Development of a multiscale thermal conductivity model for fission gas in UO2

Michael R. Tonks; Xiangyang Liu; David A. Andersson; Danielle M. Pérez; Aleksandr V. Chernatynskiy; Giovanni Pastore; Chris R. Stanek; Richard L. Williamson

doi:10.1016/j.jnucmat.2015.11.042

Development of a multiscale thermal conductivity model for fission gas in UO₂

Michael R. Tonks
, Xiangyang Liu
, David A. Andersson
, Danielle M. Pérez
, Aleksandr V. Chernatynskiy
, Giovanni Pastore
, Chris R. Stanek
, Richard L. Williamson

Physics

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

Original language	English
Pages (from-to)	89-98
Number of pages	10
Journal	Journal of Nuclear Materials
Volume	469
DOIs	https://doi.org/10.1016/j.jnucmat.2015.11.042
State	Published - Feb 1 2016

ASJC Scopus Subject Areas

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

Keywords

Fuel performance modeling
Multiscale modeling
Thermal conductivity
Uranium dioxide

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10.1016/j.jnucmat.2015.11.042

Cite this

@article{8466f86b7f694639b183fb53dea5fc19,

title = "Development of a multiscale thermal conductivity model for fission gas in UO2",

keywords = "Fuel performance modeling, Multiscale modeling, Thermal conductivity, Uranium dioxide",

author = "Tonks, \{Michael R.\} and Xiangyang Liu and Andersson, \{David A.\} and P{\'e}rez, \{Danielle M.\} and Chernatynskiy, \{Aleksandr V.\} and Giovanni Pastore and Stanek, \{Chris R.\} and Williamson, \{Richard L.\}",

year = "2016",

month = feb,

day = "1",

doi = "10.1016/j.jnucmat.2015.11.042",

language = "English",

volume = "469",

pages = "89--98",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

}

TY - JOUR

T1 - Development of a multiscale thermal conductivity model for fission gas in UO2

AU - Tonks, Michael R.

AU - Liu, Xiangyang

AU - Andersson, David A.

AU - Pérez, Danielle M.

AU - Chernatynskiy, Aleksandr V.

AU - Pastore, Giovanni

AU - Stanek, Chris R.

AU - Williamson, Richard L.

PY - 2016/2/1

Y1 - 2016/2/1

KW - Fuel performance modeling

KW - Multiscale modeling

KW - Thermal conductivity

KW - Uranium dioxide

UR - https://www.scopus.com/pages/publications/84949488504

UR - https://www.scopus.com/pages/publications/84949488504#tab=citedBy

U2 - 10.1016/j.jnucmat.2015.11.042

DO - 10.1016/j.jnucmat.2015.11.042

M3 - Article

SN - 0022-3115

VL - 469

SP - 89

EP - 98

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Development of a multiscale thermal conductivity model for fission gas in UO₂

ASJC Scopus Subject Areas

Keywords

Access to Document

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