Prediction of natural mixing in tightly packed 7-rod-bundles (p/d = 1.10)
Creators
- 1. Technische Univ. Braunschweig (Germany, F.R.). Inst. fuer Raumflug- und Reaktortechnik
Description
The predicted fine structure of flow within a 7-rod-bundle at fixed rod-to-rod gap distance (p/d = 1.1) and at different rod bundle-to-wall distances are presented (NRe = 105; NPr ≅ 1.0). The numerical code VANTACY-II has been used to calculate the single phase, fully developed turbulent flow conditions in arbitrary 2-dimensional solution domains. The code includes a model of anisotropic turbulent exchange appropriate for tight lattices. The different rod-bundle boundary structures effect the fluid flow conditions, although the influence of the hydraulics on the temperature field is partly compensated by the turbulent microconvective heat transport between central and wall subchannels. In other words, the turbulent mixing depends to a great extent on the size and on the wetted perimeter of the edge region. (orig./DG)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1116-9
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 2
- Imprint Pagination
- 696 p.
- Journal Page Range
- p. 1294-1302.
Conference
- Title
- 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
- Dates
- 10-13 Oct 1989.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 22037769
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; FUEL ELEMENT CLUSTERS; HCLWR TYPE REACTORS; HYDRAULICS; MIXING; NUMERICAL SOLUTION; PWR TYPE REACTORS; REACTOR LATTICES; SHEAR PROPERTIES; SPACE DEPENDENCE; TEMPERATURE DISTRIBUTION; TURBULENT FLOW; VELOCITY
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; MECHANICAL PROPERTIES; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS