Temperature in a fuel rod with a coated clad and temperature dependent thermal conductivity

Min Tsung Kao, Rizwan Uddin

Research output: Contribution to journalConference article

Original languageEnglish (US)
Pages (from-to)712-715
Number of pages4
JournalTransactions of the American Nuclear Society
Volume110
StatePublished - Jan 1 2014
Event2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014 - Reno, NV, United States
Duration: Jun 15 2014Jun 19 2014

ASJC Scopus subject areas

  • Safety, Risk, Reliability and Quality
  • Nuclear Energy and Engineering

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