A platform for research: civil engineering, architecture and urbanism
A platform for research: civil engineering, architecture and urbanism
Impact of water ingress on deuterium release, oxidation, and dust generation in beryllium plasma-facing components
Beryllium samples from the JET ITER-like wall limiter tiles with either co-deposits or surface cracks caused by melt damage, were immersed into boiling water for 4 h 15 min to simulate and assess the impact of coolant water ingress into a tokamak on the state of Be components. Microscopy of the water-treated surfaces and the lack of residue in the water revealed that no thermomechanical damage (cracking or exfoliation) occurred to the samples during the exposure. Ion beam analysis showed no measurable release of deuterium from the samples. Combined ion beam analysis and Raman spectroscopy indicated only some degree of surface oxidation, but no thick oxide films were formed.
Impact of water ingress on deuterium release, oxidation, and dust generation in beryllium plasma-facing components
Beryllium samples from the JET ITER-like wall limiter tiles with either co-deposits or surface cracks caused by melt damage, were immersed into boiling water for 4 h 15 min to simulate and assess the impact of coolant water ingress into a tokamak on the state of Be components. Microscopy of the water-treated surfaces and the lack of residue in the water revealed that no thermomechanical damage (cracking or exfoliation) occurred to the samples during the exposure. Ion beam analysis showed no measurable release of deuterium from the samples. Combined ion beam analysis and Raman spectroscopy indicated only some degree of surface oxidation, but no thick oxide films were formed.
Impact of water ingress on deuterium release, oxidation, and dust generation in beryllium plasma-facing components
Y. Zayachuk (author) / N. Catarino (author) / C. Smith (author) / I. Jepu (author) / C. Ayres (author) / A. Widdowson (author) / E. Alves (author) / M. Rubel (author)
2023
Article (Journal)
Electronic Resource
Unknown
Metadata by DOAJ is licensed under CC BY-SA 1.0
Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials
| DOAJ | 2021
Oxide microstructure and deuterium ingress in Zr-2.5Nb CANDU® pressure tubes
| British Library Online Contents | 2003