Actions for Analysis of large-leak test SWAT-3 Run-6 data by use of sodium-water-reaction analysis code SWAAM-I [electronic resource].

Email RIS file
Bookmark
Report an Issue

Analysis of large-leak test SWAT-3 Run-6 data by use of sodium-water-reaction analysis code SWAAM-I [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1982.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
42 pages : digital, PDF file
Additional Creators
Argonne National Laboratory, United States. Department of Energy, 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 Sodium Water Advanced Analysis Method computer code (SWAAM-I) is used to analyze the large-leak test data SWAT-3 Run-6. The SWAT-3 is the mockup of the secondary system of the Japanese breeder-reactor demonstration plant Monju. The steam-generator design for the Monju reactor was a helical-coil-tube type with a cover-gas space, and the SWAT-3 Run-6 Test vessel simulates this design of the steam generator. The objectives of this work are: (1) to examine the adequacy of the SWAAM-I code for the helical-coil-tube steam-generator system, (2) to understand and confirm the understanding of phenomena that have major design implications, and (3) to define needs for additional development of SWAAM-I code capabilities.
Report Numbers
E 1.99:anl-ct--82-4
anl-ct--82-4
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
02/01/1982.
"anl-ct--82-4"
"TI82014779"
Lin, H.C.; Shin, Y.W.
Funding Information
W-31-109-ENG-38
View MARC record | catkey: 14366886