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

Treść / Zawartość
Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
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.
Rocznik
Tom
S 1
Strony
204--210
Opis fizyczny
Bibliogr. 16 poz., rys., tab.
Twórcy
  • Gdansk University of Technology, Poland
  • Gdansk University of Technology, Poland
autor
  • Gdansk University of Technology, Poland
  • Institute of Fluid Flow Machinery, Polish Academy of Sciences, Poland
Bibliografia
  • 1. Baek J-K., Mistarihi Q., Yeo S., et al.: A Preliminary Study for Diffusion Experiments of Metallic Fission Products in Graphite for HTGR. Transaction of the Korean Nuclear Society Autumn Meeting Gyeongiu, Korea, October 29-30, 2015
  • 2. Carlton J S., Smarta R., Jenkins V.: The nuclear propulsion of merchant ships: Aspects of engineering, science and technology. Journal of Marine Engineering & Technology 2011, pp. 47-59
  • 3. Gardzilewicz A., Głuch J., Bogulicz M. (1994): DIAGAR manual for turbine set No. 3 at Kozienice Power Plant (in Polish). Maszyny Przepływowe, Sp. z o.o., Report no. 19/9
  • 4. Gorlinski Yu.E., Kut’kov V.A, Lystsov V.N., et al.: Securing the radiological safety of people and the environment at all stages of the life cycle of floating nuclear heat-and-power plants. Atomic Energy Vol. 107, No. 2, 2009, pp. 122-129
  • 5. Hirdaris, S.E.; Cheng, Y.F.; Shallcross, P.; Bonafoux, et al.: Considerations on the potential use of Nuclear Small Modular Reactor (SMR) technology for merchant marine propulsion. Ocean Engineering Vol. 79, 2014, pp. 101–130.
  • 6. Hirose, K.: 2011 Fukushima Dai-ichi nuclear power plant accident: Summary of regional radioactive deposition monitoring results. Journal of Environmental Radioactivity, 2012, pp. 13–17.
  • 7. Kowalczyk T., Głuch J., Ziółkowski P.: Analysis of possible application of high-temperature nuclear reactors to contemporary large-output steam power plants on ships. Polish Maritime Research, 2016 Vol. 23, No. 2 (90), pp. 32-41
  • 8. Lee K., Lee K-H., Lee J., et al.: A new design concept for offshore nuclear power plants with enhanced safety features. Nuclear Engineering and Design 254 2013, pp. 129-141
  • 9. Lee K-H., Kim M-G., Lee J-I., Lee 10. P-S.: Recent Advances in Ocean Nuclear Power Plant, Energies, 2015, Vol 8 pp. 11470-11492
  • 11. Lepekhin A., Andreeva-Andrievskaya L., Kuznetsov V.: Status of Russian small and medium sized reactor activities. In Proceedings of the Meeting of the International Framework for Nuclear Energy Cooperation, Rome, Italy, 6 December 2010
  • 12. McDonald C.F.: A nuclear gas turbine perspective: The indirect cycle (IDC) offers a practical solution, Proceedings of the 31. intersociety energy conversion engineering conference. Volume 2: Conversion technologies, electro-chemical technologies, Stirling engines, thermal management
  • 13. Nagatani K., Kiribayashi S., Okada Y. et al.: Emergency response to the nuclear accident at the Fukushima Daiichi Nuclear Power Plants using mobile rescue robots. Journal of FIELD ROBOTICS Vol. 30, Issue 1 2013, pp. 44-63
  • 14. Sarkisov A. A., Vysotskii V. L., Bilashenko V.P., at al.: Expected radiological and radioecological consequences of operating floating nuclear heat and power plants. Atomic Energy Vol. 104, No. 3, 2008, pp. 237-248
  • 15. Standring W.J.F, Dowdall M., Amundsen I., Strad P.: Floating nuclear power plants: Potential implications for radioactive pollution of the northern marine environment. Marine Pollution Bulletin, 58, 2009, pp.174-178
  • 16. Takamatsu K., Hu R.: New reactor cavity cooling system having passive safety features using novel shape for HTGRs and VHTRs. Annals of Nuclear Energy, 77, 2015, pp. 165-171
Uwagi
Opracowanie rekordu w ramach umowy 509/P-DUN/2018 ze środków MNiSW przeznaczonych na działalność upowszechniającą naukę (2019).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-de1e3e19-c53a-49d5-b6a1-583e1a5591c2
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