High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign

• Published in: Journal of nuclear materials 2021-02, Vol.544, p.152670, Article 152670
• Main Authors: You, J.H., Visca, E., Barrett, T., Böswirth, B., Crescenzi, F., Domptail, F., Dose, G., Fursdon, M., Gallay, F., Greuner, H., Hunger, K., Lukenskas, A., Müller, A.v., Richou, M., Roccella, S., Vorpahl, C., Zhang, K.
• Format: Article
• Language: English
• Subjects: Armor; Bombardment; Comparative studies; Demo; Design; Divertor; Electric power generation; Fabrication; Fluctuations; Fusion reactor; Heat; Heat flux; Heat transfer; High heat flux; Infrared imagery; Infrared imaging; Infrared inspection; Inspection; Interlayers; Nuclear power plants; Photomicrographs; Power plants; R&D; Research & development; State-of-the-art reviews; Thermal analysis; Thermography; Tungsten; Tungsten monoblock; Ultrasonic testing; Vertical target
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2020.152670

Divertor target is one of the most critical in-vessel components in a fusion power plant being in charge of particle and power exhaust. The targets are exposed to severe thermal loads produced by steady bombardment of impinging plasma flux. Since 2014, integrated R&D efforts have been continued aiming at developing a design concept and high-heat-flux (HHF) technologies for divertor targets of the European DEMO reactor. Recently, the second round (2017–2019) of the R&D program has been concluded. As in the first R&D round, five water-cooled target design concepts were further developed and evaluated. Fabrication technologies were improved reaching a consolidated production quality. Extensive HHF tests were conducted using small-scale mock-ups for extended loading regimes (heat flux: 20–32MW/m²). Comparative studies were performed to investigate effects of copper interlayer thickness (0.1–1 mm) and different tungsten armor materials. In the present paper, the final results of the second round HHF testing campaign are reported. The HHF performance of each design variant is discussed based on in-situ diagnostic data (infrared thermography), ultrasonic inspection images and postmortem metallographic micrographs. All monoblock-type design concepts passed the specified qualification criterion (≥500 pulses at 20 MW/m², coolant: 130 °C) without any failure or armor cracking. Moreover, two of them (ITER-like and composite pipe) remained fully intact even under 25 MW/m² (100 pulses) and 32 MW/m² (5 pulses).