Published 2012
| Version v1
Miscellaneous
Videometric void measurement in counter-current and stratified tow-phase flows
Creators
- 1. Karlsruher Institut fuer Technologie (Germany). Inst. fuer Kern- und Energietechnik
- 2. Stuttgart Univ. (Germany). Inst. fuer Kernenergetik und Energiesysteme
Description
Due to a small leak (SBLOCA) in the cold leg of a PWR reactor with long failure of all coolant injection systems the reflux condenser mode can be important. This can occur if due to the loss of coolant only steam from the upper plenum flows into the hot leg into the steam generator. The steam condensate and flows at least partially back through the hot leg into the reactor pressure vessel (RPV). This counter-current two-phase flow in the hot leg can induce flow instabilities that impede the backflow of the water into the RPV. This counter-current flow limitation (CCFL) phenomenon is studied by a new videometric method. The determination of the local gas volume fraction was compared with electrical contact probe measurements.
Additional details
Additional titles
- Original title (German)
- Videometrische Void-Messung in entgegen gerichteter und geschichteter Zweiphasenstroemung
Publishing Information
- Imprint Title
- Annual meeting on nuclear technology 2012. Documentation
- Imprint Pagination
- 1411 p.
- Journal Page Range
- 7 p.
Conference
- Title
- Annual meeting on nuclear technology 2012
- Original Conference Title
- Jahrestagung Kerntechnik 2012
- Dates
- 22-24 May 2012
- Place
- Stuttgart (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 43117150
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COUNTER CURRENT; COUNTERFLOW SYSTEMS; FLOW MODELS; FLOW VISUALIZATION; LOSS OF COOLANT; MEASURING METHODS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR VESSELS; STRATIFICATION; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; FLUID FLOW; MATHEMATICAL MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2012. Dokumentation