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Karahan, A.*; 川田 賢一; Tentner, A.*
Proceedings of 2018 ANS Winter Meeting and Nuclear Technology Expo; Embedded Topical International Topical Meeting on Advances in Thermal Hydraulics (ATH 2018) (USB Flash Drive), 4 Pages, 2018/11
An initial comparison of the SAS4A version 5.2 code predictions and observed results of two of the CABRI-1 Sodium-cooled Fast Reactor (SFR) Oxide Fuel tests has been accomplished. The selected experiments are (1) AI3, a Transient Over-Power test and (2) BI3, a Loss-of-Flow and Transient Over-Power test. The initial simulations describe the test events up to the time of cladding failure and results such as onset of the coolant boiling, time and spatial variation of the fuel pin temperature, and clad failure time and location are given. The calculated clad failure results are in reasonable agreement with the corresponding experimental results. Directions for further improvement of the mixed oxide fuel models of the SAS4A code are outlined.