Retained fuel removal from plasma-facing materials: effects of baking methods and hydrogen isotope exchange

Abstract Tungsten (W) is a prominent plasma-facing material for deuterium-tritium (D-T) fusion reactors, yet T fuel retention in W poses critical challenges to safety and operational viability. This study systematically compares three baking methods—vacuum baking, H2 gas atmosphere baking, and hydrogen (H) plasma baking—for removing D retained in W at 513 K, simulating realistic conditions for T removal in reactors. Experimental results demonstrate that D removal efficiencies reach 75% for vacuum baking after 16 h, 83% for H2 atmosphere baking after 16 h, and 99% for H plasma baking after 1 h. The superior performance of H2 atmosphere and H plasma baking is primarily driven by hydrogen isotope (HI) exchange, with efficiency strongly dependent on the concentration of H introduced into W. Higher H concentrations promote more complete exchange, leading to significantly reduced D retention. A multi-isotope Fill Level model was developed to simulate the end-to-end H plasma exchange process. The simulation reproduces the experimentally observed D removal kinetics and the emergence of HD desorption, with the D retention in good agreement with measurements. The pronounced disparity between H2 atmosphere baking and H plasma baking is fundamentally governed by the quantity of H entering W: H plasma promotes significantly greater H ingress, thereby enhancing HI exchange and resulting in a drastic reduction in D retention. This work provides both experimental validation and modelling support for HI exchange as an efficient T removal strategy.

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Publication Details

Journal
Nuclear Fusion
Published
2026-11-10
DOI
https://doi.org/10.1088/1741-4326/aec02c
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
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article

Retained fuel removal from plasma-facing materials: effects of baking methods and hydrogen isotope exchange

Yasuhisa Oya, Hai-Shan Zhou, 叶小球, Changan Chen et al.
Nuclear Fusion
Fusion materials and technologies
article

Retained fuel removal from plasma-facing materials: effects of baking methods and hydrogen isotope exchange

Yasuhisa Oya, Hai-Shan Zhou, 叶小球, Changan Chen, Qihang Liu, Wei Jin, Fei Sun, Jipeng Zhu, Yucheng Wu, Xuxu Liu, Guangyu Ma
article en

Abstract

Abstract Tungsten (W) is a prominent plasma-facing material for deuterium-tritium (D-T) fusion reactors, yet T fuel retention in W poses critical challenges to safety and operational viability. This study systematically compares three baking methods—vacuum baking, H2 gas atmosphere baking, and hydrogen (H) plasma baking—for removing D retained in W at 513 K, simulating realistic conditions for T removal in reactors. Experimental results demonstrate that D removal efficiencies reach 75% for vacuum baking after 16 h, 83% for H2 atmosphere baking after 16 h, and 99% for H plasma baking after 1 h. The superior performance of H2 atmosphere and H plasma baking is primarily driven by hydrogen isotope (HI) exchange, with efficiency strongly dependent on the concentration of H introduced into W. Higher H concentrations promote more complete exchange, leading to significantly reduced D retention. A multi-isotope Fill Level model was developed to simulate the end-to-end H plasma exchange process. The simulation reproduces the experimentally observed D removal kinetics and the emergence of HD desorption, with the D retention in good agreement with measurements. The pronounced disparity between H2 atmosphere baking and H plasma baking is fundamentally governed by the quantity of H entering W: H plasma promotes significantly greater H ingress, thereby enhancing HI exchange and resulting in a drastic reduction in D retention. This work provides both experimental validation and modelling support for HI exchange as an efficient T removal strategy.

Nuclear Fusion
Shizuoka University (JP), Hefei University of Technology (CN), Chinese Academy of Sciences (CN), China Academy of Engineering Physics (CN), Institute of Plasma Physics (CN)
Fusion materials and technologies
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