Coverart for item
The Resource Steam Generators for Nuclear Power Plants

Steam Generators for Nuclear Power Plants

Label
Steam Generators for Nuclear Power Plants
Title
Steam Generators for Nuclear Power Plants
Creator
Subject
Language
eng
Summary
Annotation
Member of
Cataloging source
EBLCP
http://library.link/vocab/creatorName
Riznic, Jovica
Dewey number
621.183
Index
no index present
LC call number
TJ285
Literary form
non fiction
Nature of contents
dictionaries
Series statement
Woodhead Publishing series in energy
http://library.link/vocab/subjectName
  • Steam-boilers
  • Nuclear power plants
Summary expansion
Steam Generators for Nuclear Power Plants examines all phases of the lifecycle of nuclear steam generators (NSGs), components which are essential for the efficient and safe operation of light water reactors (LWRs). Coverage spans the design, manufacturing, operation and maintenance, fitness-for-service, and long-term operation of these key reactor parts.Part One opens with a chapter that provides fundamental background on NSG engineering and operational experiences. Following chapters review the different NSG concepts, describe NSG design and manufacturing, and consider the particularities of SGs for VVER reactors. Part Two focuses on NSG operation and maintenance, starting with an overview of the activities required to support reliable and safe operation. The discussion then moves on to tubing vibration, followed by the water and steam cycle chemistry issues relevant to the NSG lifecycle. Finally, a number of chapters focus on the key issue of corrosion in NSGs from different angles.This book serves as a timely resource for professionals involved in all phases of the NSG lifecycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long-term operation. It is also intended as a valuable resource for students and researchers interested in a range of topics relating to NSG lifecycle management.Fulfills the need for a detailed reference on steam generators for nuclear power plantsContains comprehensive coverage of all phases of the nuclear steam generator lifecycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long-term operation in one convenient volumePresents contributions from key manufacturers and research institutes and universities
Label
Steam Generators for Nuclear Power Plants
Instantiates
Publication
Note
4.2.7.8. Flow-accelerated corrosion
Carrier category
online resource
Carrier category code
  • cr
Carrier MARC source
rdacarrier
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Contents
  • Front Cover; Steam Generators for Nuclear Power Plants; Copyright; Contents; List of contributors; Preface; Part One: Design and manufacturing; Chapter 1: Introduction to steam generators-from Heron of Alexandria to nuclear power plants: Brief history and literat; 1.1. Introduction; 1.2. Brief history of steam generation; 1.2.1. It began with water and steam; 1.2.2. The steam engine; 1.2.3. The steam locomotive; 1.2.4. Early steam boiler explosions; 1.2.5. ASME boiler and pressure vessel code; 1.2.6. Development of central electricity generation stations
  • 1.3. Splitting of the atom and emergence of nuclear power: Atoms join water and steam1.3.1. Chicago pile: The first energy from a nuclear reaction; 1.3.2. The nuclear-powered submarines and Admiral Rickover; 1.3.3. Growth of commercial nuclear power; 1.3.4. Current state of the nuclear industry; 1.4. Unique features of different steam generators; 1.4.1. PWR vertical steam generators; 1.4.2. PWR once-through steam generators; 1.4.3. PWR VVER steam generator; 1.4.4. PHWR CANDU steam generators; 1.5. Steam generators literature survey; 1.5.1. Steam generator patents; References
  • Chapter 2: Nuclear steam generator design2.1. Introduction; 2.2. Specifications; 2.3. Tube bundle; 2.4. Overall steam generator layout; 2.5. Circulation; 2.6. Other elements of the circulation system; 2.7. Feedwater inlet; 2.8. Pressure boundary design; 2.9. Conclusions; Chapter 3: Steam generator manufacturing; 3.1. Introduction, manufacturers; 3.1.1. Overview and manufacturing objectives; 3.1.2. QA requirements for nuclear manufacturing; 3.2. Manufacturing scheduling; 3.2.1. Material purchasing to support schedule; 3.3. Main sub-assemblies; 3.3.1. Tubesheet/thick shell; 3.3.2. Primary head
  • 3.3.3. Secondary shell3.3.4. Drum shell; 3.3.5. Separator sub-assembly; 3.3.6. Tube supports and shrouds; 3.4. Major assemblies; 3.5. Final assembly and preparation for shipment; 3.6. Stress reliefs; 3.7. Inspection and testing; 3.8. Shipment; 3.9. Conclusions; Chapter 4: Thermalhydraulics, circulation, and steam-water separation in nuclear steam generators; 4.1. Introduction; 4.2. Recirculating steam generators; 4.2.1. Flow paths; 4.2.1.1. Primary fluid; 4.2.1.2. Secondary fluid; 4.2.2. Heat transfer; 4.2.2.1. Fouling; 4.2.2.2. Divider plate leakage; 4.2.2.3. Preheater thermal plate leakage
  • 4.2.2.4. Tube plugging4.2.3. Steam-water separation; 4.2.4. Carryover and carryunder; 4.2.5. Effect of primary fluid on steam generator thermal performance; 4.2.6. Use of preheater; 4.2.6.1. Axial flow preheaters; 4.2.6.2. Crossflow preheaters; 4.2.7. Flow-affected phenomena leading to degradation; 4.2.7.1. High fouling rates on tubes in regions with high steam quality; 4.2.7.2. Sludge accumulation on the tubesheet; 4.2.7.3. High concentration rate of chemicals in crevices; 4.2.7.4. Cavitation erosion; 4.2.7.5. Water level oscillations; 4.2.7.6. Flow-induced vibrations; 4.2.7.7. Fatigue
Dimensions
unknown
Extent
1 online resource (580 pages)
Form of item
online
Isbn
9780081009284
Media category
computer
Media MARC source
rdamedia
Media type code
  • c
Other control number
9780081008942
Specific material designation
remote
System control number
  • ocn988865750
  • (OCoLC)988865750
Label
Steam Generators for Nuclear Power Plants
Publication
Note
4.2.7.8. Flow-accelerated corrosion
Carrier category
online resource
Carrier category code
  • cr
Carrier MARC source
rdacarrier
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Contents
  • Front Cover; Steam Generators for Nuclear Power Plants; Copyright; Contents; List of contributors; Preface; Part One: Design and manufacturing; Chapter 1: Introduction to steam generators-from Heron of Alexandria to nuclear power plants: Brief history and literat; 1.1. Introduction; 1.2. Brief history of steam generation; 1.2.1. It began with water and steam; 1.2.2. The steam engine; 1.2.3. The steam locomotive; 1.2.4. Early steam boiler explosions; 1.2.5. ASME boiler and pressure vessel code; 1.2.6. Development of central electricity generation stations
  • 1.3. Splitting of the atom and emergence of nuclear power: Atoms join water and steam1.3.1. Chicago pile: The first energy from a nuclear reaction; 1.3.2. The nuclear-powered submarines and Admiral Rickover; 1.3.3. Growth of commercial nuclear power; 1.3.4. Current state of the nuclear industry; 1.4. Unique features of different steam generators; 1.4.1. PWR vertical steam generators; 1.4.2. PWR once-through steam generators; 1.4.3. PWR VVER steam generator; 1.4.4. PHWR CANDU steam generators; 1.5. Steam generators literature survey; 1.5.1. Steam generator patents; References
  • Chapter 2: Nuclear steam generator design2.1. Introduction; 2.2. Specifications; 2.3. Tube bundle; 2.4. Overall steam generator layout; 2.5. Circulation; 2.6. Other elements of the circulation system; 2.7. Feedwater inlet; 2.8. Pressure boundary design; 2.9. Conclusions; Chapter 3: Steam generator manufacturing; 3.1. Introduction, manufacturers; 3.1.1. Overview and manufacturing objectives; 3.1.2. QA requirements for nuclear manufacturing; 3.2. Manufacturing scheduling; 3.2.1. Material purchasing to support schedule; 3.3. Main sub-assemblies; 3.3.1. Tubesheet/thick shell; 3.3.2. Primary head
  • 3.3.3. Secondary shell3.3.4. Drum shell; 3.3.5. Separator sub-assembly; 3.3.6. Tube supports and shrouds; 3.4. Major assemblies; 3.5. Final assembly and preparation for shipment; 3.6. Stress reliefs; 3.7. Inspection and testing; 3.8. Shipment; 3.9. Conclusions; Chapter 4: Thermalhydraulics, circulation, and steam-water separation in nuclear steam generators; 4.1. Introduction; 4.2. Recirculating steam generators; 4.2.1. Flow paths; 4.2.1.1. Primary fluid; 4.2.1.2. Secondary fluid; 4.2.2. Heat transfer; 4.2.2.1. Fouling; 4.2.2.2. Divider plate leakage; 4.2.2.3. Preheater thermal plate leakage
  • 4.2.2.4. Tube plugging4.2.3. Steam-water separation; 4.2.4. Carryover and carryunder; 4.2.5. Effect of primary fluid on steam generator thermal performance; 4.2.6. Use of preheater; 4.2.6.1. Axial flow preheaters; 4.2.6.2. Crossflow preheaters; 4.2.7. Flow-affected phenomena leading to degradation; 4.2.7.1. High fouling rates on tubes in regions with high steam quality; 4.2.7.2. Sludge accumulation on the tubesheet; 4.2.7.3. High concentration rate of chemicals in crevices; 4.2.7.4. Cavitation erosion; 4.2.7.5. Water level oscillations; 4.2.7.6. Flow-induced vibrations; 4.2.7.7. Fatigue
Dimensions
unknown
Extent
1 online resource (580 pages)
Form of item
online
Isbn
9780081009284
Media category
computer
Media MARC source
rdamedia
Media type code
  • c
Other control number
9780081008942
Specific material designation
remote
System control number
  • ocn988865750
  • (OCoLC)988865750

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