Tritium decay helium-3 effects in tungsten

Abstract Tritium (T) implanted by plasmas diffuses into bulk material, especially rapidly at elevated temperatures, and becomes trapped in neutron radiation-induced defects in materials that act as trapping sites for the tritium. The trapped tritium atoms will decay to produce helium-3 ( 3 He) atoms at a half-life of 12.3 years. 3 He has a large cross section for absorbing thermal neutrons, which after absorbing a neutron produces hydrogen (H) and tritium ions with a combined kinetic energy of 0.76 MeV through the 3 He(n,H)T nuclear reaction. The purpose of this paper is to quantify the 3 He produced in tungsten by tritium decay compared to the neutron-induced helium-4 ( 4 He) produced in tungsten. This is important given the fact that helium in materials not only creates microstructural damage in the bulk of the material but alters surface morphology of the material effecting plasma-surface interaction process (e.g. material evolution, erosion and tritium behavior) of plasma-facing component materials. Effects of tritium decay 3 He in tungsten are investigated here with a simple model that predicts quantity of 3 He produced in a fusion DEMO FW based on a neutron energy spectrum found in literature. This study reveals that: (1) helium-3 concentration was equilibrated to ∼6% of initial/trapped tritium concentration, (2) tritium concentration remained approximately constant (94% of initial tritium concentration), and (3) displacement damage from 3 He(n,H)T nuclear reaction became >1 dpa/year in DEMO FW.