Book1.csv

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Anonymous
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99021
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Book1.csv
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2011-08-30 11:28:32
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reactor theory
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reactor theory
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  1. neutron reaction when a nucleus deflects a neutron without absorbing the neutron and conserves kinetic energy
    Elastic scattering
  2. neutron reaction when a nucleus deflects a neutron without absorbing the neutron and kinetic energy is not conserved (the target nucleus emits a gamma ray).
    Inelastic scattering
  3. a process a neutron is absorbed by a nucleus resulting in an excited compound nucleus. The compound nucleus returns to ground state by emitting gamma rays.
    Radiative capture
  4. "neutron reaction when a neutron is absorbed by a nucleus
    resulting in the splitting of the nucleus into two new atoms
  5. Explain how changing neutron energy will affect the magnitude of a cross section for a given isotope.
  6. "Using the Liquid Drop Fission Model
    describe the fission process."
  7. "neutron reaction when a nucleus is absorbed by a nucleus
    resulting in the splitting of the nucleus into two new atoms
  8. the minimum amount of energy for fission to occur
    Critical energy
  9. "energy released in the form of kinetic energy fission fragments
    neutrons and instantaneous gamma rays."
  10. "energy release in the form of kinetic energy of beta particles
    decay gamma rays and neutrinos."
  11. a fuel type that will fission simply because of binding energy of a neutron (BE greater than EC).
    Fissile material
  12. a fuel type that requires kinetic energy in addition to binding energy of a neutron for fission to occur (BE less than EC).
    Fissionable material
  13. "Upon fissioning
    the target will split into two fission fragments
  14. List six of the products produced by fission.
    Kinetic energy of fission fragments; Kinetic energy of fission neutrons; Instantaneous gamma rays; Kinetic energy of beta particles; Decay gamma rays
  15. the number of neutrons passing through a unit area per unit time.
    "Neutron flux (fast
  16. the spatial representation of the neutron flux level.
    "Flux distribution (radial
  17. the measure of how many reactions are occurring in a unit volume per unit time.
    Reaction rate
  18. the rate at which energy is emitted as a result of nuclear fissions.
    Reactor power
  19. neutrons emitted within 10-14 seconds of the fission event and are a direct result of the fission process.
    Prompt neutron
  20. neutrons born more than 10-14 seconds after the fission event (average 12.7 sec).
    Delayed neutron
  21. Explain why thermal neutrons are required for Light Water Reactor operation.
    They use fissile materials that have large absorption cross-sections for thermal neutrons (slow) by U-235.
  22. Explain why a moderator is required in a Light Water Reactor core.
    "Since neutrons born from fission are fast
  23. Describe the mechanics of the neutron slowing down (moderation) and diffusion processes.
    Collision (elastic scattering) of the fast neutron with the hydrogen atoms in the water moderator.
  24. Describe the properties of an ideal moderator.
    A high MR (moderator ratio) with a high microscopic cross section for absorption (?a).
  25. a neutron that has a kinetic energy greater than 0.1 MeV.
    Fast neutron
  26. neutron that has a kinetic energy between 0.1 MeV and 1 eV.
    Intermediate neutron
  27. neutron that has a kinetic energy less than 1 eV.
    Slow neutron
  28. "neutron that is in thermal equilibrium with its surroundings (these can be fast
    intermediate

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