Citation: | Zhang Qi, Liu Zhenhai, Li Chenxi, Wang Haoyu, Fu Junsen, Li Junlong, Huang Yongzhong, Xiao Yao, Gu Hanyang. Development and Validation of the Sub-channel Code for Helical Cruciform Fuel Assembly of PWR[J]. Nuclear Power Engineering, 2025, 46(4): 94-101. doi: 10.13832/j.jnpe.2024.080009 |
[1] |
MALONE J, TOTEMEIER A, SHAPIRO N, et al. Lightbridge corporation’s advanced metallic fuel for light water reactors[J]. Nuclear Technology, 2012, 180(3): 437-442. doi: 10.13182/NT12-A15354
|
[2] |
CARMACK W J, PORTER D L, CHANG Y I, et al. Metallic fuels for advanced reactors[J]. Journal of Nuclear Materials, 2009, 392(2): 139-150. doi: 10.1016/j.jnucmat.2009.03.007
|
[3] |
张涛,韩文斌,申鹏飞,等. 螺旋十字型燃料棒中子物理及热工水力性能分析[J]. 核动力工程,2023, 44(S1): 69-74.
|
[4] |
CONBOY T M, MCKRELL T J, KAZIMI M S. Experimental investigation of hydraulics and lateral mixing for helical-cruciform fuel rod assemblies[J]. Nuclear Technology, 2013, 182(3): 259-273. doi: 10.13182/NT12-58
|
[5] |
CONBOY T M. Thermal-hydraulic analysis of cross-shaped spiral fuel in high power density BWRs[D]. Cambridge: Massachusetts Institute of Technology, 2007.
|
[6] |
XIAO Y, FU J S, ZHANG Q, et al. Development of a flow sweeping mixing model for helical fuel rod bundles[J]. Annals of Nuclear Energy, 2021, 160: 108428. doi: 10.1016/j.anucene.2021.108428
|
[7] |
蔡伟华,韦徵圣,李石磊,等. 5×5花瓣形燃料棒束组件内单相流动与换热特性数值模拟研究[J]. 原子能科学技术,2021, 55(11): 1939-1949. doi: 10.7538/yzk.2021.youxian.0593
|
[8] |
李惠悦. 冷却剂在星形螺旋燃料组件中的流动与传热特性研究[D]. 北京: 北京化工大学,2021.
|
[9] |
SALKO R K, AVRAMOVA M N. CTF theory manual: CASL-U-2016-1110-000[R]. Oak Ridge: Oak Ridge National Laboratory, 2016.
|
[10] |
ZHANG Q, CONG T L, XIAO Y, et al. Comparison on the thermal–hydraulic characteristics of wire-wrapped fuel and helical cruciform fuel by numerical simulation[J]. Annals of Nuclear Energy, 2022, 177: 109291. doi: 10.1016/j.anucene.2022.109291
|
[11] |
张琦,顾汉洋,肖瑶,等. 5×5螺旋十字型棒束组件阻力与交混特性实验研究[J]. 原子能科学技术,2021, 55(6): 1060-1066. doi: 10.7538/yzk.2020.youxian.0436
|
[12] |
丛腾龙,高勇,程毅,等. 螺旋十字燃料组件沸腾传热及燃料元件热力耦合特性研究[J]. 核动力工程,2023, 44(5): 216-222.
|
[13] |
张琦. 螺旋燃料组件流动传热特性研究与子通道程序开发[D]. 上海: 上海交通大学,2023.
|
[14] |
ZHANG Q, WANG H Y, LI J L, et al. Experimental study on flow resistance and phase distribution of gas-liquid flow in helical cruciform fuel assembly[J]. Annals of Nuclear Energy, 2025, 210: 110838. doi: 10.1016/j.anucene.2024.110838
|
[15] |
ZHANG Q, WANG H Y, LI J L, et al. Numerical simulation of flow and heat transfer phenomenon of helical cruciform fuel assembly under subcooled boiling[J]. Progress in Nuclear Energy, 2024, 175: 105349. doi: 10.1016/j.pnucene.2024.105349
|
[16] |
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: 137-138.
|
[17] |
CHEN J C. Correlation for boiling heat transfer to saturated fluids in convective flow[J]. Industrial & Engineering Chemistry Process Design and Development, 1966, 5(3): 322-329.
|
[18] |
BUES S G. Two phase turbulent mixing model for flow in rod bundle: WAPD-T-2438[R]. Pittsburgh: Bettis Atomic Power Laboratory, 1972.
|
[19] |
Churchill S W. Friction-factor equation spans all fluid-flow regimes[J]. Chemical Engineering, 1977, 84(24): 91-92.
|
[20] |
DITTUS F W, BOELTER L M K. Heat transfer in automobile radiators of the tubular type[J]. University of California Press, Berkeley, University of California Publications in Engineering, 1930, 2(13): 443-461.
|