Comparison of the mechanical behaviour of SiCf/SiC composites following neutron irradiation and helium implantation

Rebelo, A.J. Frias; Scholz, H.W.; Kolbe, H.; Tartaglia, G.P.; Fenici, P.

doi:10.1016/s0022-3115(98)00177-9

Cited by 22 publications

(1 citation statement)

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“…From the viewpoint of fusion structural applications, mechanical properties [2] [3], fabrication and joining [4] and neutron and/or helium irradiation behavior [5]- [8] of SiC materials have been evaluated. The characteristics of the interaction between hydrogen isotopes and structural material of blanket are needed for the design of reactors.…”

Section: Introductionmentioning

confidence: 99%

Hydrogen isotopes permeation evaluation in the advanced material for nuclear fusion blanket use

Minami

Niigawa

Ueno

et al. 2007

2007 IEEE 22nd Symposium on Fusion Engineering

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Behavior of hydrogen isotopes such as permeation, diffusion, and dissolution infusion blanket materials were investigatedfrom a viewpoint of the material development and a material design for a fusion reactor. Experiments were conducted with Reduced Activation Ferritic Steel (F82H) and various kinds ofSiC materials at elevated temperature. To evaluate permeability of SiC materials and RAFM, deuterium gas permeability was measured using newly designed device. Permeation of hydrogen through RAFM was not significantly different from that of Austenitic Steel, however the temperature dependence of the permeability diffusivity, and solubility showed marked discontinuous change around 850 degree C. Change in crystal structure from bec to fcc is a suspected cause. The measurement ofpermeability of deuterium gas in Hexoloy and CVD SiC samples were attempted at the temperature above 800 degree C. The permeability and deuterium diffusivity of Hexoloy is 2 orders of magnitude smaller than that of CVD SiC. On the pressure dependence of permeability, both linear and square-root dependence were seen.

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