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- W190282458 abstract "Calculations of the neutron flux and power distribution in the Plutonium Recycle Test Reactor utilizing a twodimensional, three energy group model were completed. Previous calculations of this nature were carried out in one dimension only and separability of the vertical and radial distributions was necessarily assumed. A study is described which, in addition to eliminating this assumption, includes a detailed analysis of the dump chamber and end effects. These calculations were performed with the multigroup, two-dimensional diffusion code 9 ANGIE. Nuclear data utilized in the code were taken, for the most part, from Henderson's compilation, which is given. Two different fuel loadings were investigated, corresponding to probable minimum and maximum spike loadings respectively. Also the effects of moderator level, shim insertion, Pu burnout, and radial reflector on flux and power distribution were studied. A summary of case descriptions is included. The moderator levels were selected to correspond to PRTR critical experiments. Variation in heat output of the UO/sub 2/ is expected to be small due to in-situ fissioning of Pu at higher exposures and therefore was not included in this study. (auth)" @default.
- W190282458 created "2016-06-24" @default.
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- W190282458 date "1960-10-31" @default.
- W190282458 modified "2023-09-24" @default.
- W190282458 title "TWO DIMENSIONAL FLUX AND POWER CALCULATIONS FOR THE PRTR" @default.
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