Future Nuclear Reactors
Third and Third-Plus+ Generation Reactors
http://en.wikipedia.org/wiki/Generation_III_reactor
Next Generation is Simpler
http://coe.berkeley.edu/forefront/spring2006/nuclear.html
Future Nuclear Reactors
Fast Neutron Reactor
http://en.wikipedia.org/wiki/Fast-neutron_reactor
Future Nuclear Reactors
Fourth Generation Reactors
http://en.wikipedia.org/wiki/Generation_IV_reactor
Gas-Cooled Fast Reactor (GFR)
features a fast-neutron-spectrum, helium-cooled reactor and closed fuel cycle
Molten Salt Reactor (MSR)
produces fission power in a circulating molten salt fuel mixture with an epithermalspectrum reactor and a full actinide recycle fuel cycle.
Sodium-Cooled Fast Reactor (SFR)
features a fast-spectrum, sodium-cooled reactor and closed fuel cycle for efficient
management of actinides and conversion of fertile uranium.
Lead-Cooled Fast Reactor (LFR)
features a fast-spectrum lead or lead/bismuth eutectic liquid metal-cooled reactor
and a closed fuel cycle for efficient conversion of fertile uranium and management of
actinides.
Future Nuclear Reactors
Supercritical-Water-Cooled Reactor (SCWR)
is a high-temperature, high-pressure water-cooled reactor that operates
above the thermodynamic critical point of water (374 degrees Celsius, 22.1
MPa, or 705 degrees Fahrenheit, 3208 psia).
Very-High-Temperature Reactor (VHTR)
a graphite-moderated, helium-cooled reactor with a once-through uranium
fuel cycle, designed to supply heat with core outlet temperatures of 1,000
degrees Celsius, which enables applications such as hydrogen production or
process heat for the petrochemical industry or others.
http://is.gd/YyRevf
Supercritical-Water-Cooled Reactor (SCWR)
is a high-temperature, high-pressure water-cooled reactor that operates
above the thermodynamic critical point of water (374 degrees Celsius, 22.1
MPa, or 705 degrees Fahrenheit, 3208 psia).
Future Nuclear Reactors
Very-High-Temperature Reactor (VHTR)
The Very-High-Temperature Reactor (VHTR) is a graphite-moderated, helium-cooled
reactor with a once-through uranium fuel cycle. The VHTR system is designed to be a
high-efficiency system that can supply process heat to a broad spectrum of hightemperature and energy-intensive, nonelectric processes. The system may
incorporate electricity generating equipment to meet cogeneration needs. The
system also has the flexibility to adopt uranium/plutonium fuel cycles and offer
enhanced waste minimization.
Thus, the VHTR offers a
broad range of process heat
applications and an option
for high-efficiency electricity
production, while retaining
the desirable safety
characteristics offered by
modular high-temperature
gas cooled reactor
Idaho Nuclear
Laboratories
Future Nuclear Reactors
NL team helps pave way to Generation IV reactor “Fourth generation
nuclear reactors, the nuclear power plants of tomorrow, will provide safer,
less expensive and more environmentally friendly energy. A critical step in
developing new Very High Temperature Reactors (VHTR) is certifying the
graphite that is used in many parts of the reactor's core. In recent years, it
has become necessary to develop new nuclear-grade graphite and certify it
for use in the next generation of gas-cooled nuclear reactors... nuclear
experts envision two different versions of gas cooled VHTRs for nextgeneration use. Both designs will require large amounts of high-quality
graphite.”
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