BR 2 bundle mockup heat transfer experiments
- 1. Kernforschungszentrum Karlsruhe (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik
Description
Heat transfer calibration tests on helium cooled bundles of 12 artificially roughened rods have been performed, with the purpose of obtaining information for the thermo-hydraulic design of the 12-rod bundle fuel element to be irradiated in BR2. The rods were electrically heated. Altogether 50 isothermal and 110 non-isothermal runs were performed. The maximum achieved rod linear power was 460 W/cm, the maximum measured wall temperature was 7900C. The code SAGAPO was developed to predict the thermodynamic performance of such clusters. This paper describes the measurements performed, the experimental set-up and the fundamentals of the SAGAPO code. The main results of the calculations performed with SAGAPO for the BR2 irradiation experiment are also given. (Auth.)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 40
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 143-156
- ISSN
- 0029-5493
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 8311056
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BR-02 REACTOR; CALIBRATION; COOLANTS; FUEL ELEMENT CLUSTERS; FUEL RODS; HEAT TRANSFER; HELIUM; HYDRAULICS; MOCKUP; PERFORMANCE; ROUGHNESS; S CODES; THERMODYNAMIC PROPERTIES
- Descriptors DEC
- BERYLLIUM MODERATED REACTORS; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; METAL MODERATED REACTORS; NONMETALS; PHYSICAL PROPERTIES; RARE GASES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STRUCTURAL MODELS; SURFACE PROPERTIES; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
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