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

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MSFR Fuel Cycle Costs Estimate based on ORNL 4541 and 4812 and 7.5 times “nuclear” inflation Old 75% capacity factor but new 10% discount rate (ORNL was 13.5%) • Fast Spectrum (MSFR 2005 to present) • 5.5 T/GWe, 6 month processing time • 550 M$ fissile 100$/g U233 or Pu= 0.85 c/kwh • Less starting and makeup salt = 0.03 cents/kwh • Processing Plant Cap + Op – Much lower rate (1/18 th MSBR) but economy of scale lost? – Also need process blanket salt – ~0.1 cents/kwh? Perhaps much higher? • Total Fuel Cycle ~ 1 cent/kwh – Again large cost uncertainty
DMSR Fuel Cycle Costs Estimate based on ORNL 4541 and 4812 and 7.5 times “nuclear” inflation Old 75% capacity factor but new 10% discount rate (ORNL was 13.5%) • Single Fluid Graphite Converter (DMSR 1980) • Runs off Thorium plus Low Enriched Uranium • 3450 kg/GWe starting fissile, No processing • 175 M$ fissile 50$/g U235= 0.26 c/kwh • Annual and startup Thorium = negligible • More carrier salt = 0.14 cents/kwh – Converter able to use inexpensive alternate salts • Average Conversion Ratio 0.8 over 30 years – ~150 kg/year U235 (in LEU) – 50$/g = 7.8M$/year = 0.12 cents/kwh – • Total Fuel Cycle = 0.52 cents/kwh – Very little uncertainty – 9 T of Pu (IFR startup) would start and run for over 30 years – Great potential for improvement
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 and 52: LWR Fuel Cycle Costs All assume 100
Page 53: MSBR 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
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The Curious Tale of Molten Salt Reactors - media.cns-snc.ca

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