Integrated aerosol and thermalhydraulics modelling for CANDU safety analysis
Description
Analysis of postulated accidents in CANDU reactors that could result in severe fuel damage requires the ability to model the formation of aerosols containing fission product materials and the transport of these aerosols from the fuel, through containment, to any leak to the atmosphere. Best-estimate calculations require intimate coupling and simultaneous solution of all the equations describing the entire range of physical and chemical phenomena involved. The prototype CATHENA/PACE-3D has been developed for integrated calculation of thermalhydraulic and aerosol events in a CANDU reactor during postulated accidents. Examples demonstrate the ability of CATHENA/PACE-3D to produce realistic flow and circulation patterns and reasonable accuracy in solution of two simple fluid-flow test cases for which analytical solutions exist
Availability note (English)
MF available from INIS under the Report Number.Files
23002191.pdf
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Additional details
Additional titles
- Augmented title (English)
- CATHENA and PACE codes
Publishing Information
- Imprint Pagination
- 30 p.
- Report number
- AECL--10167
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 23002191
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AEROSOLS; C CODES; CANDU TYPE REACTORS; CONTAINMENT BUILDINGS; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; HEAT TRANSFER; P CODES; PRIMARY COOLANT CIRCUITS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BUILDINGS; COLLOIDS; COMPUTER CODES; CONTAINMENT; COOLING SYSTEMS; DISPERSIONS; ENERGY TRANSFER; FLUID FLOW; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SOLS; THERMAL REACTORS