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- W181244 abstract "The possibilities of achieving radial neutron flux flattening in nuclear reactors are discussed. It is shown that in larger reactors a considerable neutron flux flattening is possible without the mean burn-up of the fuel being reduced to any great degree. With smaller reactors, however, the neutron flux flattening will be economically meaningless. The local neutron-flux variations resulting from the mixing of fuel elements having a varying degree of burn-up cannot be suitably eliminated by means of grey control rods. (auth)" @default.
- W181244 created "2016-06-24" @default.
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- W181244 date "1962-01-01" @default.
- W181244 modified "2023-09-27" @default.
- W181244 title "NEUTRON FLUX FLATTENING IN THERMAL REACTORS" @default.
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