Mechanical analysis of LOFT reactor internals due to loss of coolant accidents
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
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR INTERNALS
REACTORS
RESEARCH AND TEST REACTORS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR INTERNALS
REACTORS
RESEARCH AND TEST REACTORS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS