使用氘氦3燃料的紧凑型托卡马克的活化分析

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-10-11 DOI:10.1016/j.fusengdes.2025.115491

A. Morandi, D. Pettinari, M. Zucchetti

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引用次数: 0

摘要

高温超导（HTS）磁体的最新进展使托卡马克能够缩小尺寸并在更高的等离子体参数下运行。这为使用先进的燃料混合物，如氘- 3氦（DHe3）提供了可能性。与传统燃料相比，DHe3提供了减少中子诱导活化的潜力，并最大限度地减少了燃料循环中氚的存在。在使用50%氘- 50%氦混合物的聚变反应堆中，中子仅在氘-氘（DD）和氘-氚（DT）副反应中产生，而氚可以在DD反应中产生，因此在机器启动时不存在。本研究提出了一个全面的中子和活化分析紧凑，高场托卡马克使用DHe3燃料。使用开放源代码的蒙特卡罗代码OpenMC，将研究这种燃料混合物在紧凑型聚变反应堆范围内的可行性和性能。激活分析将仅限于第一壁，毯层和板内环形场线圈，并对托卡马克的布局进行了一些简化。通过分析中子相互作用和激活过程，以及设计修改，我们试图评估实施DHe3作为燃料的潜在好处和挑战。

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Activation analysis of a compact Tokamak using Deuterium–Helium3 fuel

Recent advancements in high-temperature superconducting (HTS) magnets have enabled tokamaks to reduce dimensions and operate with higher plasma parameters. This opens to the possibility of using advanced fuel mixtures such as Deuterium–

^{3}

Helium (DHe3). Compared to traditional fuels, DHe3 offers the potential to reduce neutron-induced activation and minimize the presence of tritium in the fuel cycle.

In a fusion reactor that uses a 50% Deuterium–50%

^{3}

Helium mixture, neutrons are produced solely in the Deuterium–Deuterium (DD) and Deuterium–Tritium (DT) side reactions, while Tritium can be produced during DD reactions and is therefore absent at the startup of the machine.

This study proposes a comprehensive neutronic and activation analysis of a compact, high-field tokamak employing DHe3 fuel. Using OpenMC, an open-source Monte Carlo code, the feasibility and performance of this fuel mixture within the confines of a compact fusion reactor will be investigated. The activation analysis will be limited to the First Wall, Blanket and inboard Toroidal Field coils, with some simplifications in the tokamak layout.

By analyzing neutron interactions and activation processes, as well as design modifications, we seek to assess the potential benefits and challenges associated with implementing DHe3 as fuel.

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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.