LOFT containment vessel reevaluation for -20/sup 0/F air in space previously at 50/sup 0/F
Technical Report
·
OSTI ID:5147561
An evaluation is presented of the thermal gradients in LOFT containment vessel for new conditions. The new conditions are, (a) the outside air temperature in buildings attached to the outside of the containment was reduced from 50/sup 0/F to -20/sup 0/F, and (b) the LOCE conditions for inside the containment were reduced from one where T/sub max/ = 260/sup 0/F to one where T/sub max/ = 175/sup 0/F. The four areas considered in this evaluation include all areas affected by the surrounding buildings air temperature change and include (a) the railroad door frame, (b) portions of the stiffener ring, (c) containment vessel shell, and (d) penetrations and air locks.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- OSTI ID:
- 5147561
- Report Number(s):
- LTR-12-14; RE-A-77-146
- 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
CONFIGURATION
CONTAINMENT
CONTAINMENT BUILDINGS
LOFT REACTOR
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CONFIGURATION
CONTAINMENT
CONTAINMENT BUILDINGS
LOFT REACTOR
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS