Atomistic modeling of diffusion coefficient in fusion reactor first wall material tungsten

The first wall material in a nuclear fusion reactor endures a series of complex processes, resulting in irradiation damage of its structural materials and eventually questioning its operative safety. Experimental and computer simulation are currently applied to search for irradiation damage. We used, the Material Studio software to model and calculate the crystal structure and mechanical properties, and the CASTEP module, primitive cell of iron, Fe-Cr alloy and Fe-Cr alloy with defects to calculate, analyze, and obtain the values of elastic constants and Young’s modulus. Our results showed that addition of Cr atom to conventional first wall metal materials of nuclear reactor, enhanced endurance by increasing the values of elastic constant and Young’s modulus, but distorted the symmetry of the crystal structure. We preliminarily prove and predict the possibility of the changes of mechanical properties of Low-activation martensite/ferrite under irradiation effects.

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Chemical interaction of hydrogen with graphite in regard of hydrogen recycling and chemical erosion of fusion reactor first wall material

Journal of Nuclear Materials ◽

10.1016/s0022-3115(09)80059-7 ◽

1992 ◽

Vol 191-194 ◽

pp. 326-329

Author(s):

Michio Yamawaki ◽

Kenji Yamaguchi ◽

Mutsumi Satoh ◽

Satoru Tanaka

Keyword(s):

Fusion Reactor ◽

Chemical Interaction ◽

Wall Material ◽

First Wall ◽

Chemical Erosion

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Plasma processed tungsten for fusion reactor first-wall material

Journal of Materials Science ◽

10.1007/s10853-021-05917-y ◽

2021 ◽

Author(s):

J. V. Vas ◽

J. Q. Pan ◽

N. L. Wang ◽

J. H. Xu ◽

R. Medwal ◽

...

Keyword(s):

Fusion Reactor ◽

Wall Material ◽

First Wall

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Tritium recycling, permeation and inventory in a self-cooled fusion reactor blanket using Pb17Li or Flibe as a breeder and V or Fe as a first wall material

Vacuum ◽

10.1016/0042-207x(89)90048-1 ◽

1989 ◽

Vol 39 (7-8) ◽

pp. 839-842 ◽

Cited By ~ 1

Author(s):

G Gervasini ◽

F Reiter

Keyword(s):

Fusion Reactor ◽

Wall Material ◽

First Wall ◽

Fusion Reactor Blanket

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

Proceedings, annual meeting, Electron Microscopy Society of America ◽

10.1017/s0424820100109124 ◽

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.

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