Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors

A study analyzed the neutronics of alternate cladding materials in a pressurized water reactor (PWR) environment. Austenitic type 310 (310SS) and 304 stainless steels, ferritic Fe-20Cr-5Al (FeCrAl) and APMT(TM) alloys, and silicon carbide (SiC)-based materials were considered and compared with Zirca...

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Veröffentlicht in:	Annals of nuclear energy 2015-01, Vol.75, p.703-712
Hauptverfasser:	George, Nathan Michael, Terrani, Kurt, Powers, Jeff, Worrall, Andrew, Maldonado, Ivan
Format:	Artikel
Sprache:	eng
Schlagworte:	Austenitic stainless steels Cladding Enrichment Ferritic stainless steels Heat resistant steels Mathematical models Pellets Pressurized water reactors Stainless steels Voids Zirconium base alloys
Online-Zugang:	Volltext
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