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Full-Text Articles in Nuclear Engineering
Gamma-Radiation Induced Corrosion Of Alloy 800, Mojtaba Momeni
Gamma-Radiation Induced Corrosion Of Alloy 800, Mojtaba Momeni
Electronic Thesis and Dissertation Repository
This thesis presents a newly developed mechanism and predictive model for the corrosion of Alloy 800. The Fe-Cr-Ni Alloy (Incoloy 800) is mainly used for steam generator (SG) tubing in CANDU and PWR reactors and is a candidate material for the proposed Canadian Supercritical Water Reactor (SCWR) in which it will be exposed to extreme conditions of high radiation flux and large temperature gradients. The influence of gamma radiation and water chemistry conditions on the corrosion behaviour of Alloy 800 are studied in this work. Ionizing radiation creates reducing (•eaq–, •H, •O2-) and oxidizing …
Thermal Kinetics Of Helium Irradiation Hardening In Selected Alloys For The Canadian Gen. Iv Nuclear Reactor Concept, Feifei Nie
Electronic Thesis and Dissertation Repository
In this thesis, we present nano-indentation measurements performed to quantify the increase in hardness as a result of He+ and Fe4+ implantation in both Inconel 800H and AISI 310 alloys. After annealing, the softening rate of He+ and Fe4+ implanted samples were compared, and it is found that Ni can slow the helium diffusion. Thermal activation energy Q characterizing this process was similar to the computed thermal activation energy QHe for interstitial helium diffusion within pure nickel. Indentation hardness tests were also performed at various indentation strain rates, to further study the effect of implanted …