Thermal and mechanical properties of vapour-deposited TiC coatings for the first wall of a fusion reactor

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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Mechanical properties of materials in fusion reactor first-wall and blanket systems

Journal of Nuclear Materials ◽

10.1016/0022-3115(79)90358-1 ◽

1979 ◽

Vol 85-86 ◽

pp. 795-804 ◽

Cited By ~ 47

Author(s):

E.E. Bloom

Keyword(s):

Mechanical Properties ◽

Fusion Reactor ◽

First Wall ◽

Mechanical Properties Of Materials ◽

Properties Of Materials

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Overview of the Mechanical Properties of Tungsten/Steel Brazed Joints for the DEMO Fusion Reactor

Metals ◽

10.3390/met11020209 ◽

2021 ◽

Vol 11 (2) ◽

pp. 209

Author(s):

Diana Bachurina ◽

Vladimir Vorkel ◽

Alexey Suchkov ◽

Julia Gurova ◽

Alexander Ivannikov ◽

...

Keyword(s):

Mechanical Properties ◽

Mechanical Property ◽

Best Practices ◽

Physical Properties ◽

Fusion Reactor ◽

State Of The Art ◽

Operating Conditions ◽

First Wall ◽

Brazed Joints ◽

Tungsten Steel

A Demonstration (DEMO) thermonuclear reactor is the next step after the International Thermonuclear Experimental Reactor (ITER). Designs for a DEMO divertor and the First Wall require the joining of tungsten to steel; this is a difficult task, however, because of the metals’ physical properties and necessary operating conditions. Brazing is a prospective technology that could be used to solve this problem. This work examines a state-of-the-art solution to the problem of joining tungsten to steel by brazing, in order to summarize best practices, identify shortcomings, and clarify mechanical property requirements. Here, we outline the ways in which brazing technology can be developed to join tungsten to steel for use in a DEMO application.

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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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