Scaling of deuterium retention in <3 MeV proton damaged Beryllium, Eurofer, and W-5Re in the range of 0.0003 to 6 DPA

Abstract

In continuation of earlier work on 3 MeV proton-damaged tungsten and reduced-activation steels we present new results on Eurofer97, Beryllium and W-5%Re sintered alloy irradiated <400 K. Methodical improvements result in largely reduced uncertainties. Beryllium is loaded using a 5 kV D2 + ion-source to 6.3*1021 D m−2 at 300 K. Eurofer97 and W-5Re are loaded in PSI-2 to 3*1025 D m−2. Irradiation and D-loading are conducted at ∼400 K. The D retention is measured by 3He μ-NRA. An exponential saturation fits the W-5Re D-retention data with R2 = 0.99 . The retention increases by a factor 10.3 in W-5Re, similar as in W, but on a ~7 times lower level. Within ±25% uncertainty D Retention in Eurofer97 proves to be independent of displacement damage up to 6.3 DPA. Beryllium shows increased retention by a factor 3 up to the tested maximum of 0.08 DPA. The retention in beryllium starts saturating, but the limited DPA range allows fitting the data with exponentials and power-laws.

Effect of 14.7 MeV Protons on Beryllium Micro Brush / Copper ITER First Wall using SRIM

“…SRIM is a typical code for simulating the damage parameters caused by the ion induced radiation according to the input specifications for its practical usage [14], [15], [16]. Using the Binary Collision Approximation, BCA, the profiles of vacancy interstitial Frenkel pairs (FP) as a function of the target depth can be simulated.…”