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84 results on '"Bao-Nian Wan"'

1. Progress on haptoglobin and metabolic diseases

Author

Guang Ji, Xiao Zhang, Miao Wang, Bao-Nian Wan, and Shi-Gao Zhou

Subjects
Endocrinology, Diabetes and Metabolism, 030209 endocrinology & metabolism, Inflammation, White adipose tissue, 030204 cardiovascular system & hematology, 03 medical and health sciences, 0302 clinical medicine, Diabetes mellitus, Simple obesity, Nonalcoholic fatty liver disease, Internal Medicine, medicine, Evidence Review, Polymorphism, Kidney, biology, business.industry, Mechanism (biology), Haptoglobin, Metabolic diseases, medicine.disease, medicine.anatomical_structure, Immunology, biology.protein, CD163, medicine.symptom, business
Abstract

Haptoglobin (Hp) is an acidic glycoprotein, existing in the serum and other body fluids of human beings and a variety of mammals. Hp is produced in the liver, white adipose tissue, and the kidney. The genetic polymorphisms and different phenotypes of Hp have different biological functions. Hp has antibacterial, antioxidant, and angiogenic effects and is associated with multiple diseases including simple obesity, vascular complications of diabetes mellitus, nonalcoholic fatty liver disease, hypertension, blood diseases, autoimmune diseases, and malignant tumors. Hp also participates in many life activities, indicating the importance of Hp in further studies. Previously, we found that the expression of serum Hp changed after treatment of simple obesity patients in clinical trials. However, the specific mechanism of Hp in patients with simple obesity is still unclear. The purpose of this article is to introduce recent research progress on Hp, emphasizing the relationship between Hp and the development of metabolic disease, which will improve the understanding of the functions of Hp underlying metabolic diseases and discuss future research directions.

Published
2021

2. Concept Design of CFETR Tokamak Machine

Author

Yuan Xi Wan, Xue Bing Peng, Sumei Liu, Peng Fu, M.Y. Ye, Jin Xing Zheng, Yong Chen, Ming Zhun Lei, Bao Nian Wan, Kun Lu, Yuntao Song, Xu Feng Liu, Xianggao Gao, Song Tao Wu, and Jiangang Li

Subjects
Nuclear and High Energy Physics, Tokamak, Computer science, business.industry, Nuclear engineering, Divertor, Electrical engineering, Solenoid, Superconducting magnet, Fusion power, Condensed Matter Physics, law.invention, Electromagnetic coil, law, Systems design, business, Engineering design process
Abstract

China Fusion Engineering Test Reactor (CFETR) is a tokamak reactor; one design option under the consideration of the China National Integration Design Group employs superconducting magnets. The fusion power is at the range of 50-200 MW and the duty cycle (or burning time) was envisioned as 30%-50%. The plasma current will be 10 MA and the major and minor radii are 5.7 and 1.6 m, respectively. The concept engineering design including the magnet system, vacuum vessel (VV) system, and maintenance method has been carried out in the past years. The toroidal magnetic field strength at R0 is 5 T and the maximum flux swing provided by central solenoid winding will be 160 VS. The main design work, including the electromagnetic analysis of the magnet system, has already been carried out. This paper mainly probes into the VV design and optimization based on three types of maintenance ports. Furthermore, the maintenance method, counted as one of the most important design studies, is presented specifically in this paper. It includes the design of the maintenance ports and the remote handling system design, and so on. The next design stage will mainly include mechanical design, conductor stability, different types of divertor system design, and so on.

Published
2014

3. The Accomplishments and Next-Step Plan of EAST in Support of Fusion

Author

Yuntao Song, Xiao Jie Wang, Chun Dong Hu, Qing Sheng Hu, Jian Sheng Hu, Xiang Ji, Peng Fu, Fu Kun Liu, Jiangang Li, Li Qun Hu, Bing Jia Xiao, Jin Xing Zheng, Xian Zu Gong, Yang Pin Zhao, Ge Gao, Xiang Gao, Zhao Xi Chen, Yuan Xi Wan, Liu Wei Xu, Yi Yun Huang, Jiafang Shan, Bao Nian Wan, You Wen Sun, Qing Xi Yang, and Song Ke Wang

Subjects
Nuclear and High Energy Physics, Materials science, business.industry, Nuclear engineering, Divertor, Electrical engineering, Cryopump, Plasma, Condensed Matter Physics, Electron cyclotron resonance, Neutral beam injection, Heating system, Magnet, Edge-localized mode, business
Abstract

The experimental advanced superconducting tokamak (EAST) is a superconducting tokamak, which successfully achieved the first plasma discharge in 2006. The major radius of EAST plasma is 1.9 m, and its central magnet field is 3.5 T. In the past few years, EAST has made many achievements, such as 60-s double-null divertor configuration plasma and 1-MA plasma. In 2012, 411-s long-pulse discharge with 0.28-MA plasma current and 32-s H-mode operation was achieved at the seventh campaign. In addition, various means for mitigating ELMs have also been demonstrated to facilitate long-pulse operation. The experimental results and engineering experience obtained from EAST can be used as a reference for fusion next step. To make further progress, much optimization work should be done in next step. Based on the present EAST heating system, two sets of 4-MW neutral beam injection, one set of electron cyclotron resonance heating, and lower hybrid current drive will be installed to achieve more than 30-MW total heating power. The upper divertor will be updated to W-Cu divertor, which consists of monoblock structure and tungsten armor that can withstand 10- MW·m-2 heat load. To increase the upper divertor's ash removal efficiency, one new cryopump will be added on the behind of it. Aiming to improve plasma configuration and enhance its stabilization, the EAST resonant magnetic perturbation (RMP) coils will be designed, fabricated, and installed. The RMP coils will integrate the functions of error field correction, edge localized mode, and resistive wall mode. About 45 kinds of diagnostics will be used in the next campaign and all of them will be integrated on six ports as port plug. In addition, some fusion technologies are also considered in EAST to validate for ITER and future reactor.

Published
2014

4. ICRF boronization - A new technique towards high efficiency wall coating for superconducting tokamak reactors

Author

Fu Xian Yin, Xiao Ming Wang, Xian Zhu Gong, Ping Jian Qin, Xu Den, Hen Yu Fan, Yan Ping Zhao, Di Yie Xue, Chen Fu Li, Yu De Fang, Jian Shan Mao, Ming Shen Wei, Xiang Gao, Xiaokang Yang, Yuan Xi Wan, Yu Yang, De Zhen Xu, Qing Chu Zhao, Shou Ying Zhang, Xue Mao Gu, Lei Chen, Xiaodong Zhang, Wei Chi Shen, Jian Shen Hu, Jiangang Li, Sheng Xia Liu, Guang Xing Wang, Bi Li Lin, Jun Yi Zhao, Jia Rong Luo, Yin Xian Jie, Shen Fa Li, Ji Kang Xie, Yu Zhou Mao, Yue Dong Meng, Jia Yi Ding, Bao Nian Wan, and Yin Cui Fang

Subjects
Nuclear and High Energy Physics, Glow discharge, Materials science, Tokamak, business.industry, Superconducting magnet, Plasma, engineering.material, Condensed Matter Physics, law.invention, Nuclear magnetic resonance, Coating, law, Electromagnetic shielding, engineering, Optoelectronics, HT-7, business, Ion cyclotron resonance
Abstract

A new technique for wall conditioning that will be especially useful for future larger superconducting tokamaks, such as ITER, has been successfully developed and encouraging results have been obtained. Solid carborane powder, which is non-toxic and non-explosive, was used. Pulsed RF plasma was produced by a non-Faraday shielding RF antenna with RF power of 10 kW. The ion temperature was about 2 keV with a toroidal magnetic field of 1.8 T and a pressure of 3 × 10-1 Pa. Energetic ions broke up the carborane molecules, and the resulting boron ions struck and were deposited on the first wall. In comparison with glow discharge cleaning boronization, the B/C coating film shows higher adhesion, more uniformity and longer lifetime during plasma discharges. The plasma performance was improved after ICRF boronization.

Published
1999

5. [Visible spectra analysis on edge recycling in HT-7 tokamak]

Author

Juan, Huang, Bao-Nian, Wan, Zhen-Wei, Wu, and Qian, Zhou

Subjects
Kinetics, Optics and Photonics, Models, Chemical, Spectrum Analysis, Deuterium, Algorithms, Hydrogen
Abstract

The main efforts of HT-7 superconducting tokamak were directed to quasi-steady state discharges and their relevant physics. Significant progress in obtaning high-performance discharges under quasi-steady state in HT-7 has been realized. The long pulse discharges have been obtained with a duration up to 63.95 s. The edge recycling was studied by the ratio of H to D through OSMA (Optical Spectroscopy Multichannel Analyzer) system. During the discharge, recycling dominated the particle balance. In the steady state, when the density was controllable, the deuterium(hydrogen) recycling played an important role and the recycling coefficient Ror = 1. During the later time, R1 and the density was uncontrollable. The main contribution was from the D(H) recycling and impurity from the surfaces of the limiter and the first wall due to the increased surface temperature and radiation power, and these limited the duration of long duration discharges. The influence of wall conditioning on the edge recycling was also studied through the ratio of H to D.

Published
2005

24. The Experiment of Modulated Toroidal Current on HT-7 and HT-6M Tokamak

Author

Jian-shan, Mao, primary, Phillips, P, additional, Jia-rong, Luo, additional, Yu-hong, Xu, additional, Jun-yu, Zhao, additional, Xian-mei, Zhang, additional, Bao-nian, Wan, additional, Shou-yin, Zhang, additional, Yin-xian, Jie, additional, Zhen-wei, Wu, additional, Li-qun, Hu, additional, Sheng-xia, Liu, additional, Yue-jiang, Shi, additional, Jian-gang, Li, additional, and group, HT-6M & HT-7, additional

Published
2003
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40. Removal of Particles by ICRF Cleaning in HT-7 Superconducting Tokamak

Author

Jian-sheng, Hu, primary, Jian-gang, Li, additional, Shou-yin, Zhang, additional, Xue-mao, Gu, additional, Xiao-dong, Zhang, additional, Yan-pin, Zhao, additional, Xian-zu, Gong, additional, Guang-li, Kuang, additional, Cheng-fu, Li, additional, Jia-rong, Luo, additional, Xiao-ming, Wang, additional, Xiang, Gao, additional, Bao-nian, Wan, additional, Ji-kang, Xie, additional, Yuan-xi, Wan, additional, and group, HT-7, additional

Published
2001
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47. Density scaling on n  =  1 error field penetration in ohmically heated discharges in EAST.

Author

Hui-Hui Wang, You-Wen Sun, Tong-Hui Shi, Qing Zang, Yue-Qiang Liu, Xu Yang, Shuai Gu, Kai-Yang He, Xiang Gu, Jin-Ping Qian, Biao Shen, Zheng-Ping Luo, Nan Chu, Man-Ni Jia, Zhi-Cai Sheng, Hai-Qing Liu, Xian-Zu Gong, Bao-Nian Wan, and Contributors, East

Subjects
QUANTUM perturbations, MAGNETICS, ELECTRON temperature, PLASMA devices, FUSION (Phase transformation)
Abstract

Density scaling of error field penetration in EAST is investigated with different n  =  1 magnetic perturbation coil configurations in ohmically heated discharges. The density scalings of error field penetration thresholds under two magnetic perturbation spectra are and , where br is the error field and ne is the line averaged electron density. One difficulty in understanding the density scaling is that key parameters other than density in determining the field penetration process may also be changed when the plasma density changes. Therefore, they should be determined from experiments. The estimated theoretical analysis ( in lower density region and in higher density region), using the density dependence of viscosity diffusion time, electron temperature and mode frequency measured from the experiments, is consistent with the observed scaling. One of the key points to reproduce the observed scaling in EAST is that the viscosity diffusion time estimated from energy confinement time is almost constant. It means that the plasma confinement lies in saturation ohmic confinement regime rather than the linear Neo-Alcator regime causing weak density dependence in the previous theoretical studies. [ABSTRACT FROM AUTHOR]

Published
2018
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48. Toroidal rotation induced by 4.6 GHz lower hybrid current drive on EAST tokamak.

Author

Xiang-Hui Yin, Jun Chen, Rui-Ji Hu, Ying-Ying Li, Fu-Di Wang, Jia Fu, Bo-Jiang Ding, Mao Wang, Fu-Kun Liu, Qing Zang, Yue-Jiang Shi, Bo Lyu, Bao-Nian Wan, and team, EAST

Subjects
TOKAMAKS, CRYSTALS spectra, HYSTERESIS, ELECTRIC currents, VELOCITY, X-ray imaging
Abstract

Using a tangentially viewing x-ray imaging crystal spectrometer, substantial co-current rotation driven by lower hybrid current drive (LHCD) at 4.6 GHz is observed on EAST tokamak. This study presents plasma rotation behaviors with 4.6 GHz LHCD injection. Typically, the 10–20 km/s co-current rotation change and the transport of rotation velocity from edge to core are observed. The relationship between plasma parameters and rotation is also investigated, indicating that rotation decreases with increasing internal inductance (li) and increases with increasing safety factor (q0). Hysteresis between rotation and Te plasma stored energy is observed, suggesting different response times between the electron heating and rotation acceleration by LHCD. A comparison between the rotations driven by 4.6 G LHCD and 2.45 G LHCD on EAST is also presented, in which higher frequency LHCD could induce more rotation changes. [ABSTRACT FROM AUTHOR]

Published
2017
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49. Observation of Molybdenum Emission from Impurity-Induced Long-Lived m = 1 Mode on the Experimental Advanced Superconducting Tokamak.

Author

Yong-Cai Shen, Bo Lyu, Fu-Di Wang, Yue-Jiang Shi, Bin Wu, Ying-Ying Li, Jia Fu, Bao-Nian Wan, and Team, EAST

Subjects
TOKAMAKS, MOLYBDENUM, MAGNETIC confinement, SPECTRUM analysis, SUPERCONDUCTING films, EMISSION spectroscopy
Abstract

We observe the spectra of molybdenum for the first time since the first wall of our experimental advanced superconducting tokamak (EAST) was changed mainly to molybdenum tiles. A large amount of molybdenum accumulated in the central plasma where the long-lived m = 1 mode instability bursts is shown. Molybdenum is proved to be the main impurity species observed during the formation and lifetime of impurity-induced long-lived m = 1 mode. This may indicate that a close relationship exists between the high-Z impurity accumulation and the occurrence of long-lived m = 1 mode in EAST plasmas. [ABSTRACT FROM AUTHOR]

Published
2016
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50. Effect of passive structure and toroidal rotation on resistive wall mode stability in the EAST tokamak.

Author

Guang-Jun Liu, Bao-Nian Wan, You-Wen Sun, Yue-Qiang Liu, Wen-Feng Guo, Guang-Zhou Hao, Si-Ye Ding, Biao Shen, Bing-Jia Xiao, and Jin-Ping Qian

Subjects
*PASSIVE structures (Sustainable buildings), *TOROIDAL magnetic circuits, *TOKAMAKS, *ROTATIONAL motion, *STRUCTURAL stability
Abstract

If βN exceeds βNno—wall, the plasma will be unstable because of external kink and resistive wall mode (RWM). In this article, the effect of the passive structure and the toroidal rotation on the RWM stability in the experimental advanced superconducting tokamak (EAST) are simulated with CHEASE and MARS codes. A model using a one-dimensional (1D) surface to present the effect of the passive plate is proved to be credible. The no wall βN limit is about 3li, and the ideal wall βN limit is about 4.5li on EAST. It is found that the rotation near the q = 2 surface and the plasma edge affects the RWM more. [ABSTRACT FROM AUTHOR]

Published
2014
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