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 - 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

Fingerprint

Dive into the research topics of 'Spacer grid measurements during dispersed flow film boiling in rod bundles'. Together they form a unique fingerprint.

Cite this