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- W2548453626 abstract "The high flux water cooled, beryllium moderated reactor MARIA at the Institute of Atomic Energy in Poland is used mainly as a source of neutrons for neutronography, solid state physics and for irradiation of isotopes and materials. Introduction of new fuel is planned, which makes particularly important the accuracy of computational reactivity predictions. The complicated geometry of the MARIA reactor core makes the problem of accuracy difficult to solve. The prerequisite of MARIA reactivity calculations is the determination of the quantities of He-3 and Li-6 for each beryllium block. Authors have discussed this aspect at Kranjska Gora 2002. In the present paper accuracy obtained with different core model simplifications is discussed. The codes REBUS, TRITAC and MCNP have been used for that purpose. The results of computations are compared with measurement on two critical assemblies. The computational scheme has been used to calculate reactivity effect of the new fuel." @default.
- W2548453626 created "2016-11-11" @default.
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- W2548453626 date "2003-01-01" @default.
- W2548453626 modified "2023-09-23" @default.
- W2548453626 title "Accuracy of Reactivity Predictions for the MARIA Reactor" @default.
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