Experimental confirmation of first-principles thermal conductivity in Zirconium-doped ThO2

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Ella Kartika Pek , Zilong Hua , Amey Khanolkar , J. Matthew Mann , David B. Turner , Karl Rickert , Timothy A. Prusnick , Marat Khafizov , David H. Hurley , Linu Malakkal
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Abstract

The degradation of thermal conductivity in advanced nuclear fuels due to the accumulation of fission products and irradiation-induced defects is inevitable, and must be considered as part of safety and efficiency analyses of nuclear reactors. This study examines the thermal conductivity of a zirconium-doped ThO2 crystal, synthesized via the hydrothermal method using a spatial domain thermoreflectance technique. Zirconium is one of the soluble fission products in oxide fuels that can effectively scatter heat-carrying phonons in the crystalline lattice of fuel. Thus, thermal property measurements of zirconium-doped ThO2 single crystals provide insights into the effects of substitutional zirconium doping, isolated from extrinsic factors such as grain boundary scattering. The experimental results are compared with first-principles calculations of the lattice thermal conductivity of ThO2, employing an iterative solution of the Peierls-Boltzmann transport equation. Additionally, the non-perturbative Green's function methodology is utilized to compute phonon-point defect scattering rates, accounting for local distortions around point defects, including mass difference changes, interatomic force constants, and structural relaxation. The congruence between the predicted results from first-principles calculations and the measured temperature-dependent thermal conductivity validates the computational methodology. Furthermore, the methodologies employed in this study enable systematic investigations of thermal conductivity reduction by fission products, potentially leading to the development of more accurate fuel performance codes.
掺锆ThO2第一性原理导热性的实验证实
由于裂变产物的积累和辐照缺陷,先进核燃料的导热性能下降是不可避免的,必须作为核反应堆安全性和效率分析的一部分加以考虑。本研究利用空间域热反射技术研究了通过水热法合成的锆掺杂ThO2晶体的导热性。锆是氧化物燃料中的可溶性裂变产物之一,它能有效地散射燃料晶格中的载热声子。因此,通过测量掺杂锆的ThO2单晶的热性能,可以深入了解取代锆掺杂的影响,而不受晶界散射等外在因素的影响。利用peerls - boltzmann输运方程的迭代解,将实验结果与ThO2晶格热导率的第一性原理计算结果进行了比较。此外,利用非微扰格林函数方法计算声子点缺陷散射率,考虑点缺陷周围的局部畸变,包括质量差变化、原子间力常数和结构弛豫。第一性原理计算的预测结果与测量的温度相关的导热系数之间的一致性验证了计算方法。此外,本研究中采用的方法能够系统地研究裂变产物降低导热系数,从而有可能开发出更准确的燃料性能代码。
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
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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