Prediction of reflooding in single channels and partially-blocked rod bundes
Description
A mathematical model to investigate the influence of system parameters on the flow and heat transfer during reflooding is described. The model employs equations for momentum and enthalpy of vapour and liquid phases; correlations are used to determine fluid friction and heat transfer as functions of flow regime and local conditions. Calculations which predict a selection of the UKAEA REFLEX single -channel experiments are reported. These show the effects of pressure, heat generation, inlet subcooling and flow rate. Reasonably good agreement with experiment has been obtained. The three-dimensional flow in a partially-blocked rod bundle is also examined. Calculations for a geometry typical of current designs with flow and boundary values based on the PWR-FLECHT tests are reported. (orig.)
Additional details
Publishing Information
- Imprint Title
- 5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 3
- Imprint Pagination
- 736 p.
- Journal Page Range
- p. 1628-1636.
- Report number
- KFK--3880/3
Conference
- Title
- 5. international meeting on thermal nuclear reactor safety.
- Dates
- 9-13 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16068514
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORE FLOODING SYSTEMS; DIFFERENTIAL EQUATIONS; ECCS; FLOW BLOCKAGE; FLUID FLOW; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; FUEL ASSEMBLIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS