Thermal Hydraulic Design and Analysis of a Water-Cooled Ceramic Breeder Blanket with Superheated Steam for CFETR

CHENG Xiaoman (成晓曼); MA Xuebin (马学斌); JIANG Kecheng (蒋科成); CHEN Lei (陈磊); HUANG Kai (黄凯); LIU Songlin (刘松林)

doi:10.1088/1009-0630/17/9/11

Plasma Science and Technology > 2015 > 17(9): 787-791. > DOI: 10.1088/1009-0630/17/9/11

CHENG Xiaoman (成晓曼), MA Xuebin (马学斌), JIANG Kecheng (蒋科成), CHEN Lei (陈磊), HUANG Kai (黄凯), LIU Songlin (刘松林). Thermal Hydraulic Design and Analysis of a Water-Cooled Ceramic Breeder Blanket with Superheated Steam for CFETR[J]. Plasma Science and Technology, 2015, 17(9): 787-791. DOI: 10.1088/1009-0630/17/9/11

Citation:

PDF (7576 KB)

Thermal Hydraulic Design and Analysis of a Water-Cooled Ceramic Breeder Blanket with Superheated Steam for CFETR

Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China

Funds: supported by the National Special Project for Magnetic Confined Nuclear Fusion Energy of China (Nos. 2013GB108004, 2014GB122000 and 2014GB119000), and National Natural Science Foundation of China (No. 11175207)

More Information

Received Date: September 25, 2014

Graphical Abstract

Abstract

Abstract

The water-cooled ceramic breeder blanket (WCCB) is one of the blanket candidates for China fusion engineering test reactor (CFETR). In order to improve power generation efficiency and tritium breeding ratio, WCCB with superheated steam is under development. The thermal-hydraulic design is the key to achieve the purpose of safe heat removal and efficient power generation under normal and partial loading operation conditions. In this paper, the coolant flow scheme was designed and one self-developed analytical program was developed, based on a theoretical heat transfer model and empirical correlations. Employing this program, the design and analysis of related thermal-hydraulic parameters were performed under different fusion power conditions. The results indicated that the superheated steam water-cooled blanket is feasible.
- thermal hydraulic} WCCB,
- superheated steam

FullText(HTML)

References (1)

References

Liu Songlin, Pu Yong, Cheng Xiaoman, et al. 2014,Fusion Engineering and Design, 89: 1380 2 Okano K, Asaoka Y, Yoshida T, et al. 2000, Nuclear Fusion, 40: 635 3 Nomoto Y, Ishida T, Ise H, et al. 2001, Fusion Engineering and Design, 58: 543 4 Asaoka Y, Okano K, Yoshida T, et al. 2000, Fusion Engineering and Design, 48: 397 5 Someya Y, Tobita K, Utoh H, et al. 2012, A feasible DEMO blanket concept based on water cooled solid breeder. 24th IAEA Fusion Energy Conference, Diego, USA 6 Ma Xuebin, Liu Songlin, Li Jia, et al. 2014, Plasma Science and Technology, 16: 390 7 Tobita K, Nishio S, Enoeda M, et al. 2009, Nuclear Fusion, 49: 075029 8 Tobita K, Utoh H, Liu C, et al. 2010, Fusion Engineering and Design, 85: 1342 9 Yang Shiming, Tao Wenquan. 2006, Heat Transfer.Higher Education Press, Beijng (in Chinese) 10 Liu Z, Winterton R H S. 1991, Heat and Mass Transfer, 34: 2759 11 Adou-Sena A, Ying A, Abdou M. 2006, Fusion Scienceand Technology, 5: 1094 12 Uchida M, Ishitsuka E, Kawamura H. 2003, Fusion Engineering and Design, 69: 499

[1]	Fangyuan LIU (刘方圆), Deping YU (余德平), Cheng LV (吕程), Yazhou DUAN (段亚洲), Yanjie ZHONG (钟严杰), Jin YAO (姚进). Experimental study on the jet characteristics of a steam plasma torch[J]. Plasma Science and Technology, 2018, 20(12): 125401. DOI: 10.1088/2058-6272/aad9f1
[2]	Xiaokang ZHANG (张小康), Songlin LIU (刘松林), Xia LI (李夏), Qingjun ZHU (祝庆军), Jia LI (李佳). Updated neutronics analyses of a water cooled ceramic breeder blanket for the CFETR[J]. Plasma Science and Technology, 2017, 19(11): 115602. DOI: 10.1088/2058-6272/aa808b
[3]	Yong LU (卢勇), Lijun CAI (蔡立君), Yuxiang LIU (刘雨祥), Jian LIU (刘健), Yinglong YUAN (袁应龙), Guoyao ZHENG (郑国尧), Dequan LIU (刘德权). Thermal-hydraulic analysis of the HL-2M divertor using an homogeneous equilibrium model[J]. Plasma Science and Technology, 2017, 19(9): 95601-095601. DOI: 10.1088/2058-6272/aa7628
[4]	GAO Fangfang (高芳芳), ZHANG Xiaokang (张小康), PU Yong (蒲勇), ZHU Qingjun (祝庆军), LIU Songlin (刘松林). Analysis of Time-Dependent Tritium Breeding Capability of Water Cooled Ceramic Breeder Blanket for CFETR[J]. Plasma Science and Technology, 2016, 18(8): 865-869. DOI: 10.1088/1009-0630/18/8/13
[5]	ZHU Qingjun (祝庆军), LI Jia (李佳), LIU Songlin (刘松林). Neutronics Analysis of Water-Cooled Ceramic Breeder Blanket for CFETR[J]. Plasma Science and Technology, 2016, 18(7): 775-780. DOI: 10.1088/1009-0630/18/7/13
[6]	LI Jia (李佳), ZHANG Xiaokang (张小康), GAO Fangfang (高芳芳), PU Yong (蒲勇). Neutronics Comparison Analysis of the Water Cooled Ceramics Breeding Blanket for CFETR[J]. Plasma Science and Technology, 2016, 18(2): 179-183. DOI: 10.1088/1009-0630/18/2/14
[7]	HAN Le(韩乐), CHANG Haiping(常海萍), ZHANG Jingyang(张镜洋), LIU Nan(刘楠), XU Tiejun(许铁军). The Effects of Nonuniform Thermal Boundary Condition on Thermal Stress Calculation of Water-Cooled W/Cu Divertor[J]. Plasma Science and Technology, 2014, 16(10): 988-994. DOI: 10.1088/1009-0630/16/10/16
[8]	ZHANG Shanwen(张善文), SONG Yuntao(宋云涛), WANG Zhongwei(王忠伟), LU Su(卢速), JI Xiang(戢翔), DU Shuangsong(杜双松), LIU Xufeng(刘旭峰), FENG Changle(冯昌乐), YANG Hong(杨洪), WANG Songke(王松可), LUO Zhiren(罗志仁). Rapid Thermal-Hydraulic Analysis and Design Optimization of ITER Upper ELM Coils[J]. Plasma Science and Technology, 2014, 16(10): 978-983. DOI: 10.1088/1009-0630/16/10/14
[9]	YANG Hong(杨洪), SONG Yuntao(宋云涛), WANG Zhongwei(王忠伟). Thermal and Hydraulic Analysis of the ITER Upper Vertical Stabilization Coil[J]. Plasma Science and Technology, 2014, 16(7): 706-711. DOI: 10.1088/1009-0630/16/7/13
[10]	MA Xuebin(马学斌), LIU Songlin(刘松林), LI Jia(李佳), PU Yong(蒲勇), CHEN Xiangcun(陈香存). Preliminary Design of a Helium-Cooled Ceramic Breeder Blanket for CFETR Based on the BIT Concept[J]. Plasma Science and Technology, 2014, 16(4): 390-395. DOI: 10.1088/1009-0630/16/4/16