Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2013, Article ID 217548, 11 pages
http://dx.doi.org/10.1155/2013/217548
Research Article

Fine Distributed Moderating Material with Improved Thermal Stability Applied to Enhance the Feedback Effects in SFR Cores

Department of Reactor Safety, Institute of Resource Ecology, Helmholtz-Zentrum Dresden-Rossendorf, P.O. Box 51 01 19, 01314 Dresden, Germany

Received 16 July 2013; Revised 29 August 2013; Accepted 4 September 2013

Academic Editor: Konstantin Mikityuk

Copyright © 2013 Bruno Merk. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. “IAEA TM on Innovative Fast Reactor Designs with Enhanced Negative Reactivity Feedback Features,” IAEA Headquarters, Vienna, Austria, 2012, http://www.iaea.org/NuclearPower/Meetings/2012/2012-02-27-02-29-TM-NPTD.html.
  2. R. N. Hill and H. Khalil, “Evaluation of LMR design options for reduction of sodium void worth,” in Proceedings of the International Conference on Physics of Reactors, vol. 1, pp. 11–19, Marseille, France, 1990.
  3. G. Rimpault, L. Buiron, P. Sciora, and F. Varaine, “Towards GEN IV SFR design: promising ideas for large advanced SFR core designs,” in Proceedings of the International Conference on the Physics of Reactors (PHYSOR '08), pp. 2394–2400, Bern, Switzerland, September 2008. View at Scopus
  4. L. Buiron, P. Dufour, G. Rimpault et al., “Innovative core design for generation IV sodium-cooled fast reactors,” in Proceedings of the International Conference on Advances in Nuclear Power Plants (ICAPP '07), Nice, France, May 2007. View at Scopus
  5. K. Sun, J. Krepel, K. Mikityuk, and R. Chawla, “A neutronics study for improving the safety and performance parameters of a 3600 MWth sodium-cooled fast reactor,” Annals of Nuclear Energy, vol. 53, pp. 464–475, 2013. View at Google Scholar
  6. A. Rineiski, B. Vezzoni, D. Zhang, X.-N. Chen, F. Gabrielli, and M. Marchetti, “Sodium void effect reduction and minor actinide incineration in ESFR,” Transactions of the American Nuclear Society, vol. 104, pp. 720–721, 2011. View at Google Scholar
  7. M. S. Chenaud, N. Devictor, G. Mignot et al., “Status of the astrid core at the end of the pre-conceptual design,” in Proceedings of the International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), Paris, France, March 2013.
  8. B. Merk, S. Kliem, E. Fridman, and F. P. Weiß, “On the use of zirconium based moderators to enhance the feedback coefficients in a MOX fuelled sodium cooled fast reactor,” Nuclear Science and Engineering, vol. 171, no. 2, pp. 136–149, 2012. View at Google Scholar
  9. B. Merk, E. Fridman, and F. P. Weiß, “On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors,” Annals of Nuclear Energy, vol. 38, no. 5, pp. 921–929, 2011. View at Publisher · View at Google Scholar · View at Scopus
  10. B. Merk and F.-P. Weiß, “Analysis of the influence of different arrangements for ZrH moderator material on the performance of a SFR core,” Annals of Nuclear Energy, vol. 38, no. 11, pp. 2374–2385, 2011. View at Publisher · View at Google Scholar · View at Scopus
  11. B. Merk and F. P. Weiß, “On the effect of different placing ZrH moderator material on the performance of a SFR core,” in Proceedings of the Advances in Reactor, Physics—Linking Research, Industry, and Education, Knoxville, Tenn, USA, April 2012.
  12. B. Merk and F. P. Weiß, “On the use of moderating material to enhance the feedback coefficients in SFR cores with high minor actinide content,” in Proceedings of the International Conference of Applied Psychology (ICAPP '12), Paper 12428, Chicago, Ill, USA, June 2012.
  13. B. Merk, “Moderating material to compensate the drawback of high minor actinide containing transmutation fuel on the feedback effects in SFR cores,” Science and Technology of Nuclear Installations, vol. 2013, Article ID 172518, 10 pages, 2013. View at Publisher · View at Google Scholar
  14. B. Merk, “On the use of fine distributed moderating material to enhance feedback coefficients in fast reactors,” in Proceedings of the IAEA TM on Innovative Fast Reactor Designs with Enhanced Negative Reactivity Feedback Features, Vienna, Austria, February 2012.
  15. E. A. Villarino, R. J. J. Stamm'ler, A. A. Ferri, and J. J. Casal, “HELIOS: angularly dependent collision probabilities,” Nuclear Science and Engineering, vol. 112, no. 1, pp. 16–31, 1992. View at Google Scholar · View at Scopus
  16. R. Sanchez, J. Mondot, Z. Stankovski, A. Cossic, and I. Zmijarevic, “APOLLO II: a user-oriented, portable, modular code for multigroup transport assembly calculations,” Nuclear Science and Engineering, vol. 100, no. 3, pp. 352–362, 1988. View at Google Scholar · View at Scopus
  17. IAEA Fast Reactor Database—2006 Update, http://www.iaea.org/nuclearenergy/nuclearknowledge/.
  18. A. E. Waltar and A. B. Reynolds, Fast Breeder Reactors, Pergamon Press, New York, NY, USA, 1981.
  19. A. Pay, E. Francillon, B. Steinmetz, D. Barnes, and N. Meda, “European Fast Reactor (EFR) fuel element design,” in Proceedings of the 10th International Conference on Structural Mechanics in Reactor Technology, Anaheim, Calif, USA, 1989.
  20. HELIOS Methods, Studsvik Scandpower, Waltham, Mass, USA, 2003.
  21. R. Rachamin, C. Wemple, and E. Fridman, “Neutronic analysis of SFR core with HELIOS-2, SERPENT, and DYN3D codes,” Annals of Nuclear Energy, vol. 55, pp. 194–204, 2013. View at Publisher · View at Google Scholar
  22. W. M. Mueller, J. P. Blackledge, and G. G. Libowitz, Metal Hydrides, Academic Press, New York, NY, USA, 1968.
  23. K. Tsujimoto, T. Iwasaki, N. Hirakawa, T. Osugi, S. Okajima, and M. Andoh, “Improvement of reactivity coefficients of metallic fuel LMFBR by adding moderating material,” Annals of Nuclear Energy, vol. 28, no. 9, pp. 831–855, 2001. View at Publisher · View at Google Scholar · View at Scopus
  24. D. Olander, E. Greenspan, H. D. Garkisch, and B. Petrovic, “Uranium-zirconium hydride fuel properties,” Nuclear Engineering and Design, vol. 239, no. 8, pp. 1406–1424, 2009. View at Publisher · View at Google Scholar · View at Scopus
  25. J. C. Lefèvre, C. H. Mitchell, and G. Hubert, “European fast reactor design,” Nuclear Engineering and Design, vol. 162, no. 2-3, pp. 133–143, 1996. View at Google Scholar · View at Scopus
  26. U. Rohde, U. Grundmann, and S. Kliem, “DYN3D—advanced reactor simulations in 3D,” Nuclear Energy Review, vol. 2, pp. 28–30, 2007. View at Google Scholar
  27. C. Beckert and U. Grundmann, “A nodal expansion method for solving the multigroup SP3 equations in the reactor code DYN3D,” in Proceedings of the Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications (M&C+SNA '07), Monterey, Calif, USA, April 2007. View at Scopus
  28. E. S. Funston, “Physical properties of yttrium hydride,” in Nuclear Metallurgy, A Symposium on Metallic Moderators and Cladding Materials, American Institute of Mining and Metallurgical Engineers, New York, NY, USA, 1960. View at Google Scholar
  29. C. V. Owen and T. E. Scott, “Hydrogen embrittlement of yttrium,” Journal of the Less-Common Metals, vol. 90, no. 2, pp. 275–282, 1983. View at Google Scholar · View at Scopus
  30. J. B. Vetrano, “Hydrides as neutron moderator and reflector materials,” Nuclear Engineering and Design, vol. 14, no. 3, pp. 390–412, 1971. View at Google Scholar · View at Scopus
  31. R. van Houten, “Selected engineering and fabrication aspects of nuclear metal hydrides (Li, Ti, Zr, and Y),” Nuclear Engineering and Design, vol. 31, no. 3, pp. 434–448, 1974. View at Google Scholar · View at Scopus
  32. D. W. Wootan, J. A. Caggiano, L. L. Carter, D. P. Jordheim, and A. H. Lu, “Isotope production test in the fast flux test facility,” in Proceedings LMR: A Decade of LMR Progress and Promise, Washington, DC, USA, November 1990, American Nuclear Society, La Grange Park, Ill, USA, 1990. View at Google Scholar
  33. D. W. Wootan, J. A. Rawlins, L. L. Carter, H. R. Brager, and R. E. Schenter, “Analysis and results of a hydrogen-moderated isotope production assembly in the fast flux test facility,” Nuclear Science and Engineering, vol. 103, no. 2, pp. 150–156, 1989. View at Google Scholar · View at Scopus