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| Author | : Manubhai C. Patel |
| Publisher | : |
| Total Pages | : 290 |
| Release | : 1976 |
| Genre | : Steam-boilers |
| ISBN | : |
| Author | : Gautam J. Adhia |
| Publisher | : |
| Total Pages | : 108 |
| Release | : 1975 |
| Genre | : Steam-boilers |
| ISBN | : |
| Author | : L. Stieding |
| Publisher | : |
| Total Pages | : 0 |
| Release | : 1973 |
| Genre | : |
| ISBN | : |
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| Release | : 1974 |
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| Author | : Damien Feron |
| Publisher | : Elsevier |
| Total Pages | : 1073 |
| Release | : 2012-02-21 |
| Genre | : Technology & Engineering |
| ISBN | : 085709534X |
Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches
| Author | : J. M. Alzheimer |
| Publisher | : |
| Total Pages | : 284 |
| Release | : 1979 |
| Genre | : Pressurized water reactors |
| ISBN | : |
| Author | : |
| Publisher | : |
| Total Pages | : |
| Release | : 1982 |
| Genre | : |
| ISBN | : |
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.
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| Publisher | : |
| Total Pages | : |
| Release | : 1977 |
| Genre | : |
| ISBN | : |
Denting is a form of damage that results from the rapid, linear growth of magnetite on carbon steel tube support plates in tube-to-support plate crevices. The pressure of the corrosion products distorts the tubes as well as the support plates. Although denting was first thought to be confined to those recirculating steam generators that had been converted from phosphate to AVT, it has now also been observed in plants still on phosphate, as well as in some that started on AVT. In some units, slightly abnormal eddy current signals have been observed at the top of tube sheets. No denting has been observed so far in the B and W once-through steam generators. In all, some 14 plants are affected. Inconel 600 tube defects and leaks were first observed at Surry and Turkey Point, which were severely dented. The cracks originated from the primary side, and were found to be caused by primary side stress corrosion cracking of highly strained tubing. Some minor leaks have subsequently occurred in a few other steam generators. Suggestions are included of work to elucidate the quantitative aspects of stress corrosion cracking.
| Author | : Boen-dar Liaw |
| Publisher | : |
| Total Pages | : 56 |
| Release | : 1980 |
| Genre | : Nuclear power plants |
| ISBN | : |
| Author | : |
| Publisher | : |
| Total Pages | : 32 |
| Release | : 1996 |
| Genre | : |
| ISBN | : |
The degradation of steam generator tubes in pressurized water nuclear reactors continues to be a serious problem. Primary water stress corrosion cracking is commonly observed at the roll transition zone at U-bends, at tube denting locations, and occasionally in plugs and sleeves. Outer-diameter stress corrosion cracking and intergranular attack commonly occur near the tube support plate crevice, near the tube sheet in crevices or under sludge piles, and occasionally in the free span. A particularly troubling recent trend has been the increasing occurrence of circumferential cracking at the RTZ on both the primary and secondary sides. Segmented axial cracking at the tubes support plate crevices is also becoming more common. Despite recent advances in in-service inspection technology, a clear need still exists for quantifying and improving the reliability of in- service inspection methods with respect to the probability of detection of the various types of flaws and their accurate sizing. Improved inspection technology and the increasing occurrence of such degradation modes as circumferential cracking, intergranular attack, and discontinuous axial cracking have led to the formulation of a new performance-based steam generator rule. This new rule would require the development and implementation of a steam generator management program that monitors tube condition against accepted performance criteria to ensure that the tubes perform the required safety function over the next operating cycle. The new steam generator rule will also be applied to severe accident conditions to determine the continued serviceability of a steam generator with degraded tubes in the event of a severe accident. Preliminary analyses are being performed for a hypothetical severe accident scenario to determine whether failure will occur first in the steam generator tubes, which would lead to containment bypass, or instead in the hot leg nozzle or surge line, which would not.
