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Browsing by Author Novog, David
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Showing results 16 to 32 of 32
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Publication Date
Title
Author(s)
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
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 BruceĀ 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