In 1959 the Journal of Nuclear Materials (JNM) was founded and is now celebrating its
Diamond Anniversary year. The present paper is part of a series in which single JNM …

ITER will use beryllium as a plasma-facing material in the main chamber, covering a total
surface area of about 620 m 2. Given the importance of beryllium erosion and co-deposition …

We have studied the influence of grain boundaries (GBs) on the radiation-induced defect
evolution and on H retention at 300 K, both experimentally and by computer simulations. For …

The change in surface damage/microstructures and its effects on the hydrogen (H)
isotope/helium (He) dynamic behavior are the key factors for investigating issues of tungsten …

Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal
desorption spectroscopy (TDS). In order to obtain a TDS spectrum with a prominent peak …

Simulations of deuterium (D) atom exposure in self-damaged polycrystalline tungsten at 500
K and 600 K are performed using an evolution of the MHIMS (migration of hydrogen …

In this work we investigated the adsorption of oxygen and the co-adsorption of oxygen and
hydrogen on the (110) surface of tungsten by means of Density Functional calculations. The …

The retention of hydrogen isotopes (HIs)(H, D and T) in the first, plasma exposed wall is one
of the key concerns for the operation of future long pulse fusion devices. It affects the particle …

Tritium technologies, in particular tritium extraction from lithium-lead (LiPb, 15.7 at.% Li) and
tritium concentration measurement in the eutectic alloy, are among the most challenging …

Fusion fuel retention (trapping) and release (desorption) from plasma-facing components
are critical issues for ITER and for any future industrial demonstration reactors such as …