EPJ Nuclear Sci. Technol.
Volume 3, 2017
|Number of page(s)||12|
|Published online||21 March 2017|
- J. Duderstadt, L. Hamilton, Nuclear reactor analysis (John Wiley & Sons, New York, 1976) [Google Scholar]
- J. Porta, M. Asou, Erbium: alternative poison? Stabilisation additive? What future? Prog. Nucl. Energy 38, 347 (2001) [CrossRef] [Google Scholar]
- M. Asou, J. Porta, Prospects for poisoning reactor cores of the future, Nucl. Eng. Des. 168, 261 (1997) [CrossRef] [Google Scholar]
- J. Porta et al., Qualification of the neutronic efficiency of erbium at zero burnup, Prog. Nucl. Energy 38, 355 (2001) [CrossRef] [Google Scholar]
- OECD, Nuclear energy agency report no. 6224, very high burn-ups in light water reactors (OECD, Paris, 2006) [Google Scholar]
- 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]
- M. Yamasaki et al., Development of erbia-credit super high burnup fuel: experiments and numerical analyses, Nucl. Technol. 177, 63 (2012) [CrossRef] [Google Scholar]
- S. Yamanaka et al., Thermal and mechanical properties of (U, Er)O2, J. Nucl. Mater. 389, 115 (2009) [CrossRef] [Google Scholar]
- IAEA-THPH, Thermophysical properties of materials for nuclear engineering: a tutorial and collection data (IAEA-THPH, Vienna, 2008) [Google Scholar]
- R. Sanchez et al., APOLLO2 Year 2010, Nucl. Eng. Technol. 42, 474 (2010) [CrossRef] [Google Scholar]
- 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: http://www.epr-reactor.co.uk/scripts/ssmod/publigen/content/templates/show.asp?P=290&L=EN [Google Scholar]
- 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]
- M. Oguma, Cracking and relocation behaviour of nuclear fuel pellets during rise to power, Nucl. Eng. Des. 76, 35 (1983) [CrossRef] [Google Scholar]
- 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]
- 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]
- U.S.NRC, Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO, March 2011 (2011) [Google Scholar]
- 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]
- 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]
- J.R. Lamarsh, A.J. Baratta, Introduction to nuclear engineering (Prentice Hall, Upper Saddle River, New Jersey, 2001) [Google Scholar]
- 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]
- 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]
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.