China International Nuclear Fusion Energy Program Execution

Beijing, China

China International Nuclear Fusion Energy Program Execution

Beijing, China
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Li H.,China International Nuclear Fusion Energy Program Execution | Yan G.,Shanghai JiaoTong University | Gao P.,Shanghai JiaoTong University
Proceedings of the Institution of Mechanical Engineers, Part C: Journal of Mechanical Engineering Science | Year: 2010

The method of wireless power transmission is an important method in powering wireless medical devices in vivo, but the efficiency is still low, especially when the devices move freely in random positions and orientations. Aiming at powering an endoscopic capsule, a method for improving efficiency of wireless power transmission is proposed, which is based on electromagnetic localization and synthesis of magnetic field vector. By analysing the model and experimenting in vitro, the proposed method is verified, which can improve the efficiency of the wireless power transmission because of accurate localization of the capsule and synthesis of magnetic field vector. © 2010 Authors.


Qin J.,CAS Hefei Institutes of Physical Science | Weiss K.-P.,Karlsruhe Institute of Technology | Wu Y.,CAS Hefei Institutes of Physical Science | Wu Z.,CAS Technical Institute of Physics and Chemistry | And 2 more authors.
Cryogenics | Year: 2012

This paper focuses on fatigue tests on the ITER Poloidal Field (PF) jacket made of 316L stainless steel material. During manufacture, the conductor will be compacted and spooled after cable insertion. Therefore, sample jackets were prepared under compaction, bending and straightening in order to simulate the status of PF conductor during manufacturing and winding. The fatigue properties of materials were measured at T < 7 K, including S-N and fatigue crack growth rate (FCGR). The testing results show that the present Chinese PF jacket has good fatigue properties, which conclude that the results are accordant with the requirements of ITER. © 2012 Elsevier Ltd. All rights reserved.


Foussat A.,ITER Organization | Wu W.,CAS Hefei Institutes of Physical Science | Li H.,China International Nuclear Fusion Energy Program Execution | Dolgetta N.,ITER Organization | And 2 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2012

The ITER Magnet system consists of four main coils sub-systems: 18 Toroidal Field Coils (TF-coil), a Central Solenoid (CS), 6 Poloidal Field Coils (PF-coil) and 18 Correction Coils (EFCC). The main contract of the EFCCs supply is awarded to the Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) by the Chinese Domestic Agency (CNDA). According to the pre-qualification program, ASIPP is implementing the procurement phase to qualify and validate key technologies and manufacturing methods. The Correction coils qualification activities are conducted within the framework of the procurement arrangement set up between the ITER Organization and CNDA. The paper describes the CC development including first results of the coils winding qualification trials and, qualification of a S-Glass fiber-polyimide based insulation system The CC casing assembly process and the first results of the welding trials are reported. The weld qualification, according to ASTM for 316LN austenitic steel is reported in terms of fracture toughness, fatigue crack growth, and tensile property at 4 K. The Vacuum Pressure Impregnation of CC short mock-up, with low viscosity bisphenol-F (DGEBF) epoxy resin, aims to optimization of the curing and insulation mechanical properties. © 2011 IEEE.


Zha F.,CAS Hefei Institutes of Physical Science | Song Z.,CAS Hefei Institutes of Physical Science | Peng F.,CAS Hefei Institutes of Physical Science | Dong L.,China International Nuclear Fusion Energy Program Execution | Wang M.,China International Nuclear Fusion Energy Program Execution
IEEE Transactions on Plasma Science | Year: 2013

This paper presents the commutating over-voltage snubber circuit design method of a thyristor converter that is applied to the International Thermonuclear Experimental Reactor poloidal field-converter module. In the course of poloidal field ac/dc converter normal operation, large transient surges called commutating over-voltages may be generated internally during the commutating process of thyristor, which poses a severe threat to system reliability and needs to be suppressed. In this paper, based on the analysis of reverse recovery transient of the parallel thyristors, the turn-off model of the PF converter thyristor is created and analytical expressions are derived, including the over-voltage crest value and the maximum over-voltage rise rate. Utilizing the analysis results, a systematic approach to the RC snubber circuit design is described. © 1973-2012 IEEE.


Li X.,CAS Hefei Institutes of Physical Science | Li X.,China International Nuclear Fusion Energy Program Execution | Shi Y.,CAS Hefei Institutes of Physical Science
Plasma Science and Technology | Year: 2015

With the technical requirement of the International Thermonuclear Experimental Reactor (ITER) project, the manufacture and assembly technology of the mid Edge Localized Modes (ELM) coil was developed by the Institute of Plasma Physics, Chinese Academy of Science (ASIPP). As the gap between the bracket and the Stainless Steel jacketed and Mineral Insulated Conductor (SSMIC) can be larger than 0.5 mm instead of 0.01 mm to 0.1 mm as in normal industrial cases, the process of mid ELM coil bracket brazing to the SSMICT becomes quiet challenging, from a technical viewpoint. This paper described the preliminary design of ELM coil bracket brazing to the SSMIC process, the optimal bracket brazing curve and the thermal simulation of the bracket furnace brazing method developed by ANSYS. BAg-6 foil (Bag50Cu34Zn16) plus BAg-1a paste (Bag45CuZnCd) solders were chosen as the brazing filler. By testing an SSMICT prototype, it is shown that the average gap between the bracket and the SSMIC could be controlled to 0.2-0.3 mm, and that there were few voids in the brazing surface. The results also verified that the preliminary design had a favorable heat conducting performance in the bracket. © 2015, IOP. All rights reserved.


Kang W.,Southwestern Institute of Physics | Chen J.,Southwestern Institute of Physics | Wu J.,Southwestern Institute of Physics | Niu E.,China International Nuclear Fusion Energy Program Execution
Fusion Engineering and Design | Year: 2015

Electromagnetic (EM) load is one of the most concerned design issues for the in-vessel components in the Tokamak device. For shield block (SB), quite a few of slits cut on the SB are designed to mitigate the EM load. In this study, a solid model of blanket system with other main surrounding components, such as vacuum vessel, was developed, and FE analyses were performed to address the eddy current and Lorentz force during major disruption (MD) with ANSYS EMAG code package. In order to get a regular hexahedral mesh of the SB with complex interface, a brick-like meshing is used to get a more reliable result. Key factors which potentially have great impacts on the eddy current were studied individually by SB04 of the standard blanket module, such as the depth, location and number of the slits. To better understand the effects of cooling channels on the EM load, SB04 without cooling channel are calculated to make comparisons. Two important conclusions can be made from this study. The first one is that cooling channels have a little impact on the EM load. This is because the cooling channels cut into the eddy current locally, and the global current loop is not affected. The second is that slit configuration is important to control the EM load, and their depths, locations and numbers are also important. © 2015 Elsevier B.V.


Zha F.,CAS Hefei Institutes of Physical Science | Song Z.,CAS Hefei Institutes of Physical Science | Fu P.,CAS Hefei Institutes of Physical Science | Dong L.,China International Nuclear Fusion Energy Program Execution | Wang M.,China International Nuclear Fusion Energy Program Execution
Plasma Science and Technology | Year: 2014

In nuclear fusion power supply systems, the thyristors often need to be connected in parallel for sustaining large current. However, research on the reverse recovery transient of parallel thyristors has not been reported yet. When several thyristors are connected in parallel, they cannot turn-off at the same moment, and thus the turn-off model based on a single thyristor is no longer suitable. In this paper, an analysis is presented for the reverse recovery transient of parallel thyristors. Parallel thyristors can be assumed as one virtual thyristor so that the reverse recovery current can be modeled by an exponential function. Through equivalent transformation of the rectifier circuit, the commutating over-voltage can be calculated based on Kirchhoff's equation. The reverse recovery current and commutation over-voltage waveforms are measured on an experiment platform for a high power rectifier supply. From the measurement results, it is concluded that the modeling method is acceptable.


Li J.,CAS Hefei Institutes of Physical Science | Song Z.,CAS Hefei Institutes of Physical Science | Xu L.,CAS Hefei Institutes of Physical Science | Fu P.,CAS Hefei Institutes of Physical Science | And 4 more authors.
Plasma Science and Technology | Year: 2014

A bridge arm prototype of ITER poloidal field (PF) converter modules has been designed and fabricated. Non-cophase counter parallel connection is chosen as the arm structure of the prototype. Among all factors affecting current sharing, arm structure is the main one. During the design of the arm prototype, a novel method based on inductance matrixes is employed to improve the current sharing of the bridge arm. The test results on the prototype show that the current sharing performance of the arm prototype is much better than relevant design requirement, and that the matrix method is very effective to analyze and solve the current sharing problems of thyristor converters.


Fu P.,CAS Hefei Institutes of Physical Science | Gao G.,CAS Hefei Institutes of Physical Science | Song Zh.Q.,CAS Hefei Institutes of Physical Science | Xu L.W.,CAS Hefei Institutes of Physical Science | And 6 more authors.
Fusion Science and Technology | Year: 2013

This paper introduces the preliminary design of the poloidal field alternating-current/direct-current converter for the coil power supply system applied in the ITER project; it includes the description of design inputs, converter topology optimization, system analysis, electrical design, test procedure and criteria, related interface, and control and protection.


Han X.,Huazhong University of Science and Technology | Cao Q.,Huazhong University of Science and Technology | Wang M.,China International Nuclear Fusion Energy Program Execution
Conference Record - IEEE Instrumentation and Measurement Technology Conference | Year: 2011

In this work, a linear position sensor based on a Hall Effect element with electromagnetic coils for measuring long displacement is presented. This paper proposes a novel stationary system using one pair of Helmholtz coils and one pair of Maxwell coils. The Maxwell coil pair is chose to generate uniform gradient magnetic flux intensity. The Helmholtz coil pair is used to increase the magnetic field without sacrificing linearity for reducing the measurement error near the center. Then, a computation of the quasi-static electromagnetic field of the sensor using the finite element method has been performed. Secondary model has been created on the basis of finite element results. Then this model has been optimized with respect to two criteria: linearity and sensitivity. The designed electromagnetic coils pair combining with a Hall sensor has the advantage of displacement measurement with wider range, lower cost and simple structure. © 2011 IEEE.

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