Direct numerical simulation for laminarization of turbulent forced gas flows in circular tubes with strong heating

Satake, Shin‐ichi; Kunugi, Tomoaki; Shehata, A. Mohsen; McEligot, Donald M.

doi:10.1016/s0142-727x(00)00041-2

Cited by 51 publications

(33 citation statements)

References 14 publications

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“…Hence, objectives are to measure the fundamental turbulence structure and to obtain benchmark data to assess CTFD codes at conditions in the range of ALWRs and SCRs. Conceptually, DNS codes, as by Satake et al [2000] or You, Yoo and Choi [2003], could accomplish these aims and more; however, DNS calculations must also be compared to timeresolved experimental measurements to insure adequate spatial and temporal resolutions, to uncover coding mistakes, to check for prediction of measurable quantities and consistent, useful definitions of those quantities, etc.…”

Section: -41+mentioning

confidence: 99%

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors

McEligot¹,

Condie²,

McCreery³

et al. 2005

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Section: -41+mentioning

confidence: 99%

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors

McEligot¹,

Condie²,

McCreery³

et al. 2005

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“…However, most turbulence models employed in these codes fail to give adequate heat transfer predictions for the simplest internal flows [Mikielewicz et al, 2002]. Direct Numerical Simulations should give reasonable predictions, particularly at low Reynolds numbers --but only recently have these techniques been extended to gas flows with property variation [Satake et al, 2000].…”

Section: Before They Can Be Applied With Confidence To Gas-cooled Sysmentioning

confidence: 99%

“…The treatment was further extended to include solution of the energy equation for a circular tube [Satake and Kunugi, 1998c]; three thermal boundary conditions were considered: uniform heat flux, a cosine distribution and circumferentially nonuniform wall temperature. Preliminary calculations were accomplished with full gas property variation using the properties of air [Satake et al, 2000].…”

Section: Before They Can Be Applied With Confidence To Gas-cooled Sysmentioning

confidence: 99%

Fundamental Thermal Fluid Physics of High Temperature Flows in Advanced Reactor Systems - Nuclear Energy Research Initiative Program Interoffice Work Order (IWO) MSF99-0254 Final Report for Period 1 August 1999 to 31 December 2002

McEligot¹,

Condie²,

Foust³

et al. 2002

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IntroductionBackground The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of advanced reactors for higher efficiency and enhanced safety and for deployable reactors for electrical power generation, process heat utilization and hydrogen generation. While key applications would be advanced gas-cooled reactors (AGCRs) using the closed Brayton cycle (CBC) for higher efficiency (such as the proposed Gas Turbine -Modular Helium Reactor (GT-MHR) of General Atomics [Neylan and Simon, 1996]), results of the proposed research should also be valuable in reactor systems with supercritical flow or superheated vapors, e.g., steam. Higher efficiency leads to lower cost/kwh and reduces life-cycle impacts of radioactive waste (by reducing waste/kwh). The outcome will also be useful for some space power and propulsion concepts and for some fusion reactor concepts as side benefits, but they are not the thrusts of the investigation. The objective of the project is to provide fundamental thermal fluid physics knowledge and measurements necessary for the development of the improved methods for the applications.

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“…They have also been obtaining data for the related problem of turbulence structure in the viscous layers of flows with strongly favorable pressure gradients [Chambers, Murphy and McEligot, 1983;McEligot and Eckelmann, 1993]. Direct numerical simulations by Japanese colleagues [Satake et al, 2000] have now been applied to the laminarizing data of Shehata and McEligot. For the present hypothetical concept, design flow rates are expected to give tube Reynolds numbers between 2500 and 5000. Tabulated LDV data for mean and rms axial velocities are available from Lekakis for pipe flow at Re 4130 [Durst et al, 1996] and Satake et al [2000] have direct numerical simulations at Re 4300, corresponding to the inlet conditions of Shehata and McEligot [1998].…”

Section: Related Workmentioning

confidence: 99%

Measurements of Fundamental Fluid Physics of SNF Storage Canisters

Condie¹,

Creery²,

McEligot³

2001

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SummaryWith the University of Idaho, Ohio State University and Clarksean Associates, this research program has the long-term goal to develop reliable predictive techniques for the energy, mass and momentum transfer plus chemical reactions in drying / passivation (surface oxidation) operations in the transfer and storage of spent nuclear fuel (SNF) from wet to dry storage. Such techniques are needed to assist in design of future transfer and storage systems, prediction of the performance of existing and proposed systems and safety (re)evaluation of systems as necessary at later dates.Many fuel element geometries and configurations are accommodated in the storage of spent nuclear fuel. Consequently, there is no one generic fuel element / assembly, storage basket or canister and, therefore, no single generic fuel storage configuration. One can, however, identify generic flow phenomena or processes which may be present during drying or passivation in SNF canisters. The objective of the INEEL tasks was to obtain fundamental measurements of these flow processes in appropriate parameter ranges.With the University of Idaho, an idealization of a combined drying and passivation approach has been defined in order to investigate the generic flow processes. This simulation includes flow phenomena that occur in canisters for high-enrichment and medium-enrichment fuels, where fuel element spacing in the canister is increased as compared with low enrichment fuel. Canister diameter was taken as 46 cm (18 in.) and a single basket of about 1.3 meters (4 ft.) length was considered. A long central tube ("dip tube") served as the inlet as in one earlier concept for a passivation process; while this concept apparently has not yet been selected for application, it provides an excellent example of the coupled, complex phenomena which may be present in canister flows. Suggested design flow rates for this hypothesized application indicate that the Reynolds number in the inlet tube would be expected to be between 2500 and 5000, i.e., relatively low.The local distributions of convective mass transfer characteristics (drying/passivation) are expected to depend on the freestream turbulence in the flow around stored fuel elements. The magnitudes of this turbulence depend on the turbulence distributions on the upstream side of the perforated basket support plate ("inlet plenum") and, in turn, in the impinging jet and in the inlet tube. This information can assist engineers in understanding variations of surface drying and passivation through an array and approaches to modify designs to counter non-uniformities and to improve iii distribution, as well as providing bases for assessment of computational fluid dynamics codes proposed for the purpose.A water-flow experiment with a 3/4-scale model (relative to the idealized canister) has been used for overall flow visualization and velocity measurements, with and without an array of simulated fuel elements. Observations have been made with perforated plates (representing basket support plates) having...

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Direct numerical simulation for laminarization of turbulent forced gas flows in circular tubes with strong heating

Cited by 51 publications

References 14 publications

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors

Fundamental Thermal Fluid Physics of High Temperature Flows in Advanced Reactor Systems - Nuclear Energy Research Initiative Program Interoffice Work Order (IWO) MSF99-0254 Final Report for Period 1 August 1999 to 31 December 2002

Measurements of Fundamental Fluid Physics of SNF Storage Canisters

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