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- W202874078 abstract "The latest designs of natural uranium and graphite actors are compared with the Calder Hall prototype, only in regard to the introduction in a reactor of a charge- anddischarge system without interrupting the reactor operating cycle. Several schemes are given; the basic and simplest one consists in a continuous charging and discharging. A few processing operations may be added to this basic performance in order to reach a more favorable displacement of fuel for the purpose of obtaining a better uniform thermal irradiation and of increasing the average irradiation. Two fundamental displacements have been studied, i.e., axial inversion of canal elements and radial transfer of fuel from the periphery into the central zone of a reactor core. Calculation methods and results are outlined, as were obtained by means of a particular reactor having a radially flattened flux distribution. (auth)" @default.
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- W202874078 date "1958-02-01" @default.
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- W202874078 title "FUEL CIRCULATION IN NATURAL URANIUM AND GRAPHITE REACTORS" @default.
- W202874078 hasPublicationYear "1958" @default.
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