Analysis of Possible Application of High-Temperature Nuclear Reactors to Contemporary Large-Output Steam Power Plants on Ships

This paper presents a comparative analysis of thermodynamic cycles of two ship power plant systems with a high-temperature 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.

Section: Analyzed Cycles Of Nuclear Power Plantsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Comparative Analysis of Thermodynamic Cycles of Selected Nuclear Ship Power Plants With High-Temperature Helium-Cooled Nuclear Reactor

Szewczuk-Krypa

Grzymkowska

Głuch

2018

“…The reactor itself has the shape of a cylinder filled with triple coated isotropic fuel (TRISO). This fuel has the form of small graphite balls filled with fissile material of 0,5 mm in diameter, which usually is low-enriched uranium oxide [1,7]. The greatest advantage of HTGRs is their high safety of operation.…”

Section: Introductionmentioning

confidence: 99%

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

Szewczuk-Krypa

Drosińska-Komor

Głuch

et al. 2018

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.

“…Diesel engine, gas turbine and steam turbine. The contemporary ship power plant is presented in article [14] and operational and economic analysis of some parts of the steam turbine power plant is discussed in article [3]. A summary of losses and energy efficiency of drive motors is presented in paper [18].…”

Section: Introductionmentioning

confidence: 99%

The Experimental Identification of the Dynamic Coefficients of two Hydrodynamic Journal Bearings Operating at Constant Rotational Speed and Under Nonlinear Conditions

Breńkacz

Żywica

Drosińska-Komor

2017