Unsteady RANS analysis of CNL corium convection experiment
- 1. McMaster University, Hamilton, Ontario (Canada)
Description
In the event of a severe accident, it is essential to maintain radiological material within the calandria vessel. Thermal stresses at the vessel wall have been identified as a dominant failure mechanism. There is therefore a need to analyze the heat transfer processes in the molten corium to determine if the heat removal at the exterior of the vessel wall is sufficient to maintain vessel integrity. The current research uses computational fluid dynamics (CFD) to simulate the natural convection flows and crust formation within the molten corium, including the conjugate heat transfer at the vessel wall. Unsteady Reynolds Averaged Navier-Stokes (RANS) is used to model the effects of turbulence in the fluid. This paper presents the results of a validation study on a 1/5 scale CANDU calandria vessel using molten salts as the corium simulant. Numerical predictions are compared to the experimental results provided by Canadian Nuclear Laboratories (CNL). (author)
Availability note (English)
Available from the Canadian Nuclear Society, Toronto, Ontario (Canada).Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- Imprint Title
- Enabling net zero carbon emissions through clean nuclear power. 40th Annual CNS conference and 45th CNS/CNA student conference (virtual)
- Imprint Pagination
- vp.
- Journal Page Range
- [5 p.]
- Report number
- INIS-CA--0016
Conference
- Title
- 40. Annual Canadian Nuclear Society Conference (Virtual); 45. Annual CNS/CNA Student Conference (Virtual)
- Dates
- 6-9 Jun 2021
- Place
- Toronto (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 53064605
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CORIUM; FLUID MECHANICS; NATURAL CONVECTION; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; MASS TRANSFER; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- 14 refs., 4 figs.