Thermophysical properties and oxygen transport in the (Ux,Pu1−x)O2 lattice
File(s)Pu_mixed_oxide.pdf (8.11 MB)
Accepted version
Author(s)
Cooper, MWD
Murphy, ST
Rushton, MJD
Grimes, RW
Type
Journal Article
Date Issued
2015-03-16
Date Acceptance
2015-03-09
Citation
Journal of Nuclear Materials, 2015, 461, pp.206-214
ISSN
1873-4820
Publisher
Elsevier
Start Page
206
End Page
214
Journal / Book Title
Journal of Nuclear Materials
Volume
461
Copyright Statement
© 2015 Elsevier. Licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International http://creativecommons.org/licenses/by-nc-nd/4.0/
Sponsor
Engineering & Physical Science Research Council (E
Engineering & Physical Science Research Council (EPSRC)
Grant Number
EP/I036400/1 RG62429 LBZF/093
EP/K00817X/1
Subjects
Science & Technology
Technology
Physical Sciences
Materials Science, Multidisciplinary
Nuclear Science & Technology
Mining & Mineral Processing
Materials Science
MOLECULAR-DYNAMICS SIMULATION
URANIUM-DIOXIDE
THERMAL-CONDUCTIVITY
HEAT-CAPACITY
INTERATOMIC POTENTIALS
PHYSICAL-PROPERTIES
PHASE DIAGRAM
UO2
DIFFUSION
ENTHALPY
Energy
0912 Materials Engineering
Publication Status
Published