A Review of Acoustic Vibration Criteria Compared to In-Service Experience With Steam Generator In-Line Tube Banks

1994 ◽  
Vol 116 (1) ◽  
pp. 17-23 ◽  
Author(s):  
F. L. Eisinger ◽  
R. E. Sullivan ◽  
J. T. Francis

Tube banks of operating steam generators were evaluated for resonant acoustic vibration in the transverse acoustic mode, using a number of published vibration criteria and a range of Strouhal numbers. Theoretical predictions based on computer simulations were compared to available experimental data for nonvibrating and vibrating banks. It is shown that large differences exist among the predictive methods, and most do not fully predict acoustic resonances. On a relative basis, prediction criteria of Y. N. Chen and Grotz and Arnold, with Fitzhugh-Strouhal numbers, offer the best results for steam generator tube banks.

1996 ◽  
Vol 118 (2) ◽  
pp. 221-236 ◽  
Author(s):  
F. L. Eisinger ◽  
J. T. Francis ◽  
R. E. Sullivan

Criteria are formulated for the development of acoustic vibration in transverse acoustic modes in steam generator tube banks, based on flow and acoustic parameters. Theoretical predictions are validated against available in-service data for nonvibrating and vibrating tube banks and published laboratory experimental data. The criteria can be used for the prediction of acoustic vibration in steam generator and heat exchanger tube banks both, in-line and staggered.


Author(s):  
Franktisek L. Eisinger ◽  
Robert E. Sullivan

Based on recent laboratory experimental data by Feenstra et al. [1],[2] it has been determined that for larger test section widths, the maximum acoustic pressures generated during acoustic resonance were greater by more than a factor of four than those predicted by Blevins and Bressler [3]. We have evaluated a great number of resonant and non-resonant cases from inservice experience of full size steam generator and tubular heat exchanger tube banks in order to see the general vibratory behavior of the full size units. Fifteen vibrating and twenty-seven non-vibrating cases were evaluated and compared to the Feenstra et al. relationship. It is shown that on average the results from the full size units correlate well with the Feenstra et al. relationship. A gap exists between the vibratory and the non-vibratory cases. The non-vibratory cases produce acoustic pressures which are at or below the Blevins and Bressler relationship. From the results it can be concluded that the full size units, regardless of their size and also acoustic mode, produce high acoustic pressures at resonance, with the maximum acoustic pressure on average more than fifty to seventy five times higher than the input energy parameter defined by the product of Mach number and pressure drop through the tube bank. The results are tabulated and plotted for comparison.


2008 ◽  
Vol 130 (3) ◽  
Author(s):  
Frantisek L. Eisinger ◽  
Robert E. Sullivan

Based on recent laboratory experimental data by Feenstra et al. (2004, “The Effects of Duct Width and Baffles on Acoustic Resonance in a Staggered Tube Array,” in Proceedings of the Eighth International Conference on Flow-Induced Vibration FIV 2004, E. de Langre and F. Axisa, eds., Paris France, Jul. 6–9, pp. 459–464; 2006, “A Study of Acoustic Resonance in a Staggered Tube Array,” ASME J. Pressure Vessel Technol., 128, pp. 533–540), it has been determined that for larger test section widths, the maximum acoustic pressures generated during acoustic resonance were greater by more than a factor of 4 than those predicted by Blevins and Bressler (1993, “Experiments on Acoustic Resonance in Heat Exchanger Tube Bundles,” J. Sound Vib., 164, 503–533). We have evaluated a great number of resonant and nonresonant cases from in-service experience of full size steam generator and tubular heat exchanger tube banks in order to see the general vibratory behavior of the full size units. Fifteen vibrating and twenty-seven nonvibrating cases were evaluated and compared to the Feenstra et al. relationship. It is shown that on average the results from the full size units correlate well with the relationship of Feenstra et al. A gap exists between the vibratory and the nonvibratory cases. The nonvibratory cases produce acoustic pressures, which are at or below the Blevins and Bressler relationship. From the results, it can be concluded that the full size units, regardless of their size and also acoustic mode, produce high acoustic pressures at resonance, with the maximum acoustic pressure on average more than 50–75 times higher than the input energy parameter defined by the product of Mach number and pressure drop through the tube bank. The results are tabulated and plotted for comparison.


Author(s):  
Frantisek L. Eisinger ◽  
Robert E. Sullivan

In the previous publications by Eisinger, F.L., Francis, J.T., and Sullivan, R.E., 1996, “Prediction of Acoustic Vibration in Steam Generator and Heat Exchanger Tube Banks”, ASME Journal of Pressure Vessel Technology, Vol. 118, pp. 221–236 and Eisinger, F.L. and Sullivan, R.E., 1996, “Experience with Unusual Acoustic Vibration in Heat Exchanger and Steam Generator Tube Banks”, Journal of Fluids and Structures, Vol. 10, pp. 99–107, prediction criteria for acoustic vibration or acoustic resonance were formulated utilizing flow and acoustic parameters derived from operating steam generator tube banks. Various parameters were used in those formulations, including the dominant parameter MΔp where M is the Mach number of the crossflow through the tube bank and Δp is the pressure drop through the tube bank. Here we present further evidence derived from operating experience of full size steam generator and tubular heat exchanger tube banks of which 19 experienced acoustic vibration or acoustic resonance and 27 experienced no vibration or no acoustic resonance within the operating flow range. The present data show that the decisive parameter predicting the acoustic vibration or acoustic resonance of a tube bank is the acoustic particle velocity. The acoustic particle velocity separates the acoustically vibrating banks from those non-vibrating very clearly. The behavior is demonstrated graphically showing the dimensionless acoustic particle velocity as a function of input energy parameter MΔp, Mach number M, Reynolds number Re and also Helmholtz number He = MS where S is the Strouhal number. This finding indicates that the acoustic particle velocity criterion shall be used in conjunction with the previously used criteria as the basis for the prediction of acoustic resonance in full size steam generator and tubular heat exchanger tube banks.


Author(s):  
Mitch Hokazono ◽  
Clayton T. Smith

Integral light-water reactor designs propose the use of steam generators located within the reactor vessel. Steam generator tubes in these designs must withstand external pressure loadings to prevent buckling, which is affected by material strength, fabrication techniques, chemical environment and tube geometry. Experience with fired tube boilers has shown that buckling in boiler tubes is greatly alleviated by controlling ovality in bends when the tubes are fabricated. Light water reactor steam generator pressures will not cause a buckling problem in steam generators with reasonable fabrication limits on tube ovality and wall thinning. Utilizing existing Code rules, there is a significant design margin, even for the maximum differential pressure case. With reasonable bend design and fabrication limits the helical steam generator thermodynamic advantages can be realized without a buckling concern. This paper describes a theoretical methodology for determining allowable external pressure for steam generator tubes subject to tube ovality based on ASME Section III Code Case N-759-2 rules. A parametric study of the results of this methodology applied to an elliptical cross section with varying wall thicknesses, tube diameters, and ovality values is also presented.


Author(s):  
Akber Pasha

In recent years the combined cycle has become a very attractive power plant arrangement because of its high cycle efficiency, short order-to-on-line time and flexibility in the sizing when compared to conventional steam power plants. However, optimization of the cycle and selection of combined cycle equipment has become more complex because the three major components, Gas Turbine, Heat Recovery Steam Generator and Steam Turbine, are often designed and built by different manufacturers. Heat Recovery Steam Generators are classified into two major categories — 1) Natural Circulation and 2) Forced Circulation. Both circulation designs have certain advantages, disadvantages and limitations. This paper analyzes various factors including; availability, start-up, gas turbine exhaust conditions, reliability, space requirements, etc., which are affected by the type of circulation and which in turn affect the design, price and performance of the Heat Recovery Steam Generator. Modern trends around the world are discussed and conclusions are drawn as to the best type of circulation for a Heat Recovery Steam Generator for combined cycle application.


Author(s):  
Salim El Bouzidi ◽  
Marwan Hassan ◽  
Jovica Riznic

Nuclear steam generators are critical components of nuclear power plants. Flow-Induced Vibrations (FIV) are a major threat to the operation of nuclear steam generators. The two main manifestations of FIV in heat exchangers are turbulence and fluidelastic instability, which would add mechanical energy to the system resulting in great levels of vibrations. The consequences on the operation of steam generators are premature wear of the tubes, as well as development of cracks that may leak radioactive heavy water. This paper investigates the effect of tube support clearance on crack propagation. A crack growth model is used to simulate the growth of Surface Flaws and Through-Wall Cracks of various initial sizes due to a wide range of support clearances. Leakage rates are predicted using a two-phase flow leakage model. Non-linear finite element analysis is used to simulate a full U-bend subjected to fluidelastic and turbulence forces. Monte Carlo Simulations are then used to conduct a probabilistic assessment of steam generator life due to crack development.


Author(s):  
A. D. Efanov ◽  
S. G. Kalyakin ◽  
A. V. Morozov ◽  
O. V. Remizov ◽  
A. A. Tsyganok ◽  
...  

In new Russian NPP with VVER-1200 reactor (V-392M reactor plant) in the event of an accident being due to the rupture of the reactor primary circuit and accompanied by the loss of a.c. sources, provision is made for the use of passive safety systems for necessary core cooling. Among these is passive heat removal system (PHRS). In the case of leakage in the primary circuit this system assures the transition of steam generators (SG) to operation in the mode of condensation of the primary circuit steam coming to SG piping from the reactor. As a result, the condensate from steam generators arrives at the core providing its additional cooling. To experimental investigation of the condensation mode of operation of VVER steam generator, a large scale HA2M-SG test rig was constructed. The test rig incorporates: tank-accumulator, equipped by steam supply system; SG model with volumetric-power scale is 1:46; PHRS heat exchanger simulator, cooling by process water. The rig main equipment connected by pipelines and equipped by valves. The elevations of the main equipment correspond to those of reactor project. The rig maximum operating parameters: steam pressure – 1.6 MPa, temperature – 200 Celsius degrees. Experiments at the HA2M-SG test rig have been performed to investigate condensation mode of operation of SG model at the pressure 0.4 MPa, correspond to VVER reactor pressure at the last stage of the beyond basis accident. The report presents the test procedure and the basic obtained test results.


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