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[SI]: 33100 Main Heat Transport System 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.

Number of files: 54

    1987-06-01---------Jump to [Top]
  1. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by G.H. Archinoff, J.e. Luxat, P.O. Lowe, K.E. Locke, and A.P. Muzumdar, CNS, 1987-06-01. Doc type: Paper.
    Summary: The computer code SMARTT (Simulation Method for Azimuthal and Radial Temperature Transients) is used in safety analysis of Ontario Hydro's CANDU reactors to predict fuel and pressure tube thermal and mechanical behaviour under asymmetric coolant conditions, such as stratified flow. This paper presents comparisons of SMARTT predictions, with preliminary results of two experiments in which large temperature nonuniformities developed on pressure tubes undergoing heatup and transverse strain at 1.0 MPa internal pressure.
    Keywords: [Concept] Materials [SI] 33100 Main Heat Transport System [Discipline] Materials Engineering [Topic] Performance [Phase] Operation Safety Analysis [Audience] Engineer Grad Ugrad
    - Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments NJC-1-2-07.pdf (575 kb)
    - The Drift Flux Model in the ASSERTSubchannel Code NJC-1-2-08.pdf (742 kb)
    2. 1987-09-01---------Jump to [Top]
  2. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by J.P. Mallory and P.J. Ingham, CNS, 1987-09-01. Doc type: Paper.
    Summary: Under some postulated accident conditions, decay heat is removed from a reactor core by 2-phase natural circulation or 'thermosiphoning' of the primary coolant. To assess the ability of the computer code CATHENA to predict such events, simulations were performed of thermosiphoning tests conducted in the RD-14 facility at the Whiteshell Nuclear Research Establishment.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety Thermalhydraulics [Phase] Safety Analysis [Audience] College Engineer Grad Technician Ugrad
    - CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility NJC-1-3-05.pdf (615 kb)
    3. 1987-12-01---------Jump to [Top]
  3. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by Matija Cenanovic and Hugo Maureira, CNS, 1987-12-01. Doc type: Paper.
    Summary: Proper spacing between the pressure tube and the surrounding calandria tube of the fuel channels in CANDU reactors is maintained by spacers (garter springs). It was established that many garter springs are no longer in their correct positions in Ontario Hydro's operating reactors. A novel AC device was developed at Ontario Hydro Research Division to reposition the garter springs without any harmful effect on the fuel channel integrity.
    Keywords: [Concept] Mechanical [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] - [Phase] Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - The AC Device for Repositioning of Garter Springs in CANDU Reactors NJC-1-4-09.pdf (696 kb)
    4. 1996-02-01---------Jump to [Top]
  4. Reactor Thermalhydraulics Design, Course 2.1, by W.J. Garland, Chulalongkorn University, 1996-02-01. 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)
  5. Thermal Study of Nuclear Reactors, Course 2.2, by A. Tapucu, Chulalongkorn University, 1996-02-01. 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)
  6. Reactor Thermalhydraulics Analysis, Course 2.3, by W.J. Garland, Chulalongkorn University, 1996-02-01. 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)
    - 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)
    7. 1998-02-01---------Jump to [Top]
  7. Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a, by W.J. Garland, Chulalongkorn University, 1998-02-01. 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)
    8. 2001-02-01---------Jump to [Top]
  8. CANDU Origins and Evolution, by Gordon L.Brooks, AECL, 2001-02-01. Doc type: Paper.
    Summary: This monograph discusses the origins and early evolution of the basic "figure of 8" heat transport system arrangement that has been employed in most CANDU reactors to date.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Conceptual Important Parameters Intro and Overview [Phase] Concept Design Design Evolution [Audience] Manager
    - Figure of 8 20010303.pdf (111 kb)
    9. 2009-05-30---------Jump to [Top]
  9. Large LOCA Margins in CANDU Reactors - An Overview of the COG Report, by A.P. Muzumdar and D.A. Meneley, COG, 2009-05-30. Doc type: Paper.
    Summary: This paper discusses the background and conclusions of the 2007 COG report on Large LOCA Safety Margins in CANDU Reactors, and the various initiatives that have resulted from this study since its release. The COG study challenged the notion that positive void reactivity itself is a design weakness, raised as an issue at the Convention on Nuclear Safety, to demonstrate the safety of operating CANDUs worldwide when compared to other certified LWR designs. The paper will briefly describe a new perspective on how the seemingly complex analytical results on reactor safety parameters can be compared on a level playing field, in such a manner that the non-specialist is able to understand. The paper is presented together with a companion paper that focuses on the comparison of reactivity initiated events in CANDU with some other internationally accepted LWR reactor designs.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090101.pdf (89 kb)
  10. Power Reactor Safety Comparison - A Limited Review, by D.A. Meneley and A.P. Muzumdar, COG, 2009-05-30. Doc type: Paper.
    Summary: A large amount of attention has been paid to avoiding positive coolant void reactivity in LWR reactors. This can be justified due to specific accident events that could lead to severe consequences. Somewhat less attention has been paid to other accident sequences that can lead to positive reactivity addition. Other designs, for example the CANDU-PHWR, exhibit positive coolant void reactivity but include both inherent and engineered systems that compensate for this undesirable characteristic. This paper represents the beginning of a long-term process intended to enable a balanced and fair comparison of the real safety of all reactor types.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090201.pdf (170 kb)
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