Published October 1999 | Version v1
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Correlation between the critical heat flux and the fractal surface roughness of zirconium alloy tubes

  • 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
  • 2. Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)

Description

In CANDU fuel channels, Zircaloy calandria tubes isolate the hot pressure tubes from the cool heavy water moderator. The heavy-water moderator provides a backup heat sink during some postulated loss-of-coolant accidents. The decay heat from the fuel is transferred to the moderator to ensure fuel channel integrity during emergencies. Moderator temperature requirements are specified to ensure that the transfer of decay heat does not exceed the critical heat flux (CHF) on the outside surface of the calandria tube. An enhanced CHF provides increases in safety margin. Pool boiling experiments indicate the CHF is enhanced with glass-peening of the outside surface of the calandria tubes. The objective of this study was to evaluate the surface characteristics of glass-peened tubes and relate these characteristics to CHF. The micro-topologies of the tube surfaces were analysed using stereo-pair micrographs obtained from scanning electron microscopy (SEM) and photogrammetry techniques. A linear relationship correlated the CHF as a function of the 'fractal' surface roughness of the tubes. (author)

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
16 p.
Report number
AECL--11997

Conference

Title
9. International topical meeting on nuclear reactor thermal hydraulics (NURETH-9)
Dates
3-8 Oct 1999
Place
San Francisco, CA (United States)

Optional Information

Notes
25 refs., 1 tab., 6 figs.