We present a revised strategy for Indian DEMO in the context of new technologies and
concepts in fusion research. The central idea behind the new strategy is that the power plant …

The erosion behavior and retention properties of tungsten trioxide (WO 3) and W films
exposed to low energy (∼ 50 eV) deuterium (D) ions were studied at surface temperature …

Since WC can be easily formed on tungsten (W) surface through the interaction between the
plasma and W surface in the C-containing impurity atmosphere in tokamaks, the …

Under the continuous irradiation of high‐density and high‐energy photons from the plasma
core of a fusion reactor, the plasma‐facing materials (PFMs) of tungsten (W) are in …

An accelerator-based 14-MeV neutron generator for fusion neutronics studies has been
developed in Fusion Neutronics Laboratory (FNL) at Institute for Plasma Research (IPR) …

Both microvoids and helium (He) impurities are widely present in tungsten (W) plasma-
facing materials (PFMs), where the interaction between microvoids and He atoms has led to …

The nature and type of defects formed due to heavy-ion irradiation in tungsten foils are
analyzed using transmission electron microscopy. The recrystallized tungsten foils were …

A monoenergetic neutron field is an attractive environment for neutron metrology and the
development of novel neutron detectors. Deuterium–deuterium and deuterium–tritium (DT) …

The evolution of point defects with annealing temperature is investigated in cold-rolled
tungsten samples using positron annihilation spectroscopy and transmission electron …

The erosion behavior of tungsten (W) exposed to low-energy, high flux deuterium (D)
plasma has been investigated. The samples were characterized by scanning electron …