用于 A-FNS 风险评估的氚大气扩散建模代码 ROPUCO

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-09-06 DOI:10.1016/j.fusengdes.2024.114653

Shunsuke Kenjo , Sumi Yokoyama , Kentaro Ochiai , Satoshi Sato

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引用次数: 0

摘要

在聚变中子源设施 A-FNS 中，氚不可避免地主要通过 D-Li 核反应产生。在 A-FNS 的设计活动中，必须对设施释放的氚对公众造成的辐射风险进行评估。我们开发了一种新的剂量评估代码 ROkkasho PUff COde (ROPUCO)，该代码采用高斯帕夫模型，并考虑了土壤中氚的再发射，以进行精确的氚剂量评估。在这项研究中，ROPUCO 以 1987 年查克河的实验结果和另一个氚剂量评估代码 ACUTRI 为基准进行了验证。结果表明，在平坦地形和均匀气象条件下，ROPUCO 能正确模拟大气中的氚扩散。

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Tritium atmospheric dispersion modelling code, ROPUCO, for A-FNS risk assessment

Tritium is inevitably produced in a fusion neutron source facility, A-FNS, mostly via D-Li nuclear reactions. In the design activity of the A-FNS, radiological risk assessment for the public due to the tritium released from the facility is indispensable. We have developed a new dose assessment code, ROkkasho PUff COde (ROPUCO), which employs a Gaussian Puff model with considering tritium re-emission from soil for precise tritium dose assessments. In this study, ROPUCO was validated by benchmarking the experimental results for the Chalk River in 1987 and another tritium dose assessment code, ACUTRI. The results showed that ROPUCO could properly simulate tritium dispersion in the atmosphere under flat topography and uniform meteorological conditions.

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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.