Experimental results of sodium-water reaction test No. 3 in LLTR
Computer-generated plots of the transient data obtained during the third sodium-water reaction test (SWR-3) and observations made after the test are presented. Similar to the first two tests of Series I, a double-ended guillotine rupture was produced in a water tube of the Atomics International Modular Steam Generator (AI-MSG). Prior to tube rupture, the temperature distribution in the vertical AI-MSG was linear from 600/sup 0/F at the bottom to 800/sup 0/F at the top. The rupture was located in the horizontal section 1.75 in. from the upper tubesheet. Peak pressures generated in this test were somewhat lower than the 400 psi and 500 psi measured in the prior tests; while peak temperatures, about 1600/sup 0/F, were higher than were measured previously. The interest examinations revealed no structural damage, material wastage, stress corrosion cracking, or dimensional changes. Additional reaction products have been accumulated in the bottom of the AI-MSG up to Spacer 3, so that the flow path in the AI-MSG to both the lower relief line and the drain line is restricted. The relief lines are relatively clear.
- Research Organization:
- Liquid Metal Engineering Center, Canoga Park, Calif. (USA)
- DOE Contract Number:
- EY-76-C-03-0700
- OSTI ID:
- 5010319
- Report Number(s):
- HEDL-TI-45-LMB-009
- Country of Publication:
- United States
- Language:
- English
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