The present vision for a plasma–material interface in the tokamak is an axisymmetric
poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X …

Operation of DEMO in comparison to ITER will be significantly more demanding, as various
additional limitations of physical and technical nature have to be respected. In particular a …

Modeling of impurity-seeded plasma in Large Helical Device is presented for the first time by
using the three-dimensional transport code EMC3-EIRENE. High and low recycling …

Power exhaust for a 3 GW class fusion reactor with an ITER-sized plasma was investigated
by enhancing the radiation loss from seeding impurity. The impurity transport and plasma …

Plasma-facing materials (PFMs) represent one of the most significant challenges for the
design of future nuclear fusion reactors. Inside the reactor, the divertor will experience the …

A novel rovibrationally resolved collisional-radiative model of molecular hydrogen that
includes 4,133 rovibrational levels for electronic states whose united atom principal …

We have carried out a detailed analysis that compares steady state versus pulsed tokamak
reactors. The motivations are as follows. Steady state current drive has turned out to be more …

The main objective of DEMO design activity under the Broader Approach is to develop pre-
conceptual design of DEMO options by addressing key design issues on physics …

One-dimensional SOL-divertor plasma fluid simulation code which considers anisotropy of
ion temperature has been developed so as to deal with sheath theory self-consistently. In …

An integrated divertor simulation code, SONIC, has been developed in order to predict a self-
consistent transport solution of the plasma, neutral and impurities in the scrape-off layer …