scholarly journals High Temperature Zirconium Alloys for Fusion Energy

2021 ◽  
pp. 153431
Author(s):  
DJM King ◽  
AJ Knowles ◽  
D Bowden ◽  
MR. Wenman ◽  
S. Capp ◽  
...  
Author(s):  
Dennis Whyte

The advantages of high magnetic fields in tokamaks are reviewed, and why they are important in leading to more compact tokamaks. A brief explanation is given of what limits the magnetic field in a tokamak, and why high temperature superconductors (HTSs) are a game changer, not just because of their higher magnetic fields but also for reasons of higher current density and higher operating temperatures. An accelerated pathway to fusion energy is described, defined by the SPARC and ARC tokamak designs. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.


Author(s):  
Jan Škarohlíd ◽  
Radek Škoda

Polycrystalline diamond coating is a promising possibility for prevention, or reduction of high temperature oxidation of zirconium alloys. Zirconium alloys are used as cladding material in almost all types of nuclear reactors, where creates a barrier between nuclear fuel and cooling water in the primary circuit. Hydrogen and considerable amount of heat is released during steam oxidation that may occur in an eventual accident. In this paper Zircaloy-2 alloy was covered by polycrystalline diamond layer using Plasma Enhanced Linear Antennas Microwave Chemical Vapor Deposition system reactor. X-Ray Diffraction and Raman spectroscopy measurements confirmed coverage of the surface area with crystalline and amorphous carbon layer. Characterizations were done for zirconium alloy covered with diamond layer before and after corrosion and irradiation tests - ion beam irradiation tests and high temperature steam exposure.


2013 ◽  
Vol 65 (3) ◽  
pp. 244-249 ◽  
Author(s):  
M. Kiran Kumar ◽  
S. Aggarwal ◽  
D. Beniwal ◽  
A. K. Dey ◽  
H. Singh ◽  
...  

1970 ◽  
Vol 37 (3) ◽  
pp. 257-275 ◽  
Author(s):  
G.C. Imarisio ◽  
M. Cocchi ◽  
G. Faini

2015 ◽  
Vol 465 ◽  
pp. 400-406 ◽  
Author(s):  
А.S. Kuprin ◽  
V.А. Belous ◽  
V.N. Voyevodin ◽  
V.V. Bryk ◽  
R.L. Vasilenko ◽  
...  

2020 ◽  
Vol 28 ◽  
pp. 8-14
Author(s):  
Adéla Chalupová ◽  
Martin Steinbrück ◽  
Mirco Grosse ◽  
Jakub Krejčí ◽  
Martin Ševeček

The investigations in this paper deal with the Cr-Ni alloy. The material has been recently proposed as a potential ATF concept, primarily due to its behaviour under high-temperature oxidation. A set of experiments to determine the melting point and describe the oxidation kinetics of the Cr-Ni alloy were performed in Karlsruhe Institute of Technology. Presented results reveal its superb oxidation resistance comparing to zirconium alloys. Therefore, the alloy has a great potential for nuclear applications.


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