Future Nuclear Reactors

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Future Nuclear Reactors
Third and Third-Plus Generation
Reactors http//en.wikipedia.org/wiki/Generation_I
II_reactor Next Generation is Simpler http//coe.
berkeley.edu/forefront/spring2006/nuclear.html
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Future Nuclear Reactors
Fast Neutron Reactor http//en.wikipedia.org/wiki/
Fast-neutron_reactor
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Future Nuclear Reactors
 Fourth Generation Reactors http//en.wikipedia.or
g/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 epithermal-spectrum 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.
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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).
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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
high-temperature 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
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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 next-generation use. Both designs will
require large amounts of high-quality graphite.
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