Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione

082
progress report
2010
BP
Lithium JET
Atom displacement, dpa/fpy 4.7–10 –1
He production, apppm/fpy 2
H production, apppm/fpy 9
Total heating W/cm 3 3.8–10 –1
HFTM
Atom displacement, dpa/fpy 54
He production, apppm/fpy 598
H production, apppm/fpy 2742
Total heating W/cm 3 23.08
Figure 3.57 – BP
geometrical layout of
MCNP5 code
Figure 3.58 – Main of the
outcomes of the neutronic
calculations on the BP
superimposed mesh tally
(EVEDA) lithium loop concept, the new design has been generated by enlarging the width of the lithium
flow channel from the 100 mm of the EVEDA loop target to the actual IFMIF dimensions (260 mm) and
modifying all other dimensions accordingly in order to fit the new channel size. The channel profile that has
been implemented is the variable–curvature profile (with no straight sections) formerly designed by ENEA.
As to the EVEDA design, the channel profile has now been entirely placed on the BP instead of distributing
it in between the BP and the interface frame. This solution is aimed at eliminating manufacturing problems
and alignment issues between the two components.
A first design optimization has been reached by eliminating all the unnecessary material in order to reduce
the weight as much as possible. This preliminary design has been assessed from the neutronic point of view.
Next step will be a thermo-mechanical assessment in order to evaluate the stress field in the componente,
thus optimizing the design features on this basis.
2) Neutronic calculations. In order to quantify the material damage due to neutron irradiation the following was
determined:
a) Heat deposition due to neutron and gamma interactions with nuclides.
b) Radiation damage (quantified by the number of dpa.
c) Gas production, e.g. total production of helium and hydrogen produced by neutron induced
nuclearreactions.
Preliminary neutron/gamma transport calculations have been performed for the BP via MCNP5 code,
version 1.4 (fig. 3.57).
The neutron induced cross section data files used in the calculations have been taken mainly from INPE–50
library, developed at INPE–Karlsruhe Institute of Technology (KIT), for neutron energies up to 50 MeV,
and LANL–150N, developed at Los Alamos National Laboratory, for neutron energies up to 150 MeV.
The BP profile was approximated in MCNP5 code through a combination of cylinders parallel to X
(horizontal) axis. Mapping on the BP through “superimposed mesh tally” feature of MCNP5 has been used
(fig. 3.58).
DEMO R&D in the Broader Approach activities
Development of CiC composite materials (task T1–2–5). In the framework of the Broader Approach activities
for the development of composite SiC materials, ENEA laboratories have completed the experimental plan
and the preliminary design of the test apparatus aimed at studying the erosion/corrosion of SiC composites
into PbLi.