Scaling studies and conceptual experiment designs for NGNP CFD assessment [electronic resource]
The objective of this report is to document scaling studies and conceptual designs for flow and heat transfer experiments intended to assess CFD codes and their turbulence models proposed for application to prismatic NGNP concepts. The general approach of the project is to develop new benchmark expe...
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Office of the Assistant Secretary for Nuclear Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2004.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Scaling studies and conceptual experiment designs for NGNP CFD assessment |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Office of the Assistant Secretary for Nuclear Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 2004. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through SciTech Connect. | ||
| 500 | |a 11/01/2004. | ||
| 500 | |a "ineel/ext-04-02502" | ||
| 500 | |a D. M. McEligot; G. E. McCreery. | ||
| 520 | 3 | |a The objective of this report is to document scaling studies and conceptual designs for flow and heat transfer experiments intended to assess CFD codes and their turbulence models proposed for application to prismatic NGNP concepts. The general approach of the project is to develop new benchmark experiments for assessment in parallel with CFD and coupled CFD/systems code calculations for the same geometry. Two aspects of the complex flow in an NGNP are being addressed: (1) flow and thermal mixing in the lower plenum ("hot streaking" issue) and (2) turbulence and resulting temperature distributions in reactor cooling channels ("hot channel" issue). Current prismatic NGNP concepts are being examined to identify their proposed flow conditions and geometries over the range from normal operation to decay heat removal in a pressurized cooldown. Approximate analyses have been applied to determine key non-dimensional parameters and their magnitudes over this operating range. For normal operation, the flow in the coolant channels can be considered to be dominant turbulent forced convection with slight transverse property variation. In a pressurized cooldown (LOFA) simulation, the flow quickly becomes laminar with some possible buoyancy influences. The flow in the lower plenum can locally be considered to be a situation of multiple hot jets into a confined crossflow -- with obstructions. Flow is expected to be turbulent with momentumdominated turbulent jets entering; buoyancy influences are estimated to be negligible in normal full power operation. Experiments are needed for the combined features of the lower plenum flows. Missing from the typical jet experiments available are interactions with nearby circular posts and with vertical posts in the vicinity of vertical walls - with near stagnant surroundings at one extreme and significant crossflow at the other. Two types of heat transfer experiments are being considered. One addresses the "hot channel" problem, if necessary. The second type will treat heated jets entering a model plenum. Unheated MIR (Matched-Index-of-Refraction) experiments are first steps when the geometry is complicated. One does not want to use a computational technique which will not even handle constant properties properly. The purpose of the fluid dynamics experiments is to develop benchmark databases for the assessment of CFD solutions of the momentum equations, scalar mixing and turbulence models for typical NGNP plenum geometries in the limiting case of negligible buoyancy and constant fluid properties. As indicated by the scaling studies, in normal full power operation of a typical NGNP conceptual design, buoyancy influences should be negligible in the lower plenum. The MIR experiment will simulate flow features of the paths of jets as they mix in flowing through the array of posts in a lower plenum en route to the single exit duct. Conceptual designs for such experiments are described. | |
| 520 | 0 | |a Assessment; Cfd; Designs; Experiments; Ngnp; Studies. | |
| 536 | |b DE-AC07-99ID-13727. | ||
| 650 | 7 | |a After-Heat Removal. |2 local. | |
| 650 | 7 | |a Benchmarks. |2 local. | |
| 650 | 7 | |a Coolants. |2 local. | |
| 650 | 7 | |a Design. |2 local. | |
| 650 | 7 | |a Forced Convection. |2 local. | |
| 650 | 7 | |a Heat Transfer. |2 local. | |
| 650 | 7 | |a Scalars. |2 local. | |
| 650 | 7 | |a Geometry. |2 local. | |
| 650 | 7 | |a Temperature Distribution. |2 local. | |
| 650 | 7 | |a Simulation. |2 local. | |
| 650 | 7 | |a Turbulence. |2 local. | |
| 650 | 7 | |a - Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
| 710 | 2 | |a Idaho National Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Office of the Assistant Secretary for Nuclear Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
| 856 | 4 | 0 | |u http://www.osti.gov/scitech/biblio/911231 |z Online Access (via OSTI) |
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