Developing a method for crack arrest test at microscales

Zirconium alloys are widely used in nuclear reactors due to their low absorption cross section against thermal neutrons and good mechanical properties. Inside the core of reactors, the hot water coolant reacts with zirconium and releases hydrogen into the zirconium lattice. With time, hydrogen concentration increases leading to the formation of a brittle phase known as hydrides. This process reduces the fracture toughness of zirconium alloys leading to formation of micro-cracks that can eventually lead to the costly replacement procedures. This research focuses on the development of an experimental method for determining arrest properties of zirconium and hydrides at microscales. Advanced numerical methods and experimental techniques will be used to determine under what circumstances a crack may propagate or arrest in zirconium and hydrides. The output of this project is an experimental method that helps provide better understanding of cracking mechanisms in zirconium and hydrides.

Faculty Supervisor:

Hamidreza Abdolvand

Student:

Partner:

Canadian Nuclear Laboratories

Discipline:

Engineering

Sector:

Professional, scientific and technical services; Public administration; Utilities

University:

The University of Western Ontario

Program: