Thermal-mechanical behaviour of fuel element in SCWR design
Description
This paper presents a study on thermal-mechanical behaviour of a fuel element proposed for the Canadian Supercritical Water Cooled Reactor (SCWR). In the Canadian SCWR, the coolant pressure is 25 MPa, and the temperature is 350oC at the inlet and 625oC at the outlet of the reactor core. Critical design decisions for fuel design will be the selection of the fuel sheath material and details of the fuel element design options (sheath thickness, pellet-clad gap, internal pressure, etc.). The analysis presented in this paper predicted temperature, stress and strain in the fuel element of the Canadian SCWR with a collapsible sheath using ANSYS. Typical conditions for the evaluation of the fuel behaviour, such as linear heat generation rate, coolant temperature and sheath surface heat transfer coefficient, were extracted from core and fuel channel designs. The temperature distribution in the fuel element is predicted by a thermal model and then the thermal model is coupled sequentially with a structural model to predict fuel sheath deformation under the predicted temperature distribution and external (coolant) pressure. Nonlinear thermo-mechanical simulations include nonlinear buckling with elastic-plastic deformation. Three sheath collapse phenomena are considered: (1) elastic collapse by buckling, (2) longitudinal ridging and (3) plastic collapse by yielding. The numerical models are validated against analytical and experimental data. The presented results show the temperature distribution, deformed shape, stress and strain of the fuel element, allowing the designers to select appropriate sheath material and element design options for the SCWR fuel element design. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- AECL-CW--127000-CONF-009
Conference
- Title
- Canada-China Conference on Advanced Reactor Development
- Acronym
- CCCARD-2014
- Dates
- 27-30 Apr 2014
- Place
- Niagara Falls, ON (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 49101507
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL CANS; FUEL ELEMENTS; HEAT TRANSFER; REACTOR CORES; SIMULATION; SUPERCRITICAL STATE; TURBULENT FLOW; WATER COOLED REACTORS
- Descriptors DEC
- ENERGY TRANSFER; FLUID FLOW; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 6 refs., 2 tabs., 12 figs. Paper no. CCCARD2014-5