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Yang, Y. S.; Lee, C. B.; Kim, D. H.; Bang, J. G.; Kim, Y. M.; Jung, Y. H.
Proceedings of the KNS autumn meeting2000
Proceedings of the KNS autumn meeting2000
AbstractAbstract
[en] Due to the radial variation of neutron flux and its energy spectrum inside the UO2 fuel pellet, local fission density and fissile isotope production rate are varied with the burnup, which leads to local variation of burnup, power and fissile isotope densities. RAPID(RAdial power and burnup Prediction by following fissile Isotope Distribution) program, which predicts power and burnup distribution of UO2 fuel by considering all affecting factors was inserted into FRAPCON-3 to be compared with TUBRNP model. It is expected that RAPID with more detailed models for all the fissionable nuclides would have better accuracy
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Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2000; [13 p.]; 2000 autumn meeting of the KNS; Taejon (Korea, Republic of); 26-27 Oct 2000; Available from KNS, Taejon (KR); 6 refs, 9 figs
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