Fusion Science and Technology / Volume 62 / Number 1 / July 2012 / Pages 46-49
Hydrogen/Tritium Behavior / Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology
Tungsten (W) and boron carbide (B4C) coatings deposited on metallic substrates have received considerable attention in recent years because of their potential application in nuclear fusion devices, especially as plasma facing materials (PFMs). In the present study, W and B4C coatings have been deposited by vacuum plasma spraying technology. The tritium retention behaviors of the W and B4C coatings were investigated and comparatively studied by using -ray-induced X-ray spectrometry (BIXS). The effects of tritium exposure temperature were examined as well. The obtained results showed that much stronger X-ray peaks of Ar(K) appeared in the BIXS spectra for the B4C coatings as compared with those for the W coatings, indicating of higher tritium absorbability for the B4C coatings owing to large amount of micro-pores in the coatings. After exposed to tritium gas at 923 K, significantly enhanced tritium retentions were detected for both the W and B4C coatings as compared with those exposed at 573 K.