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Hydrogen diffusion in zirconium alloys: The role of beta-phase morphology, co...
Zr is used extensively in nuclear reactors worldwide in a broad range of microstructural conditions due to its thermomechanical, corrosion and neutronic properties. However the... -
In situ loading of Zr-2.5Nb-O at cryogenic temperatures
The proposed experiment will study the deformation of a two phase Zr-2.5Nb alloy at cryogenic temperatures. It forms part of our ongoing long-term project to understand the... -
Mg_sample5_-150deg_a;s-5;e0.00;p34.74
This dataset has no description
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High temperature fatigue loading of Zr-2
Zircaloy-2 and its almost identical sister alloy Zr-4 are used extensively as fuel cladding, as well as other components in nuclear power reactors where it operates at 250-350C... -
In-situ neutron diffraction investigation of the BCC and FCC Oxide Dispersion...
ODS alloys are currently considered as one of the most promising nuclear materials for high-temperature applications in the ¿Generation-IV Nuclear Reactors¿. The proposed... -
In-situ tension and compression tests in plane strain
This proposal forms part of our larger study into the mechanics of nickel based alloys. In particular we are attempting to correlate the intergranular stress development in... -
Continuation of Proposal (RB820197): The elasto-plastic response of dual-phas...
In the current proposal we propose to test Zr-2.5Nb samples cut at a range of angles (0, 22.5, 45, 67.5 and 90°) in the RD-TD plane in in-situ compression at room temperature.... -
Intergranular strain development during biaxial loading
The experiment will measure the development of Type II intergranular strains in 316 stainless steel as a function of applied stress for stress states ranging from uniaxial to...
