Nuclear Reactor Engineering: Reactor Systems Engineering

394 Pages·1994·11.17 MB·English

by  Samuel Glasstone

NUCLEAR REACTOR
ENGINEERING
REACTOR SYSTEMS ENGINEERING
FOURTH EDITION VOLUME TWO
NUCLEAR REACTOR
ENGINEERING
REACTOR SYSTEMS ENGINEERING
FOURTH EDITION VOLUME TWO
SAMUEL GLASSTONE &
ALEXANOER SESONSKE
Springer-Science+Business Media, B.V.
© 1994 Springer Science+Business Media Dordrecht
Originally published by Chapman & Hall,lnc. in 1994
Softcover reprint of the hardcover 4th edition 1994
AII rights reserved. No part of this book may be reprinted or reproduced or utilized
in any form or by any electronic, mechanical or other means, now known or
hereafter invented, including photocopying and recording, ar by an information
starage or retrieval system, without permission in writing from the publishers.
Library of Congress Cataloging-in-Publication Data
Glasstone, Samuel, 1897-
Nuclear reactor engineering / Samuel Glasstone and Alexander
Sesonske. - 4th ed.
p. cm.
Includes bibliographical references and index.
Contents: v. 1. Reactor design basics - v. 2. Reactor systems
engineering.
ISBN 978-1-4613-5866-4 ISBN 978-1-4615-2083-2 (eBook)
DOI 10.1007/978-1-4615-2083-2
1. Nuclear reactors. 1. Sesonske, Alexander, 1921- .
II. Title.
TK9202.G55 1994
621.48'31-dc20 94-16575
CIP
Contents
PREFACE xiv
CHAPTER 8 THE SYSTEMS CONCEPT, DESIGN
DECISIONS, AND INFORMATION
TOOLS 487
INTRODUCTION 487
SYSTEMS 488
Introduction, 488; PWR Nuclear Steam Supply
System, 489.
THE COMPUTER As A DECISION TOOL 490
System Modeling, 490; System Interactions, 490;
Design Interactions and Intersystem Dependencies,
491; Sensitivity Analysis and Design Parameter
Interactions, 491; Feedback, 491; Optimization, 492;
Expert Systems and Artificial Intelligence, 493;
Computer Code Sources, 494.
v
vi Contents
INFORMATION As A DECISION TOOL 495
Introduction, 495; Abstracts, 496; Nonarchival
Literature Sources, 496; Data Centers, 497; Data
Access Networks, 498; Information Age Challenges,
498.
CHAPTER 9 ENERGY TRANSPORT 501
INTRODUCTION 501
The Role of Energy Transport in Reactor Design, 501;
Thermodynamic Viewpoint, 502; Design Methods,
503.
HEAT SOURCES IN REACTOR SYSTEMS 503
Fission Energy, 503; Spatial Distribution of Energy
Sources in Reactor Core, 505; Average and Maximum
Power in Single Fuel Channel, 507; Power and Flux
Flattening, 508; Other Heat Sources, 509.
HEAT-TRANSMISSION PRINCIPLES 509
Introduction, 509; Conduction of Heat, 509;
Convection of Heat, 511; Conduction with Convection
Boundary Conditions, 512; Radiation Heat Transfer,
515; Systems with Internal Heat Sources, 517;
Conduction in Irregular Geometries, 529; Transient
Heat Conduction, 530; Transient Heat Transfer, 534.
HEAT TRANSFER TO ORDINARY FLUIDS 535
Introduction, 535; Laminar and Turbulent Flow, 535;
Heat-Transfer Coefficients of Ordinary Fluids, 539;
Heat-Transfer Coefficients of Gases, 541.
HEAT TRANSFER TO LIQUID METALS 541
Introduction, 541; Heat Transfer in Reactor Rod
Bundles, 543.
BOILING HEAT TRANSFER 543
Pool Boiling, 543; Flow Boiling, 546; Boiling Crisis,
548; Prediction of Burnout Conditions, 549; Boiling
Heat-Transfer Coefficients, 550.
CORE FLUID FLOW 552
Introduction, 552; Flow Pressure Drop, 552; Pressure
Drop in Turbulent Flow, 554; Velocity Head Losses,
Contents vii
556; Two-Phase Flow, 558; Two-Phase Pressure
Drop, 558; Limiting Flow with Compressible Fluids,
561; Natural Circulation Cooling, 562.
564
SUBCHANNEL ANALYSIS AND SYSTEM CODES
565
CORE DESIGN CONSTRAINTS
General Considerations, 565; Peaking and
Hot-Channel Factors, 566; Idealized Axial
Temperature Distributions, 567; Heat-Flux-Related
Limitations in Pressurized-Water Reactors, 573;
Factors and Subfactors, 576; Enthalpy Rise
Hot-Channel Factor, 578; Statistical Core Design
Techniques, 580; Boiling-Water Reactors, 581;
Gas-Cooled Reactors, 583; Fast Liquid-Metal-Cooled
Reactors, 584.
CHAPTER 10 REACTOR FUEL MANAGEMENT
AND ENERGY COST CONSIDERATIONS 589
INTRODUCTION 589
PRE-REACTOR FUEL OPERATIONS 590
Production, 590; Isotopic Enrichment, 590; Isotopic
Feed Material and Separative Work Requirements,
591; Fabrication of Fuel Assemblies, 594.
IN-CORE MANAGEMENT 594
Introduction, 594; Fuel Burnup, 595; Staggered
Refueling, 596; Fuel Management Terminology, 598.
PRESSURIZED WATER REACTOR CORE MANAGEMENT 598
The Initial PWR Core and Subsequent Reload
Patterns, 598; Burnable Absorber Rods, 602; PWR
Fuel Assembly Design Trends, 603; The Fuel Reload
Design Process, 604; Levels of Core Modeling, 604;
Neutronic Analysis Methods, 605; Reload Core
Pattern Design Considerations, 605; Automation and
Optimization, 607; The Haling Principle, 607.
BOILING WATER REACTOR CORE MANAGEMENT 608
Introduction, 608; Control Cell Core, 610; BWR Fuel
Assembly Design Trends, 610; BWR Spectral Shift
Operation, 611; BWR Core Modeling Methods, 611.
viii Contents
NUCLEAR FUEL UTILIZATION 612
Introduction, 612; The Conversion Ratio, 613; The
Breeding Ratio, 615; Thorium Utilization, 618;
Plutonium Utilization, 619; Proliferation Risk, 620.
NUCLEAR ENERGY COSTS 620
Introduction, 620; Time Value of Money, 621; Capital
Costs, 623; Operation and Maintenance Costs, 625;
Fuel Costs, 625; Electric Power Generation Costs,
626; Role of Rate Regulation, 627.
NUCLEAR MATERIAL SAFEGUARDS 628
NUCLEAR CRITICALITY SAFETY 629
Introduction, 629; Design Approaches and Analysis,
629.
CHAPTER 11 ENVIRONMENTAL EFFECTS OF
NUCLEAR POWER AND WASTE
MANAGEMENT 632
INTRODUCTION 632
Environmental Concerns, 632; Emissions from
Fossil-Fueled Power Plants, 633; The Greenhouse
Effect, 634; Overview of Nuclear Power Effects, 634.
RADIATION EXPOSURE P A THW A YS 635
Introduction, 635; Regulatory Bases for Exposure
Pathways, 636; Radiation Exposure Pathways, 636;
Radiation Levels "As Low As Is Reasonably
Achievable," 638.
THE SPENT-FuEL MANAGEMENT CHALLENGE 639
ON-SITE SPENT-FuEL STORAGE 640
Introduction, 640; Spent-Fuel Logistics, 640; Pool
Storage Capacity Enhancement, 641.
CHARACTERISTICS OF SPENT FUEL 642
STORAGE AND DISPOSAL OPTIONS 644
Introduction, 644; Retrievable Storage, 645;
Permanent Disposal, 646.
MIGRATION OF WASTE RADIONUCLIDES 646
Lessons from the Oklo Reactor Waste, 648.
Contents ix
THE REPROCESSING OPTION 648
Introduction, 648; Head-End Treatment, 649;
Solvent-Extraction Separation Processes, 650; Other
Separation Processes, 654; Fuel Reprocessing Waste
Management, 656; Characteristics of Solidified
High-Level Waste, 657.
REACTOR RADW ASTE MANAGEMENT 659
Sources of Radioactivity, 659; Reactor Radwaste
Systems, 660; Pressurized-Water Reactors, 661;
Boiling-Water Reactors, 663.
WASTE HEAT MANAGEMENT 663
Condenser Cooling Requirements, 663; Regulation of
Thermal Discharges, 666; Treatment of Thermal
Discharge, 666.
CHAPTER 12 NUCLEAR REACTOR SAFETY AND
REGULATION 673
INTRODUCTION 673
Technological Risk and Public Perception, 673; Public
Acceptance of Nuclear Power Plants, 674; Defense in
Depth, 675.
ACCIDENT PREVENTION 675
Introduction, 675; Quality Assurance: Codes and
Standards, 676; Redundancy and Diversity, 677;
Inherent Reactor Stability, 678; Reactor Protection
System, 678; Reactor Trip Signals, 680; Shutdown
Cooling, 680.
ENGINEERED SAFETY FEATURES 681
Introduction, 681; The Emergency Core-Cooling
System, 682; Containment Systems, 685.
ABNORMAL EVENT ANALYSIS 691
Categories of Abnormal Events, 691; Events of
Moderate Frequency, 693; Events of Low Probability,
696.
LICENSING DESIGN BASIS EVALUATION 698
Control Element Ejection, 698; Spent-Fuel Handling
Accident, 699; Loss-of-Coolant Accident, 699;
Emergency Core-Cooling Criteria, 703.
x Contents
SEVERE ACCIDENTS 705
PWR Sequences, 706; BWR Sequences, 707.
THE SOURCE TERM 707
Introduction, 707; Barriers to the Escape of
Radioactivity, 708; Radionuclide Importance Factors,
708; Fission Product Transport Overview, 708; Fission
Product Chemistry, 709; Fine Particle Dynamics, 712;
Aerosols, 713; Explosions, 714.
SAFETY MODELING METHODS 715
Introduction, 715; Licensing "Evaluation" Models,
716; System Modeling Methods, 717; Representative
Best Estimate System Modeling Codes, 720; Modeling
of Fluid and Structure Interactions, 721; Severe
Accident Modeling, 721.
SITING REQUIREMENTS 723
Introduction, 723; Radiological Criteria of Site
Acceptability, 723; Radiation Dose Calculations, 725;
Emergency Response Planning, 730; Seismic Design
Criteria, 730; Other Natural Events, 731.
ACCIDENT EXPERIENCE AND ANALYSIS 732
Introduction, 732; The Three Mile Island Accident,
732; Impact of the Three Mile Island Accident, 733;
Chernobyl, 734; Impact of the Chernobyl Accident,
737.
SEVERE ACCIDENT MANAGEMENT 738
Introduction, 738; Information and Analysis, 738;
Supporting Instrumentation, 739; Accident
Management Strategy Development, 739; Equipment
Modification and Personnel Training, 739.
RELIABILITY AND RISK ASSESSMENT 739
Introduction, 739; Deterministic and Probabilistic
Analysis, 740; Elementary Binary State Concepts, 741;
Fault Tree Analysis, 743; Quantitative Fault Tree
Analysis, 744; Event Trees, 745; Computer Modeling,
747; Risk Assessment Studies, 748.
LICENSING AND REGULATION OF NUCLEAR PLANTS 750
Introduction, 750; Design Certification, 751; Early Site
Permit, 751; Combined Construction and Operating
License, 752; State-Level Regulation, 752.
Contents xi
NUCLEAR REACTOR SAFEGUARDS 753
Introduction, 753; Protection against Sabotage, 753.
CHAPTER 13 POWER REACTOR SYSTEMS 759
INTRODUCTION 759
PRESENT PRESSURIZED-WATER REACTORS 760
Introduction, 760; Reactor Vessel and Core, 760;
Control and Safety Systems, 765; Coolant Circulation
and Steam Generating Systems, 766.
EVOLUTIONARY PRESSURIZED-WATER REACTORS 769
Introduction, 769; Design Features, 770.
PRESENT BOILING-WATER REACTORS 774
Introduction, 774; Core and Vessel, 776; Coolant
Recirculation System, 778; Control System, 779;
Feedwater Temperature and Fuel Cycle Length, 781.
EVOLUTIONARY BOILING-WATER REACTORS 781
Introduction, 781; System Features, 783;
Standardization and Certification, 783.
HEAVY -W A TER-MODERATED REACTORS 783
Introduction, 783; Design Specifications and Core
Features, 785; Heat Removal, 785; Control System,
788; Safety Features, 789; The Evolutionary CANDU
3,789.
CHAPTER 14 PLANT OPERATIONS 791
INTRODUCTION 791
PLANT OPERATIONAL STRATEGY 792
Generation Dispatching, 792; Operating Cycle Length
and Outage Management, 792.
PLANT CONTROL 793
Normal Operational Maneuvers, 793; The Control
Room, 797.