TRAC-PF1 analysis of loss-of-fluid test L6-7/L9-2 [electronic resource].

Published:: Los Alamos, N.M. : Los Alamos National Laboratory, 1984.
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:: Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

The Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC-PF1) to provide the capability for advanced best-estimate predictions of postulated accidents in pressurized-water reactors (PWRs) and for many thermal-hydraulic experimental facilities. As part of an independent assessment of TRAC-PF1, Loss-of-Fluid Test (LOFT) L6-7/L9-2 is analyzed and compared to the calculated results. Test L6-7 simulated a cooldown transient similar to the Arkansas Nuclear One Unit-2 turbine-trip transient. During the L9-2 phase of the test, the primary-coolant pumps were tripped and natural circulation cooled the core while the plant cooldown continued. The TRAC results matched the test data well during the L6-7 portion of the transient (0.0-324 s). However, during the L9-2 portion the calculated natural-circulation flow rate in the intact loop was much higher than the measured rate.

Report Numbers:

E 1.99:la-ur-83-3658
E 1.99: conf-840813-1
conf-840813-1
la-ur-83-3658

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Note:

Published through SciTech Connect.
01/01/1984.
"la-ur-83-3658"
" conf-840813-1"
"DE84004415"
Design, construction and operation of nuclear power plants conference, Portland, OR, USA, 5 Aug 1984.
Meier, J.K.

Funding Information:

W-7405-ENG-36

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