Actions for Core thermal response during Semiscale Mod-1 blowdown heat transfer tests. [PWR] [electronic resource].

Email RIS file
Bookmark
Report an Issue

Core thermal response during Semiscale Mod-1 blowdown heat transfer tests. [PWR] [electronic resource].

Published
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1976.
Physical Description
Pages: 125 : digital, PDF file
Additional Creators
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
Selected experimental data and results calculated from experimental data obtained from the Semiscale Mod-1 PWR blowdown heat transfer test series are analyzed. These tests were designed primarily to provide information on the core thermal response to a loss-of-coolant accident. The data are analyzed to determine the effect of core flow on the heater rod thermal response. The data are also analyzed to determine the effects of initial operating conditions on the rod cladding temperature behavior during the transient. The departure from nucleate boiling and rewetting characteristics of the rod surfaces are examined for radial and axial patterns in the response. Repeatability of core thermal response data is also investigated. The test data and the core thermal response calculated with the RELAP4 code are compared.
Report Numbers
E 1.99:ancr-nureg-1285
ancr-nureg-1285
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
06/01/1976.
"ancr-nureg-1285"
Larson, T.K.
Idaho National Engineering Lab., Idaho Falls (USA)
Funding Information
E(10-1)-1375
View MARC record | catkey: 14370685