A feasibility study on the use of the MOOSE computational framework to simulate three-dimensional deformation of CANDU reactor fuel elements
- 1. Royal Military College of Canada, Chemistry and Chemical Engineering, 13 General Crerar Crescent, Kingston, Ontario, Canada K7K 7B4 (Canada)
- 2. Canadian Nuclear Laboratories, Fuel and Fuel Channel Safety, 1 Plant Road, Chalk River, Ontario, Canada K0J 1J0 (Canada)
- 3. Royal Military College of Canada, Mechanical and Aerospace Engineering, 13 General Crerar Crescent, Kingston, Ontario, Canada K7K 7B4 (Canada)
Description
Highlights: • This is the first demonstration of using the MOOSE framework for modeling CANDU fuel. • Glued and frictionless contact algorithms behave as expected for 2D and 3D cases. • MOOSE accepts and correctly interprets functions of arbitrary form. • 3D deformation calculations accurately compare against analytical solutions. • MOOSE is a viable simulation tool for modeling accident reactor conditions. - Abstract: Horizontally oriented fuel bundles, such as those in CANada Deuterium Uranium (CANDU) reactors present unique modeling challenges. After long irradiation times or during severe transients the fuel elements can laterally deform out of plane due to processes known as bow and sag. Bowing is a thermally driven process that causes the fuel elements to laterally deform when a temperature gradient develops across the diameter of the element. Sagging is a coupled mechanical and thermal process caused by deformation of the fuel pin due to creep mechanisms of the sheathing after long irradiation times and or high temperatures. These out-of-plane deformations can lead to reduced coolant flow and a reduction in coolability of the fuel bundle. In extreme cases element-to-element or element-to-pressure tube contact could occur leading to reduced coolant flow in the subchannels or pressure tube rupture leading to a loss of coolant accident. This paper evaluates the capability of the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework developed at the Idaho National Laboratory to model these deformation mechanisms. The material model capabilities of MOOSE and its ability to simulate contact are also investigated.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2015.07.028Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2015.07.028;
- PII
- S0029-5493(15)00298-8;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 293
- Journal Page Range
- p. 385-394
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48002316
- Subject category
- S42: ENGINEERING; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ALGORITHMS; ANALYTICAL SOLUTION; BOWING; CANDU TYPE REACTORS; CANNING; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; COOLANTS; FEASIBILITY STUDIES; FUEL ELEMENT CLUSTERS; FUEL PINS; IDAHO NATIONAL LABORATORY; LOSS OF COOLANT; M CODES; NUCLEAR FUELS; PRESSURE TUBES; TEMPERATURE GRADIENTS; TEMPERATURE RANGE 0400-1000 K; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DEFORMATION; ENERGY SOURCES; EVALUATION; FABRICATION; FUEL ASSEMBLIES; FUEL ELEMENTS; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; MATERIALS WORKING; MATHEMATICAL LOGIC; MATHEMATICAL SOLUTIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; TEMPERATURE RANGE; THERMAL REACTORS; TUBES; US DOE; US ORGANIZATIONS
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.