scholarly journals Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets

2021 ◽  
Vol 29 ◽  
pp. 101058
Author(s):  
Ruggero Forte ◽  
Pierluigi Chiovaro ◽  
Pietro Alessandro Di Maio ◽  
Nasr Ghoniem
Keyword(s):  
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.


2021 ◽  
Vol 27 ◽  
pp. 100978
Author(s):  
M. Moscheni ◽  
M. Carr ◽  
S. Dulla ◽  
F. Maviglia ◽  
A. Meakins ◽  
...  

2007 ◽  
Vol 82 (1) ◽  
pp. 35-40 ◽  
Author(s):  
Zhang-Jian Zhou ◽  
Zhi-Hong Zhong ◽  
Chang-Chun Ge

2015 ◽  
Vol 1769 ◽  
Author(s):  
C.E. Velasquez ◽  
M. A. F. Veloso ◽  
A. L. Costa ◽  
C. Pereira

ABSTRACTThe displacement per atom (dpa) has been a specific issue to evaluate the damage in the first wall of the Tokamak. Two different first wall materials were evaluated. In this study, MCNP5 code was used to obtain the neutron flux, the energy deposition and the main reaction rates, on the inboard and outboard first wall. The damage calculations were performed by the SPECTER code using the neutronic parameters obtained by MCNP5. The Tokamak reactor modeled has similar dimensions to the ITER. Tungsten and beryllium alloys were simulated on the outboard first wall. The results indicate which material has a higher resistance to be damage and dpa values for the analyzed material.


2009 ◽  
Vol 390-391 ◽  
pp. 963-966 ◽  
Author(s):  
P.C. Stangeby ◽  
R. Mitteau
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1987 ◽  
Vol 12 (1) ◽  
pp. 104-113 ◽  
Author(s):  
K. Taghavi ◽  
M. S. Tillack ◽  
H. Madarame

2015 ◽  
Vol 100 ◽  
pp. 2-43 ◽  
Author(s):  
Mohamed Abdou ◽  
Neil B. Morley ◽  
Sergey Smolentsev ◽  
Alice Ying ◽  
Siegfried Malang ◽  
...  
Keyword(s):  

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