LOFT reactor vessel head instrument penetration, flange thermal analysis
A redesign of the LOFT instrument penetration necessitated a reanalysis of the thermal conditions existing in the nozzle and flange during a Loss of Coolant Experiment (LOCE). The maximum temperature gradient existing in the instrument flange will be used to determine the thermal stresses and maximum number of allowable cycles for the instrument flange. Based upon the specification and thermal conditions predicted by RELAP4/MOD5, the maximum temperature gradient through the flange will not exceed 216/sup 0/F. The thermal conditions predicted by RELAP4/MOD2 for the nozzle head penetration assembly were less severe than those used in the original thermal-stress analysis, so only the flange was analyzed here. If the thermal stresses are marginal with the 216/sup 0/F ..delta..T, a more detailed analysis should be done as the heat slab model used in RELAP is only one dimensional. Conservative hand calculations were performed for a heatup rate of 100/sup 0/F per hour and it was determined that the worst temperature gradient through the flange will be less than 81/sup 0/F.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6703251
- Report Number(s):
- LTR-1119-37; RE-A-78-028; TRN: 78-016168
- Resource Relation:
- Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
Similar Records
LOFT L2-3 scoping blowdown experiment safety analyses A, B, C, CD, CE, and CF
Fuel cladding temperature predictions for LOFT LOCE Ll-5. [PWR]
Related Subjects
LOFT REACTOR
PRESSURE VESSELS
NOZZLES
REACTOR INSTRUMENTATION
TEMPERATURE GRADIENTS
THERMAL STRESSES
CONTAINERS
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
STRESSES
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors