Identification of fracture parameters for irradiated nuclear fuel

Gatt, J.-M.
Henry, R.
Zacharie-Aubrun, I.
Langlois, C.
Meille, S.

Publication date

August 2019

Publisher

HAL CCSD

Abstract

International audienceIntroduction:This paper deals with the fracture characteristics of UO$_2$ fuel. At low temperature (<900 °C) this ceramic has a brittle behavior in traction. The knowledge of fracture parameters for irradiated UO$_2$ fuel is useful to model and understand the behavior of the fuel in reactor. The crack model used in numerical simulations of the fuel rod behavior is based on two main parameters: the critical stress and the fracture toughness. The aim of this article is to analyze fracture tests to identify these two parameters at different scales. To obtain the rupture parameters, we use two kinds of sample (smooth and notched samples) with three sizes: large (28x4x4 mm$^3$), small (10x1.5x1.5 mm$^3$) and micrometric (13...

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Identification of fracture parameters for irradiated nuclear fuel

Abstract

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Identification of fracture parameters for irradiated nuclear fuel

Abstract

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