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dc.contributor.authorNelson, Andrew T.
dc.contributor.authorWhite, Joshua T.
dc.contributor.authorAndersson, David A.
dc.contributor.authorAguiar, Jeffery A.
dc.contributor.authorMcClellan, Kenneth J.
dc.contributor.authorByler, Darrin D.
dc.contributor.authorStanek, Christopher R.
dc.contributor.authorShort, Michael P
dc.date.accessioned2015-04-24T16:26:30Z
dc.date.available2015-04-24T16:26:30Z
dc.date.issued2014-04
dc.date.submitted2013-12
dc.identifier.issn00027820
dc.identifier.issn1551-2916
dc.identifier.urihttp://hdl.handle.net/1721.1/96790
dc.description.abstractNickel ferrite (NiFe[subscript 2]O[subscript 4]) is a major constituent of the corrosion deposits formed on the exterior of nuclear fuel cladding tubes during operation. NiFe[subscript 2]O[subscript 4] has attracted much recent interest, mainly due to the impact of these deposits, known as CRUD, on the operation of commercial nuclear reactors. Although advances have been made in modeling CRUD nucleation and growth under a wide range of conditions, the thermophysical properties of NiFe[subscript 2]O[subscript 4] at high temperatures have only been approximated, thereby limiting the accuracy of such models. In this study, samples of NiFe[subscript 2]O[subscript 4] were synthesized to provide the thermal diffusivity, specific heat capacity, and thermal expansion data from room temperature to 1300 K. These results were then used to determine thermal conductivity. Numerical fits are provided to facilitate ongoing modeling efforts. The Curie temperature determined through these measurements was in slight disagreement with literature values. Transmission electron microscopy investigation of multiple NiFe[subscript 2]O[subscript 4] samples revealed that minor nonstoichiometry was likely responsible for variations in the Curie temperature. However, these small changes in composition did not impact the thermal conductivity of NiFe[subscript 2]O[subscript 4], and thus are not expected to play a large role in governing reactor performance.en_US
dc.description.sponsorshipUnited States. Dept. of Energy. Office of Nuclear Energy (Consortium of Advanced Simulation for Light Water Reactors (CASL) Program)en_US
dc.language.isoen_US
dc.publisherWiley Blackwellen_US
dc.relation.isversionofhttp://dx.doi.org/10.1111/jace.12901en_US
dc.rightsCreative Commons Attribution-Noncommercial-Share Alikeen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-sa/4.0/en_US
dc.sourceProf. Short via Chris Sherratten_US
dc.titleThermal Expansion, Heat Capacity, and Thermal Conductivity of Nickel Ferrite (NiFe[subscript 2]O[subscript 4])en_US
dc.typeArticleen_US
dc.identifier.citationNelson, Andrew T., Joshua T. White, David A. Andersson, Jeffery A. Aguiar, Kenneth J. McClellan, Darrin D. Byler, Michael P. Short, and Christopher R. Stanek. “Thermal Expansion, Heat Capacity, and Thermal Conductivity of Nickel Ferrite (NiFe[subscript 2]O[subscript 4]).” Edited by M. White. J. Am. Ceram. Soc. 97, no. 5 (April 1, 2014): 1559–1565.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.contributor.approverShort, Michael P.en_US
dc.contributor.mitauthorShort, Michael P.en_US
dc.relation.journalJournal of the American Ceramic Societyen_US
dc.eprint.versionOriginal manuscripten_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/NonPeerRevieweden_US
dspace.orderedauthorsNelson, Andrew T.; White, Joshua T.; Andersson, David A.; Aguiar, Jeffery A.; McClellan, Kenneth J.; Byler, Darrin D.; Short, Michael P.; Stanek, Christopher R.en_US
dc.identifier.orcidhttps://orcid.org/0000-0002-9216-2482
mit.licenseOPEN_ACCESS_POLICYen_US
mit.metadata.statusComplete


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