SYMPOSIA PAPER
Published:
01 January 1989
STP10075S
Transport Calculation of the Gamma Field in the Ex-Core Region of the KrŠko Pressure Water Reactor
SourceResults are presented of the coupled neutron-gamma transport calculation of the KrŠko 632 MWe pressure water reactor (PWR). The DOT 4.2 transport code was used. The variation of gamma flux with fuel burnup was considered, and gamma flux was found to be nearly 50% higher at end of life (EOL) than at beginning of life (BOL) in the regions of interest. For Np and U dosimeters in the surveillance capsules the corrections to the measured neutron exposure due to the gamma reactions were determined. The effect of gamma heating on the temperature of the surveillance capsule and pressure vessel was calculated. The importance of gamma heating in the determination of the heatup and cooldown p-T curves for the plant was evaluated.
Author Information
Kodeli, I
J. Stefan Institute, Ljubljana, Yugoslavia
Glumac, B
J. Stefan Institute, Ljubljana, Yugoslavia
Najžer, M
J. Stefan Institute, Ljubljana, Yugoslavia
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Details
Developed by Committee: E10
Pages: 189–196
DOI: 10.1520/STP10075S
ISBN-EB: 978-0-8031-5069-0
ISBN-13: 978-0-8031-1184-4