Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys

A review of microstructure evolution in zirconium alloys during irradiation

Radiation damage in nanostructured materials

In the conventional rate-theory treatment of irradiation-induced dimensional changes based on the concept of dislocation bias, it is implicitly assumed that interstitials and vacancies are produced continuously and uniformly in the form of Frenkel pairs. This implies that all produced point defects are free and are available for annihilation at sinks. This approach may not be appropriate, however, for cases where the damage is produced in the form of cascades. In the cascades both vacancies and interstitials are produced in a highly segregated fashion in that the distributions of vacancies and interstitials are separated from each other in space. This spatial segregation is maintained even after the end of the thermal spike phase during which vacancies condense in the central region of the cascades whereas the high concentration of highly mobile interstitials form clusters at a certain distance from the cascade centre. The consideration of interstitial clustering within the cascade region yields ...

Production bias due to clustering of point defects in irradiation-induced cascades

Malcolm Griffiths

Papers

A review of microstructure evolution in zirconium alloys during irradiation

Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation

The formation of c-component defects in zirconium alloys during neutron irradiation

Evolution of microstructure in hcp metals during irradiation

Intergranular fracture in irradiated Inconel X-750 containing very high concentrations of helium and hydrogen