Tritium permeation through first wall in steady-state operation of the fusion reactor intor

1987 ◽  
Vol 62 (2) ◽  
pp. 87-93 ◽  
Author(s):  
A. A. Pisarev ◽  
V. M. Smirnov
Keyword(s):  
Steady State ◽  
Fusion Reactor ◽  
First Wall ◽  
Steady State Operation ◽  
Tritium Permeation

scholarly journals Advanced Helical Plasma Research towards a Steady-State Fusion Reactor by Deuterium Experiments in Large Helical Device

Atoms ◽  
2018 ◽  
Vol 6 (4) ◽  
pp. 69 ◽  
Author(s):  
Yasuhiko Takeiri
Keyword(s):  
Steady State ◽  
Spectroscopic Study ◽  
Fusion Reactor ◽  
Ion Temperature ◽  
Fusion Research ◽  
Systems Research ◽  
Steady State Operation ◽  
New Type ◽  
Plasma Research ◽  
State Fusion

The Large Helical Device (LHD) is one of the world’s largest superconducting helical system fusion-experiment devices. Since the start of experiments in 1998, it has expanded its parameter regime. It has also demonstrated world-leading steady-state operation. Based on this progress, the LHD has moved on to the advanced research phase, that is, deuterium experiment, which started in March 2017. During the first deuterium experiment campaign, an ion temperature of 10 keV was achieved. This was a milestone in helical systems research: demonstrating one of the conditions for fusion. All of this progress and increased understanding have provided the basis for designing an LHD-type steady-state helical fusion reactor. Moreover, LHD plasmas have been utilized not only for fusion research, but also for diagnostics development and applications in wide-ranging plasma research. A few examples of such contributions of LHD plasmas (spectroscopic study and the development of a new type of interferometer) are introduced in this paper.

scholarly journals A new regime that “FIRE”s fusion plasmas for long sustained and high performance reactor conditions

2021 ◽  
Author(s):  
Yong-Su Na ◽  
Hyunsun Han ◽  
Sangjin Park ◽  
Jisung Kang ◽  
Young-Ho Lee ◽  
...  
Keyword(s):  
Steady State ◽  
High Performance ◽  
Large Scale ◽  
Fusion Reactor ◽  
Fusion Reactors ◽  
Fusion Plasmas ◽  
Ion Temperature ◽  
Plasma Confinement ◽  
Fusion Plasma ◽  
Steady State Operation

Abstract We report a discovery of a fusion plasma regime suitable for commercial fusion reactor where the ion temperature was sustained above 100 million degree about 20 s for the first time. Nuclear fusion as a promising technology for replacing carbon-dependent energy sources has currently many issues to be resolved to enable its large-scale use as a sustainable energy source. State-of-the-art fusion reactors cannot yet achieve the high levels of fusion performance, high temperature, and absence of instabilities required for steady-state operation for a long period of time on the order of hundreds of seconds. This is a pressing challenge within the field, as the development of methods that would enable such capabilities is essential for the successful construction of commercial fusion reactor. Here, a new plasma confinement regime called fast ion roled enhancement (FIRE) mode is presented. This mode is realized at Korea Superconducting Tokamak Advanced Research (KSTAR) and subsequently characterized to show that it meets most of the requirements for fusion reactor commercialization. Through a comparison to other well-known plasma confinement regimes, the favourable properties of FIRE mode are further elucidated and concluded that the novelty lies in the high fraction of fast ions, which acts to stabilize turbulence and achieve steady-state operation for up to 20 s by self-organization. We propose this mode as a promising path towards commercial fusion reactors.

Alignment of small He-Bubbles during in situ deformation of Al-foils

1978 ◽  
Vol 36 (1) ◽  
pp. 396-397
Author(s):  
E. Ruedl ◽  
P. Schiller
Keyword(s):  
Fusion Reactor ◽  
Matrix Material ◽  
Fusion Reactors ◽  
First Wall ◽  
Potential Matrix ◽  
In Situ Deformation ◽  
Α Particles ◽  
Metal Aluminium

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.

scholarly journals Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment

2021 ◽  
pp. 101039
Author(s):  
R. Arredondo ◽  
K. Schmid ◽  
F. Subba ◽  
G.A. Spagnuolo
Keyword(s):  
Ion Bombardment ◽  
First Wall ◽  
Tritium Permeation

Special Features of First-Wall Heat Transfer in Liquid-Metal Fusion Reactor Blankets

1987 ◽  
Vol 12 (1) ◽  
pp. 104-113 ◽  
Author(s):  
K. Taghavi ◽  
M. S. Tillack ◽  
H. Madarame
Keyword(s):  
Heat Transfer ◽  
Liquid Metal ◽  
Fusion Reactor ◽  
Wall Heat Transfer ◽  
First Wall
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