V.N. Shah / P.E. MacDonald (eds.)

Aging and Life Extension of Major Light Water Reactor Components

Herausgeber: Shah, V N; MacDonald, P E

• Gebundenes Buch

Produktbeschreibung

In a comprehensive and lucid manner this book presents an understanding of the aging degradation of the major pressurized and boiling water reactor structures and components. The design and fabrication of each structure or component is briefly described followed by information on the associated stressors. Interactions between the design, materials, and various stressors that cause aging degradation are reviewed. In many cases, aging degradation problems have occurred, and the plant experience to date is analysed. The discussions summarize the available aging-related information and are supported with extensive references, including references to U.S. Nuclear Regulatory Commission (USNRC) documents, Electric Power Research Institute reports, U.S. and international conference proceedings and other publications. The book will prove a useful reference for engineers engaged in the operation and life extension of the present generation of nuclear power plants and for those engaged in the design of advanced light water reactors. It will also provide engineering students with insight into the practical materials-related issues associated with the design and operation of nuclear power plants. The work will also serve as a basis for programs to address the new aging-related issues likely to arise as plants get older.

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Produktdetails

• Verlag: Elsevier Science
• Seitenzahl: 968
• Erscheinungstermin: 30. Juni 1993
• Englisch
• Abmessung: 249mm x 170mm x 56mm
• Gewicht: 1701g
• ISBN-13: 9780444894489
• ISBN-10: 0444894489
• Artikelnr.: 31198569

Inhaltsangabe

(Selected) Pressurized Water Reactor Pressure Vessels. Design materials. Stressors. Degradation sites. Degradation mechanisms
radiation embrittlement
fatigue. Potential failure modes. Mitigation of embrittlement damage
reduction of thermal stresses
flux reductions
thermal annealing. Inservice inspection, surveillance and repair
inservice inspection methods
flaw distribution measurements
surveillance programs
estimating the mechanical properties of irradiated materials
weld repair. Summary, conclusions and recommendations. Pressurized Water Reactor Coolant Piping. Design and materials
geometry
materials and fabrication. Stressors;
steady
state stress
transient stresses. Degradation sites. Degradation mechanisms
fatigue
thermal embrittlement
stress corrosion cracking
corrosion
erosion and cavitation
creep. Potential failure modes. Inservice inspections
inservice inspection requirements
material considerations
inservice inspection reliability. Summary, conclusions and recommendations. Counter Measures For Tube Failures In Pressurized Water Reactor Steam Generators. Steam generator tube degradation
recirculating type steam generators
once
through steam generators. Mitigation techniques
secondary
side chemical impurity control
chemical additives that inhibit corrosion
steam generator secondary
side cleaning
shot peening and rotopeening the tubing
stress relieving the U
bends
reducing the hot
leg
side temperature repair
flaw
acceptance criteria for tube integrity
plugging
sleeving
nickel plating. Replacement of steam generators. Summary, conclusions and recommendations. Boiling Water Reactor Pressure Vessels. Design and materials. Stressors. Degradation sites. Degradation mechanisms
fatigue
intergranular stress corrosion cracking
radiation embrittlement
stress corrosion cracking. Potential failure modes. Inservice inspection, surveillance, monitoring, and repair
inservice inspection
surveillance
on
line monitoring
field repair. Summary, conclusions, and recommendations. Boiling Water Reactor Vessel Internals. Design and materials
incore instrument housings
core shroud and core plate
Shroud baffle plate
fuel supports
jet pump assemblies
top guide
core spray lines and spargers
shroud head
feedwater spargers
steam separator and dryer assemblies
materials. Stressors. Degradation sites. Degradation mechanisms
intergranular stress corrosion cracking (IGSCC)
irradiation
assisted stress corrosion cracking (IASCC)
fatigue
thermal embrittlement
radiation embrittlement. Potential failure modes. Inservice inspection, monitoring, and repair. Summary, conclusions, and recommendations.