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 out flowing 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 fl ux (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
~3centi grade while for a tungsten macro-brush mock-up it was ~5centi grade.
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