Refined analysis of effects on the LOFT containment building resulting from main steam and feedwater breaks
Technical Report
·
OSTI ID:6016205
Dynamic one-degree-of-freedom analyses of main steam breaks 8/10B and 8/11 and feedwater break 9/40 were performed using refined jet-plus-reaction force-time functions. Feedwater breaks 10/8B and 10/11 were analyzed statically using a refined maximum jet-plus-reaction force and assuming a dynamic load factor of 2. None of the breaks were found to stress the containment shell in excess of the ASME Boiler and Pressure Vessel Code allowables.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6016205
- Report Number(s):
- LTR-10-64
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURES
LOFT REACTOR
PIPES
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
STEAM LINES
STEAM SYSTEMS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURES
LOFT REACTOR
PIPES
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
STEAM LINES
STEAM SYSTEMS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS