<abstract xmlns="http://www.w3.org/1999/xhtml"><p>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.</p></abstract>

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.

Comparison Analysis of Selected Nuclear Power Plants Supplied With Helium from High-Temperature Gas-Cooled Reactor

Institute of Fluid Flow Machinery, Polish Academy of Sciences

Polish Maritime Research

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

The article presents results of efficiency calculations for two 560 MW nuclear cycles with high-temperature gas-cooled reactor (HTGR). An assumption was made...

Comparison Analysis of Selected Nuclear Power Plants Supplied With Helium from High-Temperature Gas-Cooled Reactor

Publié en ligne: 07 juin 2018

Pages: 204 - 210

DOI: https://doi.org/10.2478/pomr-2018-0043

Mots clés
HTGR, nuclear power plants, floating marine plants, nuclear power

© 2018 Natalia Szewczuk-Krypa et al., published by Sciendo

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

Comparison Analysis of Selected Nuclear Power Plants Supplied With Helium from High-Temperature Gas-Cooled Reactor

Publié en ligne: 07 juin 2018

Pages: 204 - 210

DOI: https://doi.org/10.2478/pomr-2018-0043

Mots clésHTGR, nuclear power plants, floating marine plants, nuclear power

© 2018 Natalia Szewczuk-Krypa et al., published by Sciendo

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

Mots clés
HTGR, nuclear power plants, floating marine plants, nuclear power