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Development and characterization of a high resolution portable gamma spectrometer
(2012-04-01)
The recent disaster of Fukushima in Japan combined with the high demand to enhance nuclear safety and to minimize personal exposure to radioactive materials has a significant impact on research and development of radiation ...
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 ...
Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.
(2014-08-01)
In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU ...
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 ...
Three dimensional heterogeneous finite element method for static multi-group neutron diffusion
(2010-08-01)
Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; ...
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 ...
Neutron production in a spherical phantom aboard the international space station
(2010-12-01)
Since the beginning of space exploration in last century, several kinds of devices from passive and active dosimeters to radiation environment monitors have been used to measure radiation levels onboard different space ...
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 ...