Pressure drop measurements at the KNK II annular fuel element with replaceable test bundles TOAST
Description
An annular fuel element with replaceable 19-pin test bundles for the Tolerance Enlargement Study TOAST is planned to be operated in the third core of KNK II. Due to different reasons, the up to now used coolant mixing devices in the element head and the element foot had to be revised. Therefore the pressure drops had to be measured again to support the thermal-hydraulic design of this special subassembly and its individual components. Additionally the hydraulic suppression of the test bundle in the annular element had to be demonstrated. In parallel to that, measurements with models of original size were performed in the water circuit of the IRB. The following results can be pointed out: 1. The pressure drop of 0.2 bar of the modified mixing head at nominal flow is comparable to that of the previous design. 2. The measured total pressure drop of the annular element with test bundle is 1.37 bar at nominal flow. It agrees within 3 % with the precalculated value. The sufficiently exact precalculation of the orifices in the test bundle and the coolant partition have been confirmed also by the experiments. 3. The hydraulic suppression of the test bundle in the annular element and consequently of the total subassembly in the core assembly is guaranteed
Availability note (English)
Available from INIS in electronic form
Files
Additional details
Additional titles
- Original title (German)
- Druckverlustmessungen am KNK II Ringbrennelement mit auswechselbaren Testbuendeln TOAST
Publishing Information
- Imprint Pagination
- 35 p.
- Report number
- KFK-PSB--01.01.02P15A
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34087752
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- ANNULAR FUEL ELEMENTS; FLUID FLOW; FUEL ELEMENT CLUSTERS; KNK-2 REACTOR; PRESSURE DROP; PRESSURE MEASUREMENT; REACTOR EXPERIMENTAL FACILITIES; RELOADABLE FUEL ASSEMBLIES; REPLACEABLE FUEL ASSEMBLIES; SAFETY ANALYSIS; THERMAL HYDRAULICS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENTS; HYDRAULICS; HYDRIDE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SZR TYPE REACTORS
Optional Information
- Notes
- refs, tabs, figs
- Secondary number(s)
- INIS-DE-PSB--037