Development and assessment of ASTEC-Na fuel pin thermo-mechanical models performed in the European JASMIN project

S. Perez-Martin*, W. Pfrang, N. Girault, L. Cloarec, L. Laborde, M. Buck, V. Matuzas, A. Flores y Flores, A. L. Smith, More Authors

*Corresponding author for this work

Research output: Contribution to journalArticleScientificpeer-review

3 Citations (Scopus)

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 languageEnglish
Pages (from-to)454-473
Number of pages20
JournalAnnals of Nuclear Energy
Volume119
DOIs
Publication statusPublished - 2018
Externally publishedYes

Keywords

  • CABRI programs
  • Cladding mechanical model
  • Fission gas behavior
  • Fuel pin thermo-mechanics
  • Pin failure
  • Power ramp
  • Sodium-cooled Fast Reactors
  • Transient overpower

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