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* Number of neutrons per fission ("nu-bar", <span style="text-decoration: overline">ν</span>) is a function of the particular breakup / fission fragments | * Number of neutrons per fission ("nu-bar", <span style="text-decoration: overline">ν</span>) is a function of the particular breakup / fission fragments | ||
** ...but can be averaged over inputs. In general, plutonium generates more neutrons than uranium, though <sup>233</sup>U's not bad. | ** ...but can be averaged over inputs. In general, plutonium generates more neutrons than uranium, though <sup>233</sup>U's not bad. | ||
** [[File:Montecarlofission.pdf]] | ** "[[File:Montecarlofission.pdf|Monte Carlo Approach to Sequential Neutron Emission from Fission Fragments]], LANL 2005 | ||
===Reactor Physics/Fuel Cycle=== | ===Reactor Physics/Fuel Cycle=== | ||
* Natural materials available: | * Natural materials available: |