Thermal Conductivity of UO₂ Fuel: Predicting Fuel Performance from Simulation

Simon R. Phillpot; Anter A. El-Azab; Aleksandr V. Chernatynskiy; James S. Tulenko

doi:10.1007/s11837-011-0143-x

Thermal Conductivity of UO₂ Fuel: Predicting Fuel Performance from Simulation

Simon R. Phillpot
, Anter A. El-Azab
, Aleksandr V. Chernatynskiy
, James S. Tulenko

Physics

Research output: Contribution to journal › Article › peer-review

Abstract

Recent progress in understanding the thermal-transport properties of UO ₂ for fission reactors is reviewed from the perspective of computer simulations. A path to incorporating more accurate materials models into fuel performance codes is outlined. In particular, it is argued that a judiciously integrated program of atomic-level simulations and mesoscale simulations offers the possibility of both better predicting the thermal-transport properties of UO ₂ in light-water reactors and enabling the assessment of the thermal performances of novel fuel systems for which extensive experimental databases are not available.

Original language	American English
Journal	JOM Journal of the Minerals, Metals and Materials Society
Volume	63
DOIs	https://doi.org/10.1007/s11837-011-0143-x
State	Published - Aug 1 2011

Keywords

Atomic levels
Computer simulation
Experimental database
Fuel performance
Fuels
Integrated programs
Materials model
Mesoscale simulation
Nuclear reactors
Recent progress
Thermal Performance
Thermal conductivity
Transport properties

Disciplines

Physics

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10.1007/s11837-011-0143-xLicense: Unspecified

https://doi.org/10.1007/s11837-011-0143-x

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title = "Thermal Conductivity of UO₂ Fuel: Predicting Fuel Performance from Simulation",

abstract = " Recent progress in understanding the thermal-transport properties of UO 2 for fission reactors is reviewed from the perspective of computer simulations. A path to incorporating more accurate materials models into fuel performance codes is outlined. In particular, it is argued that a judiciously integrated program of atomic-level simulations and mesoscale simulations offers the possibility of both better predicting the thermal-transport properties of UO 2 in light-water reactors and enabling the assessment of the thermal performances of novel fuel systems for which extensive experimental databases are not available.",

keywords = "Atomic levels, Computer simulation, Experimental database, Fuel performance, Fuels, Integrated programs, Materials model, Mesoscale simulation, Nuclear reactors, Recent progress, Thermal Performance, Thermal conductivity, Transport properties",

author = "Phillpot, \{Simon R.\} and El-Azab, \{Anter A.\} and Chernatynskiy, \{Aleksandr V.\} and Tulenko, \{James S.\}",

year = "2011",

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doi = "10.1007/s11837-011-0143-x",

language = "American English",

volume = "63",

journal = "JOM Journal of the Minerals, Metals and Materials Society",

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T1 - Thermal Conductivity of UO₂ Fuel: Predicting Fuel Performance from Simulation

AU - Phillpot, Simon R.

AU - El-Azab, Anter A.

AU - Chernatynskiy, Aleksandr V.

AU - Tulenko, James S.

PY - 2011/8/1

Y1 - 2011/8/1

N2 - Recent progress in understanding the thermal-transport properties of UO 2 for fission reactors is reviewed from the perspective of computer simulations. A path to incorporating more accurate materials models into fuel performance codes is outlined. In particular, it is argued that a judiciously integrated program of atomic-level simulations and mesoscale simulations offers the possibility of both better predicting the thermal-transport properties of UO 2 in light-water reactors and enabling the assessment of the thermal performances of novel fuel systems for which extensive experimental databases are not available.

AB - Recent progress in understanding the thermal-transport properties of UO 2 for fission reactors is reviewed from the perspective of computer simulations. A path to incorporating more accurate materials models into fuel performance codes is outlined. In particular, it is argued that a judiciously integrated program of atomic-level simulations and mesoscale simulations offers the possibility of both better predicting the thermal-transport properties of UO 2 in light-water reactors and enabling the assessment of the thermal performances of novel fuel systems for which extensive experimental databases are not available.

KW - Atomic levels

KW - Computer simulation

KW - Experimental database

KW - Fuel performance

KW - Fuels

KW - Integrated programs

KW - Materials model

KW - Mesoscale simulation

KW - Nuclear reactors

KW - Recent progress

KW - Thermal Performance

KW - Thermal conductivity

KW - Transport properties

UR - https://scholarsmine.mst.edu/phys_facwork/598

UR - https://doi.org/10.1007/s11837-011-0143-x

U2 - 10.1007/s11837-011-0143-x

DO - 10.1007/s11837-011-0143-x

M3 - Article

VL - 63

JO - JOM Journal of the Minerals, Metals and Materials Society

JF - JOM Journal of the Minerals, Metals and Materials Society

ER -

Thermal Conductivity of UO₂ Fuel: Predicting Fuel Performance from Simulation

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