TY - JOUR
T1 - Drift-flux modeling of void fraction for boiling two-phase flow in a tight-lattice rod bundle
AU - Hibiki, Takashi
AU - Miwa, Shuichiro
AU - Katono, Kenichi
PY - 2021/12
Y1 - 2021/12
N2 - The concept of a resource-renewal boiling water reactor (RBWR) that uses spent nuclear fuel as a nuclear fuel has been proposed to reduce the period required for the radiotoxicity of spent nuclear fuel decaying to the same level as natural uranium ore from about 100,000 years to about 300 years. The RBWR core is designed based on the tight-lattice core concept to reduce the ratio of a moderator to fuel. Since the void fraction is one of the most critical design parameters for the RBWR, this study developed the drift-flux correlation applicable to two-phase flow in the tight-lattice rod bundle. The prediction error of the newly developed drift-flux correlation is ±11.7 %. The validated rod bundle geometrical conditions are the number of rods from 4 to 37, the rod spacing from 1.0 to 2.0 mm, the rod diameter from 9.0 to 13.7 mm, the mixture volumetric flux from 0.11 to 211 m/s, and the pressure from 0.1 to 7.2 MPa. The comparison in the distribution parameter between the tight-lattice rod bundle and the conventional BWR rod bundle indicates that the distribution parameter for the tight-lattice rod bundle is larger than that for the conventional BWR rod bundle. The increased distribution parameter in the tight-lattice core may be due to the small rod spacing and the triangular array of the rods. Both of the small rod spacing and the triangular array of the rods tend to increase the distribution parameter.
AB - The concept of a resource-renewal boiling water reactor (RBWR) that uses spent nuclear fuel as a nuclear fuel has been proposed to reduce the period required for the radiotoxicity of spent nuclear fuel decaying to the same level as natural uranium ore from about 100,000 years to about 300 years. The RBWR core is designed based on the tight-lattice core concept to reduce the ratio of a moderator to fuel. Since the void fraction is one of the most critical design parameters for the RBWR, this study developed the drift-flux correlation applicable to two-phase flow in the tight-lattice rod bundle. The prediction error of the newly developed drift-flux correlation is ±11.7 %. The validated rod bundle geometrical conditions are the number of rods from 4 to 37, the rod spacing from 1.0 to 2.0 mm, the rod diameter from 9.0 to 13.7 mm, the mixture volumetric flux from 0.11 to 211 m/s, and the pressure from 0.1 to 7.2 MPa. The comparison in the distribution parameter between the tight-lattice rod bundle and the conventional BWR rod bundle indicates that the distribution parameter for the tight-lattice rod bundle is larger than that for the conventional BWR rod bundle. The increased distribution parameter in the tight-lattice core may be due to the small rod spacing and the triangular array of the rods. Both of the small rod spacing and the triangular array of the rods tend to increase the distribution parameter.
KW - Drift-flux model
KW - Rod bundle
KW - Tight lattice core
KW - Two-phase flow
KW - Void fraction
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U2 - 10.1016/j.ijheatmasstransfer.2021.121769
DO - 10.1016/j.ijheatmasstransfer.2021.121769
M3 - 21_Publication in refereed journal
VL - 180
JO - International Journal of Heat and Mass Transfer
JF - International Journal of Heat and Mass Transfer
SN - 0017-9310
M1 - 121769
ER -