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Liquid Fluoride Reactors:  A New Beginning for an Old Idea   Feb 19 th  2009 Google Tech Talk  Dr.   David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. [email_address]
Can Nuclear Help Solve our Energy and  Climate Change Problems? ,[object Object],[object Object],[object Object],[object Object]
Seven Reactor Design Priorities ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
PWRs, BWRs and CANDUs ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
What About Gas Cooled Pebble Beds? ,[object Object],[object Object],[object Object],[object Object],[object Object],*The reverse situation is true for Accelerator Driven Systems which guard against criticality accidents but do not address decay heat
What about other  Generation IV Reactors? ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],*Entire U.S. supply of Plutonium from spent fuel and  weapons program could only start 30 to 40 such reactors
What about Thorium? We keep hearing about that ,[object Object],[object Object],[object Object],[object Object],[object Object],* Historically known as Molten Salt Reactors
Liquid Fluoride / Molten Salt Overview ,[object Object],[object Object],[object Object],[object Object]
The Single Fluid, Graphite Moderated Molten Salt Breeder Reactor (MSBR)
General Attributes of the “Traditional”  1000 MWe Single Fluid MSBR Design ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],*  233 Pa is the 27 day half-life intermediate between thorium and  233 U ** Meaning it produces 6% more fissile fuel than it consumes
General Benefits of Any Molten Salt Design   ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],*Assisted by bubbling helium through the flowing salt
General Benefits of Any Molten Salt Design ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Radiotoxicity  PWR  vs  FBR * vs  LFR * * Assuming 0.1% Loss During Processing Data and graph from Sylvain David,  Institut de Physique Nucléaire d'Orsay PWR Ore Levels Turns waste management into 500 year job, not million year FPs   Fission Products
Proliferation Resistance   The  Pure  Thorium –  233 U Cycle ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],*HEU=Highly Enriched Uranium (>12%  233 U), LEU=Low Enriched Uranium
Proliferation Resistance Denatured Cycles ,[object Object],[object Object],[object Object],[object Object]
Quality of Produced Plutonium 7.4% 24.3% 5.2% fertile 242 Pu 4.8% 13.6% 5.6% Fissile and adds hard gamma rays 241 Pu 4.4% 18.1% 24.3% Spontaneous fissions high 240 Pu 9.5% 31.1% 60.3% Main fissile Component 239 Pu 73% 12.6% 1.3% Generates heat from alpha emission 238 Pu MSBR Pure Th –  233 U cycle DMSR 30 Year Once Through  PWR Reactor Grade Proliferation properties Isotope
Problems Specific to the Single Fluid, Graphite Moderated MSBR ,[object Object],[object Object],[object Object],[object Object]
Design Basics: 2 Fluid Versus Single Fluid ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],*Pa is effectively  diluted  in the blanket salt so it experiences a lower neutron flux and has a much greater probability to decay to  233 U
Converter or “Once Through” Designs ,[object Object],[object Object],[object Object]
Choice of Neutron Spectrum ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Fuel Processing Basics ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Fluoride Volatility ,[object Object],[object Object],[object Object],[object Object]
Fission Product Removal ,[object Object],[object Object],[object Object],[object Object],[object Object]
Fission Product Removal  ,[object Object],[object Object],[object Object],[object Object]
Fuel Processing Summary ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Design Evolution at  Oak Ridge National Laboratories (ORNL) ,[object Object],[object Object],[object Object],[object Object],* Time to breed enough excess fuel to start another reactor
A Strange Beginning An Aircraft Reactor?
The Aircraft Reactor Experiment ,[object Object],[object Object],[object Object],[object Object],[object Object]
The Rise and Fall of the 2 Fluid Reactor   The Late 1950s ,[object Object],[object Object],[object Object],[object Object]
Homogenous Molten Salt Reactor   Late 50s ORNL
The Rise and Fall of the 2 Fluid Reactor  Early 1960s ,[object Object],[object Object],[object Object],[object Object],[object Object],*Without having the  233 UF 4  fraction so low as to preclude breeding
1960`s, 2 Fluid,  Graphite Moderated MSBR  ,[object Object],[object Object],[object Object],[object Object]
 
Meanwhile, also in the mid 60s… Molten Salt Reactor Experiment MSRE ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
1968: The Start of the Single Fluid Era ,[object Object],[object Object],[object Object],[object Object],[object Object]
Why was the program cancelled? First, what did ORNL do  right ? ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
  What did ORNL do  wrong ? ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Post Program Developments  ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
The French TMSR   Thorium Molten Salt Reactor Design has a thorium blanket but only radial,  not axially (which would be very difficult)
Russian MOlten Salt Actinide Recycler and Transmuter  MOSART
Updating Priorities ,[object Object],[object Object],[object Object],[object Object]
Keeping in Mind… ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
New Ideas for Your Consideration ,[object Object],[object Object],[object Object]
Restating the 2 fluid Plumbing Problem ,[object Object],[object Object],[object Object],[object Object]
What is the solution?  Here’s a hint… 0.5 Infinite Slab If  H = 10 R 0.772 + Finite Cylinder 0.766 Infinite Cylinder 1 Sphere Ratio to B sphere Buckling 2 Geometry
Modified Geometry 2 Fluid Reactor*   “Tube-Within-Shell” *Patent Pending Expands power producing volume while maintaining the small inner core needed for a simple 2 Fluid design
New Concepts Advantages ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Cross Section  Graphite Free
  Example: Graphite Free, Carbon or SiC composite for barrier ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Other Variations ,[object Object],[object Object],[object Object],[object Object]
 
Critical Issue: Core-Blanket Barrier ,[object Object],[object Object],[object Object],[object Object],[object Object]
Fusion Structural Materials Studied  “ Operating Temperature Windows for Fusion Reactor structural Materials” Zinkle and Ghoniem, 2000
Graphite Cores ,[object Object],[object Object],[object Object]
 
 
Barrier Free, Fuel Processing Free? ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Power Distribution With and Without Graphite Reflector Reproduced from “Transmutation Capability of Molten Salt Reactors Feed with TRUs from LWR”  M. Frantoni and E. Greenspan, AWRIF 2005
 
Liner = Blanket Concept ,[object Object],[object Object],[object Object],[object Object]
Liner = Blanket Concept ,[object Object],[object Object],[object Object],[object Object]
DMSR Converter Reactors ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],*ORNL TM 7207 and dozens of other relevant documents available at http://thoriumenergy.blogspot.com/
Denatured Molten Salt Reactors   ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Suggested Improvements ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Suggested Improvements ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
Based on 0.2% tails, 75% capacity factor, 30 year lifetime  LWR data from “A Guidebook to Nuclear Reactors” A. Nero 1979 3.9 million$ annual enrichment costs for DMSR at 110$/SWU,  Total Fuel Costs <0.001$/kwh  At $5000/kg, uranium from sea water potentially feasible and unlimited resource 200 2.0 47 2140 0.74 DMSR  alternate salt, triple the neutron losses 150 1.5 35 1000 0.8 DMSR  single  U recycle 150  0.02$/kwh 1.5 35 1820 0.8 DMSR Converter 1 2400 If start up on  235 U 1.3 Sodium  Fast Breeder 530 5.3 125 4080 0.5-0.6 LWR with U-Pu Recycle 850 million 8.5  million 200 6400 0.5-0.6 LWR Annual Ore Costs 5000$/kg Annual Ore Costs 50$/kg U Annual Uranium Ore (t) Lifetime Uranium Ore (t) Conversion Ratio Reactor
Peak Uranium? ,[object Object],[object Object],[object Object]
Conclusions ,[object Object],[object Object],[object Object],[object Object]
What Way Forward? ,[object Object],[object Object],[object Object],[object Object]
What Way Forward? ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]
What Way Forward? ,[object Object],[object Object],[object Object],[object Object],[object Object]
What is Needed Short Term ,[object Object],[object Object],[object Object],[object Object]
EXTRA SLIDES…
Two Region Homogeneous Reactor Projected breeding ratios assume thicker blanket and  alternate barrier.  From ORNL 2751, 1958 1.112 1.066 1.054 1.105 Projected B.R. (carbon wall) 1.091 1.004 0.977 1.055 Projected B.R. (thinner wall) 1.078 0.929 0.856 0.972 Breeding ratio (Clean Core) 2.20 2.175 2.185 2.193 Neutron Yield 0.009 0.031 0.031 0.048 Leakage 0.025 0.109 0.140 0.090 Core Vessel 0.087 0.106 0.129 0.087 Salt Losses 0.603% 0.233% 0.158% 0.592% 233 U in fuel salt mole % 7 0.25 0  0 ThF 4  in fuel salt mole %   8 feet 4 feet  4 feet 3 feet Core Diameter
Graduate (or 4 th  year project) topics    all would generate “publishable” results   ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],*ATR is the Advanced Test Reactor of Idaho National Laboratories. This slide is from Dr. Darryl Siemer (retired) who is attracting student interest at Idaho State University

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Liquid Fluoride Reactors: A New Beginning for an Old Idea

  • 1. Liquid Fluoride Reactors: A New Beginning for an Old Idea Feb 19 th 2009 Google Tech Talk Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. [email_address]
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  • 9. The Single Fluid, Graphite Moderated Molten Salt Breeder Reactor (MSBR)
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  • 13. Radiotoxicity PWR vs FBR * vs LFR * * Assuming 0.1% Loss During Processing Data and graph from Sylvain David, Institut de Physique Nucléaire d'Orsay PWR Ore Levels Turns waste management into 500 year job, not million year FPs Fission Products
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  • 16. Quality of Produced Plutonium 7.4% 24.3% 5.2% fertile 242 Pu 4.8% 13.6% 5.6% Fissile and adds hard gamma rays 241 Pu 4.4% 18.1% 24.3% Spontaneous fissions high 240 Pu 9.5% 31.1% 60.3% Main fissile Component 239 Pu 73% 12.6% 1.3% Generates heat from alpha emission 238 Pu MSBR Pure Th – 233 U cycle DMSR 30 Year Once Through PWR Reactor Grade Proliferation properties Isotope
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  • 27. A Strange Beginning An Aircraft Reactor?
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  • 30. Homogenous Molten Salt Reactor Late 50s ORNL
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  • 39. The French TMSR Thorium Molten Salt Reactor Design has a thorium blanket but only radial, not axially (which would be very difficult)
  • 40. Russian MOlten Salt Actinide Recycler and Transmuter MOSART
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  • 45. What is the solution? Here’s a hint… 0.5 Infinite Slab If H = 10 R 0.772 + Finite Cylinder 0.766 Infinite Cylinder 1 Sphere Ratio to B sphere Buckling 2 Geometry
  • 46. Modified Geometry 2 Fluid Reactor* “Tube-Within-Shell” *Patent Pending Expands power producing volume while maintaining the small inner core needed for a simple 2 Fluid design
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  • 48. Cross Section Graphite Free
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  • 53. Fusion Structural Materials Studied “ Operating Temperature Windows for Fusion Reactor structural Materials” Zinkle and Ghoniem, 2000
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  • 58. Power Distribution With and Without Graphite Reflector Reproduced from “Transmutation Capability of Molten Salt Reactors Feed with TRUs from LWR” M. Frantoni and E. Greenspan, AWRIF 2005
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  • 66. Based on 0.2% tails, 75% capacity factor, 30 year lifetime LWR data from “A Guidebook to Nuclear Reactors” A. Nero 1979 3.9 million$ annual enrichment costs for DMSR at 110$/SWU, Total Fuel Costs <0.001$/kwh At $5000/kg, uranium from sea water potentially feasible and unlimited resource 200 2.0 47 2140 0.74 DMSR alternate salt, triple the neutron losses 150 1.5 35 1000 0.8 DMSR single U recycle 150 0.02$/kwh 1.5 35 1820 0.8 DMSR Converter 1 2400 If start up on 235 U 1.3 Sodium Fast Breeder 530 5.3 125 4080 0.5-0.6 LWR with U-Pu Recycle 850 million 8.5 million 200 6400 0.5-0.6 LWR Annual Ore Costs 5000$/kg Annual Ore Costs 50$/kg U Annual Uranium Ore (t) Lifetime Uranium Ore (t) Conversion Ratio Reactor
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  • 74. Two Region Homogeneous Reactor Projected breeding ratios assume thicker blanket and alternate barrier. From ORNL 2751, 1958 1.112 1.066 1.054 1.105 Projected B.R. (carbon wall) 1.091 1.004 0.977 1.055 Projected B.R. (thinner wall) 1.078 0.929 0.856 0.972 Breeding ratio (Clean Core) 2.20 2.175 2.185 2.193 Neutron Yield 0.009 0.031 0.031 0.048 Leakage 0.025 0.109 0.140 0.090 Core Vessel 0.087 0.106 0.129 0.087 Salt Losses 0.603% 0.233% 0.158% 0.592% 233 U in fuel salt mole % 7 0.25 0 0 ThF 4 in fuel salt mole % 8 feet 4 feet 4 feet 3 feet Core Diameter
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