Resistance to Helium Bubble Formation in Amorphous SiOC/Crystalline Fe Nanocomposite

Su, Qing; Wang, Tianyao; Gigax, Jonathan; Shao, Lin; Nastasi, M.

doi:10.3390/ma12010093

“…Su et al . examined the radiation tolerance of amorphous SiOC and α‐Fe (Fe/SiOC) multilayer nanocomposites at 600 °C that exhibit smaller void sizes and more swelling resistance in contrast to pure Fe films [104] . Hardly obvious voids are found in the Fe layer of the thin Fe/SiOC nanocomposites, indicating the Fe/SiOC interface facilitates point defect recombination and suppresses void swelling.…”

Section: Hetero‐phase Interfaces In Nanomaterialsmentioning

confidence: 99%

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

Su

¹

,

Jiang

²

,

Li

³

et al. 2022

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Interfaces including grain boundaries and heterophase interfaces could withstand the radiation damage via providing sites for trapping the defects. With the urgent demand for high radiation-tolerance nanostructured materials, exploration of the structural properties, especially the role of the interfaces on the radiation response in the nanomaterials, is of significant essentialness in developing the design of new radiation-resistant materials. Herein, the recent progress and development of two main kinds of interfaces, namely the grain boundaries in nanocrystalline and the hetero-phase interfaces in nanolayered materials and nano-composites, in nanostructured materials that are designed for radiation tolerance are summarized. In addition, the radiation response and resistant mechanism under irradiation conditions of the nanocrystalline materials like metals, single-phase alloys, and ceramics, as well as the nanocomposites like nanolayered metals, nanolayered ceramics, metal-carbon nanocomposite, and nanoparticle dispersed steels, are reviewed. Finally, challenges and perspectives are proposed to offer advice for the development of radiation resistance nanomaterials.

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“…To this end, various materials (such as W [47][48][49][50], addition of Rh in W [51], use of bcc Fe [52,53], Ta [54], W-Ta [55], Ta/Fe [56], Pd [57], nanocrystalline Cu [58], SiOC/Crystalline Fe nanocomposite [59], W-K [60], reduced activation steel [61], ferritic [62], ferritic/martensitic steels [63], Be pebbles [64][65][66][67], Be and beryllides [68], graphite, carbon fiber composite [69]) and high Z atoms (Zr, No, Mo, Hf, Ta) [70] have been tested but none proved satisfactory [71][72][73][74]. All show rapid surface degradation exhibiting surface blisters [75][76][77][78] and formation of fuzz [51,[79][80][81][82] or under dense nanostructure [40] after bubble.…”

Section: Introductionmentioning

confidence: 99%

Plasma Facing Material by Self-Interstitial Solid Solution Strengthening – Problem, Proposition, and a Solution

Rafique¹

2023

Preprint

0

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Bubble (point defect) – a precursor of fuzz or under dense nanostructure formation is crystal lattice defect. Suitable selection of crystal lattice which inhibit Frenkel pair generation and intrinsically promotes selfinterstitial solid solution strengthening contributes effectively towards making plasma facing material. For this, interstitial sites, their size, amount / fraction, positions, tendency of occupation and diffusion parameters (e.g. activation energies (Q), activation volumes) are determined. Fcc iron carbon alloys (austenitic stainless steels AISI / SAE 321, fcc structure, Pearson code cF4, space group Fm3̅m) are proposed as suitable candidates. Along with their room temperature fcc structure having 12 interstitial positions (4 octahedral, 6 coordination sites and 8 tetrahedral, 4 coordination sites / unit cell) to allow insertion of self (iron) atoms, they have excellent corrosion resistance, thermal conductivity, and nonmagnetic properties. After their melting, casting, and machining to required dimensions and geometry, stabilizing heat treatment is applied to precipitate all carbon as TiC and prevent formation of Cr23C6 (sensitization). This resist heat and surface degradation and yield excellent architecture which not only inhibit Frankel pair generation but will also allow bulk assimilation or surface annihilation (loop punching) of this lattice point defect. A superior thermal, fluid, and structural design augment above

show abstract

“…To this end, various materials (such as W [47][48][49][50], addition of Rh in W [51], use of bcc Fe [52,53], Ta [54], W-Ta [55], Ta/Fe [56], Pd [57], nanocrystalline Cu [58], SiOC/Crystalline Fe nanocomposite [59], W-K [60], reduced activation steel [61], ferritic [62], ferritic/martensitic steels [63], Be pebbles [64][65][66][67], Be and beryllides [68], graphite, carbon fiber composite [69]) and high Z atoms (Zr, No, Mo, Hf, Ta) [70] have been tested but none proved satisfactory [71][72][73][74]. All show rapid surface degradation exhibiting surface blisters [75][76][77][78] and formation of fuzz [51,[79][80][81][82] or under dense nanostructure [40] after bubble.…”

Section: Introductionmentioning

confidence: 99%

Plasma Facing Material by Self-Interstitial Solid Solution Strengthening – Problem, Proposition, and a Solution

Rafique¹

2020

Preprint

0

View full text Add to dashboard Cite

Bubble (point defect) – a precursor of fuzz or under dense nanostructure formation is crystal lattice defect. Suitable selection of crystal lattice which inhibit Frenkel pair generation and intrinsically promotes selfinterstitial solid solution strengthening contributes effectively towards making plasma facing material. For this, interstitial sites, their size, amount / fraction, positions, tendency of occupation and diffusion parameters (e.g. activation energies (Q), activation volumes) are determined. Fcc iron carbon alloys (austenitic stainless steels AISI / SAE 321, fcc structure, Pearson code cF4, space group Fm3̅m) are proposed as suitable candidates. Along with their room temperature fcc structure having 12 interstitial positions (4 octahedral, 6 coordination sites and 8 tetrahedral, 4 coordination sites / unit cell) to allow insertion of self (iron) atoms, they have excellent corrosion resistance, thermal conductivity, and nonmagnetic properties. After their melting, casting, and machining to required dimensions and geometry, stabilizing heat treatment is applied to precipitate all carbon as TiC and prevent formation of Cr23C6 (sensitization). This resist heat and surface degradation and yield excellent architecture which not only inhibit Frankel pair generation but will also allow bulk assimilation or surface annihilation (loop punching) of this lattice point defect. A superior thermal, fluid, and structural design augment above

show abstract

Resistance to Helium Bubble Formation in Amorphous SiOC/Crystalline Fe Nanocomposite

Cited by 10 publications

References 33 publications

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

Plasma Facing Material by Self-Interstitial Solid Solution Strengthening – Problem, Proposition, and a Solution

Plasma Facing Material by Self-Interstitial Solid Solution Strengthening – Problem, Proposition, and a Solution

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