A review of surface damage/microstructures and their effects on hydrogen/helium retention in tungsten

Li, Yonggang; Zheng, Quan; Wei, Lin‐Heng; Zhang, Chuanguo; Zhang, Zhi

doi:10.1007/s42864-020-00042-w

Cited by 43 publications

(9 citation statements)

References 346 publications

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“…[1][2][3] Specifically, in contrast to the near surface damage induced by plasma and heat, the neutron irradiation leads to the formation of radiation damage homogenously in the bulk system that dramatically affects the performance of W-PFMs, which has strong impact on the safety and economic efficiency of future fusion power plant. [4][5][6][7] Microscopically, neutron radiation damage is mainly originated from the displacement damage, producing numerous irradiation-induced defects in materials, such as vacancies, self-interstitial atoms (SIAs) and their clusters. These defects will interact with each other and intrinsic defects/impurities, which should be responsible for the microstructure evolution and performance variation of materials under neutron irradiation.…”

Section: Introductionmentioning

confidence: 99%

Influence of helium on the evolution of irradiation-induced defects in tungsten: An object kinetic Monte Carlo simulation*

Hou¹,

Li²,

Li³

et al. 2021

Chinese Phys. B

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Understanding the evolution of irradiation-induced defects is of critical importance for the performance estimation of nuclear materials under irradiation. Hereby, we systematically investigate the influence of He on the evolution of Frenkel pairs and collision cascades in tungsten (W) via using the object kinetic Monte Carlo (OKMC) method. Our findings suggest that the presence of He has significant effect on the evolution of irradiation-induced defects. On the one hand, the presence of He can facilitate the recombination of vacancies and self-interstitial atoms (SIAs) in W. This can be attributed to the formation of immobile He-SIA complexes, which increases the annihilation probability of vacancies and SIAs. On the other hand, due to the high stability and low mobility of He-vacancy complexes, the growth of large vacancy clusters in W is kinetically suppressed by He addition. Specially, in comparison with the injection of collision cascades and He in sequential way at 1223 K, the average sizes of surviving vacancy clusters in W via simultaneous way are smaller, which is in good agreement with previous experimental observations. These results advocate that the impurity with low concentration has significant effect on the evolution of irradiation-induced defects in materials, and contributes to our understanding of W performance under irradiation.

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Section: Introductionmentioning

confidence: 99%

Influence of helium on the evolution of irradiation-induced defects in tungsten: An object kinetic Monte Carlo simulation*

Hou¹,

Li²,

Li³

et al. 2021

Chinese Phys. B

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“…Since no intense neutron source with the expected energy spectrum was available, fission neutron irradiation and high energy ion implantation were used to mimic the aspects of the interaction of neutrons with tungsten [13,14]. Since then, a plethora of experimental and theoretical studies were conducted to address the issue of displacement damage creation and evolution, transmutation, helium accumulation, and the consequences on the material properties such as hydrogen isotope retention, but also thermal conductivity and mechanical properties [15][16][17][18][19]. This contribution critically reviews the existing data for a very fundamental aspect of the interaction of fusion neutrons with tungsten: the evolution of displacement damage with damage dose and its consequences on hydrogen isotope retention.…”

Section: Introductionmentioning

confidence: 99%

A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose

Schwarz-Selinger

2023

Mater. Res. Express

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Experimental results from the literature on the evolution of deuterium retention in displacement-damaged tungsten as a function of damaging dose are presented. Except for a few outliers, retention is generally found to increase with the presence of displacement damage. However, total retention results scatter by three orders of magnitude for similar exposure temperatures and are difficult to compare, because they depend on experiment-specific parameters such as the irradiation energy used to produce the displacement damage or the deuterium exposure parameters such as fluence. Even local deuterium concentration measurements were found to scatter by more than one order of magnitude. An experimental methodology is proposed that allows robust conclusions about the evolution of deuterium retention with damage dose and the results are discussed in detail. Recrystallized tungsten is irradiated with 20.3 MeV self-ions at room temperature with different damage doses ranging from 0.001 to 2.3 displacements per atom. The defects are then decorated with a low flux, low-energy deuterium plasma at 450 K sample temperature. 3He Nuclear Reaction Analysis (NRA) shows that the deuterium concentration levels off from the linear increase already at very low damage dose of about 0.005 dpa. At a damage dose of 0.23 dpa a maximum deuterium concentration of about 1.4 at% is reached. Thermal Desorption Spectroscopy (TDS) shows that with damage increasing above 0.005 dpa, the overall shape of the desorption spectra does not change substantially, only their intensities increase. Total amounts derived from TDS are in quantitative agreement with results from 3He-NRA. Experimental results following this methodology also agree quantitatively with very recent parameter-free modeling of damage evolution.

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“…Tungsten is viewed as one of the favorite plasma-facing materials (PFMs) in future fusion reactors [ 1 , 2 , 3 ]. However, tungsten’s widespread application is limited due to its high ductile-to-brittleness temperature, recrystallization brittleness, and irradiation-induced brittleness [ 4 , 5 , 6 ]. Preparing laminated composite has been proven an effective way to improve the low-temperature toughness of W [ 1 , 7 , 8 , 9 , 10 , 11 ].…”

Section: Introductionmentioning

confidence: 99%

Effect of Transition Metal Layer on Bending and Interfacial Properties of W/TiN/Ta-Laminated Composite

Cai

Wang

et al. 2023

Materials

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The widespread applications of W in the fusion reactor are limited by its low-temperature brittleness, recrystallization brittleness, and irradiation-induced brittleness. Many toughening methods were used to improve the brittleness of W, such as adding second-phase particles, adding W fibers, preparing laminated composite, and so on. Among these, preparing laminated W-based composites has been proven to effectively improve both the low-temperature and high-temperature toughness of W. In this study, W/M/TiN/Ta-laminated composites with transition metal layer (M) were synthesized through the spark plasma sintering (SPS) at three different temperatures. The effects of nano-scale (Ni, Ti, and Cr) and micron-scale (Ni, Ti, and V) transition layers on the bending and interfacial properties of the W/M/TiN/Ta composite were studied via an electron probe micro-analyzer (EPMA) and transmission electron microscope (TEM). Compared with W/TiN/Ta, the flexural strength and strain of W/Ninm/TiN/Ta were increased by 25.6% and 17.6%, respectively. Ni, Ti, and V micron transition layers can improve the combination of the W–TiN interface and decrease the joining temperature. The micron V layer has the best strengthening effect. The flexural strength of W/V/TiN/Ta reached 1294 MPa, much higher than W/Ta’s 1041 MPa.

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A review of surface damage/microstructures and their effects on hydrogen/helium retention in tungsten

Cited by 43 publications

References 346 publications

Influence of helium on the evolution of irradiation-induced defects in tungsten: An object kinetic Monte Carlo simulation*

Influence of helium on the evolution of irradiation-induced defects in tungsten: An object kinetic Monte Carlo simulation*

A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose

Effect of Transition Metal Layer on Bending and Interfacial Properties of W/TiN/Ta-Laminated Composite

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