The Curious Tale of Molten Salt Reactors - media.cns-snc.ca

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Fast Breeder Fuel Cycle Costs • Sodium Fast Breeder • Capex of reprocessing equipment??? • Fabrication costs? • Looking only at the initial load of fissile* • Need ~ 18 Tonnes Reactor Grade Pu (12 T fissile) – 100$/gram = 1.8 B$ = 2.3 c/kwh • Or start on ~ 20 T U235 at 50$/g = 1.25 c/kwh – 20 years worth of U235 for a LWR – Over a hundred years worth for a DMSR • This does ignore Pu production credit but processing costs must be factored in • IFR or TWR are about half traditional FBR startup • * Yes, there are current stockpiles of separated Pu but limited supply and paid by tax payers.
MSBR Fuel Cycle Costs Estimate based on ORNL 4541 and 4812 (1972) and 7.5 times “nuclear” inflation Old 75% capacity factor but new 10% discount rate (ORNL was 13.5%) • Single Fluid Graphite Breeder (MSBR 1970s) • 1500 kg/GWe starting fissile load • 150 M$ fissile 100$/g U233 or Pu= 0.23 c/kwh • Annual and startup Thorium = negligible • Starting and makeup salt = 0.07 cents/kwh – Enriched Lithium costs an unknown factor but likely low impact • 10 day processing cycle • Processing Plant Cap + Op – ORNL 4541, 100M$ 0.16 cents/kwh – ORNL 4812, 260M$ 0.4 c/kwh • Sounds high but still only 5$/kg of salt processed – PUREX is 1000$/kg • Total Fuel Cycle = 0.46 to 0.7 cents/kwh – Large Processing cost uncertainty
Page 2 and 3: The Curious Tale of Molten Salt Rea
Page 4 and 5: The 1970s Single Fluid, Graphite Mo
Page 6 and 7: Some Design Constraints • ThF 4 a
Page 8 and 9: Design Choices Harder or Softer Spe
Page 10 and 11: Design Choices Denatured vs Pure Th
Page 12 and 13: U.S Historic Timeline • Early 197
Page 14 and 15: Kurchatov Institute Program Mid 197
Page 16 and 17: Conference on Molten Salts in Nucle
Page 20 and 21: Summary of Current World Efforts
Page 22 and 23: Chinese TMSR Program
Page 24 and 25: Reexamining MSRs • MSRs often tho
Page 26 and 27: My Design Philosophy • “A desig
Page 28 and 29: DMSR Converter Reactors • Oak Rid
Page 30 and 31: FPs Fission Products Ingestion Radi
Page 32 and 33: Reactor Lifetime Uranium (t) Annual
Page 34 and 35: Suggested Improvements • Shorter
Page 36 and 37: Low Enriched Uranium Only DMSR •
Page 38 and 39: ORNL FHR Focus on Solid Block Fuel
Page 40 and 41: Thanks ORNL From “cooled” back
Page 42 and 43: Want Higher Power Density, More hea
Page 44 and 45: Where To From Here? • Worldwide i
Page 46 and 47: Introducing… Terrestrial Energy I
Page 48 and 49: EXTRA SLIDES…
Page 51: LWR Fuel Cycle Costs All assume 100
Page 55 and 56: DMSR Fuel Cycle Costs Estimate base
Page 57 and 58: What factors differentiate between
Page 59 and 60: Mid 60s ORNL Two Fluid MSBR
Page 61 and 62: Mid 60s ORNL Two Fluid MSBR Disadva
Page 63 and 64: Single Fluid Graphite MSBR (70s) Di
Page 65 and 66: Late 1970s DMSR Converter 30 Year O
Page 67 and 68: Traditional FUJI • Advantages vs
Page 69 and 70: 1 ½ Fluid MSFR (was TMSR) Design h
Page 71 and 72: 1 ½ Fluid MSFR (was TMSR) Disadvan
Page 73 and 74: Fusion Structural Materials Studied
Page 75 and 76: MSR 1/3 the total volume of PWR Com
Page 77 and 78: All radiation within a sealed “Ho
Page 79 and 80: Off Gas Both a Benefit and Challeng
Page 81 and 82: Advantages of all Molten Salt React
Page 83 and 84: A Brief History of Molten Salt Reac
Page 85 and 86: A Brief History of Molten Salt Reac
Page 87 and 88: I told you I’d bring this up Jess
Page 89 and 90: Pebble Bed FHR (MIT, UCB, Wisconsin
Page 91: Testing Pebble Flow UC Berkeley Als
Page 94 and 95: What factors differentiate between
Page 96: More on Molten Salt “Cooled” Re

The Curious Tale of Molten Salt Reactors - media.cns-snc.ca

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