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ADVANCEMENTS AND NEW TECHNOLOGIES IN THE FIELD OF
NUCLEAR POWER
Alan BullickDr. McGinley
EVHM 3305-H01
Overview 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
History of Nuclear Power
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
History of Nuclear Power (cont.)
EXPERIMENTAL BREEDER REACTOR I
BEGIN OPERATING 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
Current Nuclear Technologies
(PWR) PRESSURIZED WATER REACTOR (BWR) BOILING WATER REACTOR
Conventional Nuclear Limitations
CURRENT RESOURCE PROJECTIONS
RESOURCE PROJECTIONS USING BREEDER REACTORS AND MOX FUEL
Nuclear Limitations (cont.)
THERMAL INEFFICIENCIES MAINTENANCE
Current Efficiencies of PWR and BWR Designs are Limited by the Operating Temperatures of Their Rankine Cycles.
Average Efficiency is 33% 1500 MWe Nuclear Power
Plant Actually Produces 4500 MW of Power and Wastes 3000 MW.
3000 MW of Power can Power 876,000 Homes
Average Inlet/Outlet Temps: 275˚C/325˚C (525˚F/650˚F)
Every 1 to 2 Years a Conventional Nuclear Plant Needs to Refuel Portions of the Fuel Core Assembly
Every 5 Years the Turbine-Generator Must be Inspected
1-2 Months Spent Offline for Each Maintenance Process
Efficiency = ( 1 – Cold temperature / Hot temperature ) * 100
Generation IV International Forum
Members:Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, the United Kingdom, the United States, Switzerland, Euratom, the People’s Republic of China, and the Russian Federation
Designs:
(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
(GFR) Gas-Cooled Fast Reactor
Reactor Power: 600MWthNet Efficiency: 48%Coolant/Outlet Temp: 490˚C/850˚C(914˚F/1562˚F)Thermodynamic Cycle: Brayton Cycle Operating on Helium Gas
Benefits of a GFR
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
(LFR) Lead-Cooled Fast Reactor
Reactor Power: 50-150 MWe300-400 MWe1200 MWeCoolant/Outlet Temp: 1022˚F-1472˚FThermodynamic Cycle: Brayton Cycle Operating on CO2 Gas
Rankine Cycle Operating on Super Critical H20
Benefits of a LFR
Easily Scalable Design Long Refueling Intervals (10-30 Years) Nuclear Waste Management Capabilities Hydrogen and Electrical Capabilities
(MSR) Molten Salt Reactor
Reactor Power: 1000 MWeOutlet Temp: 1300˚FThermodynamic Cycle: Brayton Cycle Operating on Helium Gas
Benefits of a MSR
Large Size Highly Sustainable Closed Fuel Cycle Nuclear Waste Management Capabilities Hydrogen and Electrical Capabilities
(SFR) Sodium-Cooled Fast Reactor
Reactor Power: 150-500 MWe500-1500 MWeOutlet Temp: 550˚C (1022˚F)Thermodynamic Cycle: Brayton Cycle Operating on CO2 Gas
Benefits of a SFR
Large/Medium Size Near Term Deployment Nuclear Waste Management Capabilities
(SCWR) Supercritical-Water-Cooled Reactor
Reactor Power: 1700 MWeNet Efficiency: 44%Outlet Temp: 550˚C (1022˚F)Thermodynamic Cycle: Brayton Cycle Operating on Helium Gas
Benefits of a SCWR
Nuclear Waste Management Capabilities
(VHTR) Very-High-Temperature Reactor
Reactor Power: 600 MWthOutlet Temp: 1000˚C (1832˚F)Thermodynamic Cycle: Brayton Cycle Operating on Helium Gas
Benefits of a VHTR
Medium Size Design Design Appropriate for Hydrogen
Production
Summary of Generation IV Nuclear Reactors
Nuclear Fusion
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
International Thermonuclear Experimental Reactor
Current Results
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
Benefits
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
Summary
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
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