High pressure counterflow CHF.
Name
01282141-MIT.pdf
Description
Full printable version
Size
1.74 MB
Format
Adobe PDF
Checksum (MD5)
743843ecdf6cb2a160fd7a804294ab34
Author(s)
Walkush, Joseph Patrick
Advisor(s)
Peter Griffith.
Date Issued
1975
Publisher
Massachusetts Institute of Technology
Abstract
This is a report of the experimental results of a program in countercurrent flow critical heat flux. These experiments were performed with Freon 113 at 200 psia in order to model a high pressure water system. An internally heated annulus was used to model a fuel pin in a channel. Only low flowrates were examined. The flow regime was always bubbly or slug, with the liquid primarily on the walls. It was found that critical heat flux of about .9 of the pool boiling value can be expected for up to 20% void. Beyond this, the CHF value decreases uniformly with void. Void fractions up to 70% were investigated, with the results being slightly conservative compared to a similar experiment carried out at atmospheric pressure by Avedisian.
Description
Thesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
Includes bibliographical references.
Subjects
Nuclear Engineering
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Engineering
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
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