Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT)

•Identified four performance issues that may limit uranium-zirconium fuel lifetime.•Constituent redistribution and fuel swelling in uranium-zirconium were analyzed.•Variables driving these phenomena were discussed.•Review of mechanical constraint, temperature, grain size, fission rate, etc… Metallic...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Annals of nuclear energy 2020-02, Vol.136 (C), p.107016, Article 107016
Hauptverfasser: Williams, W.J., Wachs, D.M., Okuniewski, M.A., van den Berghe, S.
Format: Artikel
Sprache:eng
Schlagworte:
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Beschreibung
Zusammenfassung:•Identified four performance issues that may limit uranium-zirconium fuel lifetime.•Constituent redistribution and fuel swelling in uranium-zirconium were analyzed.•Variables driving these phenomena were discussed.•Review of mechanical constraint, temperature, grain size, fission rate, etc… Metallic alloy U-Zr nuclear fuels remain a candidate for future US fast reactors. However, with more than 30 years of investigation into the system, U-Zr fuel remains unqualified and lacks predictive modeling capabilities. Phenomenon identification and ranking tables (PIRT) were developed for U-Zr fuels to prioritize the study of microstructural phenomena related to fuel performance and to aid predictive models. Two areas of emphasis, fuel swelling and constituent redistribution, were identified with PIRT and were evaluated in detail. The analysis identified influencing parameters that should be considered during future studies including: external mechanical constraint, temperature, composition, crystallographic texture, temperature gradient, fabrication constraints, fission density, fission rate, initial porosity, and pre-irradiation grain size. The PIRT results support the need for a comprehensive study that focus on the decoupling of fission rate, irradiation temperature, and alloy composition to independently investigate the microstructural evolution in the multiple phases typical of advanced reactor conditions.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2019.107016