Published 2014 | Version v1
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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