Optimal size of beryllium pebbles as a neutron multiplier − helium recoil calculations aiming for swelling reduction and new proposal of neutron multiplier for advanced high-temperature tritium breeding blanket
• The relationship between the size of beryllium and helium recoil release was studied using the PHITS code. • Within the studied diameter range (10 μm to 1 mm), a smaller beryllium particle size enhances helium recoil release. • A 10 μm beryllium sphere filled with lead is proposed as a candidate material for advanced tritium breeding blankets. The relationship between the size of the neutron multiplier (diameters ranging from 10 μm to 1 mm) and helium recoil release was studied using the PHITS code to reduce swelling actively. The results indicate that a smaller particle size enhances helium recoil release. However, smaller spheres are more affected by helium irradiation from neighboring spheres. To mitigate this effect, a 10 μm beryllium sphere filled with lead is proposed as a candidate material for advanced tritium breeding blankets designed for high-temperature operation. This lead-filled material is attractive because molten lead can remove helium from the system while improving both the tritium breeding ratio and the neutron-shielding performance of the fusion blanket.
Authors
- Inesh Kenzhina (ORCID: https://orcid.org/0000-0002-9397-5848)
- Etsuo Ishitsuka (ORCID: https://orcid.org/0000-0001-5927-0652)
- Hai Quan Ho (ORCID: https://orcid.org/0000-0002-7096-3318)
- Katsuyoshi Tatenuma
- Jae-Hwan Kim
- Naoyuki Takaki
- Yevgeni Chikhray
Institutions
- Japan Atomic Energy Agency (JP)
- Tokyo City University (JP)
- Satbayev University (KZ)
- Research Organization for Information Science and Technology (JP)
- National Institutes for Quantum Science and Technology (JP)
- NOF Corporation (Japan) (JP)
- Institute of Information and Computational Technologies (KZ)
- Advanced Science Research Center (JP)
- Hanoi University of Science and Technology (VN)
Publication Details
- Journal
- Nuclear Materials and Energy
- Published
- 2026-03-01
- DOI
- https://doi.org/10.1016/j.nme.2026.102106
- Primary Topic
- Fusion materials and technologies
- Type
- article
- Field-Weighted Citation Impact
- 0.00