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Sodium-Cooled Fast Reactor

Sodium-Cooled Fast Reactor. First Preliminary Report: Fuel Composition Analysis. Base Core . Driver Fuel: Weapons Grade Plutonium Host Fuel: Natural Uranium. Comparison to Reference Core. TRU Transmutation Optimization. Two approaches: Host Fuel Modification Thorium Host Fuel

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Sodium-Cooled Fast Reactor

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  1. Sodium-Cooled Fast Reactor First Preliminary Report: Fuel Composition Analysis Fynan, Mar, Sirajuddin

  2. Base Core • Driver Fuel: Weapons Grade Plutonium • Host Fuel: Natural Uranium Fynan, Mar, Sirajuddin

  3. Comparison to Reference Core Fynan, Mar, Sirajuddin

  4. TRU Transmutation Optimization • Two approaches: • Host Fuel Modification • Thorium Host Fuel • Enriched Uranium Host Fuel (Reactor Grade) • Introduction of Burnable Poisons Fynan, Mar, Sirajuddin

  5. Host Fuel Modification • Natural thorium host fuel transmutes over double that of the natural uranium host fuel • Enriched Uranium unsuitable as a host fuel Fynan, Mar, Sirajuddin

  6. Poison impact on transmutation potential relatively low, and insensitive to poison positioning Burnable Poisons Fynan, Mar, Sirajuddin

  7. Reactor Grade Plutonium Driver Fuel • Loss of transmutation efficiency with introduction of BP Fynan, Mar, Sirajuddin

  8. Recycled LWR Spent Fuel Driver • Lower reactivity swing than WGPu driver fuel core Fynan, Mar, Sirajuddin

  9. Power Density Comparisons Fynan, Mar, Sirajuddin

  10. Power Density Comparisons • Uranium host fuel yielded highest power density (925.378 W/cc) • Average difference between max power between uranium host and thorium host ≈ 231.31 W/cc • Compositions with WGPu driver gave highest power densities • BP introduction did not detriment power out significantly ≈ 35.697 W/cc difference on average • Maximum power density independent of BP positioning Fynan, Mar, Sirajuddin

  11. Power Distribution Analysis: Axial Fynan, Mar, Sirajuddin

  12. Power Distribution Analysis: Axial • Cosine shape, with maximum at center of fuel pin • Power fluctuations are small between: • Differenet BP positioning • Uranium and thorium fuel compositions Fynan, Mar, Sirajuddin

  13. Power Distribution Analysis: Radial Fynan, Mar, Sirajuddin

  14. Power Distribution Analysis: Radial • Power peaks at center of core • Decrease occurs due to configuration of low and high energy drivers • Power increases near outer core due to increased flux from reflectors Fynan, Mar, Sirajuddin

  15. Future Prospects Fynan, Mar, Sirajuddin

  16. References • [1] N.J. Nicholas, K.L. Coop and R.J. Estep, Capability and Limitation Study of DDT Passive-Active Neutron Waste Assay Instrument (Los Alamos: Los Alamos National Laboratory, LA-12237-MS, 1992). • [2] Plutonium Fuel: An Assesment (Paris:OECD/NEA,1989) • [3] Hill RN, Wade DC, Liaw JR, and Fujita EK, Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle. Nuclear Science and Engineering: 121, 17-31 (1995) • [4] H. Conde, Introduction to ADS for Waste Incineration and Energy Production.(Uppsala University, SE751 10 Uppsala, Sweden) • Rebus3 for multi-group diffusion analysis • Argonne National Laboratory • MC2 for lattice physics calculations • Argonne National Laborator Fynan, Mar, Sirajuddin

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