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Showing results 1 to 20 of 20

Publication Date	Title	Author(s)
Apr-2013	Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor	Morreale, Andrew C.
Jul-2017	CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY	Hollingshead, Christopher William
May-2017	Comparative Safety Evaluation of Thorium Fuel to Natural Uranium Fuel in a CANDU 6 Reactor	Demers, Zachary
2017	Comparative study of accident-tolerant fuel for a CANDU lattice	Younan, Simon
Oct-2012	A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor	Trudell, David A.
2022	Development and Evaluation of Polaris CANDU Geometry Modelling and of TRACE_Mac/PARCS_Mac Coupling with RRS for CANDU Analysis	Younan, Simon
2023	DEVELOPMENT OF A TECHNIQUE TO LOCALIZE AND QUANTIFY VOLUMETRIC LOW-LEVEL WASTE FROM CANDU PLANTS	Zhou, Peixiao
2013	Development of Applicable Benchmark Experiments for (Th,Pu)O2 Power Reactor Designs Using TSUNAMI Analysis	Langton, Stephanie E.
2025	Development of Dynamic Safety Assessment Instruments for Application to Nuclear Power Plant Risk-Informed Methods	Vododokhov, Nikolai
Nov-2022	Experimental and Computational Analysis of Mixed Convection Around In-Line Cylinders	Hollingshead, Christopher
2016	A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating	Dion, Alexander
13-Jun-2018	Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors	Zhou, Feng
Nov-2015	Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor	Yee, Shaun Sia Ho
Mar-2005	NEUTRON DOSIMETRY AT ONTARIO POWER GENERATION: CALIBRATION FACTORS FOR THE SNOOPY - NP-100 NEUTRON REM-METER	Moscu, Diana F.
1981	Parametric Analysis of CANDU Neutron Transients	McCormick, T.R.
2018	Producing Medical Radioisotopes with CANDU Nuclear Reactors	Sutherland, Zachary
2016	Proliferation resistance evaluation of CANDU reactor systems with different fuel cycles	Wang, Xiaopan
Oct-2011	A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS	Friedlander, Yonni
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

Showing results 1 to 20 of 20