Rehme correlation for spacer pressure drop compared to XT-ADS rod bundle simulations and water experiment
Creators
- 1. Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany). Inst. for Nuclear and Energy Technologies
Description
The Rehme correlation is the most common formula to estimate the pressure drop of spacers in the design phase of new bundle geometries. It is based on considerations of momentum losses and takes into account the obstruction of the flow cross section but it ignores the geometric details of the spacer design. Within the framework of accelerator driven sub-critical reactor systems (ADS), heavy-liquid-metal (HLM) cooled fuel assemblies are considered. At the KArlsruhe Liquid metal LAboratory (KALLA) of the Karlsruhe Institute of Technology a series of experiments to quantify both pressure losses and heat transfer in HLM-cooled rod bundles are performed. The present study compares simulation results obtained with the commercial CFD code Star-CCM to experiments and the Rehme correlation. It can be shown that the Rehme correlation, simulations and experiments all yield similar trends, but quantitative predictions can only be delivered by the CFD which takes into account the full geometric details of the spacer geometry. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2011. Dokumentation
Publishing Information
- Imprint Title
- Annual meeting on nuclear technology 2011. Documentation
- Imprint Pagination
- 870 p.
- Journal Page Range
- 5 p.
Conference
- Title
- Annual meeting on nuclear technology 2011
- Original Conference Title
- Jahrestagung Kerntechnik 2011
- Dates
- 17-19 May 2011
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42106277
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTROL ELEMENTS; DESIGN; FLUID MECHANICS; FUEL ASSEMBLIES; GEOMETRY; NUMERICAL ANALYSIS; PRESSURE DROP; REACTOR CORES; REACTOR PROTECTION SYSTEMS; SAFETY ENGINEERING; SPACERS; SUBCRITICAL ASSEMBLIES
- Descriptors DEC
- ENGINEERED SAFETY SYSTEMS; ENGINEERING; EXPERIMENTAL REACTORS; MATHEMATICS; MECHANICS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2011. Dokumentation