MIT Libraries logoDSpace@MIT

MIT
View Item 
  • DSpace@MIT Home
  • Center for Advanced Nuclear Energy Systems (CANES)
  • Nuclear Fuel Cycle Technology and Policy Program (NFC) - Technical Reports
  • View Item
  • DSpace@MIT Home
  • Center for Advanced Nuclear Energy Systems (CANES)
  • Nuclear Fuel Cycle Technology and Policy Program (NFC) - Technical Reports
  • View Item
JavaScript is disabled for your browser. Some features of this site may not work without it.

Feasibility of Partial ZrO[subscript 2] Coatings on Outer Surface of Annular UO[subscript 2] Pellets to Control Gap Conductance

Author(s)
Feinroth, H.; Yuan, Y.
Thumbnail
DownloadNFC-080.pdf (1.055Mb)
Other Contributors
Massachusetts Institute of Technology. Nuclear Fuel Cycle Program
Metadata
Show full item record
Abstract
The viability of depositing a thin porous coating of zirconia on the outer surface of an annular UO[subscript 2] pellet is investigated experimentally. Such a layer has been proposed to buffer the contact between the fuel and cladding, thus maintaining an appropriate balance of heat transfer from the pellet to the outer and inner cladding. MIT and Gamma Engineering commissioned laboratory studies of the feasibility of depositing a controlled thickness of porous zirconia on an oxide surface. Experiments were conducted at the Thermal Spray Laboratory at SUNY-Stonybrook to produce a thin layer of Yttria Stablized Zirconia (YSZ) on alumina wafers. The experiments concluded that it is possible to use plasma spray guns to produce 50% porous layers of 15–30 micrometer thickness. Measurements were conducted at the Vitreous State Laboratory of the Catholic University of America to determine the thermal conductance of aluminazircaloy and alumina-zircaloy-YSZ sandwiches as a function of applied pressure. A relation is developed to predict the conductance at such surfaces.
Date issued
2005-06
URI
http://hdl.handle.net/1721.1/75211
Publisher
Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program
Series/Report no.
MIT-NFC;TR-080

Collections
  • Nuclear Fuel Cycle Technology and Policy Program (NFC) - Technical Reports

Browse

All of DSpaceCommunities & CollectionsBy Issue DateAuthorsTitlesSubjectsThis CollectionBy Issue DateAuthorsTitlesSubjects

My Account

Login

Statistics

OA StatisticsStatistics by CountryStatistics by Department
MIT Libraries
PrivacyPermissionsAccessibilityContact us
MIT
Content created by the MIT Libraries, CC BY-NC unless otherwise noted. Notify us about copyright concerns.