A. Dehbi
Paul Scherrer Institute
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Nuclear Engineering and Design | 1997
A. Dehbi; S Guentay
Some proposed vertical tube condensers are designed to operate at high noncondensable fractions, which warrants a simple model to predict their performance. Models developed thus far are usually not self-contained as they require the specification of the wall temperature to predict the local condensation rate. The present model attempts to fill this gap by addressing the secondary side heat transfer as well. Starting with a momentum balance which includes the effect of interfacial shear stress, a Nusselt-type algebraic equation is derived for the film thickness as a function of flow and geometry parameters. The heat and mass transfer analogy relations are then invoked to deduce the condensation rate of steam onto the tube wall. Lastly, the heat transfer to the secondary side is modelled to include cooling by forced, free or mixed convection flows. The model is used for parametric simulations to determine the impact on the condenser performance of important factors such as the inlet gas fraction, the mixture inlet flowrate, the total pressure, and the molecular weight of the noncondensable gas. The model performed simulations of some experiments with pure steam and air-steam mixtures flowing down a vertical tube. The model predicts the data quite well. The model described also provides a basis under which the presence of aerosol particles in the gas stream could be analyzed.
Nuclear Engineering and Design | 2001
A. Dehbi; D. Suckow; Salih Guentay
Abstract The POSEIDON-II experiments investigate the aerosol scrubbing by low-subcooling pools to provide data to help predictive models. The experiments consist of 17 tests which examine the dependence of the decontamination factor (DF) on water height, carrier gas steam mass fraction and particle diameter. Selected experiments demonstrate the competition of individual aerosol removal mechanisms such as impaction and condensation at the injection point. The DF is found to increase significantly with water height and steam mass fraction. The data show that important aerosol retention occurs in low-subcooling pools, and hence the standard assumption of zero decontamination in hot pools is overly conservative. The data also appreciably reduce the uncertainty in aerosol scrubbing estimates for shallow pools (
10th International Conference on Nuclear Engineering, Volume 2 | 2002
Salih Güntay; A. Dehbi; D. Suckow; Jon Birchley
Steam generator tube rupture (SGTR) incidents, such as those, which occurred in various operating pressurized, water reactors in the past, are serious operational concerns and remain among the most risk-dominant events. Although considerable efforts have been spent to understand tube degradation processes, develop improved modes of operation, and take preventative and corrective measures, SGTR incidents cannot be completely ruled out. Under certain conditions, high releases of radionuclides to the environment are possible during design basis accidents (DBA) and severe accidents. The severe accident codes’ models for aerosol retention in the secondary side of a steam generator (SG) have not been assessed against any experimental data, which means that the uncertainties in the source term following an unisolated SGTR concurrent with a severe accident are not currently quantified. The accident management (AM) procedures aim at avoiding or minimizing the release of fission products from the SG. The enhanced retention of activity within the SG defines the effectiveness of the accident management actions for the specific hardware characteristics and accident conditions of concern. A sound database on aerosol retention due to natural processes in the SG is not available, nor is an assessment of the effect of management actions on these processes. Hence, the effectiveness of the AM in SGTR events is not presently known. To help reduce uncertainties relating to SGTR issues, an experimental project, ARTIST (A eR osol T rapping I n a S team generaT or), has been initiated at the Paul Scherrer Institut to address aerosol and droplet retention in the various parts of the SG. The test section is comprised of a scaled-down tube bundle, a full-size separator and a full-size dryer unit. The project will study phenomena at the separate effect and integral levels and address AM issues in seven distinct phases: Aerosol retention in 1) the broken tube under dry secondary side conditions, 2) the near field close to break under dry conditions, 3) the bundle far-field under dry conditions, 4) the separator and dryer under dry conditions, 5) the bundle section under wet conditions, 6) droplet retention in the separator and dryer sections and 7) the overall SG (integral tests). Prototypical test parameters are selected to cover the range of conditions expected in severe accident as well as DBA scenarios. This paper summarizes the relevant issues and introduces the ARTIST facility and the provisional test program which will run between 2003 and 2007.Copyright
Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory | 2014
Roman Mukin; A. Dehbi
The main objective of the following work is to simulate flow in the secondary side of a steam generator (SG) tube bundle during tube rupture sequence using approaches for turbulence simulation. The interest in this topic stems from experimental findings at PSI in the framework of the ARTIST program (Aerosol Trapping in a Steam Generator) which show that particles that are injected into a dry SG tube bundle through a tube breach are principally retained in the region close to breach (the so-called “break-stage”). This region is characterized by highly non-uniform flow, with very high velocities near the breach, and low-velocity recirculating flow away from the breach. Owing to complexity of the flow, 3D simulations with highly resolved computational mesh near the breach were done. First, the flow inside an isolated tube with a guillotine tube breach has been studied. The next part is devoted to simulation of a gas jet entering the tube bundle SG via the guillotine tube breach. Comparison of the calculated flow with the experimental data of axial velocity distribution at different vertical levels have been performed, and we have found good agreement of the obtained results with the experiments.Copyright
12th International Conference on Nuclear Engineering, Volume 3 | 2004
S. Güntay; D. Suckow; A. Dehbi; R. Kapulla
ARTIST (A er osol T rapping I n a S team Generat or) is a seven-phase international project (2003–2007) which investigates aerosol and droplet retention in a model steam generator under dry, wet and accident management conditions, respectively. The test section is comprised of a scaled steam generator tube bundle consisting of 270 tubes and 3 stages, one 1:1 separator unit, and one 1:1 dryer unit. As a prelude to the ARTIST project, four tests are conducted in the ARTIST bundle within the 5th EU FWP SGTR. These first tests address aerosol deposition phenomena on two different scales: near the tube break, where the gas velocities are sonic, and far away from the break, where the flow velocities are three orders of magnitude lower. With a dry bundle and the full flow representing the break stage conditions, there is strong evidence that the TiO2 aerosols used (AMMD 2–4 μm, 32 nm primary particles) disintegrate into much smaller particles because of the sonic conditions at the break, hence promoting particle escape from the secondary and lowering the overall DF, which is found to be between 2.5 and 3. With a dry bundle and a small flow reproducing the far-field velocities, the overall bundle DF is of the order of 5, implying a DF of about 1.9 per stage. Extrapolating the results of the dry tests, it turns out that for steam generators with 9 or more stages, it is expected that substantial DF’s could be achieved when the break is located near the tube sheet region. In addition, better decontamination is expected using more representative proxies of severe accident aerosols (sticky, multicomponent particles), a topic which is yet to be investigated. When the bundle is flooded, the DF is between 45 and 5740, depending on the mass flow rate, the steam content, and the water submergence. The presence of steam in the carrier gas and subsequent condensation inside the broken tube causes aerosol deposition and blockages near the break, leading to an increase in the primary pressure. This has implications for real plant conditions, as aerosol deposits inside the broken tube will cause more flow to be diverted to the intact tubes, with a corresponding reduction in the source term to the secondary.© 2004 ASME
Nuclear Engineering and Design | 2004
S. Güntay; D. Suckow; A. Dehbi; R. Kapulla
Nuclear Engineering and Design | 2005
Ari Auvinen; J.K. Jokiniemi; A. Lähde; T. Routamo; P. Lundström; H. Tuomisto; J. Dienstbier; S. Güntay; D. Suckow; A. Dehbi; M. Slootman; L. Herranz; V. Peyres; J. Polo
Nuclear Engineering and Design | 2009
Y. Liao; Salih Guentay; D. Suckow; A. Dehbi
Nuclear Engineering and Design | 2013
Chris H. Rycroft; A. Dehbi; Terttaliisa Lind; S. Güntay
Nuclear Engineering and Design | 2010
Terttaliisa Lind; Yasmine Ammar; A. Dehbi; S. Güntay