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Title: Influence of steam generator plugging and break size on large-break loss-of-collant accidents

Journal Article · · Nuclear Safety
OSTI ID:226777
;  [1]
  1. Jozef Stefan Institute, Ljubljana (El Salvador)

The large-break loss-of-coolant accident (LBLOCA) is the design-basis accident in the Krsko pressurized-water reactor, the only power reactor in Slovenia. Because numbers of steam generator tubes are plugged as the steam generator ages, and this directly influences the primary system behavior during an LBLOCA, this accident was re-examined assuming various proportions of blocked tube from 0 to 22%. The size of the break was changes from 25 to 45% of the initial cold-leg cross section. The analysis was made with RELAP4/MOD6 as the main code in the conservative mode rather than as the best-estimate code. The methodology separately considers the blowdown phase, the refill phase, and the reflood phase. It was found that the peak clad temperature rises as plugging increases up to about 10% plugging and tends to be constant or even decrease as the plugging increases beyond this point. It was also found that results are strongly dependent on the methodology used. 17 refs., 9 figs., 3 tabs.

OSTI ID:
226777
Journal Information:
Nuclear Safety, Vol. 32, Issue 3; Other Information: PBD: Jul-Sep 1991
Country of Publication:
United States
Language:
English