Steam Generators for Nuclear Power Plants.

Format:

Book

Author/Creator:

Riznic, Jovica R.

Contributor:

Riznic, Jovica R.

Language:

English

Subjects (All):

Nuclear power plants.

Steam-boilers.

Physical Description:

1 online resource (1678 pages)

Edition:

2nd ed.

Place of Publication:

Chantilly : Elsevier Science & Technology, 2025.

Summary:

Steam Generators for Nuclear Power Plants, Second Edition continues its legacy of examining all phases of the lifecycle of nuclear steam generators (NSGs), components which are essential for the efficient and safe operation of nuclear reactors.

Contents:

Front Cover

Steam Generators for Nuclear Power Plants

Copyright Page

Dedication

Contents

List of contributors

About the editor

Preface

Acknowledgments

One Design and manufacturing

1 Introduction to steam generators-from Heron of Alexandria to nuclear power plants: brief history and literature survey

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 American Society of Mechanical Engineers 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 steam

1.3.1 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 Pressurized water reactor vertical steam generators

1.4.2 Pressurized water reactor once-through steam generators

1.4.3 Pressurized water reactor Vodo-Vodyanoj Energeticheskij Reaktor steam generator

1.4.4 Pressurized heavy water reactor Canadian deuterium steam generators

1.4.5 Steam generator tube rupture

1.5 Steam generators literature survey

1.5.1 Steam generator patents

Acknowledgment

References

2 Nuclear steam generator design

2.1 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

3 Steam generator manufacturing

3.1 Introduction, manufacturers

3.1.1 Overview and manufacturing objectives.

3.1.2 Quality assurance requirements for nuclear manufacturing

3.2 Manufacturing scheduling

3.2.1 Material purchasing to support the schedule

3.3 Main subassemblies

3.3.1 Tubesheet/thick shell

3.3.2 Primary head

3.3.3 Secondary shell

3.3.4 Drum shell

3.3.5 Separator subassembly

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

4 Thermalhydraulics, circulation, and steam-water separation in nuclear steam generators

Nomenclature

Acronyms

Symbols

Greek letters

4.1 Introduction

4.2 Vertical recirculating U-tube steam generators for PWR and CANDU reactor

4.2.1 Flow paths

4.2.1.1 Recirculation ratio

4.2.2 Steam generator thermalhydraulics

4.2.2.1 Heat transfer

Effect of preheater on the steam generator thermal performance

Axial flow preheaters

Crossflow preheaters

4.2.2.2 Thermal performance degradation

Divider plate leakage

Preheater thermal plate leakage

Tube plugging

4.2.2.3 Flow regimes

4.2.3 Computational modeling

4.2.3.1 Computer codes

4.2.3.2 Governing equations

4.2.3.3 Computational fluid dynamics

4.2.4 Steam-water separation

4.2.5 Flow-affected phenomena leading to degradation

4.2.5.1 Fouling

Tube fouling

Sludge accumulation on the tubesheet

Fouling on tube supporting plates

4.2.5.2 Cavitation erosion in preheater of the CANDU steam generator

4.2.5.3 Water level oscillations

4.2.5.4 Flow-induced vibrations and fretting-wear

4.2.5.5 Fatigue

4.2.5.6 Flow-accelerated corrosion

4.3 PWR once-through steam generators

4.3.1 Flow paths

4.3.2 Steam generator thermalhydraulics

4.3.2.1 Heat transfer

4.3.2.2 Computational modeling.

4.3.3 Flow-affected phenomena leading to degradation

5 Replacement steam generators

5.1 Introduction

5.2 The first steam generator replacements

5.3 Steam generator replacement becomes routine maintenance

5.4 The steam generator replacement planning process

5.5 Summary of the characteristics of replacement steam generators

5.6 Replacement steam generators in CANDU reactors

5.6.1 Bruce plant

5.6.2 Embalse

5.7 Conclusions

Reference

Two Operation and maintenance

6 Influence of water-steam cycle chemistry on steam generator integrity and performance

6.1 Introduction

6.2 Steam generator degradation

6.2.1 Corrosion issues

6.2.1.1 Wastage

6.2.1.2 Denting

6.2.1.3 Stress corrosion cracking

6.2.1.4 Pitting

6.2.2 Thermal degradation

6.3 Deposition and enrichment mechanism in steam generators

6.3.1 Corrosion product deposition

6.3.1.1 Corrosion product deposition in tube support structures

6.3.1.2 Corrosion product deposition on the TS

6.3.2 Impurity enrichment mechanism in steam generator deposits

6.4 Water chemistry treatments

6.4.1 Historical evolution of water-steam cycle chemistry treatment

6.4.2 All-volatile treatment

6.4.2.1 General

6.4.2.2 Ammonia and hydrazine only (High-AVT)

6.4.2.3 Organic amines

6.4.3 Conclusion

6.5 Optimal water-chemical influencing factors

6.5.1 Control of corrosion product generation

6.5.2 Control of redox conditions

6.5.2.1 Oxygen removal

6.5.2.2 Classification of hydrazine in the European Union

6.5.3 Impurity control

6.5.3.1 General

6.5.3.2 Main condenser leakage

6.5.3.3 Make-up water control

6.6 Additional measures for high steam generator performance

6.6.1 Corrosion product removal from steam generators

6.6.1.1 Mechanical steam generator cleaning.

6.6.1.2 Chemical steam generator cleaning

6.6.2 Minimization of corrosion product generation

6.6.2.1 Plant preservation and start-up procedure

6.6.2.2 Oxygen dosing

6.6.3 Corrosion product control by additives

6.6.3.1 Film-forming products

6.6.3.2 Dispersants

6.6.4 Minimization of the formation of an aggressive environment in steam generators

6.7 Water chemistry monitoring and control program

6.7.1 Water chemistry guidelines

6.7.2 Water chemistry surveillance

6.8 Summary

7 Corrosion and other degradation in commercial PWR/PHWR steam generator tubes

7.1 Introduction

7.2 Overview of steam generator types

7.2.1 Vertical pressurized water reactor steam generators of the Westinghouse Electric and Combustion Engineering types

7.2.2 Pressurized heavy water reactor steam generators

7.2.3 Pressurized water reactor steam generators of the KWU/Siemens/AREVA type with Alloy 800NG tubing

7.2.4 Pressurized water reactor once-through steam generators with Alloy 600SR tubing

7.2.5 VVER2 steam generators with stabilized stainless steel tubes

7.3 Primary water stress corrosion cracking

7.3.1 Types of steam generators affected, and locations affected by primary water stress corrosion cracking

7.3.2 Conditions required for the occurrence of primary water stress corrosion cracking and factors that increase the rate of primary water stress corrosion cracking

7.3.3 Consequences of primary water stress corrosion cracking and likelihood of future occurrence

7.4 Denting

7.4.1 Locations where denting has occurred

7.4.2 Types of steam generators affected by denting

7.4.3 Materials and design features required for denting to occur

7.4.4 Consequences of denting and likelihood of future occurrence

7.5 Secondary side wastage

7.5.1 Locations where wastage has occurred.

7.5.2 Conditions required for wastage to occur

7.5.3 Consequences and likely future occurrence of wastage

7.6 Secondary side pitting

7.6.1 Pitting in vertical pressurized water reactor steam generators

7.6.2 Pitting in vertical pressurized heavy water reactor steam generators

7.6.3 Pitting in horizontal VVER steam generators

7.7 Secondary side intergranular attack

7.7.1 Intergranular attack affecting once-through steam generators

7.7.2 Intergranular attack affecting pressurized heavy water reactor Alloy 600 steam generators

7.7.3 Intergranular attack affecting Alloy 800NG tubes

7.7.4 Likelihood of intergranular attack affecting new steam generators

7.8 Secondary side intergranular attack/stress corrosion cracking

7.8.1 Steam generators with Alloy 600MA and Alloy 600SR tubing

7.8.2 Steam generators with Alloy 800NG tubing

7.8.3 Vertical steam generators with Alloy 600TT tubing

7.8.4 Horizontal steam generators with stabilized stainless steel tubing

7.8.5 Causes of secondary side intergranular attack/stress corrosion cracking and methods to minimize its occurrence

7.9 Secondary side fatigue and corrosion fatigue

7.10 Secondary side wear

7.10.1 Wear in vertical steam generators

7.10.2 Wear in horizontal steam generators

7.10.3 Long-term effects of wear

7.11 Summary comments regarding control of corrosion of steam generator tubes

7.11.1 Primary side corrosion

7.11.2 Secondary side corrosion

8 Environmental degradations in PWR Steam generators

8.1 Introduction

8.2 Primary side environmental effects

8.2.1 (Primary water) stress corrosion cracking mechanisms

8.2.1.1 Operating experience

Steam generator tube bundles in alloy 600 (1972-2023+)

8.2.1.2 Partition plates

8.2.1.3 Steam generator bowl drains (1988-2008).

8.2.1.4 Safety nozzles welds (1998-2023+).

Notes:

Description based on publisher supplied metadata and other sources.

Part of the metadata in this record was created by AI, based on the text of the resource.

ISBN:

0-443-29031-8

0-443-29030-X

9780443290312

OCLC:

1553118264