Now showing items 1-10 of 10
Study of fuzzy logic in safety and control systems in nuclear power plants
Safety and control systems in Nuclear Power Plants are essentially run without intelligent systems. As nuclear industry starts to become more advanced and vendors are starting to manufacture more advance products, old ...
Specifics of forced-convection heat transfer to supercritical water flowing upward in annular and bundle flow geometries
Since annulus- and bundle-flow geometries impede coolant flow, heat transfer to the coolant would occur differently than in bare tubes. The main objective of this work is to propose and verity a universal method to accurately ...
Design of a fault tolerant control scheme based on sliding mode for Canadian supercritical water reactor
Canadian Super Critical Water Reactor (SCWR) is one of the Generation IV reactor types and possible heat source for co-hydrogen production through copper chlorine thermochemical cycle. To maintain the balance between the ...
Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry
Neutron dosimetry in reactor fields is currently conducted using thermal neutron flux monitors. It has been demonstrated that Tissue Equivalent Proportional Counters (TEPCs) have the potential to improve the accuracy of ...
Characterization of neutron fields around an intense neutron generator
Neutron fields in the vicinity of the University of Ontario Institute of Technology neutron facility have been investigated in a series of simulations and experiments. The neutron fluence at several locations around the ...
Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors
To avoid the computational effort associated with full-core neutron transport calculations, full-core neutronics calculations for Pressurized Heavy-Water Reactors (PHWRs) are usually performed in diffusion theory using an ...
Letters to a young engineer. Third edition, 2016
(University of Ontario Institute of Technology, 2016)
Simulation of in-core dose rates for an offline CANDU reactor
This thesis describes the development of a Monte Carlo simulation to predict the dose rates that will be encountered by a novel robotic inspection system for the pressure tubes of an offline CANDU reactor. Simulations were ...
Dynamic safety assessment of FPGA-based safety critical systems with applications in nuclear power generation
Field Programmable Gate Arrays (FPGAS) are a type on integrated circuit that is configured by the end user to perform desired digital logic functions. FPGAs do not run any software or operating system, as the logic functions ...
The conceptualization and parameterization of a gaseous detector rasterizing pinhole gamma camera
This thesis details the conceptualization and parameterization of a gaseous detector rasterizing pinhole gamma camera. In this thesis, there is a literature review that describes the historical development of gamma imaging, ...