Email RIS file
Bookmark
Report an Issue

Overview PWR-Blowdown Heat Transfer Separate-Effects Program [electronic resource].

Published
Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1978.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 16 : digital, PDF file
Additional Creators
Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online

Availability

I Want It
I Want It

Finding items...

Restrictions on Access
Free-to-read Unrestricted online access
Summary
The ORNL Pressurized Water Reactor Blowdown Heat Transfer Program (PWR-BDHT) is a separate-effects experimental study of thermal-hydraulic phenomena occurring during the first 20 sec of a hypothetical LOCA. Specific objectives include the determination, for a wide range of parameters, of time to CHF and the following variables for both pre- and post-CHF: heat fluxes, ..delta..T (temperature difference between pin surface and fluid), heat transfer coefficients, and local fluid properties. A summary of the most interesting results from the program obtained during the past year is presented. These results are in the area of: (1) RELAP verification, (2) electric pin calibration, (3) time to critical heat flux (CHF), (4) heat transfer coefficient comparisons, and (5) nuclear fuel pin simulation.
Report Numbers
E 1.99:conf-781146-7
conf-781146-7
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1978.
"conf-781146-7"
6. water reactor safety research meeting, Germantown, MD, USA, 6 Nov 1978.
White, J.D.
Funding Information
W-7405-ENG-26
View MARC record | catkey: 14370229