Swelling behaviour and TEM studies of SiCf/SiC composites after fusion relevant helium implantation

Scholz, H.W.; Rebelo, A.J. Frias; Rickerby, D. G.; Krogul, P.; Lee, W.E.; Evans, John H.; Fenici, P.

doi:10.1016/s0022-3115(98)00221-9

Cited by 13 publications

(4 citation statements)

References 5 publications

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“…Using dual-beam iron irradiation technology [1], potentially significant effects of He on swelling in SiC [20,21] increasing quantity of He in irradiated SiC composites due to the fact that helium triggers point-defect swelling [1]. The formation of He bubbles was observed in SiC crystals by irradiation with He ion at high temperature [12].…”

Section: Introductionmentioning

confidence: 99%

He–vacancy interaction and multiple He trapping in small void of silicon carbide

Zhang

et al. 2015

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

He–vacancy interaction and multiple He trapping in small void of silicon carbide

Zhang

et al. 2015

Journal of Nuclear Materials

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“…Cyclotron facilities (>10 MeV light ion accelerators) had been extensively used in fusion programmes to study He-embrittlement [11][12][13]. Thanks to an energy degrader, α-particles can be uniformly implanted within ~100 µm thick specimens to concentrations of several 1000 appm He [6,14], allowing for mechanical testing [15][16][17].…”

Section: Cyclotrons and α-Particle Implantationmentioning

confidence: 99%

Materials testing facilities and programmes for fission and ion implantation damage

et al. 2017

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Currently there is no fusion neutron dedicated source with a high enough flux to mimic irradiation conditions relevant to those to be experienced by the First Wall in a fusion reactor. Nevertheless, very valuable information can be obtained from existing irradiation sources, in particular Materials Test Reactors, Fast neutron reactors and Ion accelerators. Partial information is provided by these irradiation facilities that can be used to down select main materials candidates for DEMO fusion reactors and evaluate their performance under limited conditions. Modelling is an indispensable tool to interpret all the available information and build a test matrix of experiments to be carried out in a dedicated fusion neutron source.Available tools for testing materials exposed to ion or neutron irradiation, including their advantages and limitations when mimicking fusion conditions, are discussed in this paper. Next generation of fusion devices, such as DEMO, will need the input provided by a dedicated fusion neutron source to enable them to proceed in an efficient and safe manner to reach their full mission and performance.

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“…These bubbles appeared in the SiC matrix only and not in the SiC fibers. Scholz et al 10 injected He to 2,500 appm in SiC composites at 1175 K. They observed swelling of the matrix but contraction of the fibers. They concluded that the presence of the He may suppress annealing of structural damage at that temperature.…”

Section: Radiation Effectsmentioning

confidence: 99%

Tritium Inventory in ARIES-AT

Longhurst¹

2001

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This report documents an investigation into the tritium inventory expected in the ARIES-AT fusion reactor. ARIES-AT features silicon carbide fibers in a silicon carbide matrix as its primary construction. It uses the same fusion power core as the previous ARIES-RS. Based on experimental results of several researchers, consideration was given to swelling, sputtering, film coatings, erosion, and implantation. Estimates were made of tritium inventory using the TMAP4 code. About 700 g of tritium may be expected in the machine, two thirds of which would reside in the first wall. Under assumed accident conditions that involve firs wall temperatures up to 1000°C, evolution of retained tritium may be expected to vary from 0.8 to nearly 40 percent depending on the temperature of the first wall.v CONTENTS

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Swelling behaviour and TEM studies of SiCf/SiC composites after fusion relevant helium implantation

Cited by 13 publications

References 5 publications

He–vacancy interaction and multiple He trapping in small void of silicon carbide

He–vacancy interaction and multiple He trapping in small void of silicon carbide

Materials testing facilities and programmes for fission and ion implantation damage

Tritium Inventory in ARIES-AT

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