Citation: | Ye Tingpu, Lyu Lulu, Zhang Ge, He Hui, Cheng Cheng. Evaluation of Single-phase and Two-phase Mixing Models for Rod Bundle Channel[J]. Nuclear Power Engineering, 2022, 43(2): 47-52. doi: 10.13832/j.jnpe.2022.02.0047 |
[1] |
LAHEY R T JR, MOODY F J. The thermal-hydraulics of a boiling water nuclear reactor[M]. 2nd ed. La Grange Park: American Nuclear Society, 1993: 168-184.
|
[2] |
PANG B, CHENG X. Proposal of a new type of two-phase interchannel mixing model for application to subchannel analysis of PWR conditions[J]. Annals of Nuclear Energy, 2014, 73: 108-121. doi: 10.1016/j.anucene.2014.06.033
|
[3] |
KELLY J E, KAO S P, KAZIMI M S. THERMIT-2: a two-fluid model for light water reactor sub-channel transient analysis: MIT-EL-81-014[R]. USA,Cambridge: MIT, 1981.
|
[4] |
ROGERS J T, ROSEHART R G. Mixing by turbulent interchange in fuel bundles, correlations and inferences: ASME 72-HT-53[R]. USA: ASME, 1972
|
[5] |
SADATOMI M, KAWAHARA A, SATO Y. Prediction of the single-phase turbulent mixing rate between two parallel subchannels using a subchannel geometry factor[J]. Nuclear Engineering and Design, 1996, 162(2-3): 245-256. doi: 10.1016/0029-5493(95)01129-3
|
[6] |
BUES S G. Two phase turbulent mixing model for flow in rod bundle: WAPD-T-2438[R]. Pittsburgh: Bettis Atomic Power Laboratory, 1972.
|
[7] |
AVRAMOVA M. Development of an innovative spacer grid model utilizing computational fluid dynamics within a subchannel analysis tool[D]. University Park: The Pennsylvania State University, 2007.
|
[8] |
LEVY S. Prediction of two-phase pressure drop and density distribution from mixing length theory[J]. Journal of Heat Transfer, 1963, 85(2): 137-150. doi: 10.1115/1.3686033
|
[9] |
SADATOMI S, KAWAHARA A, SATO Y. Flow redistribution due to void drift in two-phase flow in a multiple channel consisting of two subchannels[J]. Nuclear Engineering and Design, 1994, 148(2-3): 463-474. doi: 10.1016/0029-5493(94)90126-0
|
[10] |
HOTTA A, SHIRAI H, AZUMA M, et al. A modified equilibrium void distribution model applicable to subchannel-scale vapor-liquid cross flow model for conventional square and tight lattice BWR fuel bundles[J]. Nuclear Engineering and Design, 2005, 235(9): 983-999. doi: 10.1016/j.nucengdes.2004.10.012
|
[11] |
SADATOMI M, KAWAHARA A, KANO K, et al. Single- and two-phase turbulent mixing rate between adjacent subchannels in a vertical 2 × 3 rod array channel[J]. International Journal of Multiphase Flow, 2004, 30(5): 481-498. doi: 10.1016/j.ijmultiphaseflow.2004.03.001
|
[12] |
LAHEY R T JR, SHIRALKAR B S, RADCLIFFE D W, et al. Out-of-pile subchannel measurements in a nine-rod bundle for water at 1000 PSIA[J]//HETSRONI G, SIDEMAN S, HARTNETTJ P. Proceedings of the international symposium on two-phase systems: Progress in Heat and Mass Transfer. Amsterdam: Elsevier, 1972: 345-363.
|
[13] |
VAN DER ROSS T. On two-phase exchange between interacting hydraulic channels[D]. Eindhoven: Eindhoven University of Technology, 1970.
|
[14] |
TAPUCU A, TEYSSEDOU A, TYE P, et al. The effect of turbulent mixing models on the predictions of subchannel codes[J]. Nuclear Engineering and Design, 1994, 149(1-3): 221-231. doi: 10.1016/0029-5493(94)90288-7
|