1. Alan Bullick
Dr. McGinley
EVHM 3305-H01

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. 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. EXPERIMENTAL BREEDER BEGIN OPERATING
REACTOR 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

5. (PWR) PRESSURIZED WATER (BWR) BOILING WATER
REACTOR REACTOR

6. CURRENT RESOURCE
PROJECTIONS
RESOURCE PROJECTIONS
USING BREEDER REACTORS
AND MOX FUEL

7. THERMAL
INEFFICIENCIES 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. 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

9. Reactor Power: 600MWth
Net Efficiency: 48%
Coolant/Outlet Temp:
490˚C/850˚C
(914˚F/1562˚F)
Thermodynamic Cycle:
Brayton Cycle Operating
on Helium Gas

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. Reactor Power:
50-150 MWe
300-400 MWe
1200 MWe
Coolant/Outlet Temp:
1022˚F-1472˚F
Thermodynamic Cycle:
Brayton Cycle Operating on
CO2 Gas
Rankine Cycle Operating on
Super Critical H20

12.  Easily Scalable Design
 Long Refueling Intervals (10-30 Years)
 Nuclear Waste Management Capabilities
 Hydrogen and Electrical Capabilities

13. Reactor Power:
1000 MWe
Outlet Temp: 1300˚F
Thermodynamic Cycle:
Brayton Cycle Operating
on Helium Gas

14.  Large Size
 Highly Sustainable Closed Fuel Cycle
 Nuclear Waste Management Capabilities
 Hydrogen and Electrical Capabilities

15. Reactor Power:
150-500 MWe
500-1500 MWe
Outlet Temp: 550˚C
(1022˚F)
Thermodynamic Cycle:
Brayton Cycle Operating
on CO2 Gas

16.  Large/Medium Size
 Near Term Deployment
 Nuclear Waste Management Capabilities

17. Reactor Power:
1700 MWe
Net Efficiency: 44%
Outlet Temp: 550˚C
(1022˚F)
Thermodynamic Cycle:
Brayton Cycle Operating
on Helium Gas

18.  Nuclear Waste Management Capabilities

19. Reactor Power:
600 MWth
Outlet Temp: 1000˚C
(1832˚F)
Thermodynamic Cycle:
Brayton Cycle Operating
on Helium Gas

20.  Medium Size Design
 Design Appropriate for Hydrogen Production

22.  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

24.  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

25.  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

26.  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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