Accumulation and Head-Loss Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris

In the event of a loss-of-coolant accident within the containment of a pressurized water reactor (PWR), piping thermal insulation and other materials in the vicinity of the break will be dislodged by break jet impingement. A series of tests was conducted on two different closed-loop test setups that...

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Bibliographic Details
Published in:Nuclear technology 2006-04, Vol.154 (1), p.69-84
Main Authors: Ghosh, Ashok K., Maji, Arup K., Leonard, Mark T., Rao, Dasari V., Letellier, Bruce C., Urgessa, Girum S., Ashbaugh, Scott G.
Format: Article
Language:English
Subjects:
Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Installations for energy generation and conversion: thermal and electrical energy
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Summary:In the event of a loss-of-coolant accident within the containment of a pressurized water reactor (PWR), piping thermal insulation and other materials in the vicinity of the break will be dislodged by break jet impingement. A series of tests was conducted on two different closed-loop test setups that were specifically designed to study the accumulation of debris and the consequent head loss across sump screens in PWRs. This paper addresses issues related to accumulation of transported debris on the sump screen and the consequent head loss. New test data that provide insights on head loss across a debris bed consisting of fragments of calcium silicate were generated.
ISSN:0029-5450
1943-7471
DOI:10.13182/NT06-A3718