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.

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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
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article

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

Inesh Kenzhina, Etsuo Ishitsuka, Hai Quan Ho, Katsuyoshi Tatenuma et al.
Nuclear Materials and Energy
Fusion materials and technologies
article

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

Inesh Kenzhina, Etsuo Ishitsuka, Hai Quan Ho, Katsuyoshi Tatenuma, Jae-Hwan Kim, Naoyuki Takaki, Yevgeni Chikhray
article en

Abstract

• 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.

Nuclear Materials and Energy
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)
Openalex Percentile: Top 10%
Fusion materials and technologies
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