导流剂对HELIAS氚育种的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Tommi Lyytinen , Antti Snicker , Timo Bogaarts , Felix Warmer
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引用次数: 0

摘要

本文利用Serpent2编码对五周期螺旋轴先进仿星器(HELIAS)进行了氚增殖计算。为了解决没有详细的导流器设计的问题,将具有分层均匀结构的简化导流器模型集成到HELIAS的参数几何中。通过参数研究、不同的导流器配置、表面积、导流器和繁殖毯的材料以及导流器后面繁殖区的厚度,评估了导流器对氚繁殖比(TBR)的影响。根据指定的输入参数,计算出的TBR损失相对于全毯覆盖范围在4%至35%之间。影响TBR损失的主要因素是导流器所占表面积的比例和被导流器置换的繁殖带的体积。TBR损失与导流管面积分数和繁殖带体积减少呈线性关系。此外,与氦冷型相比,水冷型导流器配置对TBR的负面影响更大,其影响程度与面积分数的变化相当。纯TBR优化分流器配置与Wendelstein 7- x型自上而下配置之间的TBR损失差异小于2个百分点。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Effect of divertor on tritium breeding in HELIAS
This study presents tritium breeding calculations for the five-period helical-axis advanced stellarator (HELIAS) using the Serpent2 code. To address the absence of a detailed divertor design, a simplified divertor model with a layered homogenized structure was integrated into the parametric geometry of the HELIAS. The impact of the divertor on the tritium breeding ratio (TBR) was assessed through a parametric study, varying divertor configurations, surface area, materials for both the divertor and breeding blanket, and the thickness of the breeding zone behind the divertor. Calculated TBR losses relative to full blanket coverage ranged from 4 % to 35 %, depending on the specified input parameters. The primary factors influencing TBR loss were the fraction of surface area occupied by the divertor and the volume of the breeding zone displaced by it. A linear relationship was observed between TBR loss and both the divertor area fraction and the reduction in breeding zone volume. Furthermore, water-cooled divertor configurations showed a more negative impact on TBR compared to helium-cooled, with effects comparable in significance to variations in area fraction. The difference in TBR loss between purely TBR-optimized divertor configuration and Wendelstein 7-X-like top-bottom configuration was less than 2 percentage points.
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来源期刊
Fusion Engineering and Design
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.
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