Actions for Experiments of ECCS strainer blockage and debris settling in suppression pools [electronic resource].

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Experiments of ECCS strainer blockage and debris settling in suppression pools [electronic resource].

Published
Washington, D.C. : U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, 1996.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
pages 201-225 : digital, PDF file
Additional Creators
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
If a rupture occurs in a nuclear power station pipe that leads to or from the reactor pressure vessel, the resultant Loss of Coolant Accident (LOCA) would initiate a chain of events involving complex flow phenomena. In a Boiling Water Reactor (BWR), the steam or liquid pipe break pressurizes the dry well, forcing the inert containment gases and steam through downcomers into the suppression pool, thoroughly mixing any particulates and pipe insulation debris carried with the gas flow to the pool. As the steam flow decreases, its unsteady condensation at the end of the downcomers (Condensation Oscillation and Chugging) produces continued water motion in the suppression pool and downcomers. During the blowdown event, high pressure and then low pressure pumps automatically start injecting water from the suppression pool into the reactor to keep its temperature under control. Proper functioning of this Emergency Core Cooling System (ECCS) is critical for the first 30 minutes or so, before operators have time to consider and align alternative sources of cooling water. A major concern for proper operation of the ECCS is the effect of fragmented insulation and plant particulates on the head loss at pump suction strainers. Sufficient loss could exceed the NPSH margin, causing cavitation with a resultant loss of pump capacity and longevity. The bead loss increases with the mass of debris accumulated on the pump strainers, which in turn is dependent on the debris concentration versus time in the suppression pool. This paper describes two sets of experiments that quantified the strainer head loss. One set of experiments considered the mixing and settling of fibrous insulation debris and fine iron oxide particles in the suppression pool during and after chugging. These tests used a reduced scale facility which duplicated the kinetic energy per unit water volume to define the concentration of the actual materials in the pool versus time.
Report Numbers
E 1.99:nureg/cp--0149-vol.3
E 1.99: conf-9510156--vol.3
conf-9510156--vol.3
nureg/cp--0149-vol.3
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Note
Published through SciTech Connect.
03/01/1996.
"nureg/cp--0149-vol.3"
" conf-9510156--vol.3"
"TI96007986"
23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995.
Johnson, A.B.; Murthy, P.; Hecker, G.E.; Padmanabhan.
View MARC record | catkey: 14364185