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

1997 ◽  
Vol 241-243 (1) ◽  
pp. 1082-1086 ◽  
Author(s):  
P Franzen
1999 ◽  
Vol 36 (1) ◽  
pp. 52-61
Author(s):  
Koichi Maki ◽  
Chikara Konno ◽  
Fujio Maekawa ◽  
Hiroshi Maekawa ◽  
Katsumi Hayashi ◽  
...  

2011 ◽  
Vol 25 (31) ◽  
pp. 4212-4215
Author(s):  
HAN-KI YOON ◽  
HO-JUN CHO ◽  
AKIRA KOHYAMA ◽  
TETSUJI NODA

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.


2002 ◽  
Vol 61-62 ◽  
pp. 699-704 ◽  
Author(s):  
Y Hirohata ◽  
T Jinushi ◽  
Y Yamauchi ◽  
M Hashiba ◽  
T Hino ◽  
...  

Author(s):  
E. Ruedl ◽  
P. Schiller

The low Z metal aluminium is a potential matrix material for the first wall in fusion reactors. A drawback in the application of A1 is the rel= atively high amount of He produced in it under fusion reactor conditions. Knowledge about the behaviour of He during irradiation and deformation in Al, especially near the surface, is therefore important.Using the TEM we have studied Al disks of 3 mm diameter and 0.2 mm thickness, which were perforated at the centre by double jet polishing. These disks were bombarded at∽200°C to various doses with α-particles, impinging at any angle and energy up to 1.5 MeV at both surfaces. The details of the irradiations are described in Ref.1. Subsequent observation indicated that in such specimens uniformly distributed He-bubbles are formed near the surface in a layer several μm thick (Fig.1).After bombardment the disks were deformed at 20°C during observation by means of a tensile device in a Philips EM 300 microscope.


Nature ◽  
2010 ◽  
Author(s):  
Emiliano Feresin
Keyword(s):  

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