Thermal analysis of LOFT containment vessel penetrations S-5E and S-6A
Thermal analysis of the LOFT containment vessel penetration S-6A was conducted for steady-state operation and blowdown transients. Penetration S-6A is a 20-inch pipe through which passes a 10-inch pipe from the steam generator containing 600/sup 0/F steam. Recommendations for penetration S-5E were based on the analysis of penetration S-6A. Penetration S-5E is an 18-inch pipe through which pass a 4-inch pipe containing the steam generator feedwater at 430/sup 0/F and a 0.5-inch pipe containing sample water at 600/sup 0/F. The thermal analysis is necessary to determine the maximum temperature gradient in the containment vessel around the penetrations. The outside of the penetrations protrude into a room adjacent to the containment vessel which will be maintained at a minimum temperature of 50/sup 0/F. The steady-state temperature inside the containment vessel was assumed to be 100/sup 0/F. Table I of LOFT Containment Vessel Specification S-1 was used for inside transient temperatures.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5580753
- Report Number(s):
- EGG/LTR-1217-2; ON: DE85015456
- Country of Publication:
- United States
- Language:
- English
Similar Records
LOFT containment vessel reevaluation for -20/sup 0/F air in space previously at 50/sup 0/F
Summary report of fuel rod displacement sensor for LOFT
Displacement sensor for measurement of fuel rod elongation in the LOFT reactors
Technical Report
·
Thu Dec 08 23:00:00 EST 1977
·
OSTI ID:5147561
Summary report of fuel rod displacement sensor for LOFT
Technical Report
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5553392
Displacement sensor for measurement of fuel rod elongation in the LOFT reactors
Technical Report
·
Sat Sep 01 00:00:00 EDT 1979
·
OSTI ID:5855932
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
BLOWDOWN
CONTAINERS
CONTAINMENT
CONTAINMENT SHELLS
LOFT REACTOR
PIPES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
STEADY-STATE CONDITIONS
STRESSES
SYSTEMS ANALYSIS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
THERMAL ANALYSIS
TRANSIENTS
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
BLOWDOWN
CONTAINERS
CONTAINMENT
CONTAINMENT SHELLS
LOFT REACTOR
PIPES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
STEADY-STATE CONDITIONS
STRESSES
SYSTEMS ANALYSIS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
THERMAL ANALYSIS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS