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2015 | 60 | 1 | 171-179
Tytuł artykułu

Minor actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor

Treść / Zawartość
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
An analysis of the influence of addition of minor actinides (MA) to the fast reactor fuel on the most important safety characteristics was performed. A special emphasis was given to the total control rods worth in order to describe qualitatively and quantitatively its change with MA content. All computations were performed with a homogeneous assembly model of modified BN-600 sodium-cooled fast reactor core with 0, 3 and 6% of MA. A model was prepared for the Monte Carlo neutron transport code MCNP5 for fresh fuel in the beginning-of-life (BOL) state. Additionally, some other parameters, such as Doppler constant, sodium void reactivity, delayed neutron fraction, neutron fluxes and neutron spectra distribution, were computed and their change with MA content was investigated. Study indicates that the total control rods worth (CRW) decreases with increasing MA inventory in the fuel and confirms that the addition of MA has a negative effect on the delayed neutron fraction.
Wydawca

Czasopismo
Rocznik
Tom
60
Numer
1
Strony
171-179
Opis fizyczny
Daty
wydano
2015-03-01
otrzymano
2014-04-25
zaakceptowano
2015-01-23
online
2015-03-12
Twórcy
  • Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Str., 00-665, Warsaw, Poland, Tel./Fax: +48 22 234 5297, piotr.darnowski@itc.pw.edu.pl
  • Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Str., 00-665, Warsaw, Poland, Tel./Fax: +48 22 234 5297
Bibliografia
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  • 15. Darnowski, P. (2013). Neutronic analysis of modified BN-600 fast reactor core with minor actinides. Unpublished master thesis, Warsaw University of Technology, Warsaw, Poland.
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  • 17. Grasso, G. (2007). ELSY criticality analysis with MCNP – A preliminary study. Bologna: University of Bologna Nuclear Engineering Laboratory Montecuccolino.
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  • 19. International Atomic Energy Agency. (2010). Hybrid Core Benchmark Analyses Results from a Coordinated Research Project on Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR Reactivity Effects. Vienna: Nuclear Power Technology Development Section IAEA. (IAEA-TECDOC-1623).
  • 20. Kim, Y. I., Hill, R., Grimm, K., Newton, T., Li, Z. H., Rineski, A., Mohanakrishan, P., Ishikawa, M., Lee, K. B., Danilytchev, A., & Stogov, V. (2004). BN-600 Full MOX Core Benchmark Analysis. In PHYSOR 2004 – The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, 25–29 April 2004. Chicago, IL, USA: American Nuclear Society.
  • 21. Zhang, Y., Wallenius, J., & Fokau, Y. (2010). Transmutation of americium in a medium size sodium cooled fast reactor design. Ann. Nucl. Energy, 37, 629–638.[WoS]
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  • 24. Ravnik, M., & Snoj, L. (2006). Calculation of power density with MCNP in TRIGA reactor. International Conference Nuclear Energy for New Europe, 18–21 September 2006 (Paper No. 109). Portoroz, Slovenia.
  • 25. Michalek, S., Hascik, J., & Farkas, G. (2008). MCNP5 Delayed Neutron Fraction Calculation in Training Reactor VR-1. J. Electr. Eng., 59, 221–224.
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Typ dokumentu
Bibliografia
Identyfikatory
Identyfikator YADDA
bwmeta1.element.-psjd-doi-10_1515_nuka-2015-0034
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