Thermodynamic analysis of power generation cycles with high-temperature gas-cooled nuclear reactor and additional coolant heating up to $1600 ^{\circ}$C
PBN-AR
Instytucja
Wydział Energetyki i Paliw (Akademia Górniczo-Hutnicza im. Stanisława Staszica w Krakowie)
##### Informacje podstawowe
Główny język publikacji
EN
Czasopismo
Journal of Energy Resources Technology-Transactions of the ASME (25pkt w roku publikacji)
ISSN
0195-0738
EISSN
1528-8994
Wydawca
The Americal Society of Mechanical Engineers ASME
DOI
Rok publikacji
2018
Numer zeszytu
2, art. no. 020906
Strony od-do
020906-1--020906-7
Numer tomu
140
Identyfikator DOI
Liczba arkuszy
0.5
##### Autorzy
(liczba autorów: 4)
Pozostali autorzy
+ 1
##### Słowa kluczowe
EN
high-temperature goas-cooled nuclear reactor (HTGR)
##### Streszczenia
Język
EN
Treść
Nuclear energy is one of the possibilities ensuring energy security, environmental protection, and high energy efficiency. Among many newest solutions, special attention is paid to the medium size high-temperature gas-cooled reactors (HTGR) with wide possible applications in electric energy production and district heating systems. Actual progress can be observed in the literature and especially in new projects. The maximum outlet temperature of helium as the reactor cooling gas is about 1000 °C which results in the relatively low energy efficiency of the cycle not greater than 40–45% in comparison to 55–60% of modern conventional power plants fueled by natural gas or coal. A significant increase of energy efficiency of HTGR cycles can be achieved with the increase of helium temperature from the nuclear reactor using additional coolant heating even up to 1600 °C in heat exchanger/gas burner located before gas turbine. In this paper, new solution with additional coolant heating is presented. Thermodynamic analysis of the proposed solution with a comparison to the classical HTGR cycle will be presented showing a significant increase of energy efficiency up to about 66%.
original article
peer-reviewed
##### Inne
System-identifier
idp:112160
Crossref
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