China Fusion Engineering Test Reactor (CFETR) is a test tokamak reactor being designed in China to bridge the gap between International Thermonuclear Experimental Reactor (ITER) and future fusion power plant. As one of the candidates, a water-cooled solid breeder blanket based on pressurized water and supercritical water conditions were proposed. In the concept, multiplying layers separated by three breeding layers were designed and optimized for higher tritium breeding ratio (TBR) and uniform heat distribution. This blanket adopts the Li2TiO3 lithium ceramic pebbles as the breeder, while beryllium pebbles as the neutron multiplier. In this paper, the thermal and fluid dynamic analyses of the optimized blanket on both water conditions were performed by numerical simulation, to discuss thermo-hydraulic performance of the blanket using pressurized water/supercritical water as its coolant. At first, the neutronic analysis was performed and based on the typical outboard equatorial blanket. Then, thermal and fluid dynamic analysis of the 3D model was carried out by CFX with fluid–solid coupling approach. It was found that the blanket can be effectively cooled on both water conditions, certified the feasibility of the blanket design with pressurized/supercritical water conditions. It indicated that supercritical water blanket had smaller safety margin than pressurized water blanket, but supercritical water blanket would lead to higher outlet temperature, thermal conductivity, and heat exchange efficiency also. In addition, the beryllium fraction was considered as one of the dominant factor, which leading a higher TBR in our simulations.
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October 2019
Research-Article
Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR
Jie Cheng,
Jie Cheng
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: jie.cheng@unlv.edu
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: jie.cheng@unlv.edu
1Corresponding author.
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Yingwei Wu,
Yingwei Wu
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: wyw810@xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: wyw810@xjtu.edu.cn
Search for other works by this author on:
G. H. Su,
G. H. Su
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xian 710049, Shaanxi, China
e-mail: ghsu@mail.xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road
,Xian 710049, Shaanxi, China
e-mail: ghsu@mail.xjtu.edu.cn
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Suizheng Qiu,
Suizheng Qiu
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xian 710049, Shaanxi, China
e-mail: szqiu@mail.xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road
,Xian 710049, Shaanxi, China
e-mail: szqiu@mail.xjtu.edu.cn
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Wenxi Tian
Wenxi Tian
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xian 710049, Shaanxi, China
e-mail: wxtian@mail.xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road
,Xian 710049, Shaanxi, China
e-mail: wxtian@mail.xjtu.edu.cn
Search for other works by this author on:
Jie Cheng
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: jie.cheng@unlv.edu
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: jie.cheng@unlv.edu
Yingwei Wu
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: wyw810@xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road,
Xian 710049, Shaanxi, China
e-mail: wyw810@xjtu.edu.cn
G. H. Su
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xian 710049, Shaanxi, China
e-mail: ghsu@mail.xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road
,Xian 710049, Shaanxi, China
e-mail: ghsu@mail.xjtu.edu.cn
Suizheng Qiu
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xian 710049, Shaanxi, China
e-mail: szqiu@mail.xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road
,Xian 710049, Shaanxi, China
e-mail: szqiu@mail.xjtu.edu.cn
Wenxi Tian
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xian 710049, Shaanxi, China
e-mail: wxtian@mail.xjtu.edu.cn
Xi'an Jiaotong University,
West Xianning Road
,Xian 710049, Shaanxi, China
e-mail: wxtian@mail.xjtu.edu.cn
1Corresponding author.
Manuscript received August 13, 2018; final manuscript received December 17, 2018; published online July 19, 2019. Assoc. Editor: Walter Ambrosini.
ASME J of Nuclear Rad Sci. Oct 2019, 5(4): 041302 (7 pages)
Published Online: July 19, 2019
Article history
Received:
August 13, 2018
Revised:
December 17, 2018
Citation
Cheng, J., Wu, Y., Su, G. H., Qiu, S., and Tian, W. (July 19, 2019). "Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR." ASME. ASME J of Nuclear Rad Sci. October 2019; 5(4): 041302. https://doi.org/10.1115/1.4042364
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