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Browsing by Author Novog, David

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Showing results 1 to 34 of 34

Publication Date	Title	Author(s)
2017	Axisymmetric Jet Impingement onto a Heated Cylinder	Joyal, David A
Nov-2014	CFD Study of Convective Heat Transfer to Carbon Dioxide and Water at Supercritical Pressures in Vertical Circular Pipes	Zhou, Feng
Jul-2017	CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY	Hollingshead, Christopher William
2017	Comparative study of accident-tolerant fuel for a CANDU lattice	Younan, Simon
Jun-2014	A Computational Benchmark Study of Forced Convective Heat Transfer to Water at Supercritical Pressure Flowing Within a 7 Rod Bundle	McClure, Darryl
Nov-2015	Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor	Hummel, David
Oct-2013	Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations	McEwan, Curtis E.
Apr-2012	Critical Heat Flux for a Downwards Facing Disk in a Subcooled Pool Boiling Environment	Gocmanac, Marko
2021	Development and Benchmarking of RAVEN with TRACE for use in Dynamic Probabilistic Risk Assessment	Boniface, Kendall
2022	Development and Evaluation of Polaris CANDU Geometry Modelling and of TRACE_Mac/PARCS_Mac Coupling with RRS for CANDU Analysis	Younan, Simon
2025	Development of Dynamic Safety Assessment Instruments for Application to Nuclear Power Plant Risk-Informed Methods	Vododokhov, Nikolai
-	Effect of Flow Blockages on Interfacial Area in Two-Phase Flows	Leung, Kenneth
Nov-2022	Experimental and Computational Analysis of Mixed Convection Around In-Line Cylinders	Hollingshead, Christopher
2023	An Experimental Investigation of Critical Heat Flux on a Vertical Surface Abutting a Coarse Porous Medium	Spencer, Justin H.
2015	Experimental Study of Single Phase Turbulent Pipe Flow with Variable Obstructions	Jacinto, Edilson Nogueira
2024	Fluid Dynamic Model of the Molten Salt Reactor Experiment Using Flownex Simulation Environment	Crawford, Sean
2020	Hydrogen & Deuterium Detection in Zr-2.5%Nb by Laser Induced Breakdown Spectroscopy	Kurnell, Mitchell D.
2017	An Investigation Into The Flow In Candu Fan Nozzles	Sheasgreen, Travis
2018	INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR	Moghrabi, Ahmad
Jun-2010	Large LOCA BEAU Analysis of a Generic 900MW CANDU Plant	Sabouri, Pouya
2017	Lattice Physics Calculations for Alternative Fuels for the Canadian SCWR	Glanfield, Edward Matthew
2016	LOSS OF COOLANT ACCIDENT SIMULATION FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR USING RELAP5/MOD4	Lou, Mengmeng
2025	MEASUREMENT AND CHARACTERIZATION OF DISTURBANCE WAVES IN PRESSURIZED TWO-PHASE FLOW WITH X-RAY DENSITOMETRY AND NOVEL PROCESSING METHODS	Liu, Yang
13-Jun-2018	Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors	Zhou, Feng
2021	NEUTRON FLUX MEASUREMENTS FOR UNCERTAINTY QUANTIFICATION AT THE MCMASTER NUCLEAR REACTOR	MacConnachie, Elizabeth
2023	Portable Fast Neutron Computed Tomography System for Void Fraction Measurements	Patterson, Garik
Nov-2014	Prediction of The Response of the Canadian Super Critical Water Reactor to Potential Loss of Forced Flow Scenarios	Wu, Yang
2018	Producing Medical Radioisotopes with CANDU Nuclear Reactors	Sutherland, Zachary
Jun-2015	Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel	Scriven, Michael
2019	A Study of the Thermal-Hydraulic Behaviour of the Bruce A CANDU Moderator Using a Small-Scale Model	Strack, James Michael Vincent
2020	A TRACE/PARCS Coupling, Uncertainty Propagation and Sensitivity Analysis Methodology for the IAEA ICSP on Numerical Benchmarks for Multi-Physics Simulation of Pressurized Heavy Water Reactor Transients	Groves, Kai
2023	Uncertainty Analysis in Modelling for CANDU and Pressurized Water Reactors	Tucker, Michael
2009	Validation of Computational Fluid Dynamic Tools for Single-Phase Flow Distribution in CANDU Headers	Muhana, Ala
2024	Validation of the RELAP5 Code for Loss of Heat Sink Events in the McMaster Nuclear Reactor	Ruiz, Kevin

Showing results 1 to 34 of 34