A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations

Lucuta, P.G.; Matzke, Hj.; Hastings, I.J.

doi:10.1016/s0022-3115(96)00404-7

Cited by 255 publications

(131 citation statements)

References 24 publications

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“…In addition, this revised model has improved the comparison between FRAPCON-3 predictions and the in-pile fuel temperature data to high burnup from the Halden Ultra-High Burnup Experiment. The revised Lucuta model also compares well to thermal conductivity values determined from thermal difisivity measurements on high-burnup fuel as demonstrated by Lucuta et al (1996). 'Therefore, this new model has been implemented in FRAPCON-3 instead of simply introducing a burnup enhancement factor into the existing (MATPRO-1 1 derivative) fuel thermal conductivity model.…”

Section: Burnup-dependent Conductivity For Uraniamentioning

confidence: 61%

“…Thermometers in the annular hole influence the pellet relocation towards the cladding differently than normal fuel with a large pellet and no hole. There is still a small imderprerdiction of the Halden Ultra-High Burnup data at high burnups, but the model appears to predict well against thermal di-sivity data (Lucuta et al 1996) from high-burnup fuel. Therefore, until further iri-reactor thermal data and thermal diffusivity data become available for high-burnup fuel, a large uncertainty will be used for burnups >40 GWd/MTU (*lo%) and for burnups greater than 60 GWdh4TU (*I 5%).…”

Section: Verification Of Burnup Dependencementioning

confidence: 88%

“…In Lucuta et al (1996), a revised fuel thermal conductivity model is presented that correlates the SIMFUEL data as well as the previous model (Lucuta et al 1992), but also correlates the irradiated fuel data from Daniel and Cohen, plus comparing well to low-burnup, low-temperature irradiated fuel data from early Atomic Energy of Canada, Ltd. (AECL) experiments. In addition, this revised model has improved the comparison between FRAPCON-3 predictions and the in-pile fuel temperature data to high burnup from the Halden Ultra-High Burnup Experiment.…”

Section: Burnup-dependent Conductivity For Uraniamentioning

confidence: 90%

“…The conductivity formula for sintered, stoichiometric uranium dioxide as proposed recently by Lucuta et al (1996) has been evaluated and incorporated in FRAPCON-3 in place of the MATPRO-1 1 function of temperature and porosity. This formula includes the effects of temperature, radiation (environment), fuel burnup, and porosity.…”

Section: Modifications To the Matpro Equationsmentioning

confidence: 99%

See 3 more Smart Citations

FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

Lanning¹,

Beyer²,

Painter³

1997

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Section: Burnup-dependent Conductivity For Uraniamentioning

confidence: 61%

Section: Verification Of Burnup Dependencementioning

confidence: 88%

Section: Burnup-dependent Conductivity For Uraniamentioning

confidence: 90%

Section: Modifications To the Matpro Equationsmentioning

confidence: 99%

See 2 more Smart Citations

FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

Lanning¹,

Beyer²,

Painter³

1997

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“…Furthermore, the thermal conductivity steeply decreases across the rim region because of the porous microstructure and higher local fissioning. Accordingly the thermal conductivity of irradiated U02 fuel depends on porosity and burnup as well as temperatureC 18 ). In the rim region that has very high porosity up to 20 vol% or more, the thermal conductivity degradation can be estimated using the assumption that the rim region consists of pores and fully dense materials composed of U02 matrix and solid fission products.…”

Section: Rim Effect On Thermal Conductivity Degradationmentioning

confidence: 99%

Rim Characteristics and Their Effects on the Thermal Conductivity in High Burnup UO₂Fuel

Lee

Koo

Sohn

2001

Journal of Nuclear Science and Technology

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Characteristics of high burnup U02 fuel such as threshold burnup for the formation of high burnup microstructure (rim), rim average burnup and rim width were estimated and then the thermal conductivity degradation due to the porous rim region was investigated.The threshold burnup for rim formation was estimated as a function of temperature and fission rate using Rest's model. The calculated threshold burnup, which shows a particular dependence on temperature, ranges from 40 to 50MWd/kgU at typical fuel periphery temperatures of 400 to 600°C. In addition, the rim average burnup and the rim width were obtained by statistical analysis of the data available in open literature.To consider the additional degradation of thermal conductivity in. the rim region, a formula for rim porosity was presented with the assumption that rim pores are overpressurized and that all the produced fission gases are retained in the rim pores.To estimate the thermal conductivity in the porous rim using the general correction method applicable to two-phase structure, it was assumed that the rim region consists of pores and fully dense materials composed of U02 matrix and solid fission products. Then by combining the general model for two-phase with the rim porosity developed in the present paper and HALDEN's thermal conductivity model, a thermal conductivity model for the porous rim region was developed.The predicted thermal conductivity shows an additional reduction of ~20% due to the porous rim structure which would cause to increase the fuel temperature of high burnup fuel during steady-state operation and transient irradiation.

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Burst Safety Analysis of Strengthened FeCrAl Claddings in APR1400 Fuel Rods Subject to LOCA Conditions

Ubaid,

Alaleeli,

et al. 2024

Energy Science & Engineering

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Because of their greater accident tolerance, iron‐chromium‐aluminum (FeCrAl) alloys hold great promise for applications in nuclear fuel claddings. Here, a finite element‐based computational framework is developed to analyze the thermomechanical performance of APR1400 fuel rods with FeCrAl claddings subjected to a typical LOCA condition preceded by 4 years of normal operation. The effect of enhancements in the yield and ultimate strength of FeCrAl on the burst safety of fuel rods is evaluated for various choices of pellet diameters and cladding thicknesses. The pellet diameter is increased by reducing the cladding thickness and/or the pellet‐clad gap thickness with the intention of compensating for the additional neutronic penalty of FeCrAl in comparison to the conventional Zircaloy. It is found that a reduction of the pellet‐clad gap thickness from 83 to 50 μm can increase the cladding's burst safety by up to 35%. Additionally, strengthening FeCrAl alloys has significantly improved cladding performance under LOCA (Loss of Coolant Accident) conditions. Specifically, an 80% enhancement in the yield and ultimate strength has been shown to improve the cladding burst safety by 80%. The findings of this study suggest that improved material properties and geometric modifications can significantly improve the burst safety of FeCrAl‐based ATF systems, which is an important consideration for their practical implementation.

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A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations

Cited by 255 publications

References 24 publications

FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

Rim Characteristics and Their Effects on the Thermal Conductivity in High Burnup UO₂Fuel

Burst Safety Analysis of Strengthened FeCrAl Claddings in APR1400 Fuel Rods Subject to LOCA Conditions

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A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations

Cited by 255 publications

References 24 publications

FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

Rim Characteristics and Their Effects on the Thermal Conductivity in High Burnup UO2Fuel

Burst Safety Analysis of Strengthened FeCrAl Claddings in APR1400 Fuel Rods Subject to LOCA Conditions

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Rim Characteristics and Their Effects on the Thermal Conductivity in High Burnup UO₂Fuel