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Featured researches published by Chen Jiming.
Plasma Science & Technology | 2009
Wang Pinghuai; Nobuta Yuji; Hino Tomoaki; Yamauchi Yuji; Chen Jiming; Xu Zengyu; Li Xiongwei; Liu Shi
The reduced activation ferritic/martenstic steel CLF-1 prepared by the Southwestern Institute of Physics in China was irradiated by helium ions with an energy of 5 keV at room temperature using an electron cyclotron resonance (ECR) ion irradiation apparatus. After the irradiation, the helium retention and desorption were investigated using a technique of thermal desorption spectroscopy (TDS). The experiment was conducted with both the normal and welded samples. Blisters were observed after the helium ion irradiation, and the surface density of blisters in the welded samples was lower than that in the non-welded samples. Three desorption peaks were observed in both the non-welded and welded samples. These desorption peaks corresponded to those of blister ruptures and the helium release from the inner bubbles and the defects. The amount of helium retained in the welded samples was approximately the same as that in the non-welded samples, which was much less than other reduced activation materials, such as vanadium alloy and SiC/SiC composites.
Plasma Science & Technology | 2003
Chen Jiming; Xu Ying; Deng Ying; Yang Ling; Qiu Shaoyu
A V4Ti alloy and several V4Cr4Ti alloys with different oxygen contents were studied on their tensile properties with the effect of hydrogen concentrations. The ductility of the alloys showed a successive decrease in a varied rate with an increased hydrogen concentration, while the ultimate tensile strength remained unchanged or even decreased for the high oxygen content alloy in spite of the occurrence of hardening in the low oxygen content alloy. Oxygen in the alloy causes grain boundary weakening, increasing the possibility of intergranular fractures and thus enhancing the hydrogen embrittlement. V4Ti showed a higher resistance to the hydrogen embrittlement as compared to the V4Cr4Ti alloys on a similar oxygen content level.
Plasma Science & Technology | 2002
Liu Xiang; Chen Jiming; Zhang Fu; Xu Zengyu; Ge Changchun; Li Jiangtao
B4C, SiC and C, Cu functionally graded-materials (FGMs) have been developed by plasma spraying and hot pressing. Their high-heat flux properties have been investigated by high energy laser and electron beam for the simulation of plasma disruption process of the future fusion reactors, And a study on eroded products of B4C/Cu FGM under transient thermal load of electron beam was performed. In the experiment, SEM and EDS analysis indicated that B4C and SiC were decomposed, carbon was preferentially evaporated under high thermal load, and a part of Si and Cu were melted, in addition, the splash of melted metal and the particle emission of brittle destruction were also found. Different erosive behaviors of carbon-based materials (CBMs) caused by laser and electron beam were also discussed.
Journal of Nuclear Materials | 1991
Qian Jiapu; Chen Jiming; Chen Jinbiao; Xu Zengyu; Wang Weihao; Pan Chuanjie
Abstract The compatibility of HR-1, a hydrogen embrittlement resistant steel, with static liquid lithium was evaluated by measuring its weight loss and observing the configuration of the corroded layer. The weight loss rate of HR-1 specimens was 4.86 × 10−9kg/m2 s after exposure in liquid lithium at 773 K for 2440 h. The corroded layer was porous and could be spalled easily. Ni and Cr in the corroded layer were depleted by 90 and 92%, respectively, while the original austenite in the corroded layer has been turned into ferrite.
Plasma Science & Technology | 2014
Kang Weishan; Yuan Tao; Sun Qian; Wu Jihong; Chen Jiming
Electromagnetic (EM) load is one of the key design drivers for the blanket shield block (SB) and other in-vessel components. In this article, an EM analysis method was developed to address the EM force on the SB. The plasma currents, which vary spatially and temporally, are loaded as a filament at each time point. The standard blanket module No.04 (BM04) under major disruption (MD) is selected to perform the analyses. The analyses results are validated by comparing currents on the passive structure. To better understand the effects of cooling channels and slits on the EM force, the case of SB without cooling channel and the case without slits are calculated to make comparisons. The results show that the slits play an important role in controlling the EM load on SB.
Plasma Science & Technology | 2010
Kang Weishan(康伟山); Chen Jiming; Wu Jihong
Thermal hydraulic analysis was performed for the 2004 ITER blanket design, which was based on the fabrication methods of forging, drilling and welding. Results show that, in the original design, the flow distribution in radial holes was far from uniform because different flow drivers were used in the radial holes. Improvement of the flow driver is proposed in this study. With the optimization of the flow drivers, it is clearly shown that the total pressure drop decreases and a better velocity distribution in radial holes is obtained. The more uniform heat transfer coefficient among the radial holes is beneficial for reducing thermal stress.
Plasma Science & Technology | 2002
Xu Zengyu; Liu Xiang; Chen Jiming; Wang Ming-xu; Song Jin-ren; Zhai Gengtai; Li Cheng-xin
Low-Z materials, such as carbon-based materials and Be, are major plasma-facing material (PFM) for current, even in future fusion devices. In this paper, a new type of multielement-doped carbon-based materials developed are presented along with experimental results of their properties. The results indicate a decrease in chemical sputtering yield by one order of magnitude, a decrease in both thermal shock resistance and radiation-enhanced sublimation, an evidently lower temperature desorption spectrum, and combined properties of exposing to plasma.
Plasma Science & Technology | 2003
Chen Jiming; Xu Ying; Deng Ying; Xu Zengyu
Archive | 2017
Kang Weishan; Chen Jiming; Wu Jihong; Wang Pinghuai; Yuan Tao; Sun Qian
Archive | 2017
Zheng Pengfei; Chen Jiming; Yang Shuang; Miao Xing; Wei Ran