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  2. Decay heat - Wikipedia

    en.wikipedia.org/wiki/Decay_heat

    Decay heat as fraction of full power for a reactor SCRAMed from full power at time 0, using two different correlations. In a typical nuclear fission reaction, 187 MeV of energy are released instantaneously in the form of kinetic energy from the fission products, kinetic energy from the fission neutrons, instantaneous gamma rays, or gamma rays from the capture of neutrons. [7]

  3. Nuclear fuel - Wikipedia

    en.wikipedia.org/wiki/Nuclear_fuel

    The radiation hazard from spent nuclear fuel declines as its radioactive components decay, but remains high for many years. For example 10 years after removal from a reactor, the surface dose rate for a typical spent fuel assembly still exceeds 10,000 rem/hour, resulting in a fatal dose in just minutes. [20]

  4. Spent nuclear fuel - Wikipedia

    en.wikipedia.org/wiki/Spent_nuclear_fuel

    Spent nuclear fuel contains 3% by mass of 235 U and 239 Pu (also indirect products in the decay chain); these are considered radioactive waste or may be separated further for various industrial and medical uses.

  5. Nuclear reactor physics - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_physics

    Nuclear reactor physics is the field of physics that studies and deals with the applied study and engineering applications of chain reaction to induce a controlled rate of fission in a nuclear reactor for the production of energy.

  6. Nuclear fission product - Wikipedia

    en.wikipedia.org/wiki/Nuclear_fission_product

    In nuclear reactors both caesium-137 and strontium-90 are found in locations away from the fuel because they're formed by the beta decay of noble gases (xenon-137, with a 3.8-minute half-life, and krypton-90, with a 32-second half-life) which enable them to be deposited away from the fuel, e.g. on control rods.

  7. Plutonium-240 - Wikipedia

    en.wikipedia.org/wiki/Plutonium-240

    The longer a nuclear fuel element remains in a nuclear reactor, the greater the relative percentage of 240 Pu in the fuel becomes. The isotope 240 Pu has about the same thermal neutron capture cross section as 239 Pu ( 289.5 ± 1.4 vs. 269.3 ± 2.9 barns ), [ 6 ] [ 7 ] but only a tiny thermal neutron fission cross section (0.064 barns).

  8. Burnup - Wikipedia

    en.wikipedia.org/wiki/Burnup

    In nuclear power technology, burnup (also known as fuel utilization) is a measure of how much energy is extracted from a primary nuclear fuel source. It is measured as the fraction of fuel atoms that underwent fission in %FIMA (fissions per initial metal atom) [1] or %FIFA (fissions per initial fissile atom) [2] as well as, preferably, the actual energy released per mass of initial fuel in ...

  9. Minor actinide - Wikipedia

    en.wikipedia.org/wiki/Minor_actinide

    The most important isotopes of these elements in spent nuclear fuel are neptunium-237, americium-241, americium-243, curium-242 through -248, and californium-249 through -252. Plutonium and the minor actinides will be responsible for the bulk of the radiotoxicity and heat generation of spent nuclear fuel in the long term (300 to 20,000 years in ...