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research-article

Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR

[+] Author and Article Information
Jie Cheng

ASME Student Member, School of nuclear science and technology, Xi’an Jiaotong University, West Xianning Rd, Xian, Shaanxi 710049 P. R. China
jie.cheng@unlv.edu

Yingwei Wu

School of nuclear science and technology, Xi’an Jiaotong University, West Xianning Rd, Xian, Shaanxi 710049 P. R. China
wyw810@xjtu.edu.cn

Guanghui Su

School of nuclear science and technology, Xi’an Jiaotong University, West Xianning Rd, Xian, Shaanxi 710049 P. R. China
ghsu@mail.xjtu.edu.cn

Suizheng Qiu

School of nuclear science and technology, Xi’an Jiaotong University, West Xianning Rd, Xian, Shaanxi 710049 P. R. China
szqiu@mail.xjtu.edu.cn

Wenxi Tian

School of nuclear science and technology, Xi’an Jiaotong University, West Xianning Rd, Xian, Shaanxi 710049 P. R. China
wxtian@mail.xjtu.edu.cn

1Corresponding author.

ASME doi:10.1115/1.4042364 History: Received August 13, 2018; Revised December 17, 2018

Abstract

China Fusion Engineering Test Reactor (CFETR) is a test tokamak reactor being designed in China to bridge the gap between ITER and future fusion power plant. As one of the candidates, a water-cooled solid breeder blanket based on PWR (pressurized water reactor) and SCWR (super-critical water reactor) 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 uses 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 3-D model was performed by CFX with fluid-solid coupling approach. It was found that the temperature on the blanket can be effectively cooled on both water conditions, certified the feasibility of the blanket design with pressurized/supercritical water condition. It indicated that SCWR case had smaller safety margin than PWR case, but SCWR case would lead higher outlet temperature, thermal conductivity and heat exchange efficiency also. In addition, it was found that beryllium was the dominant factor leading a higher TBR.

Copyright (c) 2018 by ASME
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