Long term research in low activation materials is being pursued in
fusion programs and the assessment of allowable elements and/or
impurities from safety and repository reasons are being studied at
Instituto Fusión Nuclear (DENIM), using ACAB code, for national
ignition facility (NIF) and inertial fusion energy (IFE) reactors.
Uncertainties in nuclear data are being considered, and experiments for
validation of modeling will be presented. Multiscale simulation of
radiation damage is now starting to be compared with experiments, and
results on the simplest material can be reported as a function of
impurities, temperature, and dose. Molecular dynamics (MD) allows us to
identify stress-strain curve of FeCr ferritic steels under irradiation,
and macroscopic conclusions can be advanced using simple models. However,
a neutron source of enough intensity and adequate energy spectrum is
needed which will be very peculiar in the case of pulsed IFE, as we
claimed in past years. Development of international fusion materials
irradiation facility (IFMIF) will be commented and compared with solutions
such as spallation, and others using ultra-intense lasers for obtaining
required irradiation magnitudes. Research on radiation damage in SiC
composite is being pursued at macroscopic level, but basic knowledge is
scarce. A systematic identification of type of stable defects is being
presented with a new tight binding MD technique. Our research on
simulation of silica irradiation damage will also be presented. The role
of tritium, when elemental tritium (HT) and titrated water (HTO) derive in
organically bound tritium (OBT) will be explained. The deposition and
absorption processes are now being considered in our calculations giving
more precision and accuracy to our conclusions of dosimetry effects. The
role of HT versus HTO and the importance of re-emission process will be
remarked, together with the long-term role of OBT.