Thermal-hydraulic and structural safety analysis of SLSF P3 experiment [electronic resource].
- Argonne, Ill. : Argonne National Laboratory, 1979. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 8 : digital, PDF file
- Additional Creators:
- Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- The Sodium Loop Safety Facility (SLSF) P3 experiment was the fourth in a series of in-reactor tests in the Engineering Test Reactor and simulated an unprotected flow coastdown in a 37 pin bundle. A comprehensive thermal-hydraulic analysis of the SLSF loop was coupled with a structural analysis of the test section hexcan outer duct in order to provide assurance, before the transient, that the loop would safely contain the P3 experiment. This analysis was performed for both the expected transient and for an off-normal condition of failure of redundant logic circuits to provide the proper pump power demand signal. Results of the analysis showed the hexcan outer duct to safely contain the P3 experiment for both conditions. The analysis for the expected transient has been verified by the successful completion of the P3 experiment.
- Published through SciTech Connect., 01/01/1979., "conf-790802-71", International conference on structural mechanics in reactor technology, Berlin, F.R. Germany, 13 Aug 1979., and Tessier, J.H.; Ragland, W.A.; Ariman, T.
- Funding Information:
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