Published 1980
| Version v1
Report
Thermal diffusivity measurements of recirculating flows to validate model tests for liquid metal reactors
Description
Before data from water model tests can be applied to sodium-cooled reactors, a lower limit for Reynolds number to give thermal similarity must be established. A route for determining this is to infer the turbulent diffusivity of heat for water and sodium in the relevant geometry by comparing measured temperature profiles to those predicted by a numerical code. Such a code has been developed, based on the finite element method, and its predictions of velocity and temperature fields compared with measurements made in a simple axisymmetric pipe expansion. Initial results are encouraging, but show the need for further refinement of the turbulence model
Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Title
- Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods
- Journal Page Range
- p. 1818-1835.
- Report number
- NUREG/CP--0014(Vol.3)
Conference
- Title
- ANS/ASME topical meeting on reactor thermal-hydraulics.
- Dates
- 9 - 12 Oct 1980.
- Place
- Saratoga, NY, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13665787
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR CORES; SPATIAL DISTRIBUTION; THERMAL DIFFUSIVITY; TURBULENT FLOW
- Descriptors DEC
- BREEDER REACTORS; DISTRIBUTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; LIQUID METAL COOLED REACTORS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC PROPERTIES