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Browsing by Author Luxat, John

Jump to: 0-9 A B C D E F G H I J K L M N O P Q R S T U V W X Y Z
 
Showing results 1 to 17 of 17
Publication DateTitleAuthor(s)
2016Analysis of Flow Reversal under Two-Phase Natural Circulation in CANDU9 during Small Loss of Coolant Accident with Loss of Class IV PowerYu, Changrui
2015Analysis of Postulated Pool Draining Accidents in the MNRSchneider, Alexander Shlomo
2022Assessment of the Long-Term Waste Management and Proliferation Resistance of Different Fuel Cycles for the Generation-IV Canadian Concept of Super-Critical Water ReactorIbrahim, Remon
May-2017Comparative Safety Evaluation of Thorium Fuel to Natural Uranium Fuel in a CANDU 6 ReactorDemers, Zachary
2021Core Design Optimization and Steady State Criticality Analysis of the Canadian Nuclear Battery™Reodikar, Sameer
2023Development of a Multiscale Analysis Methodology for Analysis of Transients in a Small Lead Cooled Advanced ReactorReale Hernandez, Cuauhtemoc
2019Diffusion resistance of claddings for corrosion protection of structural alloys in molten salt reactorsEveleigh, Cedric
2023An Experimental Investigation of Critical Heat Flux on a Vertical Surface Abutting a Coarse Porous MediumSpencer, Justin H.
2020HYBRID SYSTEMS USING SMRS: A PATH TOWARDS SUSTAINABILITY IN NUCLEAR AND CANADIAN ENERGY PRODUCTIONBysice, Stephanie
2016A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube OverheatingDion, Alexander
Nov-2014Modeling and Assessment of Emergency Mitigation Preparedness & Vulnerability for External Events in Nuclear Power PlantsAssi, Ahmad
Nov-2015Modelling Pure Thorium Bundle Implementation in the CANDU-6 ReactorYee, Shaun Sia Ho
Sep-2009PRESSURE TUBE-CALANDRIA TUBE THERMAL CONTACT CONDUCTANCECziraky, Adam
2011QUENCH OF CYLINDRICAL TUBES DURING TRANSITION FROM FILM TO NUCLEATE BOILING HEAT TRANSFER IN CANDU REACTOR CORETakrouri, Kifah
Oct-2011A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORSFriedlander, Yonni
Jun-2015Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a ChannelScriven, Michael
2016A Time-Dependent Description of In-Core Gamma Heating in the McMaster Nuclear ReactorStoll, Kurt Jason Lorenz
Showing results 1 to 17 of 17
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