Impact of Fuel Assembly Transportation on Zirconium Alloys: toward a Mechanistic Understanding

Zirconium alloys are commonly used in pressurized water reactor as fuel rod cladding tubes. After irradiation and cooling in pool, the spent nuclear fuel assemblies are transported for wet storage to a devoted site. During dry transportation, at temperatures around 400[degrees]C, the cladding experi...

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Bibliographic Details
Published in:EPJ Web of conferences 2013-01, Vol.51, p.3003-19
Main Authors: Onimus, Fabien, Ribis, Joël, Bourdiliau, Brice, Cappelaere, Chantal
Format: Article
Language:English
Subjects:
Assembly
Cladding
Cooling
Creep strength
Fuels
Internal pressure
Transportation
Zirconium base alloys
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Summary:Zirconium alloys are commonly used in pressurized water reactor as fuel rod cladding tubes. After irradiation and cooling in pool, the spent nuclear fuel assemblies are transported for wet storage to a devoted site. During dry transportation, at temperatures around 400[degrees]C, the cladding experiences a creep deformation under the hoop stress induced by the internal pressure of the fuel rod. A recovery of the radiation damage can occur during transportation that can affect the subsequent mechanical properties [1].
ISSN:2100-014X
2100-014X
DOI:10.1051/epjconf/20135103003