Experimental validation of transmutation products calculations in neutron irradiated tungsten

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
V. Chatzikos , M.I. Savva , T. Vasilopoulou , I.E. Stamatelatos , D. Terentyev , A. Stankovskiy , N. Patronis , K. Mergia
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Abstract

Neutron irradiation can significantly alter the elemental composition of a material by generating transmutation products through nuclear reactions between neutrons and atomic nuclei. These changes in composition can substantially impact the material's physical and mechanical properties. Therefore, accurately assessing the buildup of transmutation products in neutron-irradiated materials is essential for understanding and predicting these effects. Tungsten (W) is particularly critical for the first wall and divertor components in fusion reactors. As such, an accurate assessment of transmutation products in neutron-irradiated tungsten is crucial for the safety and lifespan of future fusion power plants. The scope of the present work is to experimentally validate calculations of transmutation products buildup in tungsten after neutron irradiation at the Materials Test Reactor (MTR) BR-2 at SCK CEN, Belgium. Tungsten specimens were irradiated to doses of 0.12 and 0.19 displacements per atom (dpa) within the temperature range of 600 to 1200 °C. Nuclide inventory calculations were performed using the FISPACT-II code and the TENDL-2019 cross-section library. γ-ray spectroscopy was employed to determine the specific activity levels of 181W, 185W, 188W, 188Re and 182Ta in order to validate the transmutation products calculations for rhenium (Re), osmium (Os) and tantalum (Ta). It is shown that the theoretical calculations for Re and Os concentrations are in good agreement with the experimental data, while the Ta concentration is underestimated by a factor of approximately 1.5.
中子辐照钨中嬗变产物计算的实验验证
中子辐照可以通过中子和原子核之间的核反应产生嬗变产物,从而显著改变物质的元素组成。这些成分的变化会极大地影响材料的物理和机械性能。因此,准确评估中子辐照材料中嬗变产物的积累对于理解和预测这些效应至关重要。钨(W)在聚变反应堆的第一壁和分流器组件中尤为重要。因此,准确评估中子辐照钨的嬗变产物对未来核聚变发电厂的安全性和寿命至关重要。目前的工作范围是在比利时SCK CEN的材料试验堆(MTR) BR-2上实验验证中子辐照后钨中嬗变产物积累的计算。钨样品在600至1200℃的温度范围内辐照至0.12和0.19位移/原子(dpa)的剂量。核素库存计算使用FISPACT-II代码和TENDL-2019截面库进行。利用γ射线能谱法测定了181W、185W、188W、188Re和182Ta的比活度,验证了铼(Re)、锇(Os)和钽(Ta)的嬗变产物计算。结果表明,Re和Os浓度的理论计算与实验数据吻合较好,而Ta浓度被低估了约1.5倍。
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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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