Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
5474990 | Annals of Nuclear Energy | 2017 | 13 Pages |
Abstract
The results of uncertainty analyses performed for the Korean PGSFR reactor are in a good accordance with those already published for the similar designs; thus the calculated target cross section uncertainties could be seen as realistic. The uncertainty of keff induced by cross section data reaches approximately 2%. The uncertainty induced by cross section data for fuel temperature and loss of coolant reactivity feedback effects reach 6% and 13%, respectively. These uncertainties may be reduced by applying the conventional cross section adjustment method in conjunction with sufficient amount of high-quality experimental data. The first application of conventional cross section method to PGSFR core design is introduced in the paper.
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Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Branislav Vrban, Jakub Lüley, Å tefan Äerba, Filip Osuský, Sang Ji Kim,