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Fuel cycle analysis of Advanced Burner Reactor with breed-and-burn thorium blanket 원문보기

Annals of nuclear energy, v.112, 2018년, pp.383 - 394  

Zhang, Guanheng (Corresponding author.) ,  Fratoni, Massimiliano ,  Greenspan, Ehud

Abstract AI-Helper 아이콘AI-Helper

Abstract The Seed-and-Blanket (S&B) Sodium-cooled Fast Reactor (SFR) core concept was proposed for generating a significant fraction of the core power from thorium fueled breed-and-burn (B&B) blankets without exceeding the presently verified radiation damage constraint of 200 Displacement per Atom ...

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참고문헌 (35)

  1. Prog. Nucl. Energy Ault 100 114 2017 10.1016/j.pnucene.2017.05.010 Comparing the environmental impacts of uranium- and thorium-based fuel cycles with different recycle options 

  2. Nucl. Technol. Bathke 179 1 5 2012 10.13182/NT10-203 The attractiveness of materials in advanced nuclear fuel cycles for various proliferation and theft scenarios 

  3. Bathke, C.G., et al., 2014. An assessment of the attractiveness of material associated with thorium fuel cycles. In: Transactions of the American Nuclear Society, Anaheim, California. 

  4. Nucl. Technol. Brown 194 2 233 2016 10.13182/NT15-40 Thorium fuel cycles with externally driven systems 

  5. Driscoll 1979 An Evaluation of the Breed/Burn Fast Reactor Concept 

  6. Dubberley, A.E., et al., 2000. SuperPRISM oxide and metal fuel core designs. In: Proceedings of ICONE 8, MD, USA. 

  7. Ann. ICRP Eckerman 41 2012 10.1016/j.icrp.2012.06.038 Compendium of dose coefficients based on ICRP Publication 60. ICRP Publication 119 

  8. Ellis, T.P., et al., 2010. Traveling-wave reactors: a truly sustainable and full-scale resource for global energy needs. In: Proceedings of ICAPP 2010, San-Diego, CA, USA. 

  9. Forsberg, C.W., Hopper, C.M., 1998. Definition of Weapons-Usable Uranium-233, ORNL/TM-13517. 

  10. Sustainability Greenspan 4 10 2745 2012 10.3390/su4102745 A phased development of breed-and-burn reactors for enhanced nuclear energy sustainability 

  11. Greneche, D., 2006. The thorium cycle: an assessment of its potentialities with a focus on non proliferation aspects. In: Transactions of the American Nuclear Society, Albuquerque, NM. 

  12. Hayes, S.L., et al., Development of metallic fuels for actinide transmutation. In: Proceedings of GLOBAL 2015, Paris, France. 

  13. Nucl. Sci. Eng. Heidet 171 1 13 2012 10.13182/NSE10-114 Neutron balance analysis for sustainability of breed-and-burn reactors 

  14. Rev. Accel. Sci. Technol. Heidet 8 99 2015 10.1142/S1793626815300066 Accelerator-reactor coupling for energy production in advanced nuclear fuel cycles 

  15. Nucl. Eng. Des. Heidet 2016 Impact of minor actinide recycling on sustainable fuel cycle options 

  16. Hoffman 2006 Preliminary Core Design Studies for the Advanced Burner Reactor Over a Wide Range of Conversion Ratios, ANL-AFCI-177 

  17. Prog. Nucl. Energy Hou 88 58 2016 10.1016/j.pnucene.2015.12.002 3D in-core fuel management optimization for breed-and-burn reactors 

  18. IAEA, 1999. The Physical Protection of Nuclear Material and Nuclear Facilities, INFCIRC/225/Rev.4. 

  19. Sci. Glob. Secur. Kang 9 1 2001 10.1080/08929880108426485 U-232 and the proliferation-resistance of U-233 in spent fuel 

  20. Ann. Nucl. Energy Kim 36 3 331 2009 10.1016/j.anucene.2008.12.021 Core design studies for a 1000 MWth advanced burner reactor 

  21. Nucl. Technol. Lin 197 1 29 2017 10.13182/NT16-90 Core design studies of a fast reactor and accelerator-driven system for two-stage fast spectrum fuel cycle option 

  22. Prog. Nucl. Energy Greenspan 53 7 794 2011 10.1016/j.pnucene.2011.05.002 Energy sustainability and economic stability with breed and burn reactors 

  23. J. Nucl. Mater. Manage. Pellaud 31 1 30 2002 Proliferation aspects of plutonium recycling 

  24. 10.1051/snamc/201402207 Seifried, J.E., et al., 2013. Accelerated equilibrium core composition search using a new MCNP-based simulator. In: Proceedings of Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA + MC 2013), Paris, France. 

  25. Nucl. Sci. Eng. Sekimoto 139 3 306 2001 10.13182/NSE01-01 CANDLE: the new burnup strategy 

  26. Shropshire 2009 Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems, INL/EXT-09-15254 

  27. J. Nucl. Sci. Technol. Stauff 52 7-8 1058 2015 10.1080/00223131.2015.1032380 Variations in nuclear waste management performance of various fuel-cycle options 

  28. Wigeland 2014 Nuclear Fuel Cycle Evaluation and Screening - Final Report, INL/EXT-14-31465 

  29. Nucl. Sci. Eng. Xu 151 3 261 2005 10.13182/NSE05-A2545 Impact of high burnup on PWR spent fuel characteristics 

  30. Trans. Am. Nucl. Soc. Zhang 111 p293 2014 Preliminary study of advanced sodium-cooled burner reactors with external and internal thorium blankets 

  31. Trans. Am. Nucl. Soc. Zhang 108 853 2013 Preliminary study of SFR with depleted uranium breed & burn blanket 

  32. Zhang, G., Greenspan, E., Jolodosky, A., Vujic, J., 2014. Sodium fast reactors with breed and burn blanket. In: Proceedings of the 19th Pacific Basin Nuclear Conference, Vancouver, Canada. 

  33. Prog. Nucl. Energy Zhang 82 2 2015 10.1016/j.pnucene.2014.07.044 SFR with once-through depleted uranium breed & burn blanket 

  34. Nucl. Technol. Zhang 199 2 187 2017 10.1080/00295450.2017.1337408 Advanced burner reactors with breed-and-burn thorium blankets for improved economics and resource utilization 

  35. Prog. Nucl. Energy Zhang 2017 Improved resource utilization by advanced burner reactors with breed-and-burn blankets 

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