Deposition of cesium iodide particles in bends and sections of vertical pipe under severe accident conditions

Journal of Aerosol Science

Volumn 31, Issue 9, 2000, Pages 1045-1059

  Hidaka, A ^a   Shibazaki, H ^a   Yoshino, T ^b   Sugimoto, J ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b TOSHIBA CORPORATION   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

CESIUM COMPOUNDS; COMPUTATIONAL FLUID DYNAMICS; COMPUTER SOFTWARE; DEPOSITION; NATURAL CONVECTION; NUCLEAR REACTOR ACCIDENTS; NUSSELT NUMBER; PARTICLES (PARTICULATE MATTER); PIPE FLOW; THERMAL EFFECTS; THERMAL GRADIENTS;

CESIUM IODIDE; SECONDARY FREE CONVECTION; THERMOPHORESIS;

AEROSOLS;

CESIUM IODIDE; IODIDE; UNCLASSIFIED DRUG;

AEROSOL; DEPOSITION; NUSSELT NUMBER; ORIENTATION; PIPE FLOW;

AEROSOL; ARTICLE; CALCULATION; DRY DEPOSITION; EXPERIMENTAL MODEL; NUCLEAR ACCIDENT; PRIORITY JOURNAL; SIMULATION; TEMPERATURE DEPENDENCE; TUBE; VALIDATION PROCESS;

EID: 0034124864     PISSN: 00218502     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0021-8502(00)00038-0     Document Type: Article

References (17)

1. Bayless, P. D. (1988) Analyses of natural circulation during a Surry station blackout using SCDAP/RELAP5. NUREG/CR-5214.
2. Brock J.R. On the theory of thermal forces acting on aerosol particles. J. Colloid Sci. 17:1962;768-780.
3. Castelo, A. R., Capitao, J. A., and Santi, G. D. (1999) International standard problem 40 - aerosol deposition and resuspension. Final Comparison Report, EUR 18708 EN, NEA/CSNI/R(99)4.
4. Churchill, S.W. (1983) Combined free and forced convection in channels, 2.5.10. Heat Exchanger Design Handbook. Hemisphere Publishing, Washington, DC.
5. Gelbard F., Tambour Y., Seinfeld J.H. Sectional representations for simulating aerosol dynamics. J. Colloid Interface Sci. 76(2):1980;541.
6. Hall W.B., Jackson J.D., Price P.H. Note on forced convection in a pipe having heat flux which varies exponentially along its length. J. Mech. Eng. Sci. 5:1963;40-52.
7. Heames, T. J., Williams, D. A., Bixler, N. E., Grimley, A. J., Wheatley, C. J., Johns, N. A., Domagala, P., Dickson, L. W., Alexander, C. A., Osborn-Lee, I., Zawadzki, S., Rest, J., Mason, A., & Lee, R. Y. (1992). VICTORIA: A mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions, NUREG/CR-5545.
8. Hidaka A., Igarashi M., Hashimoto K., Sato H., Yoshino T., Sugimoto J. Experimental and analytical study on the behavior of cesium iodide aerosol/vapor deposition onto inner surface of pipe wall under severe accident conditions. J. Nucl. Sci. Technol. 32(10):1995;1047-1053.
9. Hidaka, A., Maruyama, Y., Igarashi, M., Hashimoto, K., & Sugimoto, J. (1997). Experimental and analytical study on aerosol behavior in WIND project. Proc. of 8th Int. Topical Mtg. on Nucl. Reactor Thermal-Hydraulics (NURETH-8), Vol. 2, pp. 595-604.
10. Hidaka, A., Asaka, S., Ueno, S., Yoshino, T., and Sugimoto, J. (1999) Evaluation of steam generator U-tube integrity during PWR station blackout with secondary system depressurization. JAERI-Research 99-067.
11. Kajimoto, M., Muramatsu, K., Watanabe, N., Funasako, M. and Noguchi, T. (1991) Development of THALES-2, a computer code for coupled thermal-hydraulics and FP transport analyses for severe accident at LWRs and its application to analysis of FP revaporization phenomena. Proc. Int. Topical Meeting on Safety of Thermal Reactors, Portland, pp. 584-592.
12. Maruyama, Y., Igarashi, M., Nakamura, N., Hidaka, A., Hashimoto, K., and Sugimoto, J. (1996) Three-dimensional thermo-fluid-dynamic analysis of gas flow in straight piping with WINDFLOW code. Proc. Int. National Conf. on Nucl. Eng., Vol. 1, pp. 997-1008. ASME, New York.
13. Metais B., Eckert E.R.G. Forced, mixed and free convection regimes. J. Heat Transfer, Ser. C. 86:1964;295-296.
14. Rahn F.J., Collen J., Wright A.L. Aerosol behavior experiments on light water reactor primary systems. Nucl. Technol. 81:1988;158-182.
15. U.S. Nuclear Regulatory Commission, (1986). Reassessment of the technical bases for estimating source terms. NUREG-0956.
16. U.S. Nuclear Regulatory Commission, (1998). Risk assessment of severe accident-induced steam generator tube rupture. NUREG-1570.
17. Williams, D. A. (1994) OECD International standard problem number 34 Falcon code comparison report, AEA RS 3394.