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Title: Acoustics and voiding dynamics during SLSF simulations of LMFBR undercooling transients

Abstract

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.

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab., IL (USA)
Sponsoring Org.:
USDOE
OSTI Identifier:
6494487
Report Number(s):
CONF-781202-26
TRN: 79-006846
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: ASME meeting, San Francisco, CA, USA, 10 Dec 1978
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; LOSS OF FLOW; BOILING DETECTION; HYDRODYNAMICS; BOILING; ETR REACTOR; IN PILE LOOPS; REACTOR SAFETY EXPERIMENTS; SIMULATION; 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; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats

Anderson, T. T., Kuzay, T. M., Marr, W. W., Miles, K. J., Pedersen, D. R., Thompson, D. H., and Wilson, R. E.. Acoustics and voiding dynamics during SLSF simulations of LMFBR undercooling transients. United States: N. p., 1978. Web.
Anderson, T. T., Kuzay, T. M., Marr, W. W., Miles, K. J., Pedersen, D. R., Thompson, D. H., & Wilson, R. E.. Acoustics and voiding dynamics during SLSF simulations of LMFBR undercooling transients. United States.
Anderson, T. T., Kuzay, T. M., Marr, W. W., Miles, K. J., Pedersen, D. R., Thompson, D. H., and Wilson, R. E.. Sun . "Acoustics and voiding dynamics during SLSF simulations of LMFBR undercooling transients". United States. https://www.osti.gov/servlets/purl/6494487.
@article{osti_6494487,
title = {Acoustics and voiding dynamics during SLSF simulations of LMFBR undercooling transients},
author = {Anderson, T. T. and Kuzay, T. M. and Marr, W. W. and Miles, K. J. and Pedersen, D. R. and Thompson, D. H. and Wilson, R. E.},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6494487}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1978},
month = {1}
}

Conference:
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