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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
openaire   +1 more source

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 ...
openaire   +1 more source

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
openaire   +1 more source

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   +3 more
openaire   +1 more source

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 (
openaire   +1 more source

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 ...
openaire   +1 more source

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 ...
openaire   +1 more source

Reliability of Steam Generator Tubes With Axial Cracks

Journal of Pressure Vessel Technology, 1996
An approach for estimating the failure probability of tubes containing through-wall axial cracks has already been proposed by the authors. It is based on probabilistic fracture mechanics and accounts for scatter in tube geometry and material properties, scatter in residual and operational stresses responsible for crack propagation, and characteristics ...
L. Cizelj, B. Mavko, P. Vencelj
openaire   +1 more source

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   +3 more
openaire   +1 more source

Development of stabilizers for steam generator tube repair

Nuclear Engineering and Design, 1987
Abstract Fluidelastic stability, turbulence-induced and vortex-induced vibration analysis of different types of stabilizers for repairing steam generator tubes are presented. The performances of the different designs are compared with that of a common basis — the virgin tube.
openaire   +1 more source

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