Calculation of Radial Neutron-Flux Distribution in EGCR Lattice Cell
Description:
The Neutron-flux distributions in an EGCR cell containing seven rod clusters of 2.0 and 2.6% enriched uranium oxide have been obtained by using a one-velocity, one-dimensional P-3 solution to the neutron-transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experimental and calculated distributions. Flux traverses in the outer rod perpendicular to a diameter of the cluster are also presented.
Date:
August 31, 1959
Creator:
DeBoer, T. K.
Item Type:
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Partner:
UNT Libraries Government Documents Department