Critical heat flux in inclined rectangular narrow long channel

Sang W. Noh, Yong H. Kim, Kune Y. Suh, Joy L. Rempe, Fan-bill B. Cheung, Sang B. Kim

Research output: Contribution to conferencePaperpeer-review

3 Scopus citations

Abstract

In the TMI-2 accident, the lower part of the reactor pressure vessel had been overheated and then rather rapidly cooled down, as was later identified in a vessel investigation project. This accounted for the possibility of gap cooling feasibility. For this reason, several investigations were performed to determine the critical heat flux (CHF)from the standpoint of invessel retention. The experiments are conducted to investigate the general boiling phenomena, and the triggering mechanism for the CHF in a narrow gap using a 5×105 mm2 crevice type heater assembly and de-mineralized water. The test parameters include the gap size of 5 mm, and the surface orientation angles from the downward facing position (180°) to the vertical position (90°). The orientation angle affects the bubble layer and escape from the narrow gap. The CHF is lexs than that in a shorter channel, compared with the previous experiments having a heated length of 35 mm in the copper test section.

Original languageEnglish (US)
Pages2895-2903
Number of pages9
StatePublished - Dec 1 2005
EventAmerican Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 - Seoul, Korea, Republic of
Duration: May 15 2005May 19 2005

Other

OtherAmerican Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05
CountryKorea, Republic of
CitySeoul
Period5/15/055/19/05

All Science Journal Classification (ASJC) codes

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

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