Comparative analysis of neutronic features for various specimen payload configurations within the IFMIF-DONES HFTM

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-11-19 DOI:10.1016/j.fusengdes.2024.114729
I. Álvarez , M. Anguiano , F. Mota , R. Hernández , F. Moro , S. Noce , Y. Qiu , J. Park , F. Arbeiter , I. Palermo , D. Sosa
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Abstract

The International Fusion Materials Irradiation Facility- DEMO Oriented NEutron Source (IFMIF-DONES) facility is a neutron irradiation facility specifically designed to obtain data on material irradiation for the construction of DEMO (DEMOstration) fusion power plant. The purpose of this study is to investigate and compare the effects of using different realistic models of specimen distribution during the irradiation campaign in the High Flux Test Module (HFTM) in IFMIF-DONES. Parameters such as neutron fluence rate, primary displacement damage rate and gas production have been calculated for two beam footprint sizes: the standard 20×5 cm² and the reduced 10×5 cm². The standard deuteron beam energy is 40 MeV with a current of 125 mA, but other energy values such as 25, 30 and 35 MeV have also been considered to evaluate their impact on the irradiation parameters. As the idea is to reproduce the DEMO conditions, some neutron spectra in the first wall of the DCLL, WCLL and HCPB have also been evaluated to gather reference data and compare the environments of DEMO and IFMIF-DONES. The level of packaging of the specimens impacts directly the neutron fluence rate behaviour and the different specimen distribution models give rise to different primary displacement damage rate distributions, demonstrating their versatility to meet specific needs. With respect to the comparison DEMO values, IFMIF-DONES meets the requirements of primary displacement damage rate and gas production at different beam energies. This study emphasises the essential role of sample distribution in improving the accuracy of measurements made at the IFMIF-DONES facility.
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IFMIF-DONES HFTM 中各种试样有效载荷配置的中子特征比较分析
国际聚变材料辐照设施--DEMO定向中子源(IFMIF-DONES)设施是一个中子辐照设施,专门用于获取材料辐照数据,以建造DEMO(演示)聚变发电厂。本研究的目的是调查和比较在 IFMIF-DONES 的高通量测试模块(HFTM)中进行辐照活动期间使用不同的试样分布现实模型的效果。计算了两种光束足迹尺寸的参数,如中子通量率、原生位移损伤率和气体产生量:标准的 20×5 平方厘米和缩小的 10×5 平方厘米。标准氘核束能量为 40 MeV,电流为 125 mA,但也考虑了其他能量值,如 25、30 和 35 MeV,以评估它们对辐照参数的影响。由于要重现 DEMO 的条件,因此还对 DCLL、WCLL 和 HCPB 第一壁的一些中子谱进行了评估,以收集参考数据并比较 DEMO 和 IFMIF-DONES 的环境。试样的封装程度直接影响中子通量率的表现,不同的试样分布模型会产生不同的一次位移损伤率分布,这表明它们具有满足特定需求的多功能性。在比较 DEMO 值方面,IFMIF-DONES 满足了不同束能量下一次位移损伤率和气体产生量的要求。这项研究强调了样品分布在提高 IFMIF-DONES 设备测量精度方面的重要作用。
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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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