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Page Title: NEUTRON MODERATION
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Reaction Rates Summary
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Nuclear Physics and Reactor Theory Volume 1 of 2
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Neutron Slowing Down and Thermalization

Reactor Theory (Neutron Characteristics) DOE-HDBK-1019/1-93 NEUTRON MODERATION Rev. 0 Page 23 NP-02 NEUTRON MODERATION In thermal reactors, the neutrons that cause fission are at a much lower energy than the energy level at which they were born from fission.  In this type of reactor, specific materials must be included in the reactor design to reduce the energy level of the neutrons in an efficient manner. EO 2.12    DEFINE the following concepts: a.  Thermalization d.   Average logarithmic energy decrement b.  Moderator e.   Macroscopic slowing down power c.  Moderating ratio EO 2.13    LIST three desirable characteristics of a moderator. EO 2.14    Given    an    average    fractional    energy    loss    per    collision, CALCULATE  the  energy  loss  after  a  specified  number  of collisions. Neutron Slowing Down and Thermalization Fission  neutrons are produced at an average energy level of 2 MeV and immediately begin to slow down as the result of numerous scattering reactions with a variety of target nuclei.  After a number of collisions with nuclei, the speed of a neutron is reduced to such an extent that it has approximately the same average kinetic energy as the atoms (or molecules) of the medium in which  the neutron is undergoing elastic scattering.  This energy, which is only a small fraction of an electron volt at ordinary temperatures (0.025 eV at 20   C), is frequently referred to as the thermal energy, since it depends upon the temperature.  Neutrons whose energies have been reduced  to  values in this region (< 1 eV) are designated thermal neutrons.  The process of reducing the energy of a neutron to the thermal region by elastic scattering is referred to as thermalization, slowing down, or moderation.  The material used for the purpose of thermalizing neutrons is called a moderator.  A good moderator reduces the speed of neutrons in a small number of collisions, but does not absorb them to any great extent.  Slowing the neutrons in as few collisions as possible is desirable in order to reduce the amount of neutron leakage from the core and also to reduce the number of resonance absorptions in non-fuel materials.  Neutron leakage and resonance absorption will be discussed in the next module.

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