Abstract
ASTEC-Na is a computer code system which evaluates protected and unprotected accidents in Sodium-cooled Fast Reactors throughout the Initiation Phase. The fuel pin behavior models implemented in ASTEC-Na simulate the essential aspects of the thermal and mechanical behavior of SFR fuel pins in nominal and accidental conditions. Besides the improvement of existing ASTEC-Na models, a specific cladding mechanical model and an in-pin fuel relocation model have been developed during the JASMIN project, where the latter has been already implemented in the code. ASTEC-Na fuel pin behavior models are described in this paper and their transient predictions for four CABRI transient tests are compared to available experimental data as well as to SAS-SFR and SIMMER-III code calculations. Conclusions on the overall performance of ASTEC-Na fuel pin models are also presented.
Original language | English |
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Pages (from-to) | 454-473 |
Number of pages | 20 |
Journal | Annals of Nuclear Energy |
Volume | 119 |
DOIs | |
Publication status | Published - 2018 |
Externally published | Yes |
Keywords
- CABRI programs
- Cladding mechanical model
- Fission gas behavior
- Fuel pin thermo-mechanics
- Pin failure
- Power ramp
- Sodium-cooled Fast Reactors
- Transient overpower