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Anderson, T.T.; Kuzay, T.M.; Marr, W.W.; Miles, K.J.; Pedersen, D.R.; Thompson, D.H.; Wilson, R.E.
Argonne National Lab., IL (USA)1978
Argonne National Lab., IL (USA)1978
AbstractAbstract
[en] The SLSF is the largest U.S. in-reactor test vehicle for steady-state and transient experiments in an environment typical of a LMFBR core. The SLSF experiment program, sponsored by the Department of Energy, contributes to the LMFBR safety assurance program by providing data on key phenomena that occur during postulated reactor accidents. This paper describes completed SLSF experiments, in-core instrumentation used, and methods of data interpretation to determine sodium boiling and voiding dynamics. Boiling inception is shown to be identifiable from several types of in-core instruments. Location of the boiling front and void growth derived from experimental data are compared with analytical predictions. These and other data form the basis to improve understanding of accidents and to validate or guide the development of accident analysis methods
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1978; 26 p; ASME meeting; San Francisco, CA, USA; 10 - 15 Dec 1978; Available from NTIS., PC A03/MF A01
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Report
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Conference
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ACCIDENTS, BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FLUID MECHANICS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LIQUID METAL COOLED REACTORS, MECHANICS, PHASE TRANSFORMATIONS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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