Tungsten Copper Plasma Component Technology Breakthrough

Recently, French Atomic Energy Commission (CEA) / Institute of magnetic confinement fusion (IRFM) researchers announced a good news: Institute of Plasma Physics, Chinese Academy of Sciences has made key progress in the development of two types of tungsten copper heat load (HHF) test module towards plasma components (W / Cu-PFC) test. Tungsten copper towards plasma component mainly refers to perforated tube. Tungsten copper perforated tube is one of the parts of vertical divertor target plates, and the divertor has been playing an significant role in magnetic confinement fusion reactor.

The main role of divertor is that the interaction between plasma and materials processing separated in two chambers and separates the resulting doping source and the main plasma. In general, it uses High heat load irradiation for the divertor properties testing, which is an important criteria to evaluate the quality of tungsten copper perforated tube. Tungsten copper not only has high melting point, high strength, low coefficient of thermal expansion, low sputter rate, low retention and excellent wear and corrosion resistance, etc., which is recognized as the most suitable for future nuclear fusion reactor plasma-facing materials. Tungsten copper perforated tube is first to drill on tungsten block, followed by brazing or hot isostatic pressing (HIP) block and other technology tungsten chromium zirconium copper pipe connected. Since it has symmetry in structure, can relief the thermal stress concentration and eliminate the stress point so that it can withstand high thermal loads irradiation.

Tungsten copper perforated tube fabricated by HIP has well combining face and without any obvious cracks, but the wall thickness of the circumferential unevenness in the HIP process of collapse and cracking phenomenon occurs. This time, the Chinese Academy of Sciences has made a major breakthrough in the manufacture of technology in the international community for the first time to achieve mass production of tungsten copper PFC, tungsten plasma interaction to carry out a comprehensive study under the conditions of long-pulse high parameters and provides an excellent platform. According to IREM researchers report relevant results: W / Cu perforated tube (Mono-block) No. 4 block modules withstand 1,200 times 10MW / m2 and 300 20MW / m2 radiation heat load; No. 5 tungsten block withstood 500 10MW / m2 and 500 20MW / m2 radiation heat load beyond the International Thermonuclear Experimental Reactor ITER to 20MW / m2 radiation heat load 300 requirements. In addition, W / Cu plates (Flat type) module FT1 to withstand 102 times 10MW / m2,102 times 15MW / m2 and 302 times 20MW / m2 radiation heat load; Tablet Module FT2 withstood 302 times 10MW / m2,102 times 15MW / m2 and 102 times 20MW / m2 radiation heat load. Irradiation results far beyond the flat module 5 MW / m2 in the ITER design requirements, refresh the W / Cu plate member is known recording HHF tests. This also proves that the advanced nature of the plasma connecting tungsten copper PFC technology to some extent.