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Tytuł artykułu

Safety issues as a start point for further investigations of fusion hybrids

Treść / Zawartość
Identyfikatory
Warianty tytułu
Konferencja
Proceedings of the International Conference on Development and Applications of Nuclear Technologies NUTECH-2011, 11-14 September 2011, Kraków, Poland
Języki publikacji
EN
Abstrakty
EN
Nuclear power plants supply nearly one sixth of the world electric energy production. Though nuclear power is a very efficient source of energy, it produces dangerous radioactive waste composed of nuclides characterized, among others, by a long decay time and containing also significant quantities of fissible and even fissile materials. Therefore, spent nuclear fuel must be carefully stored for at least hundreds of years, all this time needing permanent supervision. Simultaneously this cumbersome waste contains also important amounts of energy that should not be simply buried forever. Thus, in spite of the fact that ultimate disposal of spent nuclear fuel in adequate geological formations is recognized as safe for the energy hungry world that tries at the same time to avoid CO2 emissions, this is a hardly acceptable solution. Fortunately, there is an effective approach, namely – spent fuel recycling, particularly with the help of nuclear fusion. Simultaneously, one has to admit that this concept has not attained yet technological maturity, thus lengthy and costly investigations still are necessary before nuclear fusion achieves development level adequate to industrial application. Since every nuclear device must be generally safe, therefore this article raises a safety issue of fusion-fission hybrid design. In order to ensure the required reliability of evaluations the development of heterogeneous model of the device was assumed as the starting point for further respective research. The performed calculations have indicated that maintenance of subcriticality even in the case of system collapse is achievable.
Słowa kluczowe
Czasopismo
Rocznik
Strony
447--450
Opis fizyczny
Bibliogr. 10 poz., rys.
Twórcy
autor
  • AGH University of Science and Technology, Faculty of Energy and Fuels, al. A. Mickiewicza 30, 30-059 Krakow, Poland, staczanowski@gmail.com
Bibliografia
  • 1. Briesmeister JF (2000) MCNP – A General Monte Carlo N-Particle Transport Code. Version 4C”. Los Alamos National Laboratory Report LA-13709-M, USA
  • 2. Klueh RL, Hashimoto N, Sokolov MA et al. (2006) Mechanical properties of neutron-irradiated nickel-containing martensitic steels: II. Review and analysis of helium-effects studies. J Nucl Mater 357;1/3:169–182
  • 3. Lee EH, Hunn JD, Byun TS, Mansur LK (2000) Effects of helium on radiation-induced defect microstructure in austenitic stainless steel. J Nucl Mater 280:18–24
  • 4. Shikama T (2008) Study of irradiation effects in materials with high-neutron-flux fission reactors. Institute for Materials Research, Tohoku University 2-1-1 Katahira, Aobaku, Sendai, Japan
  • 5. Taczanowski S (2007) Premisses for use of fusion systems for actinide waste incineration. In: Proc of the 13th Int Conf on Emerging Nuclear Energy Systems, ICENES’2007, 3–8 June 2007, Istanbul, Turkey. www.icenes2007.org/icenes_proceedings/manuscripts.pdf/Session%2010C
  • 6. Taczanowski S, Domańska G, Cetnar J (1998) Fusion-driven transmutations of nuclear waste – a misconception or an incentive for promotion of fusion energy. Fusion Eng Des 41:455–460
  • 7. Ubeyli M (2006) On the radiation damage characterization of candidate first wall materials in a fusion reactor using various molten salts. J Nucl Mater 359;3:192–201
  • 8. van der Schaaf B, Petersen C, De Carlan Y et al. (2009) High dose, up to 80 dpa, mechanical properties of Eurofer 97. J Nucl Mater 386/388:236–240
  • 9. Wakai E, Hashimoto N, Miwa Y et al. (2000) Effect of helium production on swelling of F82H irradiated in HFIR. J Nucl Mater 283/287:799–805
  • 10. Wallenius J (2012) Cladding materials and radiation damage. www.neutron.kth.se/courses/GenIV/GenIVcladding. pdf
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ8-0023-0031
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