Effects of ion irradiation on microstructure and properties of zirconium alloys—A review

Heavy ion irradiation induced dislocation loops in AREVA’s M5® alloy

Diffusion of point defects, nucleation of dislocation loops, and effect of hydrogen in hcp-Zr: Ab initio and classical simulations

Zirconium (Zr) alloys are the primary structural materials of most water reactors. Creep is considered to be one of the important degradation mechanisms of Zr alloys during reactor operating and repository conditions. Zr alloys pick up hydrogen (H2) during their service from the coolant water. Hydrogen can be present in solid solution or precipitated hydride form in Zr alloys depending upon the temperature and concentration. This study reviews the effect of hydrogen on creep behavior of Zr alloys used in the water reactors.

Creep Behavior of Hydrogenated Zirconium Alloys

The time-dependent deformation of materials or creep governs the useful life of many engineering structures It assumes even higher significance in the case of structures constituting a nuclear reactor, wherein materials bombarded with neutrons develop defects that assist faster diffusion leading to greater plastic deformation As a result, an understanding of the creep deformation process and factors controlling it is necessary for gauging the usefulness of materials in a nuclear reactor as well as for predicting life-times of various structures Thus in this work we discuss the various mechanisms of creep, the rate controlling factors, deformation mechanism maps and useful life prediction methodologies We also identify a few cases where direct application of simple creep correlations might not be feasible Finally, we discuss the various factors that control the creep behavior of materials in light water reactors

A.L. Bement

Papers

In-reactor creep of zirconium alloys.