Hydrogen desorption kinetics of hafnium hydride powders

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
J.P. Pollard , A. Dumain , B. Stratton , S. Irukuvarghula , J. Astbury , S. Middleburgh , F. Giuliani , S. Humphry-Baker
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Abstract

The kinetics of hydrogen gas release from hafnium hydride are investigated by combining experiments and density functional theory. The material is a candidate neutron shield for compact nuclear reactors, where hydrogen release will lead to a degradation in moderating function. Experimentally, we have studied the decomposition of epsilon phase (HfH2-x) powders from 25 to 1000 °C using thermogravimetry and X-ray diffraction. Isochronal heating reveals 3 characteristic desorption peaks corresponding to the release of hydrogen from each phase (ε-HfH2-x, δ-HfH1.6-x and α-Hf), at ∼ 350, 415, and 700 °C. This is well supported by the modelling output from density functional theory. A Kissinger analysis allowed for activation energies for desorption to be calculated (∼150 kJ/mol, 170 kJ/mol and 90 kJ/mol respectively). The peak shape and desorption rate data suggests that a second order diffusion limited reaction controls the ε→ε+δ desorption, a first order interface limited reaction controls ε+δ→δ, and a surface limited zeroth order reaction limits the desorption of the δ+α phases. The analysis suggests that, at least for δ→α regime, engineering solutions for improved thermal stability should focus on reductions in surface reactivity.
氢化铪粉末的氢解吸动力学
结合实验和密度泛函理论研究了氢化铪释放氢气的动力学。该材料是紧凑型核反应堆的候选中子屏蔽,氢气释放会导致缓和功能下降。在实验中,我们使用热重计和 X 射线衍射法研究了ε相 (HfH2-x) 粉末在 25 至 1000 °C 温度范围内的分解过程。等温加热显示出 3 个特征解吸峰,分别对应于 350、415 和 700 °C时各相(ε-HfH2-x、δ-HfH1.6-x 和 α-Hf)氢的释放。密度泛函理论的建模结果充分证明了这一点。通过基辛格分析,可以计算出解吸活化能(分别为 150 kJ/mol、170 kJ/mol 和 90 kJ/mol)。峰形和解吸速率数据表明,二阶扩散受限反应控制着 ε→ε+δ 的解吸,一阶界面受限反应控制着 ε+δ→δ 的解吸,而表面受限的零阶反应限制着 δ+α 相的解吸。分析表明,至少对于 δ→α 体系,提高热稳定性的工程解决方案应侧重于降低表面反应速度。
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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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