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Steam generator tube rupture (SGTR) scenarios

Nuclear Engineering and Design, 2005
The steam generator tube rupture (SGTR) scenarios project was carried out in the EU 5th framework programme in the field of nuclear safety during years 2000–2002. The first objective of the project was to generate a comprehensive database on fission product retention in a steam generator. The second objective was to verify and develop predictive models
Auvinen, A., Jokiniemi, J.K., Lähde, A., Routamo, T., Lundström, P., Tuomisto, H., Dienstbier, J., Güntay, S., Suckow, D., Dehbi, A., Slootman, M., Herranz, L., Peyres, V., Polo, J.   +13 more
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Steam generator tube rupture scenarios (SGTR)

, 2003
The Steam Generator Tube Rupture (SGTR) scenarios project was carried out in the framework of the research and training programme, EURATOM, in the field of nuclear energy during years 2000-2002.
Lähde, Anna, Auvinen, Ari, Tuomisto, H., Routamo, T., Lundström, P., Dienstbier, J., Güntay, S, Suckow, Detlef, Dehbi, A., Slootman, M., Herranz, L., Peyres, V., Polo, J., Jokiniemi, Jorma   +14 more
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Integrity of VVER steam generator tubes

Theoretical and Applied Fracture Mechanics, 1995
Abstract The eddy-current inspection is applied to Vitkovice to non-destructive testing of the steam generator tubes. The steam generator tube specimens, 16 mm by 1.5 mm, are made of AISI 321 steel with stress corrosion cracks. They were tested by the single-frequency eddy current inspection method.
M. Wilam, I. Čermáková
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Flaw analysis in steam generator tubes

International Journal of Pressure Vessels and Piping, 1986
Abstract This paper presents the flaw assessment programme undertaken in France for PWR steam generator tubes affected by stress corrosion cracking. Failure criteria were deduced from burst tests on various crack configurations. Stresses and critical crack sizes were estimated for all operating conditions.
J.-P. Hutin, F. Billon
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Damping of Steam Generator Tubes

Flow-Induced Vibration, 2003
The flow-induced vibration (FIV) analysis is one of the most critical evaluations needed to ensure long-term operation of steam generator. Original design hardware is usually based on experience and testing. Performance changes, such as an increase in power with increased feedwater flow, or tube repairs including plugs, stabilizers, and sleeves are ...
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Selection of Tube Samples for Inservice Inspection of Steam Generator Tubes

Volume 7: Operations, Applications, and Components, 2005
In Pressurized Water Reactors, a program of periodic inservice inspection of steam generator tubes is set up to monitor the integrity of the tubes. The inservice inspection is performed using nondestructive examination techniques, e.g., eddy current testing.
Guy Roussel, Leon Cizelj
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Factors Affecting Steam Generator Tube Bow

Volume 3: Design and Analysis, 2013
One of the challenges in straight shell-and-tube Steam Generator design is to avoid the tube to tube wear that can arise during operation due to higher than anticipated compressive tube loads and the resulting tube bow that can occur. Tube bow becomes significant when the compressive load in the tube exceeds its critical buckling capacity.
Moli Cao, Jennifer Nelson, Hasan Charkas, Timothy Wiger   +3 more
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Cracking in a Steam Generator U-Tube

2019
Abstract A rupture of a thirty-year-old U-tube on a steam generator for a closed-cycle pressurized-water nuclear power plant occurred, resulting in limited release of reactor water. A typical tube bundle can be over 9 m (30 ft) tall and 3 m (10 ft) in diam with over 3,000 22-mm (7/8-in.) diam Inconel Alloy 600 tubes. Tube support plates (
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Intergranular Fracture of Steam Generator Tubes

2019
Abstract A power plant using two steam generators (vertical U-tube and shell heat exchangers, approximately 21 m (68 ft) high with a steam drum diameter of 6 m (20 ft)) experienced a steam generator tube rupture. Each steam generator contained 11,012 Inconel alloy 600 (nickel-base alloy) tubes measuring 19 mm OD, nominal wall thickness ...
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Steam generator tube vibration tests

Nuclear Engineering and Design, 1985
Abstract The buildup of magnetite in the steam generators of some pressurized water reactors had led operators to propose chemical cleaning to remove this product. In some cases, the volume of magnetite formed by the corrosion of the carbon steel has been sufficient to cause “denting” or reduction of the outer diameter of the tubes where they pass ...
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