Author: Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 7
Book Description
Crack-like Indications at Dents/dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes
Author: Steam Generators for Nuclear Power Plants
Author: Jovica RiznicPublisher: Woodhead Publishing
ISBN: 0081009283
Category : Technology & Engineering
Languages : en
Pages : 580
Book Description
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 plants - Contains 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 volume - Presents contributions from key manufacturers and research institutes and universities
Stress Corrosion Crack Detection in Alloy 600 in High Temperature Caustic
Author: Bruce William BrissonPublisher:
ISBN:
Category :
Languages : en
Pages : 294
Book Description
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to environmentally assisted stress corrosion cracking. Intergranular stress corrosion cracking (IGSCC) attacks the tubes in areas of high residual stress, and in crevice regions. No method has been successfully developed to monitor steam generator tubing in-situ for crack initiation and growth. Essentially all available published IGSCC crack growth data for alloy 600 is based on non-tubing material. Although it is very likely that the current data base is applicable to tubing processing, differences between tube and other geometries make a comparison between tubing and other data important for verification purposes. However, obtaining crack initiation and growth data from tubing is difficult due to the geometry and the thin wall thickness.
Literature Survey - Stress Corrosion Cracking of Alloy 600 Steam Generator Tubing
Author: Keith MatuszykChuan Suo Fei Hang
Author: Unanticipated crack in a particular heat of alloy 600 used for Westinghouse mechanical plugs for steam generator tubes
Author: Role of Time-Dependent Deformation in Intergranular Crack Initiation of Alloy 600 Steam Generator Tubing Material
Author: United States Government Printing OfficePublisher:
ISBN: 9780160632334
Category :
Languages : en
Pages : 40
Book Description
The Role of Time-dependent Deformation in Intergranular Crack Initiation of Alloy 600 Steam Generator Tubing Material
Author: G. S. WasPublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 30
Book Description
Stress Corrosion Cracking Behavior of Alloy 600 in High Temperature Water
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 16
Book Description
SCC susceptibility of Alloy 600 in deaerated water at 360 C (statically loaded U-bend specimens) is dependent on microstructure and whether the material was cold-worked and annealed (CWA) or hot-worked and annealed (HWA). All cracking was intergranular, and materials lacking grain boundary carbides were most susceptible to SCC initiation. CWA tubing materials are more susceptible to SCC initiation than HWA ring-rolled forging materials with similar microstructures (optical metallography). In CWA tubing materials, one crack dominated and grew to a visible size. HWA materials with a low hot-working finishing temperature (925 C) and final anneals at 1010-1065 C developed both large cracks (similar to those in CWA materials) and small intergranular microcracks detectable only by destructive metallography. HWA materials with a high hot-working finishing temperature (980 C) and a high-temperature final anneal (>1040 C), with grain boundaries that are fully decorated, developed only microcracks in all specimens. These materials did not develop large, visually detectable cracks, even after more than 300 weeks exposure. A low-temperature thermal treatment (610 C for 7h), which reduces or eliminates SCC in Alloy 600, did not eliminate microcrack formation in high temperature processed HWA materials. Conventional metallographic and analytical electron microscopy (AEM) were done on selected materials to identify the factors responsible for the observed differences in cracking behavior. Major difference between high-temperature HWA and low-temperature HWA and CWA materials was that the high temperature processing and final annealing produced predominantly ''semi-continuous'' dendritic M--C3 carbides along grain boundaries with a minimal amount of intragranular carbides. Lower temperature processing produced intragranular M7C3 carbides, with less intergranular carbides.
Author: I. J. Muir