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[Phase]: Design Analysis Documents

Documents below are listed chronologically. Use the links on the left or below to filter documents by keyword. Use the links above to jump to a specific year on this page.

374 files

    1967---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  1. Nuclear Theory, Course 227, Nuclear Training Centre, OPG, 01/07/1967. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050400.pdf (2650 kb)
    - 227.00-01 Prompt, Delayed and Photo-Neutron Production 20050401.pdf (153 kb)
    - 227.00-02 Neutron Balance During Steady Reactor Operation 20050402.pdf (206 kb)
    - 227.00-03 Neutron Density, Neutron Power and Neutron Flux 20050403.pdf (103 kb)
    - 227.00-04 Neutron Flux Distribution and its Effect on Power 20050404.pdf (274 kb)
    - 227.00-05 Meaning of Criticality, Multiplication Factor, Reactivity and Neutron Lifetime 20050405.pdf (140 kb)
    - 227.00-06 Change of Reactor Power with Reactivity Change 20050406.pdf (198 kb)
    - 227.00-07 Change of Reactor Power with Time 20050407.pdf (112 kb)
    - 227.00-08 Effects of Prompt and Delayed Neutrons on Reactor Power Changes 20050408.pdf (282 kb)
    - 227.00-09 Effect of Photoneutrons on Reactor Power Changes 20050409.pdf (150 kb)
    - 227.00-10 Methods of Reactor Control 20050410.pdf (160 kb)
    - 227.00-11 Starting Up a Reactor and Increasing Power 20050411.pdf (197 kb)
    - 227.00-12 Decreasing Power and Shutting Down a Reactor 20050412.pdf (146 kb)
    - 227.00-13 Xenon Poison and its Effects on Reactor Operation 20050413.pdf (241 kb)
    - 227.00-14 Examples of Practical Reactor Behaviour 20050414.pdf (156 kb)
    2. 1971---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  2. Fast Reactor Kinetics - The QXI Code, by D.A. Meneley, K.O. Ott and E.S. Wiener, Individual Contributions, 01/03/1971. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Modelling [Phase] Design Analysis Safety Analysis [Audience] Grad Ugrad
    - 20070100.pdf (7793 kb)
    3. 1972---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 25/05/1972. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems [Phase] Concept Design Design Analysis Safety Safety Analysis [Audience] College Engineer Ugrad
    - Lecture 1 - Introduction 19720101.pdf (1091 kb)
    - Lecture 2 - Radiation 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing 19720112.pdf (1755 kb)
    - Lecture 13 - Training 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version. 19720114.pdf (2844 kb)
    - Lecture 15 - Construction 19720115.pdf (3542 kb)
    - Lecture 16 - Costs 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems 19720167.pdf (2431 kb)
    4. 1974---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  4. Nuclear Theory, Course 127, Nuclear Training Centre, OPG, 01/07/1974. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050300.pdf (5869 kb)
    - 127.00-00 Index and Objectives 20050301.pdf (244 kb)
    - 127.10-01 Nuclear Structure 20050302.pdf (571 kb)
    - 127.10-02 Neutron Reactions 20050303.pdf (156 kb)
    - 127.10-03 Fission 20050304.pdf (264 kb)
    - 127.10-04 Neutron Cross Sections and Neutron Flux 20050305.pdf (305 kb)
    - 127.10-05 The Chain Reaction 20050306.pdf (240 kb)
    - 127.10-06 Moderator Properties 20050307.pdf (296 kb)
    - 127.10-05b Neutron Balance and the Four Factor Formula 20050308.pdf (270 kb)
    - 127.10-06b Effect of Enrichment, Fuel Arrangement and Fuel Burnup on the Four Factor Formula 20050309.pdf (287 kb)
    - 127.10-07 Flux Distribution and Critical Size 20050310.pdf (203 kb)
    - 127.10-08 Function and Properties of the Reflector 20050311.pdf (219 kb)
    - 127.20-01 Review of Terms 20050312.pdf (201 kb)
    - 127.20-02 Low Power Considerations 20050313.pdf (341 kb)
    - 127.20-03 Effects Due to Temperature Changes and Void Formation 20050314.pdf (330 kb)
    - 127.20-04 Effects Due to Fission Product Accumulation 20050315.pdf (295 kb)
    - 127.20-05 Effects Due to Fuel Burnup 20050316.pdf (245 kb)
    - 127.20-06 Reactor Control 20050317.pdf (303 kb)
    - 127.20-07 The Approach to Critical and the Raising of Power 20050318.pdf (534 kb)
    - 127.20-08 Examples of Practical Reactor Behaviour 20050319.pdf (262 kb)
    - 127.20-09 Reactor Stability 20050320.pdf (135 kb)
    - 127.20-10 Safety Considerations 20050321.pdf (308 kb)
    5. 1977---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 01/01/1977. Doc type: Course.
    Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040300.pdf (82 kb)
    - Force - Momentum 20040306.pdf (90 kb)
    - Water Hammer 20040307.pdf (226 kb)
    6. 1978---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  6. Fluid Mechanics, Nuclear Training Course 123, April 1978, OPG, 01/04/1978. Doc type: Course.
    Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).  Note: Doc# 20040201 through to 20040205 are identical to OPG 223.00-1, rev January 1977 (see Doc# 20040301 through to 20040305
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040200.pdf (87 kb)
    - Parallel Pipe Flow 20040206.pdf (202 kb)
    - Compressible Flow 20040207.pdf (285 kb)
    - Water Hammer 20040208.pdf (265 kb)
    - Hydrodynamic Film Lubrication 20040209.pdf (562 kb)
  7. Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 01/04/1978. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Viscosity 20040301.pdf (147 kb)
    - Reynolds' Number 20040302.pdf (105 kb)
    - Friction in Fluid Flow 20040303.pdf (301 kb)
    - Minor Losses 20040304.pdf (213 kb)
    - Pipe Flow Problems 20040305.pdf (132 kb)
    - Appendix 20040308.pdf (489 kb)
    8. 1980---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  8. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 01/01/1980. Doc type: Report.
    Summary: A Lecture Series given at Trieste 22 January - 28 March 1980, TDAI-244 1980 August
    Keywords: [Concept] - [SI] 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Manager Ugrad
    - Title and Table of Contents 20042000.pdf (176 kb)
    - Chapter 1 - Introduction 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design 20042003.pdf (1922 kb)
    - Bibliography 20042006.pdf (111 kb)
  9. Nuclear Theory, Course 227, Nuclear Training Centre 20053700, by J.E. Crist, J. U. Burnham, A. Broughton, D. Winfield, OPG, 01/08/1980. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20053700.pdf (8430 kb)
    - 227.00-00 Index and Objectives 20053701.pdf (443 kb)
    - 227.00-01 Nuclear Structure 20053702.pdf (274 kb)
    - 227.00-02 Neutron Reactions 20053703.pdf (662 kb)
    - 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux 20053704.pdf (318 kb)
    - 227.00-04 Thermal Reactors (Basic Design) 20053705.pdf (342 kb)
    - 227.00-05 Neutron Multiplication Factor and Reactivity 20053706.pdf (196 kb)
    - 227.00-06 Neutron Flux Distribution 20053707.pdf (324 kb)
    - 227.00-07 Effect of Fuel Burnup 20053708.pdf (361 kb)
    - 227.00-08 Changes in Reactor Power with Time 20053709.pdf (328 kb)
    - 227.00-09 Source Neuron Effects 20053710.pdf (217 kb)
    - 227.00-10 Power and Power Measurement 20053711.pdf (356 kb)
    - 227.00-11 Fission Product Poisoning 20053712.pdf (866 kb)
    - 227.00-12 Reactivity Effects Due to Temperature Changes 20053713.pdf (454 kb)
    - 227.00-13 Reactivity Control 20053714.pdf (875 kb)
    - 227.00-14 The Approach to Critical 20053715.pdf (148 kb)
    - 227.00-15 Failed Fuel Monitoring 20053716.pdf (322 kb)
    - 227 Appendix A Symbols 20053717.pdf (22 kb)
    - 227 Appendix B Properties of Elements and Certain Molecules 20053718.pdf (120 kb)
    - 227 Appendix C Nuclides and Isotopes 20053719.pdf (1921 kb)
    10. 1981---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  10. Heat and Thermodynamics, Course 125, Nuclear Training Centre, OPG, 01/11/1981. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine, feedheater, condenser, steam generator, reactor.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20050100.pdf (6328 kb)
    - Module B.7 Course Procedures 20050101.pdf (302 kb)
    - Module B.6 Basics 20050102.pdf (339 kb)
    - Module B.5 Steam Tables 20050103.pdf (740 kb)
    - Module B.4.2 Entropy, Throttling and Molier Diagram 20050104.pdf (904 kb)
    - Module B.4.1 Turbine With Reheat 20050105.pdf (684 kb)
    - Module B.3.2 Feedheater Operation 20050106.pdf (569 kb)
    - Module B.3.1 Condenser Performance 20050107.pdf (594 kb)
    - Module B.2 Steam Generator 20050108.pdf (477 kb)
    - Module B.1 Reactor 20050109.pdf (826 kb)
    - B.6 Self Evaluation 20050110.pdf (87 kb)
    - B.5 Self Evaluation 20050111.pdf (69 kb)
    - B.4.2 Self Evaluation 20050112.pdf (118 kb)
    - B.4.1 Self Evaluation 20050113.pdf (103 kb)
    - B.3.2 Self Evaluation 20050114.pdf (121 kb)
    - B.3.1 Self Evaluation 20050115.pdf (118 kb)
    - B.2 Self Evaluation 20050116.pdf (137 kb)
    - B.1 Self Evaluation 20050117.pdf (102 kb)
    - Criterion Tests 20050118.pdf (134 kb)
    11. 1984---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  11. Heat and Thermodynamics, Course PI 25, Nuclear Training Centre, OPG, 01/03/1984. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: expansion and contraction, heat transfer, pressure control, Mollier diagrams, efficiency, the CANDU cycle.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20050200.pdf (3028 kb)
    - 25-0 Introduction and Course Procedures 20050201.pdf (336 kb)
    - 25-1 Basics 20050202.pdf (471 kb)
    - 25-2 Expansion and Contraction 20050203.pdf (351 kb)
    - 25-3 Heat Transfer Calculations 20050204.pdf (183 kb)
    - 25-4 Pressure Control 20050205.pdf (200 kb)
    - 25-5 Mechanisms of Heat Transfer 20050206.pdf (144 kb)
    - 25-6 Mollier Diagrams and The Turbine Process 20050207.pdf (679 kb)
    - 25-7 Efficiency and The CANDU Cycle 20050208.pdf (298 kb)
    - 25-8 Criterion Tests 20050209.pdf (105 kb)
    - 25-9 Self Evaluation Answer Sheet 20050210.pdf (309 kb)
  12. Fluid Mechanics, Nuclear Training Course 223, December 1984, OPG, 01/12/1984. Doc type: Course.
    Summary: These sections provide definitions and sample calculations for basic concepts such as pressure, density, flowrate, etc. and are NOT the same as the corresponding sections in the January 1977 version of 223.
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fuel Management [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040400.pdf (29 kb)
    - Fluid Mechanics 20040401.pdf (599 kb)
    - Answer Section 20040402.pdf (407 kb)
    13. 1988---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  13. Heat and Thermodynamics, Course 225, Nuclear Training Centre, OPG, 01/04/1988. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine with reheat, feedheater, condenser, steam generator, reactor.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20043100.pdf (4667 kb)
    - Index 20043101.pdf (208 kb)
    - Module 1 Basics 20043102.pdf (404 kb)
    - Module 2 Steam Tables 20043103.pdf (636 kb)
    - Module 3 Entropy, Throttling and Mollier Diagrams 20043104.pdf (701 kb)
    - Module 4 Turbine with Reheat 20043105.pdf (611 kb)
    - Module 5 Feedheater Operation 20043106.pdf (511 kb)
    - Module 6 Condenser Performance 20043107.pdf (546 kb)
    - Module 7 Steam Generator 20043108.pdf (382 kb)
    - Module 8 Reactor 20043109.pdf (710 kb)
    14. 1990---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  14. Nuclear Theory, Course PI 27 , Nuclear Training Centre, OPG, 01/01/1990. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050600.pdf (6624 kb)
    - PI 27.00-00 Index and Objectives 20050601.pdf (389 kb)
    - 427.00-02 Radioactivity - Spontaneous Nuclear Processes 20050602.pdf (282 kb)
    - 227.00-01 Nuclear Structure 20050603.pdf (217 kb)
    - 227.00-02 Neutron Reactions 20050604.pdf (559 kb)
    - 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux 20050605.pdf (300 kb)
    - 227.00-04 Thermal Reactors (Basic Design) 20050606.pdf (338 kb)
    - 227.00-05 Neutron Multiplication Factor and Reactivity 20050607.pdf (193 kb)
    - 227.00-06 Neutron Flux Distribution 20050608.pdf (314 kb)
    - 227.00-07 Effect of Fuel Burnup 20050609.pdf (467 kb)
    - 227.00-08 Changes in Reactor Power with Time 20050610.pdf (357 kb)
    - 227.00-09 Source Neutron Effects 20050611.pdf (294 kb)
    - 227.00-10 Reactor and Power Measurement 20050612.pdf (509 kb)
    - 227.00-11 Fission Product Poisoning 20050613.pdf (999 kb)
    - 227.00-12 Reactivity Effects Due to Temperature Changes 20050614.pdf (409 kb)
    - 227.00-13 Reactivity Control 20050615.pdf (782 kb)
    - 227.00-14 The Approach to Critical 20050616.pdf (295 kb)
  15. Nuclear Theory, Course 427, Nuclear Training Centre, OPG, 01/07/1990. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050500.pdf (2088 kb)
    - 427.00-00 Index and Objectives 20050501.pdf (246 kb)
    - 427.00-01 Atomic Structures 20050502.pdf (108 kb)
    - 427.00-02 Radioactivity 20050503.pdf (212 kb)
    - 427.00-03 Nuclear Stability and Instability 20050504.pdf (150 kb)
    - 427.00-04 Activity 20050505.pdf (117 kb)
    - 427.00-05 Neutrons and Neutron Interactions 20050506.pdf (107 kb)
    - 427.00-06 Fission 20050507.pdf (220 kb)
    - 427.00-07 Fuel, Moderator and Reactor Arrangement 20050508.pdf (141 kb)
    - 427.00-08 Neutron Life Cycle 20050509.pdf (101 kb)
    - 427.00-09 Criticality and Neutron Multiplication 20050510.pdf (183 kb)
    - 427.00-10 Changes in Reactor Power with Time 20050511.pdf (149 kb)
    - 427.00-11 Xenon : A Fission Product Poison 20050512.pdf (124 kb)
    - 427.00-12 Reactivity Effects Due to Temperature Changes 20050513.pdf (133 kb)
    - 427.00-13 Neutron Flux Control 20050514.pdf (156 kb)
    16. 1992---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  16. Nuclear Theory, Nuclear Training Course 227 20031001, OPG, 01/08/1992. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations. Revised by N. Ritter.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Cover pages and table of contents 20031001.pdf (76 kb)
    - Objectives 20031002.pdf (164 kb)
    - Chapter 1: Nuclear Structure 20031003.pdf (213 kb)
    - Chapter 2: Neutron Reactions 20031004.pdf (631 kb)
    - Chapter 3: Neutron Cross Sections, Neutron Density and Neutron Flux 20031005.pdf (289 kb)
    - Chapter 4: Thermal Reactors (Basic Design) 20031006.pdf (317 kb)
    - Chapter 5: Neutron Multiplication Factor and Reactivity 20031007.pdf (184 kb)
    - Chapter 6: Neutron Flux Distribution 20031008.pdf (321 kb)
    - Chapter 7: Effect of Fuel Burnup 20031009.pdf (395 kb)
    - Chapter 8: Changes in Reactor Power with Time 20031010.pdf (314 kb)
    - Chapter 9: Source Neutron Effects 20031011.pdf (307 kb)
    - Chapter 10: Power and Power Measurements 20031012.pdf (356 kb)
    - Chapter 11: Fission Product Measurement 20031013.pdf (838 kb)
    - Chapter 12: Reactivity Effects due to Temperature Changes 20031014.pdf (406 kb)
    - Chapter 13: Reactivity Control 20031015.pdf (732 kb)
    - Chapter 14: The Approach to Critical 20031016.pdf (384 kb)
    - Appendix: A: Symbols 20031017.pdf (23 kb)
    - Appendix: B: Properties of Elements and Certain Molecules 20031018.pdf (105 kb)
    - Appendix: C: Nuclides and Isotopes 20031019.pdf (1547 kb)
    17. 1993---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  17. Principes de Science et de Fonctionnement des Réacteurs - Chaleur et Thermodynamique, CNSC, 01/01/1993. Doc type: Course.
    Summary:
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Chaleur et Thermodynamique 20070900.pdf (850 kb)
    18. 1996---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  18. Reactor Physics & Fuelling Strategies 1.4, by R. Page, Chulalongkorn University, 01/01/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Reference to Lecture 10 - Canadian Power Reactor Fuel 20042115.pdf (2381 kb)
    - Reference to Lecture 12 - Results of a Survey on Accident and Safety Analysis Codes, Benchmarks. Verification and Validation Methods 20042117.pdf (482 kb)
  19. Nuclear Physics and Reactor Theory 1.1, by Ian Cameron, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Title and Table of Contents 20041100.pdf (132 kb)
    - Module 1 - Nuclear Structure 20041101.pdf (451 kb)
    - Module 2 - Neutron Reactions 20041102.pdf (783 kb)
    - Module 3 - Neutron Cross-Sections, Neutron Density and Neutron Flux 20041103.pdf (488 kb)
    - Module 4 - Thermal Reactors (Basic Design) 20041104.pdf (413 kb)
    - Module 5 - Neutron Multiplication Factor and Reactivity 20041105.pdf (384 kb)
    - Module 6 - Neutron Flux Distribution 20041106.pdf (313 kb)
    - Module 7 - Effects of Fuel Burnup 20041107.pdf (472 kb)
    - Module 8 - Reactor Power Response to Changes in Reactivity 20041108.pdf (574 kb)
    - Module 9 - Source Neutron Effects 20041109.pdf (278 kb)
    - Module 10 - Power and Power Measurement 20041110.pdf (421 kb)
    - Module 11 - Fission Product Poisoning 20041111.pdf (695 kb)
    - Module 12 - Reactivity Effects Due to Temperature Changes and Coolant Voiding 20041112.pdf (678 kb)
    - Module 13 - Reactivity Control 20041113.pdf (678 kb)
    - Module 14 - The Approach To Critical 20041114.pdf (315 kb)
    - Module 15 - Neutron Detectors And Reactor Instrumentation 20041115.pdf (639 kb)
    - Appendix A 20041116.pdf (72 kb)
  20. Nuclear Theory II (Kinetics) 1.2, by John L. Groh, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Supplement to Chapter 8 20041201.pdf (428 kb)
    - Supplement to Chapter 9 20041202.pdf (218 kb)
    - Supplement to Chapter 10 20041203.pdf (147 kb)
    - Supplement to Chapter 11 20041204.pdf (263 kb)
    - Supplement to Chapter 12 20041205.pdf (96 kb)
    - Supplement to Chapter 13 20041206.pdf (139 kb)
    - Supplement to Chapter 14 20041207.pdf (147 kb)
    - Workbook, Chapter 8 20041208.pdf (449 kb)
    - Workbook, Chapter 9 20041209.pdf (183 kb)
    - Workbook, Chapter 10 20041210.pdf (128 kb)
    - Workbook, Chapter 11 20041211.pdf (403 kb)
    - Workbook, Chapter 12 20041212.pdf (525 kb)
    - Workbook, Chapter 13 20041213.pdf (128 kb)
    - Workbook, Chapter 14 20041214.pdf (301 kb)
  21. Introduction to Nuclear Reactor Kinetics 1.3, by Daniel Rozon, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Predicting the evolution in time of the neutron population in a multiplying medium. Time variation of the reactor power (proportional to the total neutron population) is presented.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Table of Contents 20041800.pdf (31 kb)
    - Chapter 1 - Neutron/Nucleus Interactions and Fission 20041801.pdf (1008 kb)
    - Chapter 2 - The Diffusion Equation and the Steady State 20041802.pdf (1840 kb)
    - Chapter 3 - The Point Kinetics Equation 20041803.pdf (1190 kb)
    - Workbook to Chapter 1 - Neutron/Nucleus Interactions and Fission 20041804.pdf (447 kb)
    - Workbook to Chapter 2 - The Diffusion Equation and the Steady State 20041805.pdf (709 kb)
    - Workbook to Chapter 3 - The Point Kinetics Equations 20041806.pdf (385 kb)
    - Workbook to Chapter 4 - Elementary Solutions to the Kinetics Equations 20041807.pdf (398 kb)
    - Workbook to Chapter 5 - Approximate Solutions for Reactivity Ramps 20041808.pdf (276 kb)
  22. Reactor Physics & Fuelling Strategies 1.4, by John Brenciaglia, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Descriptive reactor physics associated with fuel management. Simulation, flux mapping. Reference text used: Fundamentals of CANDU Reactor Nuclear Design (TDAI-244) (AECL)
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Lecture 1 - Reactor Design Philosophies 20042101.pdf (665 kb)
    - Lecture 2 - Use of Reactor Design Codes 20042102.pdf (137 kb)
    - Lecture 3 - Lattice Parameter Calculations 20042103.pdf (531 kb)
    - Lecture 4 - Core Design Analysis 20042104.pdf (332 kb)
    - Lecture 5 - Time Dependence Simulation 20042105.pdf (600 kb)
    - Lecture 6 - Initial Fuel Load 20042106.pdf (253 kb)
    - Lecture 7 - Startup Physics Tests 20042107.pdf (531 kb)
    - Lecture 8 - Power Distribution Control 20042108.pdf (720 kb)
    - Lecture 9 - Safety Analysis Requirements 20042109.pdf (392 kb)
    - Chapter 10 - Fuel Design Analysis 20042110.pdf (187 kb)
    - Lecture 11 - Fueling Strategies and Cycles 20042111.pdf (745 kb)
    - Lecture 12 - Research Reactors Requirements 20042112.pdf (138 kb)
    - Reference to Lecture 8 - In-Core Fuel Management 20042113.pdf (1105 kb)
    - Reference to Lecture 9 - Role of Physics Analysis in Safety and Licensing 20042114.pdf (1389 kb)
    - Reference to Lecture 11 - Fuel Management & Reactor Operation - Review of Operating Experience 20042116.pdf (1501 kb)
  23. Reactor Thermalhydraulics Design, Course 2.1, by W.J. Garland, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: This course is concerned with the thennalhydraulic design of the process systems that are required to transport heat energy away from the nuclear reactor source and transform this heat energy into useful work (generally electrical energy).
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Basic Equations Important Parameters Process Systems Thermalhydraulics [Phase] Concept Design Design Analysis Design Evolution Design Process [Audience] Engineer Ugrad
    - Title and Table of Contents 20043701.pdf (170 kb)
    - Foreword and Glossary 20043702.pdf (74 kb)
    - Chapter 1 - Introduction 20043703.pdf (130 kb)
    - Chapter 2 - Design Requirements and Engineering Considerations 20043704.pdf (1189 kb)
    - Chapter 3 - Heat Transport System Thermalhydrauilics 20043705.pdf (447 kb)
    - Chapter 4 - Thermodynamics 20043706.pdf (309 kb)
    - Chapter 5 - Fuel Coolant Heat Transfer 20043707.pdf (245 kb)
    - Chapter 6 - Control 20043708.pdf (313 kb)
    - Chapter 7 - The Design Process 20043709.pdf (419 kb)
    - Chapter 8 - Process Design and Optimization 20043710.pdf (441 kb)
    - Appendix 1 - Comparison of Bruce A, B, & Darlington 20043711.pdf (223 kb)
  24. Thermal Study of Nuclear Reactors, Course 2.2, by A. Tapucu, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043801.pdf (96 kb)
    - Chapter 1 - Fundamental Concepts 20043802.pdf (234 kb)
    - Chapter 2 - Single Phase Fluid Equations 20043803.pdf (200 kb)
    - Chapter 3 - Principles of Heat Transfer 20043804.pdf (1061 kb)
    - Chapter 4 - Forced Convection Heat Transfer 20043805.pdf (1624 kb)
    - Chapter 7 - Heat Removal from Nuclear Reactors 20043806.pdf (1557 kb)
    - Appendix 1 - Tensors 20043807.pdf (49 kb)
    - Appendix 2 - Stress in a Fluid 20043808.pdf (256 kb)
    - Appendix 3 - A Short Summary of Orthogonal Functions Used in Chapter 4 20043809.pdf (178 kb)
    - Workbook, Chapter 4 20043810.pdf (2301 kb)
    - Workbook, Chapter 7 20043811.pdf (2043 kb)
  25. Reactor Thermalhydraulics Analysis, Course 2.3, by W.J. Garland, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Fundamentals of thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043901.pdf (144 kb)
    26. 1997---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  26. Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a, by Robin Chaplin, Chulalongkorn University, 01/01/1997. Doc type: Course.
    Summary: This lecture material is supplementary to Chulalongkorn University Training Program Course # 1.1, Nuclear Physics and Reactor Theory by Ian Cameron (Course 22106), Modules 1 to 7]
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Introduction 20041700.pdf (177 kb)
    - Section 1 - Nuclear Physics 20041701.pdf (461 kb)
    - Section 1 - Nuclear Physics (Figures) 20041702.pdf (346 kb)
    - Section 2 - Nuclear Interactions 20041703.pdf (727 kb)
    - Section 2 - Nuclear Interactions (Figures) 20041704.pdf (775 kb)
    - Section 3 - Neutron Diffusion 20041705.pdf (255 kb)
    - Section 4 - Reactor Theory 20041706.pdf (534 kb)
    - Section 4 - Reactor Theory (Figures) 20041707.pdf (456 kb)
    - Section 5 - Reactor Kinetics 20041708.pdf (1075 kb)
    - Question Bank 20041709.pdf (1095 kb)
    - Reference Data 20041710.pdf (537 kb)
  27. Monte Carlo Method for Particle Transport Simulation, Course 1.6, by E. Hussein, Chulalongkorn University, 08/04/1997. Doc type: Course.
    Summary: A brief introduction to the basics of the Monte Carlo method, how the Boltzmann particle transport equation lends itself to solution by the Monte Carlo method, specific aspects of the MCNP code.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Modelling Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 0 - Table of Contents 20043501.pdf (59 kb)
    - Chapter 1 - Introduction 20043502.pdf (30 kb)
    - Chapter 2 - Monte Carlo Method 20043503.pdf (283 kb)
    - Chapter 3 - Boltzmann Transport Equation 20043504.pdf (79 kb)
    - Chapter 4 - MCNP Input Structure 20043505.pdf (29 kb)
    - Chapter 5 - Geometry in MCNP 20043506.pdf (105 kb)
    - Chapter 6 - MCNP Source Parameters 20043507.pdf (173 kb)
    - Chapter 7 - Physics & Material Cross-Sections 20043508.pdf (67 kb)
    - Chapter 8 - Termination Parameters 20043509.pdf (30 kb)
    - Chapter 9 - Importance Sampling 20043510.pdf (122 kb)
    - Chapter 10 - Tallying 20043511.pdf (163 kb)
    - Chapter 11 - Uncertainty Analysis 20043512.pdf (177 kb)
    - Chapter 12 - Criticality in MCNP 20043513.pdf (42 kb)
    - Workbook, Chapter 1 20043514.pdf (60 kb)
    - Workbook, Chapter 2 20043515.pdf (460 kb)
    - Workbook, Chapter 3 20043516.pdf (103 kb)
    - Workbook, Chapter 4 20043517.pdf (45 kb)
    - Workbook, Chapter 5 20043518.pdf (167 kb)
    - Workbook, Chapter 6 20043519.pdf (270 kb)
    - Workbook, Chapter 7 20043520.pdf (95 kb)
    - Workbook, Chapter 8 20043521.pdf (41 kb)
    - Workbook, Chapter 9 20043522.pdf (195 kb)
    - Workbook, Chapter 10 20043523.pdf (265 kb)
    - Workbook, Chapter 11 20043524.pdf (281 kb)
    - Workbook, Chapter 12 20043525.pdf (68 kb)
  28. Reactor Core Analysis & Fuel Management, Course 1.5, by D. Rozon, Chulalongkorn University, 01/08/1997. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 5 - SLOWKIN: A Simplified Model for the Stimulation of Transients in a SLOWPOKE-2 Reactor 20043405.pdf (1297 kb)
    - Chapter 1 - Coupled Neutronics-Thermalhydaulics LOCA Analysis 20043401.pdf (970 kb)
    - Chapter 2 - Core Physics Aspects of Safety Analysis 20043402.pdf (1188 kb)
    - Chapter 4 - Fuel Management in CANDU 20043404.pdf (1542 kb)
    - Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads 20043406.pdf (330 kb)
    - Workbook, Chapter 2 - Core Physics Overheads 20043407.pdf (567 kb)
    - Chapter 3 - Fuel Management and Advanced Fuel Cycles 20043403.pdf (1436 kb)
    29. 1998---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  29. Reactor Thermalhydraulics Analysis, Course 2.3, by W.J. Garland, Chulalongkorn University, 01/02/1998. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Glossary and Foreword 20043902.pdf (152 kb)
    - Chapter 1 - Course Overview 20043903.pdf (140 kb)
    - Chapter 2 - Basic Equations for Thermalhydraulic Systems Analysis 20043904.pdf (561 kb)
    - Chapter 3 - Nodalization 20043905.pdf (303 kb)
    - Chapter 4 - Equation of State 20043906.pdf (338 kb)
    - Chapter 5 - The Rate Form of the Equation of State 20043907.pdf (512 kb)
    - Chapter 6 - Thermalhydraulic Network Simulation 20043908.pdf (343 kb)
    - Chapter 7 - Empirical Correlations 20043909.pdf (532 kb)
    - Chapter 8 - On Design Tools 20043910.pdf (481 kb)
    - Workbook, Chapter 1 20043911.pdf (151 kb)
    - Workbook Chapter, 2 20043912.pdf (767 kb)
    - Workbook Chapter 3 20043913.pdf (466 kb)
    - Workbook Chapter 4 20043914.pdf (604 kb)
    - Workbook Chapter 5 20043915.pdf (847 kb)
    - Workbook Chapter 6 20043916.pdf (614 kb)
    - Workbook Chapter 7 20043917.pdf (719 kb)
    - Workbook Chapter 8 20043918.pdf (903 kb)
    - Workbook Figures 20043919.pdf (509 kb)
  30. Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a, by W.J. Garland, Chulalongkorn University, 01/02/1998. Doc type: Course.
    Summary: Supplementary info for thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Appendices 1 - 4 1 - Time Derivatives 2 - The Reynolds Transport Theorem 3 - Rearrangement of Independent Variables 4 - Fast Calculation of Light-Water Properties 20044001.pdf (647 kb)
    - Calculation of Water Properties 20044002.pdf (947 kb)
    - THSIM User Manual 20044003.pdf (733 kb)
    - A Pedagogical Look at Fully- and Semi-Implicit Solutions to T-H Eq'ns 20044004.pdf (320 kb)
    - Basic Equations for T-H Systems Analysis 20044005.pdf (590 kb)
    - Miscellaneous Figures and Equations 20044006.pdf (315 kb)
    31. 1999---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  31. CANDU Fuel Management Course, by Ben Rouben, AECL, 01/03/1999. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Cover Page 20031100.pdf (91 kb)
    - Complete Course 20031101.pdf (286 kb)
    - Basic Characteristics of the CANDU Lattice 20031111.pdf (186 kb)
    - The CANDU Reactivity Devices 20031112.pdf (147 kb)
    - Detector Systems 20031113.pdf (141 kb)
    - Computational Scheme for CANDU Neutronics 20031114.pdf (182 kb)
    - General Discussion on CANDU Fuel Management 20031115.pdf (125 kb)
    - Equilibrium-Core Design 20031116.pdf (217 kb)
    - Ongoing Reactor Operation with Channel Refuellings 20031117.pdf (252 kb)
    - Effects of 135Xe 20031118.pdf (151 kb)
    - Summary 20031119.pdf (61 kb)
    - Basic Characteristics of the CANDU Lattice - Figures 20031121.pdf (324 kb)
    - The CANDU Reactivity Devices - Figures 20031122.pdf (404 kb)
    - Detector Systems - Figures 20031123.pdf (418 kb)
    - Computational Scheme for CANDU Neutronics - Figures 20031124.pdf (83 kb)
    - General Discussion on CANDU Fuel Management - Figures 20031125.pdf (78 kb)
    - Equilibrium-Core Design - Figures 20031126.pdf (309 kb)
    - Ongoing Reactor Operation with Channel Refuellings - Figures 20031127.pdf (323 kb)
    - Effects of 135Xe - Figures 20031128.pdf (99 kb)
    32. 2000---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  32. RFSP Training Course, by Benoit Arsenault, AECL, 29/03/2000. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Chapter 01 - Course Agenda 20054301.pdf (106 kb)
    - Chapter 02 - General Intro to Methods of Physics Analysis & Physics Computer Codes 20054302.pdf (381 kb)
    - Chapter 03 - The RFSP Direct-Access File 20054303.pdf (274 kb)
    - Chapter 04 - RFSP Model 20054304.pdf (400 kb)
    - Chapter 05 - Time-Average Model 20054305.pdf (322 kb)
    - Chapter 06 - Spatial Kinetics 20054306.pdf (272 kb)
    - Chapter 07 - Powderpufs-V 20054307.pdf (348 kb)
    - Chapter 08 - *Simulate and *Intrep 20054308.pdf (494 kb)
    - Chapter 09 - Flux and Power Mapping in RFSP 20054309.pdf (375 kb)
    - Chapter 10 - RRS Modelling in RFSP 20054310.pdf (275 kb)
    - Chapter 11 - *INSTANTAN 20054311.pdf (127 kb)
    - Chapter 12 - RFSP Code Development 20054312.pdf (336 kb)
    33. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  33. Heat and Thermodynamics Course, CNSC, 01/01/2002. Doc type: Course.
    Summary: This module covers the following areas pertaining to thermodynamics: Introduction, Heat and Thermodynamics - The Basics, Reactor and Heat Transport System Normal Operation, Heat Transport System Component Operation
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Cover Page 20030900.pdf (83 kb)
    - 20030901.pdf (647 kb)
    - Presentation 20030902.pdf (1557 kb)
  34. Introduction to Reactor Physics, by Ben Rouben, AECL, 01/09/2002. Doc type: Course.
    Summary: This is a descriptive course on the physics of CANDU reactors. The objective is to familiarize you with the basic concepts and ideas, definitions and quantities which are important in the understanding of reactor physics. The discussion will be at a basic level, as this is an introduction to the subject. Very little emphasis is placed on complex equations or difficult mathematics. The desired outcome of this course is that you will be able in the future to understand and follow reactor-physics discussions in meetings, reports or presentations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - 20040501.pdf (369 kb)
    - Presentation 20040502.pdf (13610 kb)
    35. 2003---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  35. Fluid Mechanics, CNSC, 24/06/2003. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Presentation 20040602.pdf (610 kb)
    - 20040601.pdf (353 kb)
    - 20070300.pdf (336 kb)
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