Feasibility study of gamma-ray spectroscopy for the determination of the fusion power at the SPARC tokamak

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

Fusion Engineering and Design Pub Date : 2025-09-12 DOI:10.1016/j.fusengdes.2025.115403

Simone Lorenzo Fugazza , Giulia Marcer , Massimo Nocente , Alessandro Ciurlino , Gabriele Croci , Marco Dalla Rosa , Andrea Dal Molin , Erik Gallo , Giuseppe Gorini , Miriam Parisi , Prasoon Raj , Marica Rebai , Matthew Reinke , Davide Rigamonti , Federico Scioscioli , Marco Tardocchi , JET Contributors

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引用次数: 0

Abstract

SPARC is a high-field, compact tokamak aiming to obtain a fusion gain Q

>

1 in Deuterium-Tritium (DT) plasmas for the first time in a magnetic confinement fusion reactor. Fusion power measurement is a key diagnostic requirement. In this work we present a scoping study of a gamma-ray spectrometer for the determination of the fusion power at SPARC. Measurements are based on the detection of the 16.7 MeV and

\sim

14 MeV gamma-rays produced by the weak secondary channel

T {(D, γ)}^{5} He

of the DT fusion reaction, whose branching ratio has been recently measured at the JET tokamak. Starting from the numerical calculation of the DT gamma source and a first evaluation of the sources of background radiation, we determine the fusion power range where measurements are possible at SPARC. We find that the fusion power can be determined in the broad range of 0.2 MW to 140 MW, when different neutron and gamma-ray attenuators are employed depending on the operational conditions. Potential additional applications of the gamma-ray detector scoped in this work are also briefly discussed.

查看原文本刊更多论文

伽玛射线光谱法测定SPARC托卡马克聚变功率的可行性研究

SPARC是一种高场紧凑型托卡马克，旨在首次在磁约束聚变反应堆中获得氘-氚（DT）等离子体的聚变增益Q>；1。聚变功率测量是一项关键的诊断要求。在这项工作中，我们提出了一个伽马射线光谱仪的范围研究，以确定在SPARC的聚变功率。测量是基于检测DT聚变反应的弱次级通道T(D,γ)5He产生的16.7 MeV和~ 14 MeV伽马射线，其分支比最近在JET托卡马克上测量。从DT伽玛源的数值计算和背景辐射源的首次评估开始，我们确定了在SPARC可以测量的聚变功率范围。我们发现，当根据运行条件使用不同的中子和伽马射线衰减器时，聚变功率可以在0.2 MW到140 MW的宽范围内确定。本文还简要讨论了在本研究范围内的伽马射线探测器的潜在附加应用。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.