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Wyświetlanie 1-2 z 2
Tytuł:
Comparative analysis of thermodynamic cycles of selected nuclear ship power plants with hightemperature helium- cooled nuclear reactor
Autorzy:
Szewczuk-Krypa, N.
Grzymkowska, A.
Głuch, J.
Powiązania:
https://bibliotekanauki.pl/articles/260189.pdf
Data publikacji:
2018
Wydawca:
Politechnika Gdańska. Wydział Inżynierii Mechanicznej i Okrętownictwa
Tematy:
nuclear ship power plant
nuclear reactor
HTGR
gas turbine
steam turbine
combined cycle
Opis:
This paper presents a comparative analysis of thermodynamic cycles of two ship power plant systems with a hightemperature helium- cooled nuclear reactor. The first of them is a gas system with recuperator , in which classical gas chamber is substituted for a HTGR reactor (High Temperature Gas-cooled Reactor) . The second of the considered cycles is a combined gas-steam system where working medium flux from gas turbine outlet is directed into waste heat boiler and its heat is utilized for production of superheated steam to drive steam turbine. Preliminary calculations of the combine cycles showed that it is necessary to expand the system by adding to its steam part an inter-stage overheat for secondary steam, owing to that a required degree of steam dryness at outlet from the turbine can be reached, ensuring its correct operational conditions. The analyzed power systems were compared to each other with regard to efficiency of their thermodynamic cycles. Also, efficiency of particular cycles were subjected to optimization in respect to such parameters as : working gas temperature at outlet from reactor in gas system as well as steam pressure at outlet from waste heat boiler and partition pressure in steam part of combined system. Advantages of nuclear power plants compared with the classical power systems dominating currently in sea transport were also discussed.
Źródło:
Polish Maritime Research; 2018, S 1; 218-224
1233-2585
Pojawia się w:
Polish Maritime Research
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Comparison analysis of selected nuclear power plants supplied with helium from high-temperature gas-cooled reactor
Autorzy:
Szewczuk-Krypa, N.
Drosińska-Komor, M.
Głuch, J.
Breńkacz, Ł.
Powiązania:
https://bibliotekanauki.pl/articles/258918.pdf
Data publikacji:
2018
Wydawca:
Politechnika Gdańska. Wydział Inżynierii Mechanicznej i Okrętownictwa
Tematy:
HTGR
nuclear power plants
floating marine plants
nuclear power
Opis:
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.
Źródło:
Polish Maritime Research; 2018, S 1; 204-210
1233-2585
Pojawia się w:
Polish Maritime Research
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-2 z 2

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