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  • CANTEACH Project Mandate
    Home What s New CANTEACH Project Library Help Overview Mandate Partners Credits CANTEACH Project Mandate This page is under construction Copyright CANTEACH canteach candu org Disclaimer

    Original URL path: http://www.nuceng.ca/canteachmirror/mandate.html (2014-10-09)
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  • CANTEACH: Credits
    Origins and Evolution John S Foster 1921 2001 was AECL s President and CEO between 1974 and 1977 He was a fellow of the Royal Society of Canada past president of the World Energy Council and recipient of the gold medal of the Association of Professional Engineers of Ontario along with many other honours Dan Meneley AECL Engineer Emeritus retired October 2001 PhD Reactor Physics University of London 1963 Chief

    Original URL path: http://www.nuceng.ca/canteachmirror/credits.html (2014-10-09)
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  • CANTEACH Library
    this simulator is available from IAEA on request IAEA CANDU Instrumentation Control Course by Dr Mike MacBeth AECL September 13 18 1998 SNERDI Shanghai 1 Instrumentation Equipment pdf 2 78Mb 100 pages Doc 20041601 1 1 Introduction to Instrumentation 1 2 ISA Symbols 1 3 Pressure Instrumentation 1 4 Level Instrumentation 1 5 Flow Instrumentation 1 6 Temperature Instrumentation 1 7 Control Valves and Accessories 2 Electronic Control pdf 1 64Mb 81 pages Doc 20041602 2 1 Control Concepts 2 2 Control and Process Considerations 2 3 Boiler Level Control 3 Controller Tuning pdf 499Kb 39 pages Doc 20041603 3 1 Ultimate Sensitivity Method 3 2 CANDU Control Computer System 4 Computer Input Output Subsystems pdf 474Kb 44 pages Doc 20041604 4 1 Computer Input Output Subsystem Considerations 4 2 Digital Control Concepts 5 Control Programs pdf 792Kb 74 pages Doc 20041605 5 1 Moderator Temperature Control program 5 2 Steam Generator Level Control Program 5 3 Pressure Control 6 Nuclear Instrumentation pdf 507Kb 23 pages Doc 20041606 6 1 Log and Linear Ranges 6 2 Log Range Detectors 6 3 Linear Range Detectors 7 Reactor Control and Protection pdf 613Kb 32 pages Doc 20041607 7 1 Recovery from a

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  • CANTEACH Library
    718 Reactor Heat Transport System Simulation and Analysis Industrial Monitoring and Detection Techniques 4L04 6L04 Science for Nuclear Energy and Radiation a comprehensive course for Grade School and High School Science Teachers Books An Introduction to the CANDU Nuclear Energy Conversion System by A A Harms 1975 Reproduced here with the kind permission of A A Harms Summary The CANDU nuclear reactor has recently attracted considerable attention both at home and abroad The increasing interest in this distinctly Canadian nuclear energy system has identified the need for an introductory description of the basic elements of the CANDU reactor suitable for a readership with a wide range of professional qualifications It is believed that this monograph can serve as a self study guide and as a supportive text for the scientist engineer and other technically oriented individual with little previous exposure to nuclear engineering in general and who possesses only a passing familiarity with the CANDU nuclear reactor in particular An attempt has been made to be impressionistic on both the analytical scientific and the systems descriptive level A detailed discussion of specialized topics such as reactor physics plant engineering and reactor operations is outside the scope of this text from

    Original URL path: http://www.nuceng.ca/canteachmirror/mcmaster.html (2014-10-09)
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  • Basic Search
    Institute of Technology UofT Hold Ctrl key for multiple selection Select the Keywords Hold Ctrl key for multiple selection SI What and Where Discipline How and Why Topic How and Why Phase When Audience Level Who 00000 General Project 10000 Site and Improvements 20000 Buildings and Structures 30000 Reactor Steam Generators and Auxiliaries 31000 Reactor 32000 Moderator System 32100 Moderator Main Circuit 32200 Moderator Purification System 32300 Moderator Cover Gas System 32500 Moderator Collection System 32700 Moderator Liquid Poison System 33000 Primary Heat Transport System 33100 Main Heat Transport System 33300 Primary Heat Transport Auxiliaries 33400 Cooling Systems 33500 Gas Control System 33600 Overpressure Relief System 33700 D2O Sampling System 33800 Collection System 33900 Installation and Maintenance Equipment 34000 Auxiliary System 35000 Fuel Transfer and Storage 36000 Steam Generator Steam and Water Systems 37000 Fuel 38000 Heavy Water Management 39000 Not assigned 40000 Turbine Generator and Auxiliaries 50000 Electric Power Systems 60000 Instrumentation and Control 70000 Common Processes and Services 80000 Construction Plant 90000 Operations and Commissioning Biology Chemical Engineering Chemistry Civil Engineering Electrical Engineering Environmental Engineering General Engineering General Science Health Physics History Materials Engineering Mathematics Mechanical Engineering Nuclear Engineering Physics Psychology Basic Equations Conceptual Corrosion Costs Fluid Mechanics

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  • Bill Garland's Nuclear Engineering Site - direct to Who's Who

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    Original URL path: /courses/courseindex.htm (2014-10-09)


  • CANTEACH Library: A Reactor in a Nutshell
    3 U 238 The result of the fission is fission products that are radioactive radiation fast neutrons and heat The fast neutrons have a low probability of inducing further fissions and hence generating more neutrons thus sustaining a chain reaction So we need to slow down the neutrons i e thermalize or moderate them which we do by using a moderator such as water We also need to remove the heat generated We control the process by controlling the number of neutrons since the number of fissions per second and hence the heat produced is proportional to the number of neutrons present to induce the fissions From this we can directly derive the basic functional requirements of a reactor We need fuel U 235 a moderator to thermalize the fast neutrons a coolant to remove the heat a control system to control the number of neutrons shielding to protect equipment and people from radiation Animations from Atomic Alchemy Nuclear Processes Heat engines to take away the heat generated by fissioning The fissioning process generates heat We typically use the heat engine process to turn this heat into a more useable that is flexible transportable convenient form of energy The heat

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  • Portfolio -1/1
    10 02 to WJG image file Some tec pdf 8 of 8 File info 00000 General Carbon Cycle pdf size 64 K Description Source William Snook email 2001 10 02 to WJG image file Some tec pdf 2 of 8 File info 00000 General Darlington Layout pdf size 240 K Description Source William Snook 2001 07 20 CD to WJG image 940188 Darlington Layout pdf File info 00000 General Darlington Reactor pdf size 227 K Description Source William Snook 2001 07 20 CD to WJG image 940188 Darl Reactor pdf File info 00000 General Genealogy Poster pdf size 197 K Description Source William Snook 2001 07 20 CD to WJG image 980889 Genealogy Poster pdf File info 00000 General Genealogy slide jpg size 92 K Description Source Ron Page slide collection CD volume 1 1 image 0002 File info 00000 General NPD Reactor Cutaway pdf size 448 K Description Source William Snook email 2001 08 09 to WJG image Cutaway pdf File info 00000 General Russian Chernoby pdf size 279 K Description Source William Snook email 2001 08 27 to WJG File info 00000 General Russian Plan Smo pdf size 404 K Description Source William Snook email 2001 08 27

    Original URL path: http://www.nuceng.ca/canteachmirror/imagelib/00000-general.htm (2014-10-09)
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