From High-Entropy Alloys to High-Entropy Ceramics: The Radiation-Resistant Highly Concentrated Refractory Carbide (CrNbTaTiW)C

Tunes, Matheus A.; Fritze, Stefan; Osinger, Barbara; Willenshofer, Patrick; Alvarado, Andrew; Martínez, E.; Menon, Ashok S.; Ström, Petter; Greaves, Graeme; Lewin, Erik; Jansson, Ulf; Pogatscher, Stefan; Saleh, Tarik A.; Vishnyakov, Vladimir; El-Atwani, Osman

doi:10.2139/ssrn.4349924

Cited by 1 publication

(3 citation statements)

References 96 publications

(115 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…39 Xe bubbles (∼2.1 nm) were observed in (CrNbTaTiW)C after 300 keV Xe + irradiation at 300 °C for 10 dpa, which are much smaller than those observed in nuclear fuel ceramics such as UO 2 or U 3 Si 2 . 46…”

Section: B Radiation-induced Defect Clusters and Gas Bubblesmentioning

confidence: 99%

“…For instance, the chemical compositions of metal elements still show a uniform distribution across the grain boundaries in 3 MeV Zr 2+ irradiated (ZrNbTaTi)C at 25, 300, and 500 °C37 as well as 300 keV Xe + irradiated (CrNbTaTiW)C at 300 °C according to energy dispersive spectrometry (EDS) analysis. 46 Nevertheless, these RIS studies were conducted with heavy ions to emulate the irradiation damage caused by neutrons in the actual reactors. Due to differences in displacement efficiencies between neutrons and heavy ions, 48 additional studies may be needed to evaluate the RIS resistance in the CCC under neutron irradiation.…”

Section: Influence Of Grain Boundariesmentioning

confidence: 99%

“…It is also observed that the nanocrystalline (CrNbTaTiW)C with a grain size of 9.8 nm exhibits no dislocation loops after irradiation with 300 keV Xe + ions at 300 °C. 46 However, grain growth may also occur in the nanocrystalline CCC at elevated temperatures, as shown in nanocrystalline (CrNbTaTiW)C.…”

Section: Influence Of Grain Boundariesmentioning

confidence: 99%

See 2 more Smart Citations

Compositionally complex carbide ceramics: A perspective on irradiation damage

Trinh,

Wang,

Bawane

et al. 2024

Journal of Applied Physics

View full text Add to dashboard Cite

Extensive experimental and computational studies have demonstrated outstanding physical and chemical properties of the novel materials of compositionally complex carbides (CCCs), enabling their promising applications in advanced fission and fusion energy systems. This perspective provides a comprehensive overview of radiation damage behavior reported in the literature to understand the fundamental mechanisms related to the impact of multi-principal metal components on phase stability, irradiation-induced defect clusters, irradiation hardening, and thermal conductivity of compositionally complex carbides. Several future research directions are recommended to critically evaluate the feasibility of designing and developing new ceramic materials for extreme environments using the transformative “multi-principal component” concept. Compared to the existing materials for nuclear applications including stainless steels, nickel alloys, ZrC, SiC, and potentially high-entropy alloys, as well as certain other compositionally complex ceramic families. CCCs appear to be more resistant to amorphization, growth of irradiation defect clusters, and void swelling.

show abstract

Section: B Radiation-induced Defect Clusters and Gas Bubblesmentioning

confidence: 99%

Section: Influence Of Grain Boundariesmentioning

confidence: 99%