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[Topic]: Basic Equations 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.

143 files

    1972---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  1. An Introduction to the CANDU Nuclear Energy Conversion System, by Archie Harms, McMaster University, 25/05/1972. Doc type: Book.
    Summary:
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations Conceptual Intro and Overview Reactor Physics Thermalhydraulics [Phase] Concept Design Safety [Audience] College Engineer Technician Ugrad
    - Table of Contents and Chapter 1: Introduction 19750101.pdf (622 kb)
    - Chapter 2: Nuclear Processes 19750102.pdf (493 kb)
    - Chapter 3: Neutron Physics 19750103.pdf (567 kb)
    - Chapter 4: Reactor Statics 19750104.pdf (650 kb)
    - Chapter 5: Reactor Dynamics 19750105.pdf (428 kb)
    - Chapter 6: Control and Operations 19750106.pdf (499 kb)
    - Chapter 7: Thermal-hydraulic Analysis 19750107.pdf (439 kb)
    - Chapter 8: Nuclear Reactor Materials 19750108.pdf (781 kb)
    - Chapter 9: Safety Analysis 19750109.pdf (152 kb)
    - Chapter 10: CANDU Reactors part 1 19750110.pdf (764 kb)
    - Chapter 10: CANDU Reactors part 2 19750111.pdf (686 kb)
    2. 1980---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  2. Mathematics, Course 221, OPG, 01/04/1980. Doc type: Course.
    Summary: This course proves an introduction to two topics: equipment reliability evaluation, and calculus.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043000.pdf (3593 kb)
    - 221.00-1 Index and Objectives 20043001.pdf (124 kb)
    - 221.00-2 Indroduction 20043002.pdf (132 kb)
    - 421.10-4 Standard Notation 20043003.pdf (122 kb)
    - 421.20-1 Algebra Fundamentals 20043004.pdf (239 kb)
    - 421.40-1 Graphs 20043005.pdf (153 kb)
    - 421.40-2 Graphing Functions 20043006.pdf (80 kb)
    - 321.10-3 Logarithms and Exponentials 20043007.pdf (210 kb)
    - 321.10-4 Use of Logarithmic Scaled Graph Paper 20043008.pdf (347 kb)
    - 221.10-1 Basic Reliability Concepts 20043009.pdf (154 kb)
    - 221.20-1 The Straight Line 20043010.pdf (166 kb)
    - 221.20-2 The Derivative 20043011.pdf (259 kb)
    - 221.20-3 Simple Applications of Derivatives 20043012.pdf (127 kb)
    - 221.20-4 Differentiating Exponential Functions 20043013.pdf (193 kb)
    - 221.20-5 The Derivative in Science and Technology 20043014.pdf (213 kb)
    - 221.30-1 The Integral 20043015.pdf (194 kb)
    - 221.30-2 Application of the Integral as an Infinite Sum 20043016.pdf (371 kb)
    - 221.40-1 Appendix 1 : Review Exercises 20043017.pdf (202 kb)
    - 221.40-2 Appendix 2 : Questions Bearing Directly on Course 221 Content from Recent AECB Nuclear General Examinations 20043018.pdf (75 kb)
    - 221.40-3 Appendix 3 : Solving Quadratic Equations 20043019.pdf (84 kb)
    - 221.40-4 Answers to Assignments and Review Exercises 20043020.pdf (268 kb)
    3. 1981---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. Mathematics, Nuclear Training Course 121, OPG, 01/07/1981. Doc type: Course.
    Summary: Probability and reliability concepts applied to station operation.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept [Audience] Engineer Manager
    - Cover page, Table of contents, Objectives 20040101.pdf (167 kb)
    - Introduction 20040102.pdf (194 kb)
    - Probability 20040103.pdf (610 kb)
    - Safety Systems Analysis 20040104.pdf (404 kb)
    - Safety Systems Analysis - Solutions to Sample Problems 20040105.pdf (455 kb)
    - The Binomial Distribution and Power System Reliability 20040106.pdf (302 kb)
    - The Normal Distribution and Applications 20040107.pdf (193 kb)
    - Basic Reliability Concepts 20040108.pdf (638 kb)
    - Operation in the Wearout Mode 20040109.pdf (237 kb)
    - Some Modern Reliability Topics 20040110.pdf (634 kb)
    - Appendix 1: Confidence Limits 20040111.pdf (219 kb)
    - Appendix 2: Solutions to Assignments 20040112.pdf (636 kb)
    4. 1990---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  4. Reliability for Management and Professional Staff , Course PI 21, Nuclear Training Centre, OPG, 01/01/1990. Doc type: Course.
    Summary: A six part introductory reliability course for management and professional staff.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043300.pdf (1585 kb)
    - Course Table of Contents 20043301.pdf (219 kb)
    - PI 21.00 Intro to the Course 20043302.pdf (104 kb)
    - PI 21.01 An Introduction to Reliability 20043303.pdf (166 kb)
    - PI 21.02 Reliability Concepts 20043304.pdf (384 kb)
    - PI 21.03 Process Systems 20043305.pdf (185 kb)
    - PI 21.04 Availability of Safety Systems 20043306.pdf (250 kb)
    - PI 21.05 Modern Reliability Techniques 20043307.pdf (208 kb)
    - PI 21.06 Reporting and Administration 20043308.pdf (111 kb)
    5. 1996---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. 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)
  6. 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)
  7. 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)
  8. 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)
  9. Introduction to Nuclear Reactor Engineering, Course 3.1, by J. Koclas, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations [Phase] Concept Design [Audience] College Manager Technician Ugrad
    - Introduction to Nuclear Engineering 20044101.pdf (1855 kb)
    - A Guidebook to Nuclear Reactors by Anthony V. Nero 20044102.pdf (1874 kb)
    - Miscellaneous CANDU-Related Viewgraphs 20044103.pdf (1045 kb)
    10. 1997---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  10. 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)
    11. 1998---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  11. Neutronic Analysis of Reactors, Course 1.7, by J. Koclas, Chulalongkorn University, 01/02/1998. Doc type: Course.
    Summary: Covers methods used to solve reactor physics problems in both steady state and transient.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations [Phase] Design [Audience] Engineer Grad Ugrad
    - Chapter 0 - Title and Table of Contents 20043601.pdf (175 kb)
    - Chapter 1 - Introduction 20043602.pdf (102 kb)
    - Chapter 2 - Parameter Definitions 20043603.pdf (144 kb)
    - Chapter 3 - Derivation of the Space-Time Kinetics Equations 20043604.pdf (174 kb)
    - Chapter 4 - Energy Condensation 20043605.pdf (137 kb)
    - Chapter 5 - Matrix Form of Equations 20043606.pdf (60 kb)
    - Chapter 6 - Spatial Mesh Considerations 20043607.pdf (592 kb)
    - Chapter 7 - Statics 20043608.pdf (255 kb)
    - Chapter 8 - Numerical Methods in Reactor Statics 20043609.pdf (420 kb)
    - Chapter 9 - KInetics Methods Classification 20043610.pdf (34 kb)
    - Chapter 10 - Point Kinetics 20043611.pdf (233 kb)
    - Chapter 11 - Elementary Numerical Integration Techniques 20043612.pdf (218 kb)
    - Chapter 12 - Adiabatic Method 20043613.pdf (140 kb)
    - Chapter 13 - Quasistatic Method 20043614.pdf (102 kb)
    - Chapter 14 - Modal Synthesis 20043615.pdf (164 kb)
    - Chapter 15 - Mesh Centered Finite Difference 20043616.pdf (409 kb)
    - Chapter 16 - Time Integration of the Space-Time Kinetics Equations 20043617.pdf (178 kb)
    - Chapter 17 - Comparisons of Spatial Approximations 20043618.pdf (300 kb)
  12. 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)
  13. 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)
    14. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  14. 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)
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