Article
Nuclear Science & Technology
Eunnam Bang, Hyoung Chan Kim, Kyungmin Kim, Jieun Choi, Suk-Ho Hong
Summary: The quality of joint between armor materials and heat sink is crucial in the engineering of the divertor vertical target. The gas pressure casting method is effective in improving the bonding strength between tungsten armor and pure copper interlayer, enhancing the overall performance of the component.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Materials Science, Multidisciplinary
J. de Prado, M. Sanchez, I. Izaguirre, D. Swan, A. Urena
Summary: The Cu-Ge system has been evaluated as a filler material for heat sink components in future fusion power plants. The results showed that increasing Ge content resulted in lower brazing temperatures and decreased thermal affectation on the base material. The rigid filler manufacturing route produced more continuous joints and both lower and richer Ge compositions led to joints with higher strength.
MATERIALS TODAY COMMUNICATIONS
(2022)
Article
Materials Science, Multidisciplinary
Javier de Prado, Maria Sanchez, David Swan, Alejandro Urena
Summary: This study evaluated the mechanical properties and microstructure correlation of a W-CuCrZr joint brazed using 80Cu-20Ti filler material in a high vacuum furnace. Results showed that the as-received hardness of W remained unchanged, while the CuCrZr base material softened after the brazing process. The shear strength of the brazed joint was 96 +/- 15 MPa, with fracture propagating at the W-braze interface.
Article
Thermodynamics
Mingxiang Lu, Le Han, Jianhong Zhou, Qi Zhao, Qiang Li, Xuemei Chen
Summary: This study analyzed the thermohydraulic and thermal fatigue characteristics of a W/Cu flat-type microchannel cooling structure. The numerical results showed good temperature uniformity and heat transfer performance, while the experimental results demonstrated its ability to withstand 1000 cycles of thermal fatigue under a steady-state heat load of 20 MW/m(2).
APPLIED THERMAL ENGINEERING
(2024)
Article
Nuclear Science & Technology
Zhen Chen, Qiang Li, Wuqingliang Peng, Ran Wei, Wanjing Wang, Kecheng Jiang, Jichao Wang, Zhiwei Pan, Chunyi Xie, Xiang Geng, Lingming Huang, Guangnan Luo
Summary: This study investigates a novel hypervapotron cooling concept and designs a W/Cu flat-type mock-up to enhance the heat removal capability of divertor PFCs in a fusion reactor. Thermal simulations demonstrate the excellent heat removal capability of the cross-ribs structure, and the prepared compound module performs well in HHF testing.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
Ji-Chao Wang, Wanjing Wang, Qiang Li, Sigui Qin, Mingzhun Lei, Guang-Nan Luo
Summary: The fatigue property of W/steel joints is crucial for predicting the life of the First Wall (FW), requiring the evaluation of fatigue performance with coolant of normal pressure and temperature. By combining numerical calculation and experiment validation, the relationship between heat flux, maximum temperature, and strain is established to predict FW life using the Manson-Coffin formula (MC). The feasibility of this method is confirmed through fatigue tests in a High Heat Flux test platform equipped with an electron gun.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Materials Science, Multidisciplinary
Yuanyuan Chen, Yuan Huang, Lu Han, Dongguang Liu, Laima Luo, Chong Li, Chenxi Liu, Zumin Wang
Summary: W/CuCrZr alloy composite panels are promising plasma-facing components for future nuclear-fusion reactors, and a vacuum diffusion bonding method involving sandblasting of the W substrate surface and Cu electroplating was developed to achieve high bond strength. The improved joint obtained with this method showed superior shear bond strength and bonding quality compared to conventional vacuum diffusion bonding methods.
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
(2021)
Article
Materials Science, Multidisciplinary
Yuanyuan Chen, Zhang Liu, Chenxi Liu, Yuan Huang, Yongchang Liu, Zumin Wang
Summary: This study developed a method for bonding W-Y2O3 composites and CuCrZr heat sinks, which improved the interface bonding strength through surface nanoporosification, Cu magnetron sputtering, and annealing. The well-integrated interface facilitated the development of plasma-facing components for future fusion devices.
MATERIALS CHARACTERIZATION
(2022)
Article
Nuclear Science & Technology
T. Yamashita, M. Tokitani, Y. Hamaji, H. Noto, S. Masuzaki, T. Muroga
Summary: In this study, the reliable bonding between tungsten and reduced activation ferritic/martensitic steel was achieved using BNi-6 filler material, with a pure copper interlayer to absorb residual stress. The heat treatment process resulted in a fine joint structure without cracks or large pores, and detailed analysis showed that Ni and P elements contributed to the hardening effect of the bonding layer. Heat loading tests indicated that these hardening layers did not negatively impact the joint properties.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
M. Tokitani, Y. Hamaji, Y. Hiraoka, S. Masuzaki, H. Tamura, H. Noto, T. Tanaka, T. Muroga, A. Sagara
Summary: The deformation and fracture behavior of oxide dispersion strengthened copper alloy and stainless steel joints were investigated, revealing differences in plastic deformation and fracture behavior between the joints. The influence of a second-step heat treatment on the joints was also examined, showing no significant changes in microstructure or mechanical strength.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Nuclear Science & Technology
I. Izaguirre, J. de Prado, M. Sanchez, D. Salazar, A. Urena
Summary: The paper studies the use of melt-spinning technique to fabricate flexible 80Cu-20Ti ribbons, which can be used to cover the divertor or first wall pipe in future fusion reactors. The best conditions for fabrication are a 0.8 mm diameter nozzle and a linear wheel-speed of 30 m/s. The fabricated ribbons exhibit low Cu4Ti intermetallic phase formation, enhancing their adaptability. The ribbons are large enough to cover the perimeter of the pipe. The selected conditions are also suitable for use as filler material in W-CuCrZr brazed joints, resulting in high metallic continuity interfaces with no thermal effect on the W base material.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Nuclear Science & Technology
Siqing Feng, Xuebing Peng, Yuntao Song, Peng Liu, Wei Song, Xin Mao, Xinyuan Qian, Muhammad Salman Khan
Summary: This paper describes a continuous V-shaped structure with a hypervapotron for a divertor target, which improves cooling performance and detachment in the strike point area. The design and manufacture of this structure are discussed.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Chemistry, Multidisciplinary
Ya Xi, Gaoyong He, Xiang Zan, Kang Wang, Dahuan Zhu, Laima Luo, Rui Ding, Yucheng Wu
Summary: The microstructure and damage of the upper divertor components in EAST were analyzed using metallography, EBSD, and SEM. The components exhibited cracking, recrystallization, and interface debonding due to the combined effects of heat load and plasma irradiation. Cracks propagated downward along the heat flux direction, displaying intergranular fracture. The thermal loads caused recrystallization and the formation of cracks in both recrystallized and rolled areas. EBSD boundary maps revealed the recrystallization area determined by the heat flux distribution. Debonding occurred at the Cu/CuCrZr interface of cooling components near the thermal loading area, leading to structural integrity damage.
APPLIED SCIENCES-BASEL
(2023)
Article
Physics, Fluids & Plasmas
Mingxiang Lu, Le Han, Qi Zhao, Juncheng Qiu, Jianhong Zhou, Dinghua Hu, Nanyu Mou, Xuemei Chen
Summary: This study proposes a new strategy using microchannel cooling technology to remove high heat load on the divertor. The results demonstrate that this method is effective in reducing temperature and improving the stability of the divertor, providing a promising solution for divertor design.
PLASMA SCIENCE & TECHNOLOGY
(2022)
Article
Nuclear Science & Technology
Nanyu Mou, Xiyang Zhang, Qianqian Lin, Xianke Yang, Le Han, Lei Cao, Damao Yao
Summary: This paper introduces an improved vacuum brazing technology for connecting copper to oxide dispersion strengthened copper alloy and summarizes the production process, high heat flux testing, non-destructive testing, and surface results of the flat-type copper/oxide dispersion strengthened copper/steel mockup after the high heat flux test. The test results demonstrate that the mockup manufactured according to the production process still has structural integrity and interface integrity under cyclic high heat loads.
NUCLEAR ENGINEERING AND TECHNOLOGY
(2023)
Article
Optics
Zhiwei Pan, Shenghong Huang, Yong Su, Meixia Qiao, Qingchuan Zhang
OPTICS AND LASERS IN ENGINEERING
(2020)
Article
Nuclear Science & Technology
Kun Tian, Tiejun Xu, Le Han, Lei Yang, Lei Cao, Lei Li, Damao Yao
Summary: This study introduces the design and test results of the in-vessel cooling water system for the lower divertor of EAST, proving that the design is rational and meets the requirements, providing support for the next design phase.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Thermodynamics
Shenghong Huang, Linlin Wang, Zhiwei Pan, Zhanru Zhou
Summary: A new scheme incorporating hybrid submillimetre/micro/nano-structured surfaces has been proposed for highly efficient and reliable water cooling in future nuclear fusion engineering. Experimental results show promising enhancements in heat transfer performance and flow resistance compared to existing cooling schemes, indicating potential for practical application.
APPLIED THERMAL ENGINEERING
(2021)
Article
Nuclear Science & Technology
Zhen Chen, Qiang Li, Wuqingliang Peng, Ran Wei, Wanjing Wang, Kecheng Jiang, Jichao Wang, Zhiwei Pan, Chunyi Xie, Xiang Geng, Lingming Huang, Guangnan Luo
Summary: This study investigates a novel hypervapotron cooling concept and designs a W/Cu flat-type mock-up to enhance the heat removal capability of divertor PFCs in a fusion reactor. Thermal simulations demonstrate the excellent heat removal capability of the cross-ribs structure, and the prepared compound module performs well in HHF testing.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Physics, Fluids & Plasmas
Shenghong Huang, Zhiwei Pan, Menglai Jiang, Kai Zhao, Yong Su
Summary: In this study, the deep cracking failure process on the tungsten layer of a flat-type divertor mockup during high heat flux loadings was monitored and measured using an improved digital image correlation technique. The thermal-mechanical behavior, from deformation to crack initiation and propagation, was successfully measured and traced based on full field and local strain and displacement measurements of the target divertor mockup.
Article
Physics, Fluids & Plasmas
Xiyang Zhang, Lei Yin, Tiejun Xu, Nanyu Mou, Damao Yao
Summary: The design of the China Fusion Engineering Test Reactor (CFETR) device is a crucial task in the research on fusion energy in China. This article proposes a new concept of an integral hybrid divertor blanket for CFETR, which can be installed and disassembled through remote handling (RH) technology. The article focuses on the conceptual design, stability analysis, RH process planning, and flow field analysis of cooling scheme for the Dome module, providing a solid foundation for subsequent thermal-hydraulic analysis.
IEEE TRANSACTIONS ON PLASMA SCIENCE
(2022)
Article
Nuclear Science & Technology
Nanyu Mou, Qing Zhuang, Xiyang Zhang, Le Han, Beiyan Jiang, Lei Cao, Mianjun Duan, Damao Yao
Summary: This study successfully prepares high-quality ODS-Cu / 316L clad plates using the explosive welding method. The bonding interface is sound, without cavities, and exhibits enhanced hardness and higher tensile stress. Helium leak testing confirms the integrity of the welded clad plates at cyclic room and high temperatures.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Physics, Fluids & Plasmas
Nanyu Mou, Le Han, Damao Yao
Summary: This article presents a test on the heat absorption coefficient of tungsten, indicating that it is stable at around 0.54. This provides a reference for the engineering design of the upgraded EAST lower divertor PFCs and offers important guidance for the research on the next-generation fusion facility CFETR.
IEEE TRANSACTIONS ON PLASMA SCIENCE
(2022)
Article
Materials Science, Multidisciplinary
Hui Wang, Zhuoming Xie, Xiang Cheng, Ke Jing, Linchao Zhang, Junfeng Yang, Rui Liu, Le Han, Lei Cao, Xianping Wang, Qianfeng Fang, Changsong Liu, Xuebang Wu
Summary: The microstructural evolution and thermal fatigue resistance of two tungsten composites, WZC and WYO, were investigated under cyclic heat loads. The WZC composite showed better thermal shock resistance than WYO due to the intrinsic properties of the particles. The study also revealed an interesting crack mechanism in tungsten composites. These findings are important for evaluating the thermal fatigue resistance of composites and their application in fusion reactors.
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
(2023)
Article
Nuclear Science & Technology
Nanyu Mou, Xiyang Zhang, Qianqian Lin, Xianke Yang, Le Han, Lei Cao, Damao Yao
Summary: This paper introduces an improved vacuum brazing technology for connecting copper to oxide dispersion strengthened copper alloy and summarizes the production process, high heat flux testing, non-destructive testing, and surface results of the flat-type copper/oxide dispersion strengthened copper/steel mockup after the high heat flux test. The test results demonstrate that the mockup manufactured according to the production process still has structural integrity and interface integrity under cyclic high heat loads.
NUCLEAR ENGINEERING AND TECHNOLOGY
(2023)
Article
Nuclear Science & Technology
Yunhua Tong, Xiang Gao, Lei Cao, Yuanlai Xie, Ning Tang, Ling Tao, Wei Yi, Xiaoming Liu, Chen Li, Cunxiang Tao, Yi Liu
Summary: In this study, the detailed design of the pipeline joint structure of the calorimeter verification prototype is examined, focusing on the impact of the structural design of the target panel pipeline joint. The manufacturing process and strength of the integrated pipeline structure of the target panel are analyzed under a design pressure of 4 MPa. The pressure test of the sample verifies that its structure can meet the design requirements, providing reference for the effective structural design and manufacturing of the NNBI calorimeter prototype.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Physics, Fluids & Plasmas
Qianqian Lin, Lei Cao, Qing Zhuang, Nanyu Mou, Le Han, Damao Yao
Summary: The heat removal capacity of the divertor in nuclear fusion engineering is crucial for the safe operation of magnetic confinement nuclear fusion devices under extreme heat flux conditions. Current evaluation methods are limited to small experimental components and do not allow for comparison under different loading and cooling conditions. A new method based on the cooling water thermal decay time constant has been developed to assess the heat removal capacity of the divertor and other high heat load components in real-time. This method provides a quantitative analysis and evaluation of the heat transfer capacity of the divertor system.
