Investigation of slightly forced buoyant flow in a training reactor
Creators
- 1. Nuklear Technikai Intezet, Budapesti Muszaki es Gazdasagtudomanyi Egyetem (Hungary)
Description
A measurement based on the temperature noise analysis method was carried out in the Training Reactor of the Budapest University of Technology and Economics. The main goals were the estimation of the flow velocity immediately above the reactor core and investigation of the thermal-hydraulical conditions of the reactor, mainly in the core. Subsequently 2D and 3D computations were carried out with the aid of the code CFX- 4.3. The main objective of the 2D calculation was to clarify the thermal-hydraulical conditions of the whole reactor tank with a reasonable computing demand. It was also necessary to accomplish 3D numerical investigations of the reactor core and the space above since three dimensional effects of the flow could only be studied in this way. In addition, obtaining certain boundary conditions of the 3D computations was another significant aim of the 2D investigations. It is important that the results of the noise analysis and the operational measuring system of the reactor gave us a basis for verifying our computations.(author)
Files
35095322.pdf
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Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-6207-17-2
- Imprint Title
- Proceedings of the International Conference Nuclear Energy in Central Europe 2001
- Imprint Pagination
- 97.2 Megabytes
- Journal Page Range
- [8 p.]
- Report number
- INIS-SI--04-001
Conference
- Title
- International Conference Nuclear Energy in Central Europe 2001
- Dates
- 10-13 Sep 2001
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 35095322
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUDAPEST TRAINING REACTOR; C CODES; COMPUTER CALCULATIONS; FLUID FLOW; NUMERICAL ANALYSIS; REACTOR CORES; TEMPERATURE NOISE; THERMAL HYDRAULICS; TRAINING REACTORS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MATHEMATICS; MECHANICS; NOISE; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWR TYPE REACTORS
Optional Information
- Notes
- 4 refs., 1 tab., 6 figs. Imprint:702 refs., 125 tabs., 526 figs.