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Mechanical analysis of LOFT reactor internals due to loss of coolant accidents

Technical Report ·
DOI:https://doi.org/10.2172/6798116· OSTI ID:6798116
A linear elastic analysis of the LOFT reactor internals was conducted to demonstrate the structural integrity of the reactor system during two Loss-of-Coolant Accidents (LOCA). Time dependent pressure transients were used to predict the behavior of the internals for the following LOCA's: 14'' 15 msec reactor vessel nozzle hot leg break; and 14'' 15 msec reactor vessel nozzle cold leg break. For the most severe design LOCA (Cold Leg LOCA), the LOFT reactor internals can safely withstand stresses due to a combination of pressure transient loading and seismic loading.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
6798116
Report Number(s):
LTR-1115-34(Suppl.1); RE-E-77-189(Suppl.1)
Country of Publication:
United States
Language:
English