Nuclear Engineering Commons^™

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 Q_He 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 …

Thermal Kinetics Of Ion Irradiation Hardening In Selected Alloys For The Canadian Gen. Iv Nuclear Reactor Concept, Heygaan Rajakumar

Electronic Thesis and Dissertation Repository

Canada is designing supercritical water fission reactors (SCWR) to increase the thermal efficiency of nuclear power generation from ~34% to ~48%. The temperature and pressure of a supercritical water reactor core is very high compared to a CANDU reactor. This thesis examines irradiation hardening and thermal recovery of two candidate alloys, AISI 310 and Inconel 800H, for the Canadian SCWR.

Samples of both alloys are mechanically ground and polished, then irradiated using 8.0 MeV Fe ions. The use of ion irradiation safely and quickly simulates neutron damage. The change in the hardness of the samples is then studied during a …