Sodium-water reaction testing in support of LMFBR steam generator development
Journal Article
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:5558049
This paper briefly describes the Large Leak Test Rig after its conversion for the second series program to test internals typical of the Clinch River Breeder Reactor steam generator. The test article instrumentation provided and the data gathered are described. An explanation of the phenomena observed is discussed. The Series II tests are dedicated to investigating intermediate-to-large sodium-water reaction (SWR) and nonreactive events (nitrogen-sodium). The first two tests were double-ended guillotine (DEG) nonreactive tests utilizing single and double rupture disks for sodium containment to investigate pure hydraulic effects. The third test was locatd in about the same location as the other two and was a SWR DEG test. 9 refs.
- Research Organization:
- Rockwell Int, Canoga Park, Calif
- OSTI ID:
- 5558049
- Journal Information:
- Am. Soc. Mech. Eng., (Pap.); (United States), Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Vol. 81-JPGC-NE-3; ISSN ASMSA
- Country of Publication:
- United States
- Language:
- English
Similar Records
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
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SODIUM COOLED REACTORS
SPECIFICATIONS
STEAM GENERATORS
TEST FACILITIES
TESTING
THERMAL POWER PLANTS
TUBES
VAPOR GENERATORS