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  2. Transient Reactor Test Facility - Wikipedia

    en.wikipedia.org/wiki/Transient_Reactor_Test...

    The fuel is a graphite uranium mixture, with 1 part uranium to 10,000 parts graphite. The active portion of the fuel assembly is about 48 inches, with a graphite reflector of about 24 inches above and below the active portion. The active portion of the fuel assemblies are encased with Zircaloy. There is also a graphite axial reflector, composed ...

  3. Sequoyah Fuels Corporation - Wikipedia

    en.wikipedia.org/wiki/Sequoyah_Fuels_Corporation

    Sequoyah Fuels Corporation owned and operated a uranium processing plant near Gore, Oklahoma. The company was created in 1983 as a subsidiary of Kerr-McGee. In 1988 it was sold to General Atomics. [1]

  4. Nuclear fuel - Wikipedia

    en.wikipedia.org/wiki/Nuclear_fuel

    Cladding is the outer layer of the fuel rods, standing between the coolant and the nuclear fuel. It is made of a corrosion -resistant material with low absorption cross section for thermal neutrons , usually Zircaloy or steel in modern constructions, or magnesium with small amount of aluminium and other metals for the now-obsolete Magnox reactors .

  5. Fuel element failure - Wikipedia

    en.wikipedia.org/wiki/Fuel_element_failure

    A fuel element failure is a rupture in a nuclear reactor's fuel cladding that allows the nuclear fuel or fission products, either in the form of dissolved radioisotopes or hot particles, to enter the reactor coolant or storage water. [1] The de facto standard nuclear fuel is uranium dioxide or a mixed uranium/plutonium dioxide.

  6. Zirconium alloys - Wikipedia

    en.wikipedia.org/wiki/Zirconium_alloys

    One of the main uses of zirconium alloys is in nuclear technology, as cladding of fuel rods in nuclear reactors, especially water reactors. A typical composition of nuclear-grade zirconium alloys is more than 95 weight percent [ 1 ] zirconium and less than 2% of tin , niobium , iron , chromium , nickel and other metals, which are added to ...

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  8. Boiling water reactor safety systems - Wikipedia

    en.wikipedia.org/wiki/Boiling_water_reactor...

    The five criteria for ECCS are to prevent peak fuel cladding temperature from exceeding 2200 °F (1204 °C), prevent more than 17% oxidation of the fuel cladding, prevent more than 1% of the maximum theoretical hydrogen generation due the zircalloy metal-water reaction, maintain a coolable geometry, and allow for long-term cooling.

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