Published December 1999
| Version v1
Report
Temperature field in the downcomer of the UM 2x4 experimental loop facility, University of Maryland, USA. International Standard Problem ISP-43, Tests A and B
Description
The first results of pre-test calculations of 2 experiments performed on the title facility are presented. The experiments addressed the issue of the mixing of 2 streams of coolant having different temperatures in a model of the nuclear reactor downcomer. They simulated processes occurring during the dilution of boron in the primary coolant circuit. The calculations, which were performed by using the FLUENT 5.0 code, provided the coolant temperature values in 185 points of the downcomer
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.czAdditional details
Additional titles
- Original title (Czech)
- Teplotni pole v sestupne sachte experimentalniho zarizeni UM 2x4 Loop Facility, University of Maryland, USA. Mezinarodni standardni problem ISP-43, testy A a B
Publishing Information
- Imprint Pagination
- 48 p.
- Report number
- UJV--11348-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 36101199
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLANT LOOPS; F CODES; FLOW MODELS; FLUID FLOW; FLUID MECHANICS; MIXING; PRIMARY COOLANT CIRCUITS; TEMPERATURE DISTRIBUTION; UMNE-1 REACTOR
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICAL MODELS; MECHANICS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 tab., 41 figs., 10 refs.