The effect of displacement damage on deuterium retention in ITER-grade tungsten exposed to low-energy,high-flux pure and helium-seeded deuterium plasmas |
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Authors: | VKh Alimov B Tyburska-Püschel Y Hatano J Roth K Isobe M Matsuyama T Yamanishi |
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Affiliation: | 1. SCK CEN, Nuclear Materials Science Institute, Boeretang 200, Mol B-2400, Belgium;2. Université Catholique de Louvain, Institute of Mechanics, Materials and Civil Engineering, Louvain-la-Neuve 1348, Belgium;3. National Centre for Scientific Research “Demokritos”, Institute of Nuclear and Radiological Science and Technology, Energy and Safety, 15341 Agia Paraskevi, Athens, Greece;4. University of Liège, Place du 20 Août 7, Liège B-4000, Belgium |
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Abstract: | Samples prepared from polycrystalline ITER-grade tungsten were damaged by irradiation with 20 MeV W ions at room temperature to a fluence of 1.4 × 1018 W/m2. Due to the irradiation, displacement damage peaked near the end-of-range, 1.35 μm beneath the surface, at 0.89 displacements per atom. The damaged as well as undamaged W samples were then exposed to low-energy, high-flux (1022 D/m2 s) pure D and helium-seeded D plasmas to an ion fluence of 3 × 1026 D/m2 at various temperatures. Trapping of deuterium was examined by the D(3He,p)4He nuclear reaction at 3He energies varied from 0.69 to 4.0 MeV allowing determination of the D concentration at depths up to 6 μm. It has been found that (i) addition of 10% helium ions into the D plasma at exposure temperatures of 440–650 K significantly reduces the D concentration at depths of 0.5–6 μm compared to that for the pure plasma exposure; (ii) generation of the W-ion-induced displacement damage significantly increases the D concentration at depths up to 2 μm (i.e., in the damage zone) under subsequent exposures to both pure D and D–He plasmas. |
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