| Autor: |
Corson, James, Chung, Alice, Muller, Steven |
| Zdroj: |
Nuclear Technology; Feb2024, Vol. 210 Issue 2, p261-268, 8p |
| Abstrakt: |
This paper presents the Fuel Analysis under Steady-state and Transient (FAST) code contribution to the P2M Simulation Exercise on past fuel melting irradiation experiments organized within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency's Framework for Irradiated Experiments (FIDES). The benchmark consists of comparisons to two power ramps (xM-3 and HBC-4) that experienced fuel centerline melting. In general, FAST accurately captured the behavior of the fuel rods during the tests, though there are some notable discrepancies between the FAST results and the cladding elongation and fission gas release during the xM-3 power ramp. [ABSTRACT FROM AUTHOR] |
| Databáze: |
Supplemental Index |
| Externí odkaz: |
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