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Polarization, passivation, intercalation, and generation: an examination of In-Situ and Ex-Situ analytical techniques for the study of carbon anode materials for the electrochemical generation of elemental fluorine.
(2011-12-01)
The field of industrial fluorine generation has not made significant progress in the past 60 years due to the difficulty and hazards surrounding the use of hydrofluoric acid (HF) and fluorine gas. This work examines various ...
Study of fuzzy logic in safety and control systems in nuclear power plants
(2016-03-01)
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
(2016-08-01)
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 ...
Assessment of FLUENT CFD code as an analysis tool for SCW applications
(2012-08-01)
Chosen as one of six Generation‒IV nuclear-reactor concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to the reactor‟s high pressures and ...
Design of a fault tolerant control scheme based on sliding mode for Canadian supercritical water reactor
(2016-08-01)
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 ...
The application of experimental microdosimetry to mixed-field neutron-gamma dosimetry
(2012-12-01)
Absorbed dose distributions in lineal energy for neutrons and gamma rays were measured by using both a tissue-equivalent walled counter (TEPC) and a graphite-walled low pressure proportional counter (GPC) in the Am-Be ...
One-dimensional single phase natural circulation model of FLiNaK in Molten Salt Loop
(2019-04-01)
This work studied a coolant for a molten salt type reactor in terms of a natural circulation behavior. A natural circulation model using MATLAB was developed. This model is for the Molten Salt Loop currently under development ...
A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes
(2018-01-01)
Wall thinning of carbon steel in CANDU reactor outlet feeder pipes due to Flow Accelerated Corrosion (FAC) is identified as one of the challenges for CANDU reactors since it would force them to shut down due to safety ...
Conceptual design of a thermal hydraulic loop for multiple test geometries at supercritical conditions named supercritical phenomena experimental test apparatus (SPETA)
(2012-04-01)
The efficiency of nuclear reactors can be improved by increasing the operating pressure of current nuclear reactors. Current CANDU-type nuclear reactors use heavy water as coolant at an outlet pressure of up to 11.5 MPa. ...
Determining the effectiveness of nuclear security through computer simulation
(2015-09-01)
There is a growing concern from both national regulators and the International
Atomic Energy Agency (IAEA) about the threat posed by attacks against iconic targets such as nuclear power plants. This has led to an increased ...