Artigo de peri??dico
Analysis of materials for heat transport in tokamaks
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2161-6795
1
10
10.4236/wjnst.2020.101005
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Autor
BELLONI, MARCIO
CONTI, THADEU das N.
Resumen
Every nuclear power reactor, whether of fusion or fission, is essentially a
thermal system that generates electricity. In this sense, there are several problems
in relation to this heat transport. The model of plasma confinement by
magnetic force, in the nuclear fusion (sterellator and tokamak), has only been
20 years and recently some success in the quality of the generated plasma has
been achieved. However, due to the large amount of energy coming from the
plasma, the choice of the material that will carry the generated energy is quite
troublesome, due to the need to handle a very high temperature for the nuclear
fission standards. Solutions are explored by the scientific community to
transport the energy generated in the case of the primary circuit, after exceeding
breakeven temperature and models that are based on the fission
reactors of the fourth generation and those currently in operation, to search
for solutions regarding the transport of heat generated for the generation of
electric energy. Several materials such as pressurized water, sodium, helium
and boron have been considered and studied to form the primary heat transfer
circuit for the exchanger. A thorough analysis of these materials is necessary.
This research looked at some of these materials for heat transport and
power generation. Lithium and helium were found to be the probable materials
for conveying heat and cooling in the blanket. The results show that research
on blanket materials needs more attention. The quality of these materials
needs to be improved by material research, with the ODS EUROFER alloy
and other research to reduce material erosion by helium nano bubbles.
Plasma quality needs to be improved to keep constant and free of impurities
when using lithium in liquid form.