Browsing by Author "Piro, Markus"
Now showing items 1-6 of 6
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Assessing the behaviour of solid particulates in the flow of molten salt reactor coolant circuits
Arthurs, Cole William (2023-04-01)This work investigated solid particulate behaviour in molten salt nuclear reactors. Solid particulates are expected to form from fission products reacting with fuel components, creating compounds with melting temperatures ... -
Calculating thermochemical equilibrium for multiphysics simulations of nuclear materials : development of yellowjacket gibbs energy minimiser
Bajpai, Parikshit (2022-11-01)Nuclear fuels and structural materials are highly complex systems that are remarkably challenging to understand and model. Material behaviours are influenced by multiple physical phenomena such as mechanics, chemistry, ... -
Computational fluid dynamic investigations of flow through an aged CANDU pressure tube
Lu, Zheng (2021-08-01)Single-phase, isothermal computational fluid dynamics simulations of twelve simplified CANDUTM 37M fuel bundles sitting in both as-received and aged pressure tubes were performed with Hydra in this work. The predicted ... -
Developing a framework for thermodynamic measurements of fluoride salt nuclear fuel
Hallatt, Daniel Bryan (2019-10-01)With a single liquid acting simultaneously as a primary coolant and a nuclear fuel, molten salt reactor development has been challenged with understanding the behavior of its complex fluoride solution under various conditions. ... -
Material properties and mechanical behaviour of large-scale additively manufactured multi-layered steels
Tenuta, Eric Michael (2020-03-01)Metal Big Area Additive Manufacturing is an additive manufacturing technique based on gas metal arc welding. The systems’ dual nozzle design prints two steels simultaneously; in this study, the test samples are made from ... -
Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl
Breeden, Benjamin A. T. (2022-07-01)The primary goal of this work was to enhance MELCOR’s material modelling capabilities via one-way coupling of Thermochimica. MELCOR is a state-of-the-art code used to simulate the severe accident progression of a nuclear ...