Open Access
EPJ Nuclear Sci. Technol.
Volume 3, 2017
Article Number 8
Number of page(s) 12
Published online 21 March 2017
  1. J. Duderstadt, L. Hamilton, Nuclear reactor analysis (John Wiley & Sons, New York, 1976) [Google Scholar]
  2. J. Porta, M. Asou, Erbium: alternative poison? Stabilisation additive? What future? Prog. Nucl. Energy 38, 347 (2001) [CrossRef] [Google Scholar]
  3. M. Asou, J. Porta, Prospects for poisoning reactor cores of the future, Nucl. Eng. Des. 168, 261 (1997) [CrossRef] [Google Scholar]
  4. J. Porta et al., Qualification of the neutronic efficiency of erbium at zero burnup, Prog. Nucl. Energy 38, 355 (2001) [CrossRef] [Google Scholar]
  5. OECD, Nuclear energy agency report no. 6224, very high burn-ups in light water reactors (OECD, Paris, 2006) [Google Scholar]
  6. M. Yamasaki, The study on erbia credit super-high-burnup fuel with isotopically modified erbia, in ANS 2010 Winter Meeting, Las Vegas, November 7–11, 2010 (2010) [Google Scholar]
  7. M. Yamasaki et al., Development of erbia-credit super high burnup fuel: experiments and numerical analyses, Nucl. Technol. 177, 63 (2012) [CrossRef] [Google Scholar]
  8. S. Yamanaka et al., Thermal and mechanical properties of (U, Er)O2, J. Nucl. Mater. 389, 115 (2009) [CrossRef] [Google Scholar]
  9. IAEA-THPH, Thermophysical properties of materials for nuclear engineering: a tutorial and collection data (IAEA-THPH, Vienna, 2008) [Google Scholar]
  10. R. Sanchez et al., APOLLO2 Year 2010, Nucl. Eng. Technol. 42, 474 (2010) [CrossRef] [Google Scholar]
  11. UK EPR, The pre-construction safety report, sub-chapters 4.2 (fuel system design) and 4.4 (thermal and hydraulic design) (UK EPR, 2012), available at: [Google Scholar]
  12. W.G. Luscher, K.J. Geelhood, Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4 and MATPRO, US-NRC NUREG/CR-7024, August 2010 (2010) [Google Scholar]
  13. M. Oguma, Cracking and relocation behaviour of nuclear fuel pellets during rise to power, Nucl. Eng. Des. 76, 35 (1983) [CrossRef] [Google Scholar]
  14. K.J. Geelhood, W.G. Luscher, C.E. Beyer, FRAPCON-3.4: A Computer Code for the Calculation of Steady-State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, NUREG/CR-7022, PNNL-19418, Washington D.C. (2011), Vol. 1 [Google Scholar]
  15. T. Kozlowski, T. Downar, Pressurized water reactor MPX/UO2 core transient benchmark final report, NEA/NSC/DOC(2006)20, Technical Report (OECD/NEA and US NRC, Paris, 2006) [Google Scholar]
  16. U.S.NRC, Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO, March 2011 (2011) [Google Scholar]
  17. R. Gregg, A. Worrall, Effect of highly enriched/highly burnt UO2 fuels on nuclear design parameters and economics, in Advances in Nuclear Fuel Management III (ANFM 2003), Hilton Head Island, South Carolina, October 5–8, 2003 (2003) [Google Scholar]
  18. J.R. Secker et al., Optimum Discharge Burnup and Cycle Lenght for PWRs, in Advances in Nuclear Fuel Management III (ANFM 2003), Hilton Head Island, South Carolina, October 5–8, 2003 (2003) [Google Scholar]
  19. J.R. Lamarsh, A.J. Baratta, Introduction to nuclear engineering (Prentice Hall, Upper Saddle River, New Jersey, 2001) [Google Scholar]
  20. R.D. Mosteller, The Doppler-defect benchmark: overview and summary of results, in Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications, Monterey, April 15–19, 2007 (2007) [Google Scholar]
  21. S.C. McCutcheon, J.L. Martin, T.O. Barnwell Jr., Water quality, in Handbook of hydrology, edited by D.R. Maidment (McGraw-Hill, New York, 1993) [Google Scholar]

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