Minor actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor
By: Piotr Darnowski and Nikolaj Uzunow
References
- 1. Bunker, M. E. (1983). Early reactors – from Fermi's water boiler to novel power prototypes., 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:.
- 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 Unpublished doctoral dissertation, Royal Institute of Technology, Stockholm, Sweden.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.,, 597–605.
- 10. Salvatores, M., & Palmiotti, G. (2011). Radioactive waste partitioning and transmutation with advanced fuel cycles: Achievements and challenges.,, 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.
- 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 transmutation and fuel burnup in BN-600 hybrid fast reactor core.,(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.,, 629–638.
- 22. Rineiski, A., Ishikawa, M., Jang, J., Mohanakrishnan, P., Newton, T., Rimpault, G., Stanculescu, A., & Stogov, V. (2011). Reactivity coefficients in BN-600 core with minor actinides.,, 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.,, 221–224.
- 26. Brookhaven National Laboratory. (2013). National Nuclear Data Center. December 10, 2013, from.
- 27. Lewis, E. E. (2008). Fundamentals of nuclear reactor physics. New York: Academic Press.
- 28. Wallenius, J. (2012). Physics of americium transmutation.,(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.,, 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.,, 1589–1598.
DOI: https://doi.org/10.1515/nuka-2015-0034 | Journal eISSN: 1508-5791 (formerly 0029-5922) | Journal ISSN: 0029-5922
Language: English
Page range: 171 - 179
Submitted on: Apr 25, 2014
Accepted on: Jan 23, 2015
Published on: Mar 12, 2015
Published by: Institute of Nuclear Chemistry and Technology
In partnership with: Paradigm Publishing Services
Related subjects:
© 2015 Piotr Darnowski, Nikolaj Uzunow, published by Institute of Nuclear Chemistry and Technology
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.