Flow excursion time scales in the advanced neutron source reactor

Nuclear Engineering and Design

Volumn 177, Issue 1-3, 1997, Pages 131-145

  Sulfredge, C D ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0346580055     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(97)00190-8     Document Type: Article

References (15)

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2. Collier, J.G., 1981. Convective Boiling and Condensation. McGraw Hill, New York, pp. 189-191.
3. Costa, J., 1967. Measurement of the momentum pressure drop and study of the appearance of vapor and change in the void fraction in subcooled boiling at low pressure. Proc. Meeting of the European Group Double-Phase, Winfrith. Translated from French as ORNL/TR-90/21.
4. Crabtree, A., Siman-Tov, M., 1993. Thermophysical properties of saturated light and heavy water for advanced neutron source applications. ORNL/TM-12322.
5. Davis, E.J., Anderson, G.H., 1966. The incipience of nucleate boiling in forced convection flow. AIChE J. 12, 774-780.
6. Felde, D.K. et al., 1994. Advanced neutron source reactor thermal-hydraulic test loop facility description. ORNL/ TM-12397.
7. Harrington, R.M. et al., 1992. Advanced Neutron Source Conceptual Safety Analysis Report, Oak Ridge National Laboratory, Ch. 15.
8. Hsu, Y.Y., 1962. On the size range of active nucleation cavities on a heating surface. ASME J. Heat Transfer 84, 207-213.
9. Ledinegg, M., 1938. Instability of flow during natural and forced circulation. Die Warme 61, 891-898.
10. Levy, S., 1967. Forced convection subcooled boiling - prediction of vapor volumetric fraction. Int. J. Heat Mass Transfer 10, 951-965.
11. Mikic, B.B., Rohsenow, W.M., Griffith, P., 1970. On bubble growth rates. Int. J. Heat Mass Transfer 13, 657-666.
12. Saha, P., Zuber, N., 1974. Point of net vapor generation and vapor void fraction in subcooled boiling. Proc. 5th Int. Heat Transfer Conf. Tokyo 4, 175-179.
13. Siman-Tov, M., Gambill, W.R., Nelson, W.R., Ruggles A.E., Yoder, G.L., 1991. Thermal-hydraulic correlations for the advanced neutron source reactor fuel element design and analysis. Proc. 1991 ASME Winter Annu. Meet., Atlanta.
14. Wemple, C.A. et al., 1993. Advanced Neutron Source Idaho National Engineering Laboratory Monthly Report for January 1993, Memo to Selby, D.L. of ORNL.
15. Yoder, G.L. et al., 1994. ANS Transient Thermal Hydraulic Task Monthly Progress Report For December 1993, Memo to Harrington, R.M. and Rosenbalm, K.F. of ORNL.