Wyniki wyszukiwania - Biblioteka Nauki

1

Klasyfikator rozmyty użyteczny we wstępnym doborze profili łopatkowych turbin parowych

100%

Szewczuk-Krypa N.

Przegląd Mechaniczny

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2018

|

tom nr 9

25--27

PL

W artykule przedstawiona została próba stworzenia wstępnego modelu klasyfikatora rozmytego użytecznego we wstępnym doborze profili łopatkowych turbin parowych. Dobór odpowiedniego rozwiązania dokonywany jest na podstawie parametrów przepływu czynnika przez wieńce turbiny. Tego typu narzędzie decyzyjne może okazać się przydatne zarówno w przypadku modernizacji istniejącego już obiektu, w którym zdiagnozowane uszkodzenia wymuszają kapitalny remont układu przepływowego, jak i przy projekcie nowego urządzenia.

EN

The article presents an attempt to create a preliminary fuzzy classifier model in the preliminary selection of steam turbines blade profiles. The selection of the appropriate solution is made on the basis of the parameters of the flow of the medium through the turbine rims. This type of decisionmaking tool may prove useful both in the case of the modernization of anexisting facility, in which the diagnosed faults force a complete overhaul of the flow system as well as the design of a new device.

2

Wyznaczenie charakterystyk eksploatacyjnych siłowni turbinowej o mocy 400 MW z reaktorem wysokotemperaturowym w zmiennych warunkach pracy

51%

Drosińska-Komor M. , Szewczuk-Krypa N. , Głuch J.

Przegląd Mechaniczny

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2017

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tom nr 6

45--47

PL

W artykule przedstawiono charakterystyki sprawnościowe dla siłowni turbinowej o mocy 400 MW zasilanej przez reaktor wysokotemperaturowy. Przedstawione charakterystyki stworzone zostały dla zmiennych warunków pracy opisanego obiegu. Obliczenia numeryczne symulujące działanie siłowni wykonano w programie DIAGAR. Jako zmienne warunki ruchu obiegu jądrowego przyjęto zmianę ciśnienia w skraplaczu. Na tej podstawie określono zmianę sprawności oraz jednostkowego zużycia ciepła omawianego układu.

EN

In the article performance characteristic for the 400 MW nuclear steam power plant are presented. Characteristics were created for steam turbine variable working conditions. Numerical calculations that simulate system operation in DIAGAR have been prepared. As a variable working conditions of nuclear steam power plant changes of condenser pressure were adopted.

3

Comparative analysis of thermodynamic cycles of selected nuclear ship power plants with hightemperature helium- cooled nuclear reactor

51%

Szewczuk-Krypa N. , Grzymkowska A. , Głuch J.

Polish Maritime Research

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2018

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tom S 1

218--224

EN

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.

4

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

51%

Szewczuk-Krypa N. , Drosinska-Komor M. , Gluch J. , Brenkacz L.

Polish Maritime Research

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2018

|

tom 25

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nr Special Issue S1

5

Comparative analysis of thermodynamic cycles of selected nuclear ship power plants with high-temperature helium-cooled nuclear reactor

51%

Szewczuk-Krypa N. , Grzymkowska A. , Gluch J.

Polish Maritime Research

|

2018

|

tom 25

|

nr Special Issue S1

XX

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

6

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

51%

Szewczuk-Krypa N. , Drosińska-Komor M. , Głuch J. , Breńkacz Ł.

Polish Maritime Research

|

2018

|

tom S 1

204--210

EN

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.