CANDU OVERVIEW WORKBOOK. prepared by: DR. GEORGE BEREZNAI. AECL Professor of Nuclear Engineering

Transcription

1 .Rev. 2, February 1998 CANDU OVERVIEW WORKBOOK prepared by: DR. GEORGE BEREZNAI AECL Professor of Nuclear Engineering Department of Nuclear Technology Faculey of Engineering Chulalongkorn University

2 pageo 1 Chapter 0: Course..,troduction TABLE OF CONTENTS INTRODUCTION CHAPTER 1. OVERALL UNIT Module 1A: Reactor Safety Module 1B: Controlling the Energy Conversion Process Module 1C: CANDU Nuclear Systems Module 10: CANDU Balance of Plant, I&C and Safety Systems Module 1E: Simulator Exercises CHAPTER 2: REACTOR & MODERATOR SYSTEMS Module 2A: Reactor Structures and Assemblies Module 2B: Reactivity Control Devices Module 2C: Moderator System CHAPTER 3: REACTOR REGULATING SYSTEM Module 3A: Measuring Instruments & Techniques Module 3B: Control Algorithms Module 3C: Simulator Exercises CHAPTER 4: HEAT TRANSPORT SYSTEM Module 4A: Main Circuit Module 4B: Pressure & Inventory Control System Module 4C: Warmup and Cooldown Module 40: Simulator Exercises CHAPTER 5: STEAM, TURBINE & FEEDWATER SYSTEMS Module 5A: Steam System Module 5B: Simulator Exercises CHAPTER 6: SFECIAL SAFETY SYSTEMS Module 6A: Reliability Concepts Module 6B: Shutdown System #1 Module 6C: Shutdown System #2 Module 60: Emergency Core Cooling System Module 6E: Containment System Module 6F: Simulator Exercises Department ofnuclear Technology FacuffyofEngmeenng Chula/ongkom University

3 page 0-2 Chapter 0: Course Introduction COURSE INTRODUCTION COURSE OBJECTIVES: At the successful completion of this course the participants will be able to: 1. Describe the following features of a CANDU Generating unit: the principles of overall unit operation and control the functions, equipment and operation of the main process systems how each major system is controlled how reactor safety and the protection of the public is achieved; 2. Conduct normal and abnormal operations on a simulated CANDU-9 Generating unit, including: power maneuvers poison override operation recovery from a reactor trip recovery from a turbine trip responses to reactor, heat transport, steam and feedwater system malfunctions. Department of Nuclear Technology Faculty of Engineering Chulalongkorn University

4 CANDU OVl1rview page 0-2 \ C,~apter 0: Course '...,bduction COURSE INTRODUCTION COURSE OBJECTIVES: At the successful completion of this course the participants will be able to: 1. Describe the following features of a CANDU Generating unit: the principles of overall unit operation and control the functions, equipment and operation of the main process systems how each major system is controlled how reactor safety and the protection of the public is achieved; 2. Conduct normal and abnormal operations on a simulated CANDU 9 Generating unit, including: power maneuvers poison override operation recovery from a reactor trip recovery from a turbine trip responses to reactor, heat transport, steam and feedwater system malfunctions. Department of Nuclear Technology Faculty ofengineering Chulalongkom University

5 Dr. George Beraznai page 0-3 j Chapter 0: Course Introduction 1. COURSE EMPHASIS AND APPROACH Emphasis is on participants learning Learning is best done by doing: => read the reference text => complete written assignments => understand what you do on the simulator Learning is helped by repetition and by reference to existing knowledge This course is about how nuclear power plants 'work' Importance of each system, subsystem and equipment to overall unit operation CANDU 9 will be used to illustrate learning objectives that involve station specific details Specialist training for individual systems, equipment and techniques will be given in subsequent courses Written assignments based on lectures, reading material and simulator exercises will be done in the classroom Department of Nuclear Technology FacuftyofEngmeering Chulalongkom University

6 pageo-4 Chapter 0: Course Introduction 2. 'Top-down' Approach to Studying Nuclear Power Plants 2.1 Traditional approach is 'bottom-up': learn theory and apply to model problems in each subject area; do a few case-studies in usually unrelated areas; practical equipment and integrated systems applications are rare; on-the-job training is usually concentrated on area of specialty; usual result: good detailed knowledge in one or two areas of specialty, but limited understanding of overall system. 2.2 Approach in this course 'top-down': every participant needs to know how a nuclear power plant 'works'; each participant has a different need for specialized knowledge; each participant has a different level of current knowledge; Nuclear Power Plants I......,j,,j,,j, MAGNOX Pressurized Boiling Pressurized Advanced Light Water Light Water Heavy Water Gas Cooled Systems Reactor, Primary Heat Transport, Secondary Heat Transport, Electrical, Service Water, Air, Containment, Instrumentation and Control, Safety, etc. ~ ~ ~ ~ ~ ~ Equipment Pumps, Motors, Valves, Piping, Heat Exohangers, Steam Generators, Control Rods, Compressors, Breakers, Computers, Turbines, Generators, etc. ~! ~ + ~ ~ ~ ~ ~ ~ cience Fundamentals Mathematics, Fluid Mechanics, Heat Transfer, Thermodynamics, Nuclear Physics, Chemistry, Electicity Electronics, Mechanical, Control. etc. each person has a different learning style; expected result: every participant attains a common level of overall knowledge, but individuals will study different areas to different extent depending on personal needs and preferences. t DeparlmentofNudearTechnorogy Faculty ofengineering Chulalongkom University

7 page 0-5 Chapter 0: Course Introduction 3. COURSE PLAN DAY1: DAY 2: DAY 3: DAY 4: DAY 5: INTRODUCTION OVERALL UNIT REACTOR AND MODERATOR SYSTEMS REACTOR CONTROL HEAT TRANSPORT MAIN CIRCUIT HEAT TRANSPORT PRESSURE AND INVENTORY CONTROL STEAM, TURBINE & FEEDWATER SYSTEMS BOILER PRESSURE CONTROL BOILER LEVEL CONTROL SPECIAL SAFETY SYSTEMS Department of Nuclear Technology Faculty of Engineering Chulalongkom University

8 page 0-6 Chapter 0: Course Introduction 3.1 DAY 1 COURSE PLAN INTRODUCTION OVERALL UNIT ENERGY CONVERSION IN CANDU GENERATING STATIONS REACTOR SAFETY CANDU STATION SYSTEMS - REACTOR - MODERATOR - HEAT TRANSPORT - STEAM & FEEDWATER - TURBINE, GENERATOR, CONDENSATE & FEEDHEATING - ELECTRIC POWER - INSTRUMENTATION AND CONTROL - SAFETY SYSTEMS (Ref. Text: 1-2 to 1-7) (Ref. Text: 1-8 to 1-12) (Ref. Text: 1-13to 1-31) SIMULATOR START-UP, INITIALIZATION COMMON DISPLAY FEATURES PLANT OVERVIEW TURBINE GENERATOR UPR POWER MANEUVER Department ofnuclear Technology Faculty ofengineering Chula/ongkom University

9 page 0-7 Chapter 0: Course 'ntroduction 3.2 DAY 2 COURSE PLAN REACTOR AND MODERATOR REACTOR ASSEMBLY FUELCHANNELASSEMBLIES FUEL MODERATOR REACTOR CONTROL REACTOR CONTROL REQUIREMENTS REACTOR INSTRUMENTATION REACTIVITY CONTROL DEVICES REACTOR REGULATING SYSTEM PROGRAMS (Ref. Text: 2-2 to 2-6) (Ref. Text: 2-7 to 2-9) (Ref. Text: 2-10 to 2-12) (Ref. Text: 2-12 to 2-19) (Ref. Text: 3-2 to 3-5) (Ref. Text: 3-6 to 3-10) (Ref. Text: 3-11 to 3-19) (Ref. Text: 3-20 to 3-28) SIMULATOR SHUTDOWN RODS REACTIVITY CONTROL LIQUID ZONES CONTROL ZONAL FLUX TRENDS FLUX MAPPING RRS/DPR REACTOR STEPBACK AND RECOVERY ONE BANK OF ABSORBER RODS DROP ALL LIQUID ZONE PUMPS TRIP FAIL OPEN LIQUID ZONE 1 & 2 INLET VALVES DeparlmentofNudearTechnowgy FacuffyofEngmeering Chulalongkom University

10 CANDU Overviflw page DAY 3 COURSE PLAN Chapter 0: Course,... Oduction HEAT TRANSPORT MAIN HEAT TRANSPORT PRESSURE AND INVENTORY CONTROL SHUTDOWN COOLING HEAT TRANSPORT AUXILIARIES HEAT TRANSPORT SYSTEM OPERATION (Ref. Text: 4-2 to 4-7) (Ref. Text: 4-8 to 4-12) (Ref. Text: 4-13 to 4-14) (Ref. Text: 4-15 to 4-16) (Ref. Text: 4-17 to 1-19) SIMULATOR PHT MAIN CIRCUIT PHT FEED & BLEED PHT INVENTORY CONTROl. PHTPRESSURECONTROL BLEED CONDENSER CONTROL PHT LRV (CV20) FAILS OPEN PHT STEAM BLEED VALVE (CV22) FAILS OPEN PHT FEED VALVE (CV12) FAILS OPEN PRESSURIZER SURGE VALVE (MV1) FAILS CLOSE PHT BLEED VALVE (CV5) FAILS OPEN Department ofnuclear Technology FacuUyofEngmeering Chula!ongkom University

11 pageo-9 Chapter 0: Course",,' oduction 3.4 DAY 4 COURSE PLAN STEAM, TURBINE & FEEDWATER Steam Generator (Boiler) Steam System Turbine and Condenser Feedwater System Generator Conventional Plant Services ELECTRIC POWER (Ref. Text: 5-2 to 5-4) (Ref. Text: 5-5 to 5 8) (Ref. Text: 5-9 to 5-11) (Ref. Text: 5-12 to 5-15) (Ref. Text: 5-16 to 5-17) (Ref. Text: 5-18 to 5-19) SIMULATOR STEAM GENERATOR FEED PUMPS STEAM GENERATOR LEVEL CONTROL STEAM GENERATOR LEVEL TRENDS STEAM GENERATOR LEVEL MANUAL CONTROL EXTRACTION STEAM TURBINE GENERATOR UPR FAIL CLOSED ALL FEEDWATER LCVs & MVs TURBINE SPURIOUS TRIP FEEDWATER LCV101 FAILS OPEN FEEDWATER LCV101 FAILS CLOSED ALL MAIN BFPs TRIP THROTTLE PT FAILS LOW Department of Nuclear Technology Faculty ofengineering Chulalongkom University

12 3.5 DAY 5 COURSE PLAN SPECIAL SAFETY SYSTEMS SHUTDOWN SYSTEM REQUIREMENTS SHUTDOWN SYSTEM NUMBER 1 SHUTDOWN SYSTEM NUMBER 2 EMERGENCY CORE COOLING SYSTEMS CONTAINMENT SYSTEM paf}! 0-10 Chapter 0: Course I,.., 6duction (Ref. Text: 6-2 to 6-6) (Ref. Text: 6-7 to 6-15) (Ref. Text: 6-15 to 6-26) (Ref. Text: 6-26 to 6-31) (Ref. Text: 6-32 to 6-35) SIMULATOR REACTOR TRIP AND RECOVERY ALL ASRVs FAIL OPEN RIH#1 SMALL BREAK 100% MAIN STEAM HEADER BREAK REACTOR SETBACKISTEPBACK BOTH FAIL LOSS OF CLASS IV POWER EVENT DIAGNOSIS Department of Nuclear Technology Faculty of Engineering Chulalongkom University