Brazing Technology for Plasma Facing Components in Nuclear Fusion Applications Using Low and Graded CTE Interlayers

2008 ◽  
Vol 59 ◽  
pp. 192-197 ◽  
Author(s):  
Carlo Gualco ◽  
Marco Grattarola ◽  
Alberto Federici ◽  
Francesco Mataloni ◽  
Karol Iždinský ◽  
...  

In Plasma Facing Components (PFCs) for nuclear fusion reactors, the protective material, carbon based or tungsten, has to be joined to the copper alloy heat sink for optimum heat transfer. High temperature vacuum brazing is a possible joining process as long as a proper interlayer is introduced to mitigate the residual stresses due to the mismatch of thermal expansion coefficient (CTE). Pure copper can act as plastic compliant layer, however for carbon based materials a proper structuring of the joining surface is necessary to meet the thermal fatigue lifetime requirements. In this work pure molybdenum and tungsten/copper Metal Matrix Composites (W-wires in Cu-matrix) interlayers have been studied as alternative to pure copper for carbon based protective materials in flat tile configuration. Finite element simulations of the brazing process have been performed to evaluate the expected residual stress reduction near the metal-carbon interface. In fact it has been demonstrated that stiff low CTE interlayers can shift the peak stresses from the weak carbon-metal interface to the strongest metal-metal one. Relevant samples have been manufactured and subjected to preliminary metallographic and thermal shock tests. Results obtained so far are encouraging and active cooled mock-ups are being prepared for high heat flux testing. Research work is in progress as regards monoblock configuration with both Wf/Cu MMC and graded Cu/W plasma sprayed and HIPped layers.

2021 ◽  
Vol 11 (24) ◽  
pp. 11653
Author(s):  
Michael Rieth ◽  
Michael Dürrschnabel ◽  
Simon Bonk ◽  
Ute Jäntsch ◽  
Thomas Bergfeldt ◽  
...  

Plasma facing components for energy conversion in future nuclear fusion reactors require a broad variety of different fabrication processes. We present, along a series of studies, the general effects and the mutual impact of these processes on the properties of the EUROFER97 steel. We also consider robust fabrication routes, which fit the demands for industrial environments. This includes heat treatment, fusion welding, machining, and solid-state bonding. Introducing and following a new design strategy, we apply the results to the fabrication of a first-wall mock-up, using the same production steps and processes as for real components. Finally, we perform high heat flux tests in the Helium Loop Karlsruhe, applying a few hundred short pulses, in which the maximum operating temperature of 550 °C for EUROFER97 is finally exceeded by 100 K. Microstructure analyses do not reveal critical defects or recognizable damage. A distinct ferrite zone at the EUROFER/ODS steel interface is detected. The main conclusions are that future breeding blankets can be successfully fabricated by available industrial processes. The use of ODS steel could make a decisive difference in the performance of breeding blankets, and the first wall should be completely fabricated from ODS steel or plated by an ODS carbon steel.


Author(s):  
Andrei Khodak ◽  
Douglas Loesser ◽  
Michael Messineo ◽  
Arthur Brooks ◽  
Michael Jaworski ◽  
...  

1992 ◽  
Vol 196-198 ◽  
pp. 596-601 ◽  
Author(s):  
J. Gilligan ◽  
M. Bourham ◽  
O. Hankins ◽  
W. Eddy ◽  
J. Hurley ◽  
...  

Nukleonika ◽  
2015 ◽  
Vol 60 (2) ◽  
pp. 285-288 ◽  
Author(s):  
Yashashri Patil ◽  
S. Khirwadkar ◽  
S. M. Belsare ◽  
Rajamannar Swamy ◽  
M. S. Khan ◽  
...  

Abstract This paper is focused on various aspects of the development and testing of water cooled divertor PFCs. Divertor PFCs are mainly designed to absorb the heat and particle fluxes outflowing from the core plasma of fusion devices like ITER. The Divertor and First Wall Technology Development Division at the Institute for Plasma Research (IPR), India, is extensively working on development and testing of divertor plasma facing components (PFCs). Tungsten and graphite macro-brush type test mock-ups were produced using vacuum brazing furnace technique and tungsten monoblock type of test mock-ups were obtained by hot radial pressing (HRP) technique. Heat transfer performance of the developed test mock-ups was tested using high heat flux tests with different heat load conditions as well as the surface temperature monitoring using transient infrared thermography technique. Recently we have established the High Heat Flux Test Facility (HHFTF) at IPR with an electron gun EH300V (M/s Von Ardenne Anlagentechnik GmbH, Germany) having maximum power 200 kW. Two tungsten monoblock type test mock-ups were probed using HHFTF. Both of the test mock-ups successfully sustained 316 thermal cycles during high heat flux (HHF) tests. The test mock-ups were non-destructively tested using infrared thermography before and after the HHF tests. In this note we describe the detailed procedure used for testing macro-brush and monoblock type test mock-ups using in-house transient infrared thermography set-up. An acceptance criteria limit was defined for small scale macro-brush type of mock-ups using DTrefmax value and the surface temperature measured during the HHF tests. It is concluded that the heat transfer behavior of a plasma facing component was checked by the HHF tests followed by transient IR thermography. The acceptance criteria DTrefmax limit for a graphite macro-brush mock-up was found to be ~3°C while for a tungsten macro-brush mock-up it was ~5°C.


2001 ◽  
Vol 56-57 ◽  
pp. 285-290 ◽  
Author(s):  
F Escourbiac ◽  
P Chappuis ◽  
J Schlosser ◽  
M Merola ◽  
I Vastra ◽  
...  

Author(s):  
K. Nakamura ◽  
M. Akiba ◽  
S. Suzuki ◽  
K. Satoh ◽  
K. Yokoyama ◽  
...  

2007 ◽  
Vol 82 (15-24) ◽  
pp. 1730-1738 ◽  
Author(s):  
F. Escourbiac ◽  
A. Durocher ◽  
A. Grosman ◽  
F. Cismondi ◽  
X. Courtois ◽  
...  

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