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The Uranium Fuel Cycle

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The Uranium Fuel Cycle Robert Tsai November 21, 2006 Overview Front end Mining Milling Enrichment / fuel fabrication Service period Back end Transport and storage ... – PowerPoint PPT presentation

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Title: The Uranium Fuel Cycle


1
The Uranium Fuel Cycle
  • Robert Tsai
  • November 21, 2006

2
Overview
  • Front end
  • Mining
  • Milling
  • Enrichment / fuel fabrication
  • Service period
  • Back end
  • Transport and storage
  • Disposal (open fuel cycle)
  • Reprocessing (closed fuel cycle)

3
Mining Processes
  • World reserves
  • 3.1 million tU
  • Open-pit mining 30
  • Underground mining 38 (55 in 1990)
  • In situ leaching (ISL) 21

4
Milling Uranium Extraction
  • Grinding (100 microns)
  • Acid (H2SO4) or alkaline (Na2CO3 / NaHCO3) leach
  • Solid / liquid separation of slurry
  • Purification (simple or extensive)
  • Precipitation diuranate salt (e.g. Na2U2O7)
  • Drying

Uranium oxide concentrate (UOC) (predominantly
U3O8)
5
Milling Uranium Conversion
  • Dissolving of U3O8 in HNO3
  • Calcination (strong heating) ? UO3
  • Reduction with H2 ? UO2
  • Hydrofluorination (HF) ? UF4
  • Fluorination (F2) ? UF6
  • In most cases, end-use requires conversion to UF6
    for enrichment
  • However, certain reactors (CANDU) can use
    natural UO2

6
Enrichment
  • Natural uranium 235U 0.7, 238U 99.3
  • Reactor-grade 235U increased to 3-5
  • Necessary to sustain fission chain reaction
  • Methods
  • Gas diffusion (GD)
  • High-speed gas centrifugation (GC)
  • 5 of power requirements for GD
  • Laser technology (still in development)
  • Afterward, UF6 converted back to UO2 for
    mechanical processing (fuel rods)

7
Service Period
  • Fission process depletes fuel
  • 235U ? 92Kr, 141Ba
  • 238U ? 239U ? 239Pu
  • PWRs and BWRs reloaded bet/1-2 years, 1/4-1/3 of
    assemblies replaced
  • Complicated optimization problem
  • Maximize core reactivity
  • Top priority to safety / operational limitations

8
Transport and Storage
  • At Reactor (AR) storage
  • Handle intense radioactivity of
    freshly-discharged fuel
  • Wet (cooling ponds) vs. dry
  • Transport via heavily-shielded flasks
  • Away From Reactor (AFR) storage
  • Similar set-up to AR facilities
  • NRC has repeatedly confirmed storages safety,
    minimal environmental impact

9
Disposal (Open Fuel Cycle)
  • No permanent disposal procedures have been
    implemented in the world
  • Plans for 2010?
  • Consensus burial deep underground after period
    of interim storage
  • Safeguards vitrification, corrosion-resistant
    canisters, constant monitoring (106 years)
  • U.S. waste Yucca Mountain in Nevada

10
Reprocessing (Closed Fuel Cycle)
  • Similar process as with fresh feed
  • Benefits
  • Resource conservation
  • Decreased waste load
  • Use of ex-military material
  • Uranium plutonium ? MOX fuel
  • Major challenge build-up of by-products

11
Conclusions
  • Front end
  • Well developed and understood process
  • Gas centrifugation best available enrichment
    technology
  • Future of lasers questionable
  • Back end
  • Underground disposal viable but will always have
    critics
  • Reprocessing necessary but has limitations
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