Download or read book Steam Generator Feedwater Pipe Cracking in Nuclear Steam Supply Systems written by S. M. Schloss and published by . This book was released on 1980 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of cracking in feedwater piping adjacent to the steam generators in nine pressurized water written by A. Goldberg and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Metallurgical Investigation of Cracks in the Steam Generator Feedwater Piping of Salem Station written by L. Albertin and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of Cracking in Feedwater Piping Adjacent to the Steam Generators in Nine Pressurized Water Reactor Plants written by Alfred Goldberg and published by . This book was released on 1980 with total page 216 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Thermal fatigue cracking of feedwater piping to steam generators written by and published by . This book was released on 1993 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of Cracking in Steam Generator Feedwater Piping in Pressurized Water Reactor Plants written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Cracking in feedwater piping was detected near the inlet to steam generators in 15 pressurized water reactor plants. Sections with cracks from nine plants are examined with the objective of identifying the cracking mechanism and assessing various factors that might contribute to this cracking. Using transmission electron microscopy, fatigue striations are observed on replicas of cleaned crack surfaces. Calculations based on the observed striation spacings gave a cyclic stress value of 150 MPa (22 ksi) for one of the major cracks. The direction of crack propagation was invariably related to the piping surface and not to the piping axis. These two factors are consistent with the proposed concept of thermally induced, cyclic, tensile surface stresses and it is concluded that the overriding factor in the cracking problem was the presence of such undocumented cyclic loads.

Download or read book Degradation of Steam Generator Tubing and Components by Operation of Pressurized water Reactors written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Experience in operating pressurized water reactors (PWR) has shown a number of materials degradation processes to have occurred in their steam generators. These include stress corrosion cracking (SCC), intergranular attack, generalized dissolution, and pitting attack on steam generator tubes; mechanical damage to steam generator tubes; extensive corrosion of tubing support plates (denting); and cracking of feedwater lines and steam generator vessels. The current status of the understanding of the causes of each of these phenomena is reviewed with emphasis on their possible significance to reactor safety and directions the nuclear industry and the NRC should be taking to reduce the rate of degradation of steam generator components.

Download or read book Evaluation of Steam Generator Tube Rupture Events written by L. B. Marsh and published by . This book was released on 1980 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Potential for Stress Corrosion Cracking in Steam Generator Tube Plugs Supplied by Babcock and Wilcox written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Resolution of Generic Safety Issue 188 written by U.s. Nuclear Regulation Comion and published by CreateSpace. This book was released on 2014-07-25 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report addresses Generic Safety Issue (GSI) 188, “Steam Generator Tube Leaks or Ruptures Concurrent with Containment Bypass from Main Steam Line or Feedwater Line Breaches,” which concerns the potential for additional tube leakage or ruptures from the growth of existing cracks in steam generator tubes resulting from the dynamic loads following a main steam line break (MSLB) or feedwater line break (FWLB). To address the issue, this report provides the technical findings from thermal-hydraulic transient analyses and sensitivity studies, a simplified finite-element model of steam generator support structures and tubes, and structural analyses and sensitivity studies of the potential for crack growth. The results show that the additional dynamic loads from an MSLB are greater than those from an FWLB. The report concludes that dynamic loads from an MSLB are low and do not affect the structural integrity of tubes and do not lead to additional leakage or ruptures beyond what would be determined using differential pressure loads alone. Therefore, GSI-188 is closed, and the staff recommends no changes to existing regulations or guidance with respect to the dynamic loads induced by a breach of the main steam or feedwater line.

Download or read book Identification of Unresolved Safety Issues Relating to Nuclear Power Plants written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Program Support Branch and published by . This book was released on 1979 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-11 with total page 486 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Regulatory Commission Issuances written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1982 with total page 774 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Circumferential Cracking of Steam Generator Tubes written by and published by . This book was released on 1997 with total page 165 pages. Available in PDF, EPUB and Kindle. Book excerpt: On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-03, {open_quote}Circumferential Cracking of Steam Generator Tubes.{close_quote} GL 95-03 was issued to obtain information needed to verify licensee compliance with existing regulatory requirements regarding the integrity of steam generator tubes in domestic pressurized-water reactors (PWRs). This report briefly describes the design and function of domestic steam generators and summarizes the staffs̀ assessment of the responses to GL 95-03. The report concludes with several observations related to steam generator operating experience. This report is intended to be representative of significant operating experience pertaining to circumferential cracking of steam generator tubes from April 1995 through December 1996. Operating experience prior to April 1995 is discussed throughout the report, as necessary, for completeness.

Download or read book Nuclear Safety written by and published by . This book was released on 1963 with total page 1548 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Report of the U S Nuclear Regulatory Commission Piping Review Committee Evaluation of seismic designs a review of seismic design requirements for nuclear power plant piping written by U.S. Nuclear Regulatory Commission. Piping Review Committee. Pipe Crack Task Group and published by . This book was released on 1984 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Steam Generators for Nuclear Power Plants written by Jovica Riznic and published by Woodhead Publishing. This book was released on 2017-05-24 with total page 580 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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