Paper

The development and testing of the thermal break divertor monoblock target design delivering 20 MW m−2 heat load capability

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Published 20 October 2017 © 2017 Culham Centre for Fusion Energy
, , Citation M Fursdon et al 2017 Phys. Scr. 2017 014042 DOI 10.1088/1402-4896/aa8c8e

1402-4896/2017/T170/014042

Abstract

The design and development of a novel plasma facing component (for fusion power plants) is described. The component uses the existing 'monoblock' construction which consists of a tungsten 'block' joined via a copper interlayer to a through CuCrZr cooling pipe. In the new concept the interlayer stiffness and conductivity properties are tuned so that stress in the principal structural element of the component (the cooling pipe) is reduced. Following initial trials with off-the-shelf materials, the concept was realized by machined features in an otherwise solid copper interlayer. The shape and distribution of the features were tuned by finite element analyses subject to ITER structural design criterion in-vessel components (SDC-IC) design rules. Proof of concept mock-ups were manufactured using a two stage brazing process verified by tomography and micrographic inspection. Full assemblies were inspected using ultrasound and thermographic (SATIR) test methods at ENEA and CEA respectively. High heat flux tests using IPP's GLADIS facility showed that 200 cycles at 20 MW m−2 and five cycles at 25 MW m−2 could be sustained without apparent component damage. Further testing and component development is planned.

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10.1088/1402-4896/aa8c8e