There is a common difficulty in elastic-plastic impact codes such as EPIC[2,3] NONSAP[4], etc.. Most of these codes use the simple linear functions usually taken from static problem to represent the displacement compo...There is a common difficulty in elastic-plastic impact codes such as EPIC[2,3] NONSAP[4], etc.. Most of these codes use the simple linear functions usually taken from static problem to represent the displacement components. In such finite element formulation, the stress components are constant in each element and they are discontinuous in any two neighboring elements. Therefore, the bases of using the virtual work principle in such elements are unreliable. In this paper, we introduce a new method, namely, the compatible stress iterative method, to eliminate the above-said difficulty. The calculated examples show that the calculation using the new method in dynamic finite element analysis of high velocity impact is valid and stable, and the element stiffness can be somewhat reduced.展开更多
The lower cryopump ports in International Thermonuclear Experimental Reactor (ITER) as a part of the vacuum vessel play many important roles. As the boundary of vacuum it must be ensured against structural damage. I...The lower cryopump ports in International Thermonuclear Experimental Reactor (ITER) as a part of the vacuum vessel play many important roles. As the boundary of vacuum it must be ensured against structural damage. In this study a finite element model of the lower cryopump ports was developed by ANSYS code with a purpose to evaluate the stress and displacement level on it. Two kinds of loads were taken into account. One was the hydrostatic pressure including the normal operation pressure and test pressure. The other was the seismic load. The analysis results show that the peak stress does not exceed the allowable stress for either the hydrostatic pressure or the seismic load according to the ITER structural design criterion, which indicates that the structure has a good safety margin.展开更多
A finite element model of the International Thermonuclear Experimental Reactor (ITER) in-vessel viewing port was developed by the ANSYS code in order to evaluate the stress level of this structure. The thermal, elas...A finite element model of the International Thermonuclear Experimental Reactor (ITER) in-vessel viewing port was developed by the ANSYS code in order to evaluate the stress level of this structure. The thermal, elastic and modal analyses were made in succession based on the loads designated by the ITER International team. The designed loads include electromagnetic loads, seismic loads, pressure, temperature and gravity. The preliminary results of the finite element analysis (FEA) show that the stress intensity exceeded the allowable stress and the maximum stress was concentrated in the geometric discontinuous region of the shroud stub extension (SSE). Therefore, the SSE has been modified recently. For the modified structure, we found that the stresses do not exceed the allowable value for all load combinations. In addition the modal analysis results show that the natural frequencies of the IVV port structure are located in the typical diapason of seismic excitation.展开更多
A structural analysis of the International Thermonuclear Experimental Reactor (ITER) vacuum vessel's lower port region was presented by means of a finite element analysis method. The purpose is to evaluate the stre...A structural analysis of the International Thermonuclear Experimental Reactor (ITER) vacuum vessel's lower port region was presented by means of a finite element analysis method. The purpose is to evaluate the stress and displacement level on this structure under various combinations of five designed loads, including the gravity of the vacuum vessel, seismic loads, electromagnetic loads, and possible pressure loads to ensure structural safety. The cyclic symmetry finite element model of this structure was developed by using ANSYS code. The re- sults showed that the maximum stress does not exceed the allowable value for any of the load combinations according to ASME code and the nine vacuum vessel (VV) supports have the ability to sustain the entire VV and in vessel-components and withstand load combinations under both normal as well as off-normal operation conditions. Stress mainly concentrates on the connecting region of the VV support and lower port stub extension.展开更多
The structural design of equatorial diagnostic port plug for international thermonuclear experimental reactor (ITER) was discussed in this paper. The induced electromagnetic (EM) loads of port plug and blanket shi...The structural design of equatorial diagnostic port plug for international thermonuclear experimental reactor (ITER) was discussed in this paper. The induced electromagnetic (EM) loads of port plug and blanket shielding module (BSM) were presented. The finite element analysis (FEA) and numerical calculation of the system were performed under the maximum loads. According to the American Society of Mechanical Engineers (ASME) criteria, the EM stress is far below the admissible failure boundary, which indicates that the system can resist the cooperative action of EM loads and device deadweight. The analysis could provide technical data and references for further analysis and optimized design of the system.展开更多
In this study both electric heating and fluid heating were proposed to bakeout the port plug structure being inserted in the middle of the international thermonuclear experimental reactor (ITER) vacuum vessel. The c...In this study both electric heating and fluid heating were proposed to bakeout the port plug structure being inserted in the middle of the international thermonuclear experimental reactor (ITER) vacuum vessel. The coupled thermal and structural analyses were carried out. The results, such as the distributions of the temperature field, thermal stress and thermal deformation of the port plug, were obtained. Based on the American Society of Mechanical Engineers (ASME) criteria, the reliability and feasibility of the heating technique were verified. The results provide detailed information on the selection of a preferable method for future engineering experiments.展开更多
Thermal analysis of the equatorial thermal shield for ITER is conducted in order to confirm that the cooling tube design was reasonable under both the plasma operational and the baking operational conditions. The stru...Thermal analysis of the equatorial thermal shield for ITER is conducted in order to confirm that the cooling tube design was reasonable under both the plasma operational and the baking operational conditions. The structural performance was analyzed by means of the finite element software ANSYS. A comparison of the results with design requirements shows that the results of the simulation are within allowable design requirements, which indicates the feasibility and reliability of the equatorial thermal shield structure.展开更多
ITER in-wall shielding (IIS) is situated between the doubled shells of the ITER Vacuum Vessel (IVV). Its main functions are applied in shielding neutron, gamma-ray and toroidal field ripple reduction. The structur...ITER in-wall shielding (IIS) is situated between the doubled shells of the ITER Vacuum Vessel (IVV). Its main functions are applied in shielding neutron, gamma-ray and toroidal field ripple reduction. The structure of IIS has been modelled according to the IVV design criteria which has been updated by the ITER team (IT). Static analysis and thermal expansion analysis were performed for the structure. Thermal-hydraulic analysis verified the heat removal capability and resulting temperature, pressure, and velocity changes in the coolant flow. Consequently, our design work is possibly suitable as a reference for IT's updated or final design in its next step.展开更多
The neutron shielding component of ITER (International Thermonuclear Experimental Reactor) vacuum vessel is a kind of structure resembling a wall in appearance. A FE (finite element) model is set up by using ANSYS...The neutron shielding component of ITER (International Thermonuclear Experimental Reactor) vacuum vessel is a kind of structure resembling a wall in appearance. A FE (finite element) model is set up by using ANSYS code in terms of its structural features. Static analysis, thermal expansion analysis and dynamic analysis are performed. The static results show that the stress and displacement distribution are allowable, but the high stress appears in the junction between the upper and lower parts. The modal analysis indicates that the biggest deformation exists in the port area. Through modal superposition, the single-point response has been found with the lower rank frequency of the acceleration seismic response spectrum. But the deformation and the stress values are within the permissible limit. The analysis results would benefit the work in the next step and provide some reference for the implementation of the engineering plan in the future.展开更多
利用大型有限元分析软件ANSYS分析了国际热核实验反应堆(ITER)Side校正场线圈(CC)端部三维大圆弧模压成形及释放模具后导体的回弹效应,研究了不同半径成形时导体内外表面的应力、应变的分布及释放模具后导体的回弹规律。设计了1套模压...利用大型有限元分析软件ANSYS分析了国际热核实验反应堆(ITER)Side校正场线圈(CC)端部三维大圆弧模压成形及释放模具后导体的回弹效应,研究了不同半径成形时导体内外表面的应力、应变的分布及释放模具后导体的回弹规律。设计了1套模压成形模具,通过修模的方式在该套成形模具上进行了不同半径成形试验,测得了不同成形半径时模压成形后的回弹量值。试验结果验证了所建立的有限元分析模型的正确性。有限元分析和试验结果表明:ITERSideCC端部三维大圆弧可通过模压成形达到所需的大半径要求,为ITER Side CC端部三维大圆弧成形提供了一种可行方案。展开更多
The ITER equatorial thermal shield is located inside the cryostat and outside the vacuum vessel, and its purpose is to provide a thermal shield from hot components to the superconducting magnets. Electromagnetic analy...The ITER equatorial thermal shield is located inside the cryostat and outside the vacuum vessel, and its purpose is to provide a thermal shield from hot components to the superconducting magnets. Electromagnetic analysis of the equatorial thermal shield was performed using the ANSYS code, because electromagnetic load was one of the main loads. The 40 sector finite element model was established including the vacuum vessel, equatorial thermal shield, and superconducting magnets. The main purpose of this analysis was to investigate the eddy current and electromagnetic force in the equatorial thermal shield during plasma disruption. Stress analysis was implemented under the electromagnetic load. The results show that the equatorial thermal shield can accommodate the calculated electromagnetic loads.展开更多
文摘There is a common difficulty in elastic-plastic impact codes such as EPIC[2,3] NONSAP[4], etc.. Most of these codes use the simple linear functions usually taken from static problem to represent the displacement components. In such finite element formulation, the stress components are constant in each element and they are discontinuous in any two neighboring elements. Therefore, the bases of using the virtual work principle in such elements are unreliable. In this paper, we introduce a new method, namely, the compatible stress iterative method, to eliminate the above-said difficulty. The calculated examples show that the calculation using the new method in dynamic finite element analysis of high velocity impact is valid and stable, and the element stiffness can be somewhat reduced.
基金National 973 programme of the Ministry of Science and Technology of China(No.2004CB720704)
文摘The lower cryopump ports in International Thermonuclear Experimental Reactor (ITER) as a part of the vacuum vessel play many important roles. As the boundary of vacuum it must be ensured against structural damage. In this study a finite element model of the lower cryopump ports was developed by ANSYS code with a purpose to evaluate the stress and displacement level on it. Two kinds of loads were taken into account. One was the hydrostatic pressure including the normal operation pressure and test pressure. The other was the seismic load. The analysis results show that the peak stress does not exceed the allowable stress for either the hydrostatic pressure or the seismic load according to the ITER structural design criterion, which indicates that the structure has a good safety margin.
基金supported by the State Key Development Program for Basic Research of China(Grant No.2004CB720704)
文摘A finite element model of the International Thermonuclear Experimental Reactor (ITER) in-vessel viewing port was developed by the ANSYS code in order to evaluate the stress level of this structure. The thermal, elastic and modal analyses were made in succession based on the loads designated by the ITER International team. The designed loads include electromagnetic loads, seismic loads, pressure, temperature and gravity. The preliminary results of the finite element analysis (FEA) show that the stress intensity exceeded the allowable stress and the maximum stress was concentrated in the geometric discontinuous region of the shroud stub extension (SSE). Therefore, the SSE has been modified recently. For the modified structure, we found that the stresses do not exceed the allowable value for all load combinations. In addition the modal analysis results show that the natural frequencies of the IVV port structure are located in the typical diapason of seismic excitation.
基金supported by National 973 programme (MOST) of China (No.2004CB720704)
文摘A structural analysis of the International Thermonuclear Experimental Reactor (ITER) vacuum vessel's lower port region was presented by means of a finite element analysis method. The purpose is to evaluate the stress and displacement level on this structure under various combinations of five designed loads, including the gravity of the vacuum vessel, seismic loads, electromagnetic loads, and possible pressure loads to ensure structural safety. The cyclic symmetry finite element model of this structure was developed by using ANSYS code. The re- sults showed that the maximum stress does not exceed the allowable value for any of the load combinations according to ASME code and the nine vacuum vessel (VV) supports have the ability to sustain the entire VV and in vessel-components and withstand load combinations under both normal as well as off-normal operation conditions. Stress mainly concentrates on the connecting region of the VV support and lower port stub extension.
文摘The structural design of equatorial diagnostic port plug for international thermonuclear experimental reactor (ITER) was discussed in this paper. The induced electromagnetic (EM) loads of port plug and blanket shielding module (BSM) were presented. The finite element analysis (FEA) and numerical calculation of the system were performed under the maximum loads. According to the American Society of Mechanical Engineers (ASME) criteria, the EM stress is far below the admissible failure boundary, which indicates that the system can resist the cooperative action of EM loads and device deadweight. The analysis could provide technical data and references for further analysis and optimized design of the system.
基金supported by the ITER Organizationthe Diagnostic Working Group of ASIPP
文摘In this study both electric heating and fluid heating were proposed to bakeout the port plug structure being inserted in the middle of the international thermonuclear experimental reactor (ITER) vacuum vessel. The coupled thermal and structural analyses were carried out. The results, such as the distributions of the temperature field, thermal stress and thermal deformation of the port plug, were obtained. Based on the American Society of Mechanical Engineers (ASME) criteria, the reliability and feasibility of the heating technique were verified. The results provide detailed information on the selection of a preferable method for future engineering experiments.
基金supported by International Thermonuclear Experimental Reactor(ITER)Specific Plan(2009GB101004)
文摘Thermal analysis of the equatorial thermal shield for ITER is conducted in order to confirm that the cooling tube design was reasonable under both the plasma operational and the baking operational conditions. The structural performance was analyzed by means of the finite element software ANSYS. A comparison of the results with design requirements shows that the results of the simulation are within allowable design requirements, which indicates the feasibility and reliability of the equatorial thermal shield structure.
基金the National 973 program of China(No.2004CB720704)
文摘ITER in-wall shielding (IIS) is situated between the doubled shells of the ITER Vacuum Vessel (IVV). Its main functions are applied in shielding neutron, gamma-ray and toroidal field ripple reduction. The structure of IIS has been modelled according to the IVV design criteria which has been updated by the ITER team (IT). Static analysis and thermal expansion analysis were performed for the structure. Thermal-hydraulic analysis verified the heat removal capability and resulting temperature, pressure, and velocity changes in the coolant flow. Consequently, our design work is possibly suitable as a reference for IT's updated or final design in its next step.
基金the National 973 program of China(No.2004CB720704)
文摘The neutron shielding component of ITER (International Thermonuclear Experimental Reactor) vacuum vessel is a kind of structure resembling a wall in appearance. A FE (finite element) model is set up by using ANSYS code in terms of its structural features. Static analysis, thermal expansion analysis and dynamic analysis are performed. The static results show that the stress and displacement distribution are allowable, but the high stress appears in the junction between the upper and lower parts. The modal analysis indicates that the biggest deformation exists in the port area. Through modal superposition, the single-point response has been found with the lower rank frequency of the acceleration seismic response spectrum. But the deformation and the stress values are within the permissible limit. The analysis results would benefit the work in the next step and provide some reference for the implementation of the engineering plan in the future.
文摘利用大型有限元分析软件ANSYS分析了国际热核实验反应堆(ITER)Side校正场线圈(CC)端部三维大圆弧模压成形及释放模具后导体的回弹效应,研究了不同半径成形时导体内外表面的应力、应变的分布及释放模具后导体的回弹规律。设计了1套模压成形模具,通过修模的方式在该套成形模具上进行了不同半径成形试验,测得了不同成形半径时模压成形后的回弹量值。试验结果验证了所建立的有限元分析模型的正确性。有限元分析和试验结果表明:ITERSideCC端部三维大圆弧可通过模压成形达到所需的大半径要求,为ITER Side CC端部三维大圆弧成形提供了一种可行方案。
基金supported by the International Thermonuclear Experimental Reactor (ITER) Specific Plan of China(No.2009GB101004)
文摘The ITER equatorial thermal shield is located inside the cryostat and outside the vacuum vessel, and its purpose is to provide a thermal shield from hot components to the superconducting magnets. Electromagnetic analysis of the equatorial thermal shield was performed using the ANSYS code, because electromagnetic load was one of the main loads. The 40 sector finite element model was established including the vacuum vessel, equatorial thermal shield, and superconducting magnets. The main purpose of this analysis was to investigate the eddy current and electromagnetic force in the equatorial thermal shield during plasma disruption. Stress analysis was implemented under the electromagnetic load. The results show that the equatorial thermal shield can accommodate the calculated electromagnetic loads.