Performance evaluation of U-Mo/Al dispersion fuel by considering a fuel-matrix interaction

Cited 29 time in webofscience Cited 0 time in scopus
  • Hit : 231
  • Download : 0
Because the interaction layers that form between U-Mo particles and the Al matrix degrade the thermal properties of U-Mo/Al dispersion fuel, an investigation was undertaken of the undesirable feedback effect between an interaction layer growth and a centerline temperature increase for dispersion fuel. The radial temperature distribution due to interaction layer growth during irradiation was calculated iteratively in relation to changes in the volume fractions, the thermal conductivities of the constituents, and the oxide thickness with the burnup. The interaction layer growth, which is estimated on the basis of the temperature calculations, showed a reasonable agreement with the post-irradiation examination results of the U-Mo/Al dispersion fuel rods irradiated at the HANARO reactor. The U-Mo particle size was found to be a dominant factor that determined the fuel temperature during irradiation. Dispersion fuel with larger U-Mo particles revealed lower levels of both the interaction layer formation and the fuel temperature increase. The results confirm that the use of large U-Mo particles appears to be an effective way of mitigating the thermal degradation of U-Mo/Al dispersion fuel.
Publisher
KOREAN NUCLEAR SOC
Issue Date
2008-08
Language
English
Article Type
Article
Keywords

THERMAL COMPATIBILITY; ALUMINUM; POWDERS; HEAT; AL

Citation

NUCLEAR ENGINEERING AND TECHNOLOGY, v.40, no.5, pp.409 - 418

ISSN
1738-5733
URI
http://hdl.handle.net/10203/255642
Appears in Collection
NE-Journal Papers(저널논문)
Files in This Item
There are no files associated with this item.
This item is cited by other documents in WoS
⊙ Detail Information in WoSⓡ Click to see webofscience_button
⊙ Cited 29 items in WoS Click to see citing articles in records_button

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0