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  • CANTEACH
    the mandate to produce technical educational material on CANDU with a focus on why CANDU is designed the way it is not just how it is designed The resulting web site has been archived at CANTEACH rev1 CANTEACH rev2 First version In early 2002 the CANTEACH projected moved to COG sponsorship and administration The site was moved to COG web space on 2002 05 17 This site has a working search and filter engine but the metadata keyword database is not fully populated This site has been archived as CANTEACH rev2 CANTEACH rev3 Current version Good progress was made in adding new documentation up to about 2005 when I got sidetracked by the UNENE initiative but from 2007 onwards there was considerable effort put in by the good people at COG and myself to improving the CANTEACH site to add better search and filtering capility based on keyword metadata A decision was made to halt further development of the existing site static html with a bit of php scripting for the search engine in favour of a new site based on MS Sharepoint similar to that used by COG internally The metadata keyword database was populated This new site permits

    Original URL path: http://www.nuceng.ca/canteach/index.htm (2014-10-09)
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  • Directions
    left on Longwood Road then right on Main Street West to the Visitors Inn From Downtown Hamilton King Street West past Hwy 403 and left on Macklin Street to the Visitors Inn McMaster University is located in the west end of Hamilton From Toronto Take the QEW west towards Hamilton to Highway 403 Travel on the 403 past Hwy 6 exit past the York Road exit past the Main Street East exit Take the Main Street West exit At the traffic lights at the top of the ramp turn left onto Main St W You are now heading west on Main St W Go past the hospital on your right to the intersection of Main and Cootes Drive Hang a right onto Cootes and take the first exit That takes you to the west end of Campus Turn right as you enter the campus and stop at the kiosk to pay the parking fee Park near the smoke stack The Nuclear bldg is nearby attached to the reactor Just ask the parking attendant to point you in the right direction You have to enter the bldg at the front See the receptionist to let you in Accessibility by Airports Hamilton

    Original URL path: http://www.nuceng.ca/faq/directions.htm (2014-10-09)
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  • CANDU textbook
    Chapter by chapter Cover pdf 100kb Frontmatter pdf 78kb as of 2014 09 27 Prologue CANDU in Context pdf 360kb by Dr William J Garland as of 2014 09 18 Chapter 1 Introduction to Nuclear Reactors pdf 700kb by Dr Robin Chaplin as of 2014 09 18 Appendix Historical Background pdf 210kb by Dr Robin Chaplin as of 2014 09 18 Chapter 2 Genealogy of CANDU Reactors pdf 2 3Mb by Dr Robin Chaplin as of 2014 09 18 Chapter 3 Nuclear Processes and Neutron Physics pdf 1 7Mb by Dr Guy Marleau as of 2014 09 27 Chapter 4 Reactor Statics pdf 1 0Mb by Dr Benjamin Rouben and Dr Eleodor Nichita as of 2014 09 18 Chapter 5 Reactor Dynamics pdf 590kb by Dr Eleodor Nichita and Dr Benjamin Rouben as of 2014 09 18 Chapter 6 Thermalhydraulic Design by Dr Nikolas K Popov in preparation Chapter 7 Thermalhydraulic Analysis by Dr Nikolas K Popov in preparation Chapter 8 Plant Systems pdf 3 1Mb by Dr Robin Chaplin as of 2014 09 18 Chapter 9 Plant Operations pdf 2 5Mb by Dr Robin Chaplin as of 2014 09 18 Chapter 10 Instrumentation and Control pdf 735kb by Dr G Alan Hepburn as of 2014 09 18 Chapter 11 Electrical Systems by Jin Jiang in preparation Chapter 12 Radiation Protection and Environmental Safety pdf 3 2Mb by Dr Edward Waller as of 2014 09 18 Chapter 13 Reactor Safety Safety Analysis pdf 100kb by Dr Victor G Snell as of 2014 09 18 Chapter 14 Nuclear Reactor Materials pdf 1 2Mb by Dr Derek H Lister and Dr William G Cook as of 2014 09 18 Chapter 15 Nuclear Process Systems Chemistry and Corrosion pdf 900kb by Dr William G Cook and Dr Derek H Lister as of 2014

    Original URL path: http://www.nuceng.ca/candu/index.htm (2014-10-09)
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  • Current Research Interests
    The correlation library needs to be extended extensively An in house core physics code exists but it needs to be extended in its property library and simulation of transients One Ph D student Dave Gilbert has worked on a Reactor Simulation Editor geared to provide a robust environment for DIY agents in reactor physics core modelling Bench Marking Reactor Physics and Thermalhydraulics The existing standard industrial codes are qualified for use on large power reactors Increasingly these codes are being called upon for use on small cores such as research and isotope production reactors Herein the research objectives relating to reactor physics are to prove with respect to research reactors such as the McMaster Nuclear Reactor that diffusion theory is adequate for core analysis fuel substitution predictions and control rod calibration predictions that the computer codes Dragon and WIMS give accurate cell parameters that a recipe for the use of these codes on research reactors can be developed and that analytical error estimates of diffusion theory can be provided To achieve these objectives Dragon and WIMS will be compared to in core measurements to MCNP and to accepted bench mark problems and perturbation theory will be pursued as a means of providing an analytical estimation of diffusion theory errors In the area of thermalhydraulics the objective is to prove the adequacy of the codes and of the current MNR design There exists a substantial experimental database for MTR type reactors the SPERT and BORAX tests The McMaster Nuclear Reactor is a MTR type reactor The research objective is to glean as much information from these tests to support the MNR Safety Analysis Report One Ph D student now graduated has completed working on this project A perennial reactor physics question is whether a full 3 D reactor physics model is needed for fast transient analysis of the MNR core or whether a point model will suffice Deterministic Reactor Analysis To support reactor operations and safety analysis MNR needs to be characterized both thermalhydraulically and neutronically The detailed velocity distributions in the MNR fuel assemblies have been measured experimentally using laser doppler anemometry by T S Ha at the Master s level The next steps are to characterize the core bypass flow investigate the influence of the entrance effects on assembly flow determine air cooling limits of the fuel Probabilistic Safety Analysis Probabilistic Safety Analysis PSA has been conducted for the McMaster Nuclear Reactor This PSA work and deterministic analysis form the basis for the current Safety Analysis Report required for licensing To support this work event trees and fault trees are constructed for 4 accident events suspected of being the main contributors to risk LOCA LOR loss of flow and flow blockage Current PSAs have a number of limitations that need to be addressed as indicated below An estimation of nonevent probabilities can be made using Bayesian statistics and other statistical techniques A sensitivity analysis needs to be conducted to determine the acceptability of the Bayesian approach Conventional PSA methodology

    Original URL path: http://www.nuceng.ca/research.htm (2014-10-09)
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  • Graduate Students
    the Distributed Approach S Marshall M Eng 1995 1997 Fission Product Free Correction Factors J Kennedy M Eng 1997 2000 A Comparison of MNR Irradiation Experiments with Simulation I Vencil M Eng 1998 2000 Statistical Estimation Of The Unavailability of the MNR Safety Amplifier Full text of thesis and supporting files zip 4 1Mb R Simionescu M Eng co supervised by Dr W F S Poehlman 1998 2000 Iodine Monitoring and Advising System N Safaian M Eng 2001 2003 Development of the MCNP Model for Darlington Nuclear Generating Station T S Ha M Eng 2000 2003 Subchannel Flows in MNR Plate Assemblies full text of thesis pdf 4 98 Mb L Tayebi M A Sc 2004 2006 Monitoring and Advising System for Iodine Status Ph D Students R Sollychin Ph D l983 1990 A Study of Pressure Response and Two Phase Phenomena in a Nuclear Power Plant Pressurizer S Adebiyi Ph D l985 1987 transferred to A A Harms The Hierarchy And Geometry Of Fission Reactor Dynamics G Gaboury Ph D 1987 1993 A Space Time Reactor Simulation with Integral Thermalhydraulics J Whitlock Ph D 1991 1995 Reduction of the Coolant Void Effect in a CANDU Lattice Cell R Leger

    Original URL path: http://www.nuceng.ca/grads/grads.htm (2014-10-09)
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  • Publications by Bill Garland
    HOME Publications Journal Papers Conference Papers Technical Reports Meeting Presentations Publications grouped by topic

    Original URL path: http://www.nuceng.ca/papers/papers.htm (2014-10-09)
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  • LIGHT WATER APPROXIMATIONS
    above plus a simple thermal hydraulic loop simulation This was produced in part by a former student If you download the FORTRAN or C code please send an email to Bill Garland so that you can be kept up to date on revisions See the journal publication page for the full papers J6 J8 J13 Note These papers are password protected because to copyright restrictions Individuals can contact me for further information Water Properties in Excel Based on the above water property fits Excel spreadsheet functions were created by Glen R McGee using Visual Basic for Applications VBA to calculate water properties This is recommended to anyone using Excel to analyse thermalhydraulic data ReadMe file pdf 12kb supporting documentation short but contains important and useful information T mach2o xls xls 86kb sample file containing the functions in action sample wjg xks xls 340kb another sample file showing the functions in action and a comparison to the IAPWS funtions also included see below Other available light water property software include IAPWS Water97 v13 xla Excel Add In for Properties of Water and Steam in SI Units authored by Bernhard Spang Hamburg Germany available at http alexmichinel com index php p 1

    Original URL path: http://www.nuceng.ca/water/h2ohome.htm (2014-10-09)
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  • Heavy Water
    also Approximate functions for the fast computation of the thermodynamic properties of heavy water by Ahmet Durmayaz Nuclear Energy and Design 178 pp309 329 1997 The approach taken is the same as for the light water fits Glen McGee prepared a front end for H2O and D2O He used CRL s SCOUT routines for D2O I believe Andrew Firla at Ontario Power Generation did some fits to D2O years ago that were accurate to about 1 as I recall Bob Horvath formerly at OH and now at Babcock Wilcox Canada coded Philip Hill s D2O tables that AECL uses Zip file 41 kb containing Fortran source code and an executable Haldun Tezel now at the CNSC did some DSNP work for Dan Meneley years ago at UNB He prepared some D2O props at that time Zip file 94 kb containing Fortran source code and an executable Ji Zhang at AECL prepared D2O fits to Hill using the same methodology as I used for H2O This was part of UNB s DSNP work again with Meneley All subroutines for the heavy water properties have been tested by Ji The accuracies of those calculations are shown in the beginning of each subroutine

    Original URL path: http://www.nuceng.ca/d2o/d2ohome.htm (2014-10-09)
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