CFD simulations of the single-phase and two-phase coolant flow of water inside the original and modified CANDU 37-element bundles
Creators
- 1. Stern Laboratories, Hamilton, Ontario (Canada)
Description
Single-phase (inlet temperature of 180° C, outlet pressure of 9 MPa, total power of 2 MW and flow rate of 13.5 Kg/s), and two-phase (inlet temperature of 265° C, outlet pressure of 10 MPa, total power of 7.126 MW and flow rate of 19 Kg/s) water flows inside a CANDU thirty seven element fuel string are simulated using a Computational Fluid Dynamics (CFD) code with parallel processing and results are presented in this paper. The analyses have been performed for the original and modified (11.5 mm center element diameter) designs with skewed cosine axial heat flux distribution and 5.1% diametral creep of the pressure tube. The CFD results are in good agreement with the expected temperature and velocity cross-sectional distributions. The effect of the pressure tube creep on the flow bypass is detected, and the CHF improvement in the core region of the modified design is confirmed. The two-phase flow model reasonably predicted the void distribution and the role of interfacial drag on increasing the pressure drop. In all CFD models, the appendages were shown to enhance the production of cross flows and their corresponding flow mixing and asymmetry. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- Imprint Title
- Flexible fuel for the future. 11th international conference on CANDU fuel
- Imprint Pagination
- 60.9 Megabytes
- Journal Page Range
- [14 p.]
Conference
- Title
- 11. International conference on CANDU fuel
- Dates
- 17-20 Oct 2010
- Place
- Niagara Falls, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 47028634
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CREEP; FLUID MECHANICS; FUEL ELEMENT CLUSTERS; PRESSURE TUBES; TWO-PHASE FLOW
- Descriptors DEC
- FLUID FLOW; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES
Optional Information
- Notes
- 5 refs., 2 tabs., 9 figs.