He, Ne, Ar-bombardment of carbon first wall structures

2005 ◽  
Vol 228 (1-4) ◽  
pp. 319-324 ◽  
Author(s):  
P. Träskelin ◽  
K. Nordlund ◽  
J. Keinonen
Keyword(s):  
First Wall ◽  
Wall Structures

Implantation Measurements to Determine Tritium Permeation in First Wall Structures

1983 ◽  
Vol 4 (2P2) ◽  
pp. 677-680
Author(s):  
D. F. Holland ◽  
R. A. Causey ◽  
M. L. Sattler
Keyword(s):  
First Wall ◽  
Wall Structures ◽  
Tritium Permeation

scholarly journals Hydrogen uptake in vanadium first wall structures

1996 ◽  
Author(s):  
E P Simonen ◽  
R H Jones
Keyword(s):  
Hydrogen Uptake ◽  
First Wall ◽  
Wall Structures

An evaluation of the application of fracture mechanics procedures to fusion first wall structures

1981 ◽  
Vol 103 ◽  
pp. 149-154 ◽  
Author(s):  
G.R. Odette ◽  
R.O. Ritchie ◽  
P. McConnell ◽  
W. Server
Keyword(s):  
Fracture Mechanics ◽  
First Wall ◽  
Wall Structures

Failure of first wall structures by fatigue crack growth

1988 ◽  
Vol 155-157 ◽  
pp. 679-682 ◽  
Author(s):  
E. Diegele ◽  
T. Fett ◽  
D. Munz ◽  
H. Stamm
Keyword(s):  
Fatigue Crack ◽  
Fatigue Crack Growth ◽  
Crack Growth ◽  
First Wall ◽  
Wall Structures

Elastic-Plastic Analysis of Slender First Wall Structures

1985 ◽  
Vol 8 (1P2A) ◽  
pp. 586-591
Author(s):  
G.E. Orient ◽  
P.J. Gierszewski ◽  
J.K. Garner
Keyword(s):  
First Wall ◽  
Elastic Plastic ◽  
Wall Structures ◽  
Plastic Analysis

High Temperature Strength of Three ODS Ferritic/ Martensitic Steels

2007 ◽  
Vol 345-346 ◽  
pp. 1011-1014 ◽  
Author(s):  
Han Ki Yoon ◽  
Akihiko Kimura
Keyword(s):  
High Temperature ◽  
Fusion Reactor ◽  
Martensitic Steel ◽  
Operating Temperature ◽  
Oxide Dispersion Strengthened ◽  
High Temperature Strength ◽  
Martensitic Steels ◽  
First Wall ◽  
Wall Structures ◽  
Interesting Approach

Oxide dispersion strengthened (ODS) materials is leading candidates for blanket/first-wall structures of the fusion reactor. ODS materials for structure application in fusion rector would allow to increase the operating temperature to approximately 650. Therefore, this work focused on the optimization of metallurgical features to improve high temperature strength and elongation through understanding of contents of Cr and Al. In the study, the three kinds of ODS steels such as 19Cr-ODS (K1), 13Cr-Al-ODS (K2) and 19Cr-Al-ODS (K4) with Y2O3 content of 0.37wt% have been produced. And tensile test were performed on three ODS ferritic/martensitic steel between RT, 300, 400 and 600Dispersion hardening represents an interesting approach to improve the mechanical properties at elevated temperature, as they are foreseen in the future fusion reactor It has been successfully demonstrated that it is possible to expanse the temperature range for the application of fusion reactor.

Impact of COMPASS-U vacuum vessel and the first wall structures on signals of in-vessel magnetic diagnostic coils

2021 ◽  
Vol 171 ◽  
pp. 112579
Author(s):  
V. Kindl ◽  
T. Markovič ◽  
P. Turjanica ◽  
I. Ďuran ◽  
V. Weinzettl ◽  
...  
Keyword(s):  
Vacuum Vessel ◽  
First Wall ◽  
Wall Structures

Low Cycle Fatigue Lifetime of HIP Bonded Bi-metallic First Wall Structures of Fusion Reactors

1998 ◽  
Vol 35 (10) ◽  
pp. 705-711
Author(s):  
Toshihisa HATANO ◽  
Satoshi SATO ◽  
Toshiyuki HASHIMOTO ◽  
Kazunori KITAMURA ◽  
Kazuyuki FURUYA ◽  
...  
Keyword(s):  
Low Cycle Fatigue ◽  
Fusion Reactors ◽  
Cycle Fatigue ◽  
First Wall ◽  
Fatigue Lifetime ◽  
Wall Structures
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