Artigo de peri??dico
Very high temperature reactor (VHTR)
Reactor a temperatura muito elevada (VHTR) - uma proposta para reactores da gera????o IV
Registro en:
2525-8761
3
8
10.34117/bjdv8n3-139
0000-0002-6689-3011
Sem Percentil
Sem Percentil CiteScore
Autor
ANDRADE, DELVONEI A. de
ALMEIDA, MADISON C. de
ALONSO, VANESSA M.
PAIXAO, CLAUDIA M.
ARQUINTO, JULIANA
KOTANI, PALOMA O.
MARINHO, THAYNA C.
Resumen
The Generation IV reactors depict a revolution in terms of electricity supply for the future. The
proof of concept originated in the Generation IV forum, which listed six possible technological
routes for a future of nuclear generation based on fissile material, which includes safety
requirements, nuclear energy efficiency and less waste generation. These are the very high
temperature reactor (VHTR); supercritical water-cooled reactor (SCWR); molten salt reactor
(MSR); gas-cooled fast reactor (GFR); sodium cooled fast reactor (SFR); and lead-cooled fast
reactor (LFR). The present study explored the possibilities, the obstacles, as well as the
challenges to be overcome, for the Very High Temperature Reactor (VHTR). VHTR technology
seems to be versatile; it originates on the advancement of another type, the High Temperature
Reactor (HTR). USA, Germany and UK were main countries in this avant-garde research. In
addition to generating electrical energy, VHTR can provide heat for industrial sectors and other
applications. Like any nuclear technology, challenges regarded to safety and the environment are
key points in the implementation of the system. VHTR was here prospected, with its ???pros and
cons???; as a promising way to a safe nucleoelectric energy. Summarizing, VHTR is shown as a
possible alternative, as long as studies of high-strength materials go ahead. In short, the reactor
becomes a viable source of thermonuclear generation, also associated with hydrogen production.
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