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Nuclear technologies alan bullick

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Nuclear technologies alan bullick

  1. 1. Alan Bullick Dr. McGinleyEVHM 3305-H01
  2. 2.  History Current Technologies  BWR  PWR Limitations  Resources  Thermal Inefficiencies  Maintenance New Fission Reactor Designs and Benefits  (GFR) Gas-Cooled Fast Reactor  (LFR) Lead-Cooled Fast Reactor  (MSR) Molten Salt Reactor  (SFR) Sodium-Cooled Fast Reactor  (SCWR) Supercritical-Water-Cooled Reactor  (VHTR) Very-High-Temperature Reactor New Fusion Design Technology  Tokamak  Results
  3. 3. CHICAGO PILE 1 DECEMBER 2, 1942 Created by Enrico Fermi Consisted of a Pile of Uranium Contained Within Graphite Bricks Control Rods Manually Operated Built on a Racket Court Underneath the Alonzo Stagg Field Stadium of the University of Chicago
  4. 4. EXPERIMENTAL BREEDER BEGIN OPERATINGREACTOR I DECEMBER 20, 1951 World’s First Nuclear Power Plant to Generate Electricity Decommissioned in 1964 Located in Arco Idaho a.k.a (Atomic City) Nuclear Reactor Became Site of Idaho National Labs
  7. 7. THERMALINEFFICIENCIES MAINTENANCE Current Efficiencies of PWR  Every 1 to 2 Years a and BWR Designs are Limited Conventional Nuclear Plant by the Operating Needs to Refuel Portions of Temperatures of Their Rankine Cycles. the Fuel Core Assembly Average Efficiency is 33%  Every 5 Years the Turbine-  1500 MWe Nuclear Power Generator Must be Inspected Plant Actually Produces 4500  1-2 Months Spent Offline for MW of Power and Wastes 3000 MW. Each Maintenance Process  3000 MW of Power can Power 876,000 Homes  Average Inlet/Outlet Temps: 275˚C/325˚C (525˚F/650˚F) Efficiency = ( 1 – Cold temperature / Hot temperature ) * 100
  8. 8. Members:Argentina, Brazil, Canada, France, Japan, the Republic of Korea,the Republic of South Africa, the United Kingdom, the UnitedStates, Switzerland, Euratom, the People’s Republic of China,and the Russian FederationDesigns:(GFR) Gas-Cooled Fast Reactor(LFR) Lead-Cooled Fast Reactor(MSR) Molten Salt Reactor(SFR) Sodium-Cooled Fast Reactor(SCWR) Supercritical-Water-Cooled Reactor(VHTR) Very-High-Temperature Reactor
  9. 9. Reactor Power: 600MWthNet Efficiency: 48%Coolant/Outlet Temp:490˚C/850˚C(914˚F/1562˚F)Thermodynamic Cycle:Brayton Cycle Operatingon Helium Gas
  10. 10.  Small/Modular Able to be Used as a Conventional Nuclear Power Plant Waste Conversion Facility Able to Utilize Pebble Bed Fuel Technology in Some Designs Hydrogen and Electrical Capabilities
  11. 11. Reactor Power:50-150 MWe300-400 MWe1200 MWeCoolant/Outlet Temp:1022˚F-1472˚FThermodynamic Cycle:Brayton Cycle Operating onCO2 GasRankine Cycle Operating onSuper Critical H20
  12. 12.  Easily Scalable Design Long Refueling Intervals (10-30 Years) Nuclear Waste Management Capabilities Hydrogen and Electrical Capabilities
  13. 13. Reactor Power:1000 MWeOutlet Temp: 1300˚FThermodynamic Cycle:Brayton Cycle Operatingon Helium Gas
  14. 14.  Large Size Highly Sustainable Closed Fuel Cycle Nuclear Waste Management Capabilities Hydrogen and Electrical Capabilities
  15. 15. Reactor Power:150-500 MWe500-1500 MWeOutlet Temp: 550˚C(1022˚F)Thermodynamic Cycle:Brayton Cycle Operatingon CO2 Gas
  16. 16.  Large/Medium Size Near Term Deployment Nuclear Waste Management Capabilities
  17. 17. Reactor Power:1700 MWeNet Efficiency: 44%Outlet Temp: 550˚C(1022˚F)Thermodynamic Cycle:Brayton Cycle Operatingon Helium Gas
  18. 18.  Nuclear Waste Management Capabilities
  19. 19. Reactor Power:600 MWthOutlet Temp: 1000˚C(1832˚F)Thermodynamic Cycle:Brayton Cycle Operatingon Helium Gas
  20. 20.  Medium Size Design Design Appropriate for Hydrogen Production
  21. 21.  Fusion is the Process Powering the Sun Recreating Difficulties on Earth  Material Limitations  Gravitational Limitations Solutions  Control Plasma Created From Ionized Atoms Using Super-Cooled Super-Conducting Magnets Named Tokamaks
  22. 22.  The Joint European Torus (JET) was Able to Produce a 16 MW Pulse for 1 Second in 1997 The Tora Supra was Able to Sustain Plasma Confinement for 6.5 Minutes in 2003. Current Goal is to Achieve Power Multiplication of 10x
  23. 23.  Radioactive Half-life of Tritium is 12.3 Years Instead of the 700 Million Year Half-life of Uranium The Fusion Process Has a Higher Energy/Mass Fuel Ratio Than the Fission Process
  24. 24.  Nuclear Power Remains a Very Viable Option Even Without Future Technological Advancements Nuclear Advancements Will be Able to Aid Developing Countries With Both Electrical and Water Generation Capabilities Generation IV Nuclear Plants Allow For the Possibility of a Hydrogen Fueled Future
  25. 25. [1] (2011, June 29). U.S & World Population Clocks. U.S. Census Bureau. [Online] Available:[2] AREVA Communications Department, All About Nuclear Energy: From Atom to Zirconium. AREVACOM ed. Paris,France: AREVA, April 2008[3] “Nuclear Energy,” Alternative Energy, vol. 2, N. Schlager and J. Weisblatt, Eds. Detroit, MI: Thompson Gale, 2006,pp. 169-208[4] An Energy Landmark: Idaho’s Pioneering Experimental Breeder Reactor-I. Idaho National Laboratory. [Online]Available:[5] A. B. Reynolds, Bluebells and Nuclear Energy. Madison, WI: Cogito Books, 1996[6] New Nuclear Technology Opportunities: Coal Steam from a Nuclear Boiler. Coal2Nuclear. [Online] Available:[7] (2002 Dec.). Ten Nations Preparing Today for Tomorrow’s Energy Needs: A Technology Roadmap for GenerationIV Nuclear Energy Systems. U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV InternationalForum. [Online] Available:[8] S. Hough (2009 April). Supercritical Rankine Cycle: A Synopsis of the Cycle, it’s Background, PotentialApplications and Engineering Challenges. University of Idaho. [Online] Available:[9] M. Ragheb. (2011, July 1). Chapter 1: Nuclear Reactor Concepts and Thermodynamic Cycles. University of Illinois atUrbana-Champaign. [Online] Available:[10] ITER Organization. (2011) ITER: The Way to New Energy. ITER. [Online] Available:[11] (2011, March 9). Economics of Nuclear Power. World Nuclear Association. [Online] Available: