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Comparison analysis of selected nuclear power plants supplied with helium from high-temperature gas-cooled reactor

Abstrakt

The article presents results of efficiency calculations for two 560 MW nuclear cycles with high-temperature gas-cooled reactor (HTGR). An assumption was made that systems of this type can be used in so-called marine nuclear power plants. The first analysed system is the nuclear steam power plant. For the steam cycle, the efficiency calculations were performed with the code DIAGAR, which is dedicated for analysing this type of systems. The other system is the power plant with gas turbine, in which the combustion chamber has been replaced with the HTGR. For this system, a number of calculations were also performed to assess its efficiency. Moreover, the article names factors in favour of floating nuclear power plants with HTGRs, which, due to passive safety systems, are exposed to much smaller risk of breakdown than other types of reactors which were in common use in the past. Along with safety aspects, it is also economic and social aspect which make the use of this type of systems advisable.

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Wersja publikacji
Accepted albo Published Version
DOI:
Cyfrowy identyfikator dokumentu elektronicznego (otwiera się w nowej karcie) 10.2478/pomr-2018-0043
Licencja
Creative Commons: CC-BY-NC-ND otwiera się w nowej karcie

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Kategoria:
Publikacja w czasopiśmie
Typ:
artykuł w czasopiśmie wyróżnionym w JCR
Opublikowano w:
Polish Maritime Research nr 25, strony 204 - 210,
ISSN: 1233-2585
Język:
angielski
Rok wydania:
2018
Opis bibliograficzny:
Szewczuk-Krypa N., Drosińska-Komor M., Głuch J., Breńkacz Ł.: Comparison analysis of selected nuclear power plants supplied with helium from high-temperature gas-cooled reactor// Polish Maritime Research. -Vol. 25, iss. S1(97) (2018), s.204-210
DOI:
Cyfrowy identyfikator dokumentu elektronicznego (otwiera się w nowej karcie) 10.2478/pomr-2018-0043
Weryfikacja:
Politechnika Gdańska

wyświetlono 197 razy

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