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Author:   V.N. Shah ,  P.E. MacDonald (Idaho National Engineering Laboratory, Idaho Falls, ID, USA)
Publisher:   Elsevier Science & Technology
Imprint:   Elsevier Science Ltd
Dimensions:   Width: 15.90cm , Height: 4.40cm , Length: 24.10cm
Weight:   1.840kg
ISBN:  

9780444894489

ISBN 10:   0444894489
Pages:   968
Publication Date:   30 June 1993
Audience:   Professional and scholarly ,  Professional & Vocational
Format:   Hardback
Publisher's Status:   Active
Availability:   Out of stock  
The supplier is temporarily out of stock of this item. It will be ordered for you on backorder and shipped when it becomes available.

Table of Contents

(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.

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