Gas permeability of SiC/SiC composites as fusion reactor material

During the operation of a fusion reactor, a certain type of transients could induce rapid cooldown of the reactor with relatively high or increasing system pressure. This induces a high tensile stress at the inner surface of the blanket, which is called the thermal shock. Test Blanket Module (TBM) has been designed to account for the performance of DEMO-relevant blanket. But, the TBM uses helium as coolant and tritium as purge gas, and FM steel, SiC f / SiC composites as a structural material. The SiC f / SiC composites with a SiC sub-layer/ PyC interlayers were therefore fabricated in order to improve the oxidation resistance. In the refractory field SiC f / SiC composites need to investigate residual stress and thermal shock behavior when high chemical stability and corrosion resistance are necessary. In this study, SiC f / SiC composite were fabricated by NITE process and the chemical vapor infiltration (CVI) method. SiC f / SiC composites have been examined and the detail analyses of the microstructure and the mechanical strength were conducted. Various pyrolytic carbons ( PyC ) with SiC interlayer coatings were applied to the composites for improvement of the mechanical properties at the interface.

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Hydrogen trapping in and release from tungsten: Modeling and comparison with graphite with regard to its use as fusion reactor material

Journal of Nuclear Materials ◽

10.1016/s0022-3115(96)00664-2 ◽

1997 ◽

Vol 241-243 (1) ◽

pp. 1082-1086 ◽

Cited By ~ 10

Author(s):

P Franzen

Keyword(s):

Fusion Reactor ◽

Hydrogen Trapping ◽

Reactor Material

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Effect of Shielding Design Margin on the Quantity of Fusion Reactor Material

Fusion Technology ◽

10.13182/fst99-a91 ◽

1999 ◽

Vol 36 (1) ◽

pp. 52-61

Author(s):

Koichi Maki ◽

Chikara Konno ◽

Fujio Maekawa ◽

Hiroshi Maekawa ◽

Katsumi Hayashi ◽

...

Keyword(s):

Fusion Reactor ◽

Reactor Material ◽

Shielding Design ◽

Design Margin

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Helium gas permeability of SiC/SiC composite used for in-vessel components of nuclear fusion reactor

Fusion Engineering and Design ◽

10.1016/j.fusengdes.2005.01.002 ◽

2005 ◽

Vol 73 (1) ◽

pp. 51-56 ◽

Cited By ~ 34

Author(s):

T. Hino ◽

E. Hayashishita ◽

Y. Yamauchi ◽

M. Hashiba ◽

Y. Hirohata ◽

...

Keyword(s):

Fusion Reactor ◽

Gas Permeability ◽

Nuclear Fusion ◽

Nuclear Fusion Reactor ◽

Helium Gas

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Electrophoretic deposition in the production of SiC/SiC composites for fusion reactor applications

Journal of the European Ceramic Society ◽

10.1016/j.jeurceramsoc.2008.04.004 ◽

2008 ◽

Vol 28 (14) ◽

pp. 2801-2807 ◽

Cited By ~ 35

Author(s):

Saša Novak ◽

Katja Rade ◽

Katja König ◽

Aldo R. Boccaccini

Keyword(s):

Electrophoretic Deposition ◽

Fusion Reactor ◽

Sic Composites

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SiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment Conditions

Advances in Science and Technology ◽

10.4028/www.scientific.net/ast.73.27 ◽

2010 ◽

Vol 73 ◽

pp. 27-35 ◽

Cited By ~ 2

Author(s):

C.H. Chen ◽

J.J. Kai ◽

F.R. Chen ◽

Y. Katoh

Keyword(s):

Fusion Reactor ◽

Energy Shift ◽

Average Diameter ◽

Irradiation Temperature ◽

Number Density ◽

The Matrix ◽

Irradiation Behaviour ◽

Sic Composites ◽

Electron Energy Loss ◽

Small Bubbles

We developed a new method to quantify the He atoms in the SiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment Conditions. We focus on the cavities measurements of the energy shift of the He K-edge of the electron energy loss spectrum. The method is based on mapping the density of He atoms inside the measured bubbles. Combining with the number density and the average diameter of the cavities, we are able to distinguish and estimate the amount of He atoms in the cavities and in the matrix, respectively. We found that small bubbles contain much higher density of He atoms than the larger ones. At irradiation temperature above 1000oC, all the He atoms are trapped inside the bubbles. On the contrary, it is not the case at the lower irradiation temperature.

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