1. bookVolume 60 (2015): Issue 1 (March 2015)
Journal Details
License
Format
Journal
eISSN
1508-5791
First Published
25 Mar 2014
Publication timeframe
4 times per year
Languages
English
access type Open Access

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

Published Online: 12 Mar 2015
Volume & Issue: Volume 60 (2015) - Issue 1 (March 2015)
Page range: 171 - 179
Received: 25 Apr 2014
Accepted: 23 Jan 2015
Journal Details
License
Format
Journal
eISSN
1508-5791
First Published
25 Mar 2014
Publication timeframe
4 times per year
Languages
English
Abstract

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.

Keywords

1. Bunker, M. E. (1983). Early reactors – from Fermi's water boiler to novel power prototypes. Los Alamos Science, Winter/Spring, 124–131.Search in Google Scholar

2. Waltar, A. E., Reynolds, A., Todd, D. R., & Tsvetkov, P. V. (2011). Fast spectrum reactors. New York : Springer.Search in Google Scholar

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.Search in Google Scholar

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).Search in Google Scholar

5. International Atomic Energy Agency. (2006). Fast Reactor Database 2006 Update. Vienna: Nuclear Power Technology Development Section IAEA. (IAEA-TECDOC-1531).Search in Google Scholar

6. U.S. DOE Nuclear Research Advisory Committee and the Generation IV International Forum. (2002). A Technology Roadmap for Generation IV Nuclear Energy Systems.Search in Google Scholar

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.Search in Google Scholar

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.Search in Google Scholar

9. Westlen, D. (2007). Reducing radiotoxicity in the long run. Prog. Nucl. Energy, 49, 597–605.10.1016/j.pnucene.2007.02.002Search in Google Scholar

10. Salvatores, M., & Palmiotti, G. (2011). Radioactive waste partitioning and transmutation with advanced fuel cycles: Achievements and challenges. Prog. Part. Nucl. Phys., 66, 144–166.10.1016/j.ppnp.2010.10.001Search in Google Scholar

11. Nifenecker, H., Meplan, O., & David, S. (2003). Accelerator driven subcritical reactors. Philadelphia, USA: Institute of Physics Publishing.10.1887/0750307439Search in Google Scholar

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.Search in Google Scholar

13. Los Alamos National Laboratory. (2008). MCNP – A General Monte Carlo N-Particle Transport Code Version 5. Los Alamos: X-5 Monte Carlo Team.Search in Google Scholar

14. Goorley, T. (2004). Criticality calculations with MCNP5: A primer. Los Alamos: Los Alamos National Laboratory X-5. (LA-UR-04-0294).Search in Google Scholar

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.Search in Google Scholar

16. Aziz, M., & Hassan, M. I. (2012). Isotopic transmutation and fuel burnup in BN-600 hybrid fast reactor core. Arab J. Nucl. Sci. App., 45(2), 419–426.Search in Google Scholar

17. Grasso, G. (2007). ELSY criticality analysis with MCNP – A preliminary study. Bologna: University of Bologna Nuclear Engineering Laboratory Montecuccolino.Search in Google Scholar

18. Juutilainen, P. (2008). Simulating the behaviour of the fast reactor JOYO. IYNC 2008, 20–26 September 2008 (Paper No. 163). Interlaken, Switzerland.Search in Google Scholar

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).Search in Google Scholar

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.Search in Google Scholar

21. Zhang, Y., Wallenius, J., & Fokau, Y. (2010). Transmutation of americium in a medium size sodium cooled fast reactor design. Ann. Nucl. Energy, 37, 629–638.10.1016/j.anucene.2009.12.014Search in Google Scholar

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. J. Nucl. Sci. Technol., 48, 635–645.10.1080/18811248.2011.9711744Search in Google Scholar

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.Search in Google Scholar

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.Search in Google Scholar

25. Michalek, S., Hascik, J., & Farkas, G. (2008). MCNP5 Delayed Neutron Fraction Calculation in Training Reactor VR-1. J. Electr. Eng., 59, 221–224.Search in Google Scholar

26. Brookhaven National Laboratory. (2013). National Nuclear Data Center. December 10, 2013, from http://www.nndc.bnl.gov.Search in Google Scholar

27. Lewis, E. E. (2008). Fundamentals of nuclear reactor physics. New York: Academic Press.Search in Google Scholar

28. Wallenius, J. (2012). Physics of americium transmutation. Nucl. Eng. Technol., 44(2), 199–206.10.5516/NET.01.2012.505Search in Google Scholar

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, 26–34.10.1016/j.anucene.2012.08.009Search in Google Scholar

30. Zhang, Y. (2012). Transmutation of Am in sodium fast reactors and accelerator driven systems. Unpublished doctoral dissertation, Royal Institute of Technology, Stockholm, Sweden.Search in Google Scholar

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, 1589–1598.10.1016/j.nucengdes.2006.04.019Search in Google Scholar

Recommended articles from Trend MD

Plan your remote conference with Sciendo