Published September 1977
| Version v1
Report
Restricted
Investigation of the coolant flow distribution in a pressurized water reactor
Creators
- 1. Kraftwerk Union A.G., Erlangen (Germany, F.R.)
Description
The coolant flow distribution of the nuclear power station Stade was measured with a model in the scale 1:7, using water at a temperature of 600C and flow masses up to 1,000 t/h. The flow distribution in the core of the reactor model was measured with different stagnation plates; some tests were run with asymmetric coolant recirculation (3-loop or 2-loop operation). (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
An einem im Massstab 1:7 ausgefuehrten Modell des Reaktors des Kernkraftwerks Stade wurden Stroemungs-Untersuchungen mit Wasser bei 600C und Durchsatzmengen bis zu 1.000 t/h durchgefuehrt. Die Kuehlmitteldurchsatzverteilung wurde im Kern des Reaktormodells mit verschiedenen Stauplatten vor der Kerneintrittsseite gemessen; ausserdem wurden Versuche mit unsymmetrischer Kuehlmittelzufuhr (3-Kreis und 2-Kreisbetrieb) durchgefuehrt. (orig.)
Files
Additional details
Additional titles
- Original title (German)
- Untersuchung der Stroemungsverhaeltnisse in einem Druckwasserreaktor
Publishing Information
- Imprint Pagination
- 32 p.
- Report number
- BMFT-FB-K--77-14
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 9376506
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- COOLANTS; DISTRIBUTION; FLOW MODELS; LIQUID FLOW; MASS TRANSFER; MEDIUM TEMPERATURE; MOCKUP; REACTOR CORES; STADE REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID FLOW; MATHEMATICAL MODELS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 24 figs.; 1 tab.