3D modeling of missing pellet surface defects in BWR fuel

•A global/local analysis procedure for missing pellet surface defects is proposed.•This is applied to defective BWR fuel under blade withdrawal and high power ramp conditions.•Sensitivity of the cladding response to key model parameters is studied. One of the important roles of cladding in light wat...

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Bibliographic Details
Published in:Nuclear engineering and design 2016-10, Vol.307, p.155-171
Main Authors: Spencer, B.W., Williamson, R.L., Stafford, D.S., Novascone, S.R., Hales, J.D., Pastore, G.
Format: Article
Language:English
Subjects:
Boiling water reactors
Cladding
defective pellet
Defects
Failure
Fuels
GENERAL STUDIES OF NUCLEAR REACTORS
MATHEMATICS AND COMPUTING
Modelling
multiphysics simulation
NUCLEAR FUEL CYCLE AND FUEL MATERIALS
nuclear fuel performance
Pellets
Three dimensional models
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Summary:•A global/local analysis procedure for missing pellet surface defects is proposed.•This is applied to defective BWR fuel under blade withdrawal and high power ramp conditions.•Sensitivity of the cladding response to key model parameters is studied. One of the important roles of cladding in light water reactor fuel rods is to prevent the release of fission products. To that end, it is essential that the cladding maintain its integrity under a variety of thermal and mechanical loading conditions. Local geometric irregularities in fuel pellets caused by manufacturing defects known as missing pellet surfaces (MPS) can in some circumstances lead to elevated cladding stresses that are sufficiently high to cause cladding failure. Accurate modeling of these defects can help prevent these types of failures. The BISON nuclear fuel performance code developed at Idaho National Laboratory can be used to simulate the global thermo-mechanical fuel rod behavior, as well as the local response of regions of interest, in either 2D or 3D. In either case, a full set of models to represent the thermal and mechanical properties of the fuel, cladding and plenum gas is employed. A procedure for coupling 2D full-length fuel rod models to detailed 3D models of the region of the rod containing a MPS defect is detailed here. The global and local model each contain appropriate physics and behavior models for nuclear fuel. This procedure is demonstrated on a simulation of a boiling water reactor (BWR) fuel rod containing a pellet with an MPS defect, subjected to a variety of transient events, including a control blade withdrawal and a ramp to high power. The importance of modeling the local defect using a 3D model is highlighted by comparing 3D and 2D representations of the defective pellet region. Parametric studies demonstrate the effects of the choice of gaseous swelling model and of the depth and geometry of the MPS defect on the response of the cladding adjacent to the defect.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2016.07.008