Mechanistic verification of empirical UO2 fuel fracture models

Gamble, Kyle; Knight, Travis W.; Roberts, Elwyn; Hales, Jason D.; Spencer, Benjamin W.

doi:10.1016/j.jnucmat.2021.153163

Cited by 9 publications

(6 citation statements)

References 26 publications

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“…Furthermore, the model could be coupled to existing fission gas behavior models for pore size, as well as evolving density models for the current porosity within the fuel, in order to have an evolving tensile strength as irradiation progresses. This tensile strength can be used as a criterion for crack initiation when modeling fracture, as has been done by many researchers [9,10,11,12,13].…”

Section: Fracture Modelingmentioning

confidence: 99%

“…Slightly less damage is observed in the doped UO 2 case, thanks to the Its higher tensile strength. The discrete approach to modeling fracture involves coupling to the extended finite element method and observing the actual fracture-related discontinuities in the mesh [10,13]. At present, the discrete approach is limited to modeling radial crack formation, and is typically done on a cross-sectional slice-or multiple cross-sectional slices stacked along the axial direction of the fuel rod.…”

Section: Fracture Modelingmentioning

confidence: 99%

“…The tensile strengths provided from AFC feature very limited uncertainty (see Table 3.2) even though the tensile strength of UO 2 can vary from 80 to 150 MPa, depending on the microstructural features and manufacturing processes [15]. Gamble et al [13] investigated the effect of tensile strength uncertainty on predictions regarding the number of cracks that form during irradiation. The ranges evaluated exceeded the values of both AFC measurements, and there was found to be high uncertainty in the number of radial cracks that form, due to randomization of the tensile strength.…”

Section: Fracture Modelingmentioning

confidence: 99%

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Multiscale Modeling of Cr2O3-doped UO2 Creep and Fracture

Gamble

Cooper

2021

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The pursuit of UO 2 fuel with various dopants (e.g., Cr 2 O 3 and Al 2 O 3 ) for improved accident tolerance due to larger grain sizes and suspected reductions in fission gas release and creep requires advanced modeling and simulation tools. Such tools enable rapid multiscale development and enhanced understanding of material behavior in regimes for which experimental measurements may be lacking. This work builds on previous multiscale modeling efforts targeting the fission gas behavior of Cr 2 O 3 -doped UO 2 , in order to begin exploring the effects of dopants on mechanical properties, with a particular focus on creep and fracture. The results indicate that dislocation climb is the most dominate creep mechanism at almost all temperatures, and sensitivity analyses provide evidence in further support of this claim.The limited experimental data generated by the U.S. Department of Energy's Advanced Fuels Campaign (AFC) on the tensile strength of Cr 2 O 3 -doped UO 2 indicate that fracture may be less severe in doped specimens. The results on creep and fracture are preliminary, given the large degree of uncertainty associated with the models.

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Section: Fracture Modelingmentioning

confidence: 99%

Section: Fracture Modelingmentioning

confidence: 99%

Section: Fracture Modelingmentioning

confidence: 99%

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Multiscale Modeling of Cr2O3-doped UO2 Creep and Fracture

Gamble

Cooper

2021

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“…The large fragment size correlations were briefly mentioned in Section 2.2. The functional form of the equations were summarized by Gamble et al [21]. Figure 5.1 and Figure 5.2 are reproduced from [21] illustrating the number of large fragments that form alongside available experimental data.…”

Section: Large Fragment Size Correlationsmentioning

confidence: 99%

BISON Fuel Fragmentation Relocation and Dispersal (FFRD) Assessment Database for Eventual Use in Bayesian Calibration

Gamble

2023

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Existing light-water reactor (LWR) fuel vendors have been interested in seeking increased discharge burnups of nuclear fuel rods for improved economics for quite a few years. With increased burnups come additional challenges that must be addressed. It has been experimentally observed that average burnups higher than the current regulatory limit of 62 MWd/kgU may undergo fuel fragmentation, relocation, and dispersal (FFRD) during a loss-of-coolant accident (LOCA). Industry must demonstrate approaches to mitigate FFRD. In an effort to support industry, the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program within the U.S. Department of Energy (DOE) has for several years invested in developing multiscale models and creating a validation/assessment database for these models to study the mechanisms driving FFRD. This report provides an update on changes made to the assessment database and new models added to BISON to support the study of fuel rod behavior during FFRD. An effort has been initiated this year to begin adding dedicated inputs to the publicly available Virtual Test Bed (VTB) repository for industry use. A section of this report details the efforts made in this area. NEAMS has recently developed new capabilities in the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework's stochastic tools module for calibration using Bayesian inference. The goal in the future is to use these capabilities to calibrate and identify weaknesses in the existing BISON models for FFRD. The report concludes with a discussion on the models most likely to benefit the most from such calibration. iv

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“…Work on further validation of models such as the one detailed in this paper is ongoing. On the modelling side, recent work by Gamble has used a volumescaled Weibull distribution [37] in a model built based on XFEM. Their work is currently limited to radial cracks, whilst our work using peridynamics is able to model a wide range of crack morphologies including branching.…”

Section: Comparison Of Models and Post-irradiation Examination Datamentioning

confidence: 99%

Application of Weibull Fracture Strength Distributions to Modelling Crack Initiation Behaviour in Nuclear Fuel Pellets Using Peridynamics

Jones¹,

Haynes²,

Rossiter³

et al. 2022

Preprint

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This is a PDF file of an article that has undergone enhancements after acceptance, such as the addition of a cover page and metadata, and formatting for readability, but it is not yet the definitive version of record. This version will undergo additional copyediting, typesetting and review before it is published in its final form, but we are providing this version to give early visibility of the article. Please note that, during the production process, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal pertain.

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Mechanistic verification of empirical UO2 fuel fracture models

Cited by 9 publications

References 26 publications

Multiscale Modeling of Cr<sub>2</sub>O<sub>3</sub>-doped UO<sub>2</sub> Creep and Fracture

Multiscale Modeling of Cr<sub>2</sub>O<sub>3</sub>-doped UO<sub>2</sub> Creep and Fracture

BISON Fuel Fragmentation Relocation and Dispersal (FFRD) Assessment Database for Eventual Use in Bayesian Calibration

Application of Weibull Fracture Strength Distributions to Modelling Crack Initiation Behaviour in Nuclear Fuel Pellets Using Peridynamics

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