Effects of helium ash on fusion reactor operation and analogies with fission reactors / Effekte von Heliumasche auf den Betrieb von Fusionsreaktoren und Analogien zu Spaltreaktoren

Kerntechnik ◽  
1999 ◽  
Vol 64 (4) ◽  
pp. 183-186
Author(s):  
G. Kamelander ◽  
H. Bürbaumer
Author(s):  
J. L. Brimhall

Transmission electron microscopy has long been used to study the microstructual evolution in materials as a result of radiation damage. The radiation environment in a fusion reactor is unlike that in well-studied fission reactors, therefore unique microstructures in fusion reactor materials may occur. The fusion reactor energy spectra will be strongly peaked at 14 MeV, whereas typical fission neutron energy spectra are peaked in the range 0.5 to 1.0 MeV We need to know how this higher energy neutron spectra in a fusion reactor will perturb the radiation damage states normally observed in fission reactor irradiations.


Author(s):  
M.L. Jenkins ◽  
C.A. English

Materials within fission reactors are exposed to fluxes of fast neutrons with energy up to a few MeV, whilst the first wall of a future fusion reactor will be bombarded with neutrons of energy peaking at about 14MeV. The consequent radiation damage leads to serious problems in reactor design. For this reason one of the major objectives for much recent research has been to try to understand the mechanisms of the damage created by fast neutrons. Damage accumulates only rather slowly in fission reactors, so neutron damage effects in fission reactors have often been simulated by charged- particle bombardment using accelerators of various types. Similarly there will be a tendency in the future to extrapolate data obtained with fission-neutrons to the more energetic fusion-neutrons because no high-flux source of fusion-energy neutrons is available. One of the difficulties of the simulation approach is that the various irradiation methods produce different energy spectra of primary knock-on atoms.


2021 ◽  
Author(s):  
Lu Wang ◽  
Hai-Shan Zhou ◽  
Hao-Dong Liu ◽  
Yu-Ping Xu ◽  
Wan-Jing Wang ◽  
...  

Abstract Tritium (T) permeation through plasma-facing component (PFC) into the coolant is a major concern of fusion reactor operation. In this work, deuterium (D) permeation through CLAM steel, CLAM/CLAM and CLAM/Fe-Cr-Al samples prepared by hot isostatic pressing (HIP) are tested in a linear plasma device. Only the downstream surfaces of the samples are oxidized with controlled atmosphere to form permeation barrier. No significant effect on D diffusion and penetration can be observed for the joining interfaces, while the dense oxide layer at the downstream side plays an important role in suppressing D permeation. The downstream surface oxidization of CLAM/Fe-Cr-Al is found to effectively reduce D permeation flux by a factor up to 1000.


2004 ◽  
Vol 54 (S3) ◽  
pp. C47-C52
Author(s):  
R. Stankiewicz ◽  
R. Zagórski

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