future nuclear reactors third and third-plus+ generation reactors next generation is simpler
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Future Nuclear Reactors
Third and Third-Plus+ Generation Reactorshttp://en.wikipedia.org/wiki/Generation_III_reactor
Next Generation is Simplerhttp://coe.berkeley.edu/forefront/spring2006/nuclear.html
Future Nuclear Reactors
Fast Neutron Reactorhttp://en.wikipedia.org/wiki/Fast-neutron_reactor
Future Nuclear Reactors
Fourth Generation Reactorshttp://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 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.
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
Idaho Nuclear Laboratories
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
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.”
Thorium Sites
Thorium Energy Alliance5. http://www.thoriumenergyalliance.com/ThoriumSite/objectives.html Thorium Energy Alliance on Facebookhttp://www.facebook.com/group.php?gid=110551728517&ref=ts Torium Energy Alliance Videos http://is.gd/kn5g8