Critical heat flux in inclined rectangular narrow long channel

Sang W. Noh; Yong H. Kim; Kune Y. Suh; Joy L. Rempe; F. Bill Cheung; Sang B. Kim

Critical heat flux in inclined rectangular narrow long channel

Sang W. Noh, Yong H. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim

Mechanical Engineering

Research output: Contribution to conference › Paper › peer-review

4 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 language	English (US)
Pages	2895-2903
Number of pages	9
State	Published - 2005
Event	American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 - Seoul, Korea, Republic of Duration: May 15 2005 → May 19 2005

Other

Other	American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05
Country/Territory	Korea, Republic of
City	Seoul
Period	5/15/05 → 5/19/05

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering
Safety, Risk, Reliability and Quality

Cite this

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title = "Critical heat flux in inclined rectangular narrow long channel",

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.",

author = "Noh, {Sang W.} and Kim, {Yong H.} and Suh, {Kune Y.} and Rempe, {Joy L.} and Cheung, {F. Bill} and Kim, {Sang B.}",

year = "2005",

language = "English (US)",

pages = "2895--2903",

note = "American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 ; Conference date: 15-05-2005 Through 19-05-2005",

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TY - CONF

T1 - Critical heat flux in inclined rectangular narrow long channel

AU - Noh, Sang W.

AU - Kim, Yong H.

AU - Suh, Kune Y.

AU - Rempe, Joy L.

AU - Cheung, F. Bill

AU - Kim, Sang B.

PY - 2005

Y1 - 2005

N2 - 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.

AB - 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.

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T2 - American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05

Y2 - 15 May 2005 through 19 May 2005

ER -

Critical heat flux in inclined rectangular narrow long channel

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