1981
DOI: 10.1115/1.3244434
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Critical Heat Flux Experiments and Correlation in a Long, Sodium-Heated Tube

Abstract: Critical heat flux (CHF) experiments were performed in the Steam Generator Test Facility (SGTF) at Argonne National Laboratory for application to liquid metal fast breeder reactor steam generators. The test section consisted of a single, straight, vertical, full-scale LMFBR steam generator tube with force-circulated water boiling upwards inside the tube heated by sodium flowing countercurrent in a surrounding annulus. The test section tube parameters were as follows: 10.1 mm i.d., 15.9 mm o.d., material = 2 1/… Show more

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Cited by 15 publications
(7 citation statements)
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“…(5) for the heat flux rather than Eq. (6). As in the simplest form of the gradient analysis, a sodium heat transfer coefficient taken from Ref.…”
Section: Coefficient Methodsmentioning
confidence: 99%
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“…(5) for the heat flux rather than Eq. (6). As in the simplest form of the gradient analysis, a sodium heat transfer coefficient taken from Ref.…”
Section: Coefficient Methodsmentioning
confidence: 99%
“…A form of this method was used in the analysis of experimental data presented in Ref. 6. Equation (1) was solved numerically with initial condition, Eq.…”
Section: Developing Methodsmentioning
confidence: 99%
See 2 more Smart Citations
“…Several models for this calculation were treated in detail in [21]. The most complete model (the developing method) was used in this study as described [21,22]. (The results [21] indicate that simpler models also will give good accuracy in the post-CHF region.)…”
Section: Experimental Data Facilitymentioning
confidence: 99%