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Browsing by Author Luxat, John
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Showing results 1 to 17 of 17
Publication Date
Title
Author(s)
2016
Analysis of Flow Reversal under Two-Phase Natural Circulation in CANDU9 during Small Loss of Coolant Accident with Loss of Class IV Power
Yu, Changrui
2015
Analysis of Postulated Pool Draining Accidents in the MNR
Schneider, Alexander Shlomo
2022
Assessment of the Long-Term Waste Management and Proliferation Resistance of Different Fuel Cycles for the Generation-IV Canadian Concept of Super-Critical Water Reactor
Ibrahim, Remon
May-2017
Comparative Safety Evaluation of Thorium Fuel to Natural Uranium Fuel in a CANDU 6 Reactor
Demers, Zachary
2021
Core Design Optimization and Steady State Criticality Analysis of the Canadian Nuclear Battery™
Reodikar, Sameer
2023
Development of a Multiscale Analysis Methodology for Analysis of Transients in a Small Lead Cooled Advanced Reactor
Reale Hernandez, Cuauhtemoc
2019
Diffusion resistance of claddings for corrosion protection of structural alloys in molten salt reactors
Eveleigh, Cedric
2023
An Experimental Investigation of Critical Heat Flux on a Vertical Surface Abutting a Coarse Porous Medium
Spencer, Justin H.
2020
HYBRID SYSTEMS USING SMRS: A PATH TOWARDS SUSTAINABILITY IN NUCLEAR AND CANADIAN ENERGY PRODUCTION
Bysice, Stephanie
2016
A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating
Dion, Alexander
Nov-2014
Modeling and Assessment of Emergency Mitigation Preparedness & Vulnerability for External Events in Nuclear Power Plants
Assi, Ahmad
Nov-2015
Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor
Yee, Shaun Sia Ho
Sep-2009
PRESSURE TUBE-CALANDRIA TUBE THERMAL CONTACT CONDUCTANCE
Cziraky, Adam
2011
QUENCH OF CYLINDRICAL TUBES DURING TRANSITION FROM FILM TO NUCLEATE BOILING HEAT TRANSFER IN CANDU REACTOR CORE
Takrouri, Kifah
Oct-2011
A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS
Friedlander, Yonni
Jun-2015
Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel
Scriven, Michael
2016
A Time-Dependent Description of In-Core Gamma Heating in the McMaster Nuclear Reactor
Stoll, Kurt Jason Lorenz