Dose assessment of gaseous tritium release from deuterium-tritium fusion devices based on steady-state plume model

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-03-14 DOI:10.1016/j.fusengdes.2025.114965

Weijie Cui , Zaixin Li , Qixiang Cao , Bo Cao

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Abstract

The deuterium-tritium fusion represents a promising avenue for achieving commercial controlled nuclear fusion, but the usage of radioactive tritium poses significant environmental and radiological risks to personnel. To evaluate the radiological impact on nearby staff and the public from atmospheric tritium released during the steady-state operation of fusion devices, this study developed a dose assessment code based on the steady-state Gaussian plume model. Using tritium water vapor release rates from the ITER safety report as the source term, we calculated the tritium doses absorbed via inhalation and skin contact for various age groups, utilizing 2023 ECMWF reanalysis meteorological data for an inland basin site in China, a hypothetical site in Daya Bay, and the ITER site. The results indicate that the maximum public dose near the inland basin site is 0.030 mSv/yr, near the Daya Bay site is 0.015 mSv/yr, and near the ITER site is 0.018 mSv/yr, all of which are well below the ITER project's limit of 0.1 mSv/yr. Thus, fusion devices are radiologically safe for the surrounding personnel under normal operation.

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.