Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
10156561 | Applied Radiation and Isotopes | 2018 | 20 Pages |
Abstract
This paper compares the calculated and measured increase of the neutron flux density distribution behind the reactor pressure vessel in the azimuthal profile that has arisen from the replacement of 164 fuel pins located close to reactor internals by pins with the higher enrichment. This work can be understood as the first step in the characterization of the effect of incorrectly calculated pin power or burn-up in the fuel assembly at the core boundary relative to the neutron flux distribution behind reactor pressure vessel. Based on a good agreement between the calculated and experimental values, it can be concluded that the mathematical model used to evaluate the power increase is correct.
Related Topics
Physical Sciences and Engineering
Physics and Astronomy
Radiation
Authors
Michal KoÅ¡Å¥ál, VojtÄch Rypar, Evžen Losa, David Harut, Martin Schulc, VÃt Klupák, ZdenÄk MatÄj, FrantiÅ¡ek Cvachovec, Bohumil Jánský, Evžen Novák, TomáÅ¡ Czakoj, Vlastimil JuÅÃÄek, Sergey Zaritsky,