Spacer grid measurements during dispersed flow film boiling in rod bundles

L. E. Hochreiter, S. Ergun, F. B. Cheung, T. F. Lin, G. S. Rhee, S. M. Bajorek, J. M. Kelly

Research output: Contribution to journalConference articlepeer-review

Abstract

Data is provided on the rod bundle spacer grid temperature behavior in a highly dispersed two-phase flow situation representative of a PWR or BWR reflood transient. The instrumented spacer grids indicate a quenching behavior or a superheated temperature depending on the reflood conditions.

Original languageEnglish (US)
Pages (from-to)643-647
Number of pages5
JournalTransactions of the American Nuclear Society
Volume95
StatePublished - Dec 21 2006
Event2006 Winter Meeting of the American Nuclear Society - Albuquerque, NM, United States
Duration: Nov 12 2006Nov 16 2006

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Industrial and Manufacturing Engineering
  • Energy Engineering and Power Technology

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