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Modeling dislocation evolution in irradiated alloys

Conference ·
DOI:https://doi.org/10.1007/BF02647229· OSTI ID:5303748
Neutron irradiation of structural materials leads to such observable changes as creep and void swelling. These effects are due to differential partitioning of point defects. Although most radiation-produced point defects recombine with an antidefect, a very small fraction of the defects survive. The surviving defect fraction is directly related to the density and type of extended defects that act as point defect sinks. Defect partitioning requires the presence of more than one type of sing and that at least one of the sinks has a capture efficiency for either vacancies or interstitials that is different from that of the other sink(s). For example, dislocations provide the interstitial bias'' that drives swelling and the ration of the dislocation to cavity sink strength determines the swelling rate. These sink strengths change during irradiation and an explicit model of their evolution is required to simulate swelling or creep. Such a model has been developed; the influence of various model assumptions and parameters is discussed. The model simulates the evolution of Frank faulted interstitial loops, providing a dislocation source and the glide/climb of the dislocation network leading to annihilation of dislocation segments. Good agreement is found between model predictions and experimental data. Swelling simulations are shown to be quite sensitive to the dislocation model. 39 refs., 7 figs., 2 tabs.
Research Organization:
Oak Ridge National Lab., TN (USA)
Sponsoring Organization:
DOE/ER
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5303748
Report Number(s):
CONF-8809322-2; ON: DE90004921
Country of Publication:
United States
Language:
English