Book ChapterDOI
Irradiation Creep Behavior of Zr-Base Alloys
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The article was published on 2002-01-01. It has received 28 citations till now. The article focuses on the topics: Creep & Zirconium alloy.read more
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Book ChapterDOI
Radiation Effects in Zirconium Alloys
F. Onimus,J.L. Béchade +1 more
TL;DR: In this article, the effects of neutron irradiation on zirconium alloys are described, describing damage creation and point-defect evolution leading to loops formation and secondary-phase evolution under irradiation.
Journal ArticleDOI
Irradiation creep and growth of zirconium alloys: A critical review
TL;DR: A review of the evolution in measurement methodologies (either from controlled experiments in materials test reactors or gauging of power reactor components) is described together with the results gleaned from such measurements.
Journal ArticleDOI
3D fuel cracking modelling in pellet cladding mechanical interaction
TL;DR: In this paper, a mathematical formulation which couples a viscoplastic law for creep with a multi-surface plastic softening law for cracking is detailed, leading a two inelastic strains model.
ReportDOI
Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO
TL;DR: In this paper, the U.S. Nuclear Regulatory Commission (NRC) uses the computer codes FRAPCON-3 and FRAPTRAN to model steady state and transient fuel behavior, respectively, in regulatory analysis.
Journal ArticleDOI
Finite element simulation of Pellet-Cladding Interaction (PCI) in nuclear fuel rods
N. Marchal,C. Campos,C. Garnier +2 more
TL;DR: In this paper, the use of finite element method to simulate locally the phenomenon of Pellet-Cladding Interaction (PCI) in nuclear fuel rods is discussed. But the authors focus on the effect of fuel fracture properties on clad loading.