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

Treść / Zawartość
Identyfikatory
Warianty tytułu
Konferencja
All-Polish Seminar on Mössbauer Spectroscopy OSSM 2014 (10th ; 15-18.06.2014 ; Wrocław, Poland)
Języki publikacji
EN
Abstrakty
EN
An analysis of the infl uence 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 modifi ed 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-oflife (BOL) state. Additionally, some other parameters, such as Doppler constant, sodium void reactivity, delayed neutron fraction, neutron fl uxes 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 confi rms that the addition of MA has a negative effect on the delayed neutron fraction.
Czasopismo
Rocznik
Strony
171--179
Opis fizyczny
Bibliogr. 31 poz., rys.
Twórcy
autor
  • Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Str., 00-665, Warsaw, Poland, Tel./Fax: +48 22 234 5297
autor
  • Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Str., 00-665, Warsaw, Poland, Tel./Fax: +48 22 234 5297
Bibliografia
  • 1. Bunker, M. E. (1983). Early reactors – from Fermi’s water boiler to novel power prototypes. Los Alamos Science, Winter/Spring, 124–131.
  • 2. Waltar, A. E., Reynolds, A., Todd, D. R., & Tsvetkov, P. V. (2011). Fast spectrum reactors. New York : Springer.
  • 3. Fjaestad, M. (2009, August). Why did the Breed reactor fail? – Swedish and international nuclear development in a Cold War context. Centre of Excellence for Science and Innovation Studies – Electronic Working Paper Series. Paper No. 186. Stockholm, Sweden.Retrieved November 10, 2013, from: http://www.kth.se/dokument/itm/cesis/CESISWP186.pdf.
  • 4. International Atomic Energy Agency. (2007). Liquid metal cooled reactors: Experience in design and operation. Vienna: Nuclear Power Technology Development Section IAEA. (IAEA-TECDOC-1569).
  • 5. International Atomic Energy Agency. (2006). Fast Reactor Database 2006 Update. Vienna: Nuclear Power Technology Development Section IAEA.(IAEA-TECDOC-1531).
  • 6. U.S. DOE Nuclear Research Advisory Committee and the Generation IV International Forum. (2002). A Technology Roadmap for Generation IV Nuclear Energy Systems.
  • 7. Westlen, D. (2007). Why faster is better – on minor actinide transmutation in hard neutron spectra. Unpublished doctoral dissertation, Royal Institute of Technology, Stockholm, Sweden.
  • 8. Nuclear Energy Agency – Organisation for Economic Co-Operation and Development. (2002). Accelerator-Driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles – A Comparative Study. Paris: NEA OECD.
  • 9. Westlen, D. (2007). Reducing radiotoxicity in the long run. Prog. Nucl. Energy, 49, 597–605.
  • 10. Salvatores, M., & Palmiotti, G. (2011). Radioactive waste partitioning and transmutation with advanced fuel cycles: Achievements and challenges. Prog. Part.Nucl. Phys., 66, 144–166.
  • 11. Nifenecker, H., Meplan, O., & David, S. (2003).Accelerator driven subcritical reactors. Philadelphia,USA: Institute of Physics Publishing.
  • 12. Wallenius, J. (2011). Transmutation of nuclear waste.Royal Institute of Technology. Retrieved August, 2012,from KTH Reactor Physics Division http://neutron.kth.se/courses/Transmutation.shtml.
  • 13. Los Alamos National Laboratory. (2008). MCNP −A General Monte Carlo N-Particle Transport Code Version 5. Los Alamos: X-5 Monte Carlo Team.
  • 14. Goorley, T. (2004). Criticality calculations with MCNP5: A primer. Los Alamos: Los Alamos National Laboratory X-5. (LA-UR-04-0294).
  • 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.
  • 16. Aziz, M., & Hassan, M. I. (2012). Isotopic transmutationand fuel burnup in BN-600 hybrid fast reactor core. Arab J. Nucl. Sci. App., 45(2), 419–426.
  • 17. Grasso, G. (2007). ELSY criticality analysis with MCNP – A preliminary study. Bologna: University of Bologna Nuclear Engineering Laboratory Montecuccolino.
  • 18. Juutilainen, P. (2008). Simulating the behaviour of the fast reactor JOYO. IYNC 2008, 20–26 September 2008 (Paper No. 163). Interlaken, Switzerland.
  • 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.
  • 22. Rineiski, A., Ishikawa, M., Jang, J., Mohanakrishnan, P., Newton, T., Rimpault, G., Stanculescu, A., & Stogov, V. (2011). Reactivity coeffi cients in BN-600 core with minor actinides. J. Nucl. Sci. Technol., 48, 635–645.
  • 23. Mazgaj, P. E. (2010). Conceptual neutronic design of a 300 MWth lead fast reactor core. Unpublished M.Sc. thesis, Warsaw University of Technology, Warsaw, Poland.
  • 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.
  • 26. Brookhaven National Laboratory. (2013). National Nuclear Data Center. December 10, 2013, from http://www.nndc.bnl.gov.
  • 27. Lewis, E. E. (2008). Fundamentals of nuclear reactor physics. New York: Academic Press.
  • 28. Wallenius, J. (2012). Physics of americium transmutation.Nucl. Eng. Technol., 44(2), 199–206.
  • 29. Zhang, Y., Wallenius, J., & Jolkkonen, M. (2013). Transmutation of americium in a large sodium-cooled fast reactor loaded with nitride fuel. Ann. Nucl. Energy,53, 26–34.
  • 30. Zhang, Y. (2012). Transmutation of Am in sodium fast reactors and accelerator driven systems. Unpublished doctoral dissertation, Royal Institute of Technology, Stockholm, Sweden.
  • 31. Tucek, K., Carlsson, J., & Wider, H. (2006). Comparison of sodium and lead-cooled fast reactors regarding reactor physics apects severe safety and economical issues. Nucl. Eng. Design, 236, 1589–1598.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-be7478b5-115c-4cb6-b8cc-f948146c32ef
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