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Fuel Cycle and Management

Development of Erbia-Credit Super-High-Burnup Fuel: Evaluation of Minimum Erbia Content for Criticality Safety Analyses

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Pages 18-27 | Published online: 20 Mar 2017

References

  • GREGG R. and WORRALL A., “Effect of Highly Enriched0 Highly Burnt UO2 Fuels on Nuclear Design Parameters and Economics,” Proc. Advances in Nuclear Fuel Management III (ANFM III), Hilton Head Island, South Carolina, October 5–8, 2003, American Nuclear Society (2003) (CD-ROM).
  • SECKER J. R. et al., “Optimum Discharge Burnup and Cycle Length for PWRs,” Proc. Advances in Nuclear Fuel Management III (ANFM III), Hilton Head Island, South Carolina, October 5–8, 2003, American Nuclear Society (2003) (CD-ROM).
  • DAMON D. R. and MOREY D. C., “Criticality Safety Limits at 5 to 20% Enrichment,” Trans. Am. Nucl. Soc., 78, 138 (1998).
  • PAULSON L. E. and PETERS W. C., “GE Validation to Support Fuel Fabrication up to 10% Enrichment,” Trans. Am. Nucl. Soc., 78, 139 (1998).
  • YAMASAKI M. et al., “Development of Erbia-Credit Super High Burnup Fuel: Experiments and Numerical Analyses,” Nucl. Technol., 177, 63 (2012).
  • YOSHIOKA K. et al., “A Minimal-Content Gadolinia in Above-5wt% Enrichment Fuel for Criticality Safety in Next Generation LWR,” Proc. Advances in Nuclear Fuel Management IV (ANFM IV), Hilton Head Island, South Carolina, April 12–15, 2009, American Nuclear Society (2009) (CD-ROM).
  • SUGIMURA N. et al., “The Concept of Erbia Bearing Super-High-Burnup Fuel,” Proc. Advances in Nuclear Fuel Management IV (ANFM IV), Hilton Head Island, South Carolina, April 12–15, 2009, American Nuclear Society (2009) (CD-ROM).
  • YAMASAKI M. et al., “The Outline of Development Project on Erbia Bearing Super-High-Burnup Fuel,” Proc. Advances in Nuclear Fuel Management IV (ANFM IV), Hilton Head Island, South Carolina, April 12–15, 2009, American Nuclear Society (2009) (CD-ROM).
  • “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations,” ORNL/TM-2005/39, Version 6, Oak Ridge National Laboratory (2009).
  • NAGAYA Y. et al., “MVP/GMVP Version 2: General Purpose Monte-Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods,” JAERI 1348, Japan Atomic Energy Research Institute (2005).
  • KUROISHI T. et al., “Calculated Results of KUCA Criticality Experiments for Er-SHB Fuel by Using SCALE Code System,” Proc. Int. Conf. Nuclear Criticality 2011 (ICNC2011), Edinburgh, Scotland, United Kingdom, September 19–23, 2011 (CD-ROM).

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