CANDU 6 fuel channel thermal hydraulics analysis: comparison between CANFLEX bundle and 37-element bundle
Creators
- 1. Power Engineering Faculty, Bucharest Politehnica University, 313 Splaiul Independentei, RO-060032, Bucharest 16 (RO)
Description
The paper describes a thermal-hydraulics analysis of a CANDU 6 fuel channel for two different cases: the channel is fueled with the 37 elements bundle and the channel is fuelled with the CANFLEX bundle. The analysis is performed using the RELAP5/SCADAP mod3.4 code. For each case pressure and temperature at inlet header, pressure and temperature at outlet header and channel power represent the boundary conditions. The RELAP 5 model consists in an inlet feeder modeled as a pipe component with 20 volumes, inlet end fitting, fuel channel modeled as a pipe component with 12 volumes, outlet end fitting and outlet feeder modeled as a pipe component with 21 volumes. The paper presents results obtained for transients representative for loss of coolant accident. (authors)
Availability note (English)
Available from authors or Power Engineering Faculty, Bucharest Politehnica University, 313 Splaiul Independentei, RO-060032, Bucharest 16 (RO)Additional details
Publishing Information
- Publisher
- Editura Universul Energiei
- Imprint Place
- Bucharest (Romania)
- Imprint Title
- International Conference on Energy-Environment, CIEM 2005
- Imprint Pagination
- 615 p.
- Journal Page Range
- p. 6.7-6.12
Conference
- Title
- international conference on energy-environment
- Acronym
- CIEM 2005
- Dates
- 20-21 Oct 2005
- Place
- Bucharest (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 36114894
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; LOSS OF COOLANT; PIPE FITTINGS; PIPES; PRESSURE DEPENDENCE; R CODES; SIMULATION; TEMPERATURE DEPENDENCE; THERMAL HYDRAULICS; TRANSIENTS; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; FLUID MECHANICS; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MECHANICS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TUBES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 4 refs., 7 figs.