA-FR to Predict Tritium Behaviour in Tritium Breeding Blanket System
Yonghee Lee
10/7/25, 11:40 AM

Yonghee Lee1, Alice Ying2, Mu-Young Ahn1, Hyung Gon Jin3, Sungbo Moon1, Myungho Kim1
1Korea Institute of Fusion Energy, Daejeon, Korea
2University of California, Los Angeles (UCLA), LA, USA
3Korea Atomic Energy Research Institute, Daejeon, Korea

To implement a tritium breeding blanket in a fusion reactor, extensive research and efforts are required. Among these, the development of a...
43. Influence of lithium precursor deficiency and excess during solid-state synthesis on radiation-induced effects in biphasic Li4SiO4-Li2TiO3 ceramics
Arturs Zarins
10/7/25, 1:30 PM

Arturs Zarins1,2, Laura Dace Pakalniete1, Annija Liepkalne1, Liga Avotina1, Artis Kons3, Guna Krieke4, Jekabs Cirulis4, Andris Antuzevics4
1 – Institute of Chemical Physics, Faculty of Science and Technology, University of Latvia, Riga, Latvia; 2 – Department of Environment and Technologies, Faculty of Natural Sciences and Healthcare, Daugavpils University, Daugavpils, Latvia; 3 – Department...
50. Synthesis, Characterization, and Testing of High-Lithium-Density Composite Breeders
Michael Moorehead
10/7/25, 1:50 PM

Michael Moorehead, Priyanshi Agrawal, Malachi Nelson, Chase Taylor, Wei Tang, Timothy Yoder, Mario Daniel Matos II, Jorgen Rufner, Pierre-Clement Simon, Lin Yang
Idaho National Laboratory

Solid tritium breeder materials must first and foremost have sufficiently high concentrations of lithium to enable a plant-scale tritium breeding ratio greater than 1:1. However, in addition to lithium...
45. Corrosion behavior of F82H by LTZO ceramic breeder pebbles
Keisuke Mukai
10/7/25, 2:10 PM

Keisuke Mukai,1,2*, Kosuke Kataoka3, Juro Yagi3, Motoki Nakajima4, Jae-Hwan Kim4, Takashi Nozawa4
1　National Institute for Fusion Science, National Institutes of Natural Science, Toki, Gufu 509-5292, Japan
2　The Graduate University for Advanced Studies, SOKENDAI, Toki, Gifu 509-5292, Japan
3　Graduate School of Energy Science, Kyoto University, Uji, Kyoto 611-0011, Japan
4　National...
48. The enhanced sintering and mechanical properties of Li4SiO4 by the introduction of a secondary phase
Qilai Zhou (Wuhan University of Technology)
10/7/25, 2:30 PM

Qilai Zhou a, Yifu Xu a, Kaixuan Zhu a
a School of Materials Science and Engineering, Wuhan University of Technology, Wuhan 430070, China

Abstract:
Lithium orthosilicate (Li4SiO4) is considered as a promising solid tritium breeding material for fusion reactors due to its high lithium density and subsequent high tritium generation rate. However, its limited sinterability and inadequate...
67. Thermal Cycling Test of ACB Pebbles in Comparison with Standard Long‐Term Annealed Samples
Julia Leys (Karlsruhe Institute of Technology)
10/7/25, 2:50 PM

Julia Leys, Thomas Bergfeldt, Oliver Leys, Regina Knitter
Karlsruhe Institute of Technology (KIT), Institute for Applied Materials (IAM), Karlsruhe, Germany

Advanced Ceramic Breeder (ACB) pebbles represent the EU reference material for solid tritium breeders. Their application is foreseen in the ITER TBM and in DEMO. Therefore, comprehensive knowledge about their material properties are...
51. Powder Synthesis with Core-shell Structure for Tritium Breeder
Young Ah Park
10/7/25, 3:40 PM

Young Ah Park, Yi-Hyun Park
Korea Institute of Fusion Energy (KFE), Korea

Lithium orthosilicate (Li4SiO4) and Lithium metatitanate (Li2TiO3) have been studied as promising tritium breeder for fusion energy. Li4SiO4 has a lithium density of 0.51g/cm3, which is higher than the lithium density of Li2TiO3 (0.43g/cm3), resulting in higher tritium production efficiency. However, Li4SiO4 is prone...
52. Enrichment of Lithium-6 using Electrodialysis with Ionic Conductor Membrane
Kenji Morita
10/7/25, 4:00 PM

Kenji Morita, Kodai Ishii, Makiko Sekiya, Yumiko Tanaka, Tsuyoshi Hoshino
Rokkasho Institute for Fusion Energy, National Institutes for Quantum Science and Technology (QST), Rokkasho, Aomori 039-0212, Japan.
Keywords: Lithium-6 Enrichment, Ionic Conductor, Electrodialysis, Breeding blanket
In fusion power generation, achieving tritium self-sufficiency necessitates a sufficient ratio of...
54. Improvement of lithium isotope enrichment ratio and enrichment rate by electrochemical active control of adsorbed ions in intermittent voltage electrodialysis
Shumpei Iwasaki
10/7/25, 4:20 PM

Kiyoto Shin-mura1, Shumpei Iwasaki1, Kazuya Sasaki1
1Hirosaki University

Current major plans for thermonuclear power generation use the nuclear fusion reaction of deuterium and tritium. Tritium, which is almost absent in nature, must be generated in a fusion reactor by the fission reaction of lithium 6 isotope (6Li) with neutrons. For this purpose, technology for enriching the 6Li isotope...
49. Results from the Continuous Operation of the KALOS Process
Oliver Leys (Karlsruhe Institute of Technology)
10/7/25, 4:40 PM

Oliver Leysa, Julia Leysa, Regina Knittera
a. Karlsruhe Institute of Technology (KIT), Institute for Applied Materials (IAM), Karlsruhe, Germany

Abstract:　 The KALOS process is used at the Karlsruhe Institute of Technology for the production of Advanced Ceramic Breeder (ACB) pebbles. These pebbles, composed of lithium orthosilicate with a strengthening phase of lithium metatitanate, are...
55. Modelling transport of dust particles, and fragmentation estimates in the HCPB-BB of DEMO
Dario Passafiume
10/8/25, 9:10 AM

Dario Passafiume1, Marc Kamlah1
1Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe, Germany

The European solid breeder blanket concept Helium Cooled Pebble Bed (HCPB) uses advanced lithium ceramic breeder (ACB) material in the form of pebbles. During the HCPB breeder blanket operation, a fragmentation of the pebbles due to thermomechanical loads can occur, as...
56. Molecular dynamics simulations of helium diffusivity in lithium orthosilicate crystals using a machine learning potential
ruijie zhang (Department of Nuclear Engineering, Seoul National University, Seoul 08826.)
10/8/25, 9:30 AM

Ruijie Zhang, Takuji Oda Department of Nuclear Engineering, Seoul National University

Abstract:
Li₄SiO₄ is a promising solid tritium breeding material due to its high lithium density, thermal stability, and excellent tritium release performance. The Li-n reaction inevitably produces helium atoms, which are initially produced in bulk. Helium atoms have a closed-shell structure and small...
57. Optimized Design of HCCB Breeding Blanket with Casing Structure for Enhanced TBR in DEMO Reactor
Xiaoyong Wang
10/8/25, 9:50 AM

Xiaoyong Wang, Ziqiang Zhao, Zaixin Li
Southwestern Institute of Physics, No.5 Huangjin Road, Shuangliu District, Chengdu City, Sichuan Province, China

The breeding blanket is a key component of the DEMO reactor, essential for tritium breeding, energy extraction, and nuclear shielding. To achieve a higher Tritium Breeding Ratio (TBR), a novel helium-cooled ceramic breeder (HCCB) blanket...
68. Preliminary Engineering Analysis for CN HCCB TBM Regarding ITER New Baseline Scenario
Xinghua Wu
10/8/25, 10:10 AM

Xinghua Wu, Shen Qu, Ruyan Li, Qixiang Cao, Fengchao Zhao, Long Zhang, Xiaoyu Wang
Southwestern Institute of Physics,P.O.Box 432, Chengdu, 610041, China

Among the different TBM concepts proposed for DEMO design of different countries, China finally determined to develop the Helium Coolant Ceramic Breeder (HCCB) TBM, following the strategy of national magnetic confined fusion energy...
63. Pebble Beds Thermal Expansion Measurement with Radial Expansion Correction of the Sample Holder
Harsh Patel
10/8/25, 11:00 AM

Harsh Patel1, *, Maulik Panchal1, Aroh Shrivastava1, 2, Paritosh Chaudhuri1, 2
1Institute for Plasma Research, Bhat, Gandhinagar – 382428, India
2Homi Bhabha National Institute, Anushaktinagar, Mumbai – 400094, India

An experimental setup was developed to measure the coefficient of thermal expansion (CTE) of lithium ceramic pebble beds within the typical operating temperature range of...
66. Effect of Li-depletion on thermal conductivity in Li2BeSiO4
Daigo Kanamori
10/8/25, 11:20 AM

Daigo Kanamori, Keisuke Mukai, Makoto. I. Kobayashi,
a The Graduate University for Advanced Studies, SOKENDAI, Toki, Gifu 509-5292,Japan
b National Institute for Fusion Science, Toki, Gifu 509-5292, Japan
Keywords : Solid breeder materials, Li-depletion, thermal conductivity, molecular dynamics

To realize fusion reactor, it is necessary to develop tritium breeders and neutron...
65. Dual-Direction Hot-Wire Measurements of Anisotropic effective thermal conductivity in Fusion Pebble Beds
Maulik Panchal
10/8/25, 11:40 AM

Maulik Panchal1,, Harsh Patel1, Paritosh Chaudhuri1,2
1Institute for Plasma Research, Bhat, Gandhinagar - 382428, India.
2Homi Bhabha National Institute, Anushaktinagar, Mumbai - 400094, India.
E-mail address: maulikpanchal@ipr.res.in
Accurate prediction of thermal performance within the breeder zones of fusion blankets is critically dependent on the effective thermal conductivity (keff)...
40. [CBBI] Neutronics experiments on the mock-ups of WCCB and COOL blanket under D-T neutron irradiation conditions
Qingjun Zhu

Qingjun Zhu a, Qiankun Shao a, Wuhui Chen a, Jie Bao b, Hua Dua a, Songlin Liu a
a. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
b. Department of Nuclear Physics, China Institute of Atomic Energy, Beijing 102413, China

Abstract:The tritium production performance of the fusion blanket reaches the expected index, which is the primary prerequisite...
46. Annealing self-healing behavior of ion-irradiated tritium breeders and the compatibility with RAFM steel
Shouxi Gu

Shouxi Gu1, Qiang Qi1,2, Hai-Shan Zhou1,2
1Institute of Plasma Physics, Hefei Institutes of Physical Sciences, Chinese Academy of Sciences, Hefei, 230031, China
2Science Island Branch, Graduate School of USTC, Hefei, 230036, China

The neutron energy spectrum in solid breeder blankets spans from 10−8 to 14 MeV, generating primary knock-on atoms (PKAs) with energies ranging from 10−4 to...
44. Chemical stability and mechanical strength change of two-phase mixture sintered compacts of Li2O and Li8ZrO6 under simulated operating conditions for tritium breeding materials
Minato Bannai

Minato Bannai1, Kiyoto Shin-mura1, Shido Kosuke1, Kazuya Sasaki1
1Hirosaki University
Fusion energy is expected to be the next generation energy source. For practical use, stable plasma confinement in a fusion reactor and efficient breeding of tritium, one of the fuels, are essential. Tritium is produced by the nuclear fission reaction between lithium (mass number 6), which is loaded as a...
53. Chemical stability and mechanical strength change of two-phase mixture sintered compacts of Li2O and Li8ZrO6 under simulated operating conditions for tritium breeding materials
Minato Bannai

Minato Bannai1, Kiyoto Shin-mura1, Shido Kosuke1, Kazuya Sasaki1
37. Investigation of hydrogen isotope release behavior in long-term annealed tritium breeding pebbles
Qiang Qi

Qiang Qi1,2*, Shouxi Gu1, Yingchun Zhang3, Hai-Shan Zhou1,2, Guang-Nan Luo1,2

1Institute of Plasma Physics, Hefei Institutes of Physical Sciences, Chinese Academy of Sciences, Hefei, 230031, China
2Science Island Branch, Graduate School of USTC, Hefei, 230036, China
3School of Materials Science and Engineering, University of Science and Technology Beijing, 30 Xueyuan Road, Haidian...
35. Neutronics analysis of the ceramic breeder blanket materials irradiation in the IFMIF-DONES test modules
Dr Arkady Serikov (Karlsruhe Institute of Technology (KIT))

Ali Abou-Sena, Frederik Arbeiter, Santiago Becerril, Achim Kupferschmitt, Dieter Leichtle, Jin Hun Park, Yuefeng Qiu, Arkady Serikov, Guangming Zhou
33. Neutronics experiments on the mock-ups of WCCB and COOL blanket under D-T neutron irradiation conditions
Qingjun Zhu

Qingjun Zhua, Qiankun Shaoa, Wuhui Chena, Jie Baob, Hua Duaa, Songlin Liua
a. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
b. Department of Nuclear Physics, China Institute of Atomic Energy, Beijing 102413, China

Abstract:The tritium production performance of the fusion blanket reaches the expected index, which is the primary prerequisite for the...
30. Study on tritium release behavior of ceramic pebbles fabricated by Centrifugal granulation method
guangfan tan

guangfan tan, Yasuhisa Oya, Qilai Zhou

One of the key problems in fusion reactor fuel cycle is the efficient acquisition of tritium. How to obtain ceramic pebbles with high lithium content, excellent mechanical properties and good tritium release is the future development goal. In this study, Li2TiO3, Li4SiO4 and biphasic Li2TiO3-Li4SiO4 pebbles were successfully prepared by centrifugal...
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