Results 241 to 250 of about 36,185 (292)

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, Ari, Jokiniemi, Jorma K., Lähde, Anna, Routamo, Tomi, Lundström, P., Tuomisto, H., Dienstbier, J., Güntay, S., Suckow, Detlef, Dehbi, A., Slootman, M., Herranz, L., Peyres, V., Polo, J.   +13 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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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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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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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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Leak-before-break in steam generator tubes

International Journal of Pressure Vessels and Piping, 1990
Abstract The steam generator tubing constitutes one of the main barriers against the release of activity to the environment. The capacity of the tubing to withstand safely the loads exerted on it during normal operation and faulted conditions is therefore the most important factor in steam generator safety evaluation.
B. Flesch, B. Cochet
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Vibration Damping of Stabilized Steam-Generator Tubes

Volume 4: Fluid Structure Interaction, 2005
The integrity of steam-generator tubes is an important aspect of the long-term reliable operation of nuclear power plants. In situations where a tube is judged to be at risk, it must be either plugged, or removed, or reliably stabilized in some manner to avoid excessive motion of the tube due to flow-induced vibration.
V. P. Janzen, Y. Han, B. A. W. Smith, S. M. Fluit   +3 more
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Ginna Steam Generator Tube Rupture

1984
At 9:25 a. m. on January 25, 1982, a single steam generator tube ruptured in the “B” steam generator at the R. E. Ginna Nuclear Power Plant. Prior to the incident, the plant, a two-loop Westinghouse design, had been operating at full power with no indications of primary to secondary leakage.
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Inner tube optimization of double-tube once-through steam generator

International Journal of Heat and Mass Transfer, 2013
Abstract We present a double-tube once-through steam generator (DOTSG) with an outer straight tube and an inner helical tube in this paper. For the purpose of the compact structure and lower pressure drop, the inner helical tube is optimized. The tube length and the combined pressure drop are considered as the two objective functions, and the pitch ...
Xinyu Wei, Chunhui Dai, Li Wang, Fuyu Zhao   +3 more
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