Influence of the nanoscale oxide particles on mechanical properties and irradiation resistance of oxide-dispersionstrengthened(ODS)ferritic steels is of critical importance for the use of the material in fuel cladding...Influence of the nanoscale oxide particles on mechanical properties and irradiation resistance of oxide-dispersionstrengthened(ODS)ferritic steels is of critical importance for the use of the material in fuel cladding or blanket components in advanced nuclear reactors.In the present work,impact of structures of oxide dispersoids on the irradiation hardening of ODS ferritic steels was studied.Specimens of three kinds of high-Cr ODS ferritic steels containing oxide dispersoids with different number density and average size were irradiated with high-energy Niions at about−50℃.The energy of the incident Ni ions was varied from 12.73 to 357.86 MeV by using an energy degrader at the terminal so that a plateau of atomic displacement damage(∼0.8 dpa)was produced from the near surface to a depth of 24m in the specimens.展开更多
The progress of research going on in Group of Energy Materials (GEM), Material Research Center, in 2014 isin the following three aspects.1. Facility developmentIn order to push forward our study on fusion reactor mate...The progress of research going on in Group of Energy Materials (GEM), Material Research Center, in 2014 isin the following three aspects.1. Facility developmentIn order to push forward our study on fusion reactor materials, we upgraded the irradiation terminal (128#)of the sector focused cyclotron (SFC) at HIRFL, by developing a new specimen stage specific for irradiation withlow-fluence scattered ions. So far the terminal is capable of irradiation to both very low fluences (106 ions/cm2) andvery high fluences (typically 1016 ions/cm2) for various materials. Specimen temperature can be readily controlledusing the L-N2 cooling stage or the the high-T stage (up to 600 oC). Our recent investigation with transmissionelectron microscopy (TEM) of the defects produced by high-energy Ne ions in steel specimens provides a clearevidence that defects were produced uniformly along the depth in the specimen, indicating that the energy degraderof the terminal works effectively to disperse the ion energy in a wide range. A photo of the terminal together witha SRIM estimate of depth profiles of damage in an 8% Cr reduced activation ferritic/martensitic steel (RAFMS) isshown in Fig. 1.展开更多
Aluminum-added Oxide-Dispersion-Strengthened(ODS)ferritic steel is the prime candidate for the fuel cladding of the accident-tolerant fuel technology.Under in-pile condition,the fuel cladding has to endure the intensi...Aluminum-added Oxide-Dispersion-Strengthened(ODS)ferritic steel is the prime candidate for the fuel cladding of the accident-tolerant fuel technology.Under in-pile condition,the fuel cladding has to endure the intensive radiation from fast neutrons.展开更多
By hydrolysing titanium isopropoxide in a long hydrocarbon chain surfactant-containing solution, TiO2 fine particles with a diversity of well-defined morphologies was synthesized in this study by a hydrothermal route....By hydrolysing titanium isopropoxide in a long hydrocarbon chain surfactant-containing solution, TiO2 fine particles with a diversity of well-defined morphologies was synthesized in this study by a hydrothermal route. The structural change during the formation process was monitored by scanning electron microscopy, transmission electron microscopy and X-ray diffraction analysis. TiO2 with various morphologies such as particle, sheet, rod, tube and flower-like shape was obtained by carefully controlling the preparation conditions. The experimental results show that the pH value is crucial for shape control of the produced TiO2 because it can change the charge state of the surfactant in the solution and the adsorption potential of the surfactant on the TiO2 surface. The shape evolvement of anatase TiO2 was elucidated by quenching the reaction at different stage and the formation mechanism of different shaped TiO2 was suggested.展开更多
In this study,the effects of the fluid cooling and electric field line deformation were investigated in a dielectric barrier discharge(DBD)plasma source.The DBD plasma jet is improved by covering the ground electrode ...In this study,the effects of the fluid cooling and electric field line deformation were investigated in a dielectric barrier discharge(DBD)plasma source.The DBD plasma jet is improved by covering the ground electrode and a power electrode with insulating oil.We obtained positive results as insulating oil prevents arc formation,while it improved the supplied power and plasma jet length,and increased radical production.Radical production of this nonthermal plasma jet is studied with polyvinyl alcohol-potassium iodide liquid.展开更多
Spontaneous transition of the plasma confinement mode was observed in thehelical-axis heliotron device 'Heliotron J' for three different plasma heating schemes, i.e.ECH-only, NBI-only and the combination of EC...Spontaneous transition of the plasma confinement mode was observed in thehelical-axis heliotron device 'Heliotron J' for three different plasma heating schemes, i.e.ECH-only, NBI-only and the combination of ECH and NBI. The transition seems to occur above a certaincritical density. In addition to the confinement transition, a spontaneous shift of the hittingposition of the divertor plasma flux on the wall was observed. This shift could be related with thechange of the edge field topology caused by non-inductive toroidal currents.展开更多
Oxide dispersion strengthened （ODS） steels can be used as the structural materials in the future fusion reactors and the fuel cladding materials in the advanced fission reactors. However, the weldability of ODS stee...Oxide dispersion strengthened （ODS） steels can be used as the structural materials in the future fusion reactors and the fuel cladding materials in the advanced fission reactors. However, the weldability of ODS steels is a severe problem. In the present study, defect-free joints of the 15Cr-ODS ferritic steel were achieved by friction stir welding at different rotation speeds. The recrystallization, hardness and tensile properties are highly related with the rotation speed of the stir tool. The higher rotation speed results in coarser grains in the top SZ, while the grain size exhibits more complicated relation with the rotation speed in the SZ center. The joint welded at 250 rpm exhibits a maximum tensile strength of 974 MPa that reaches about 84% of that of the base metal.展开更多
Herein,we employ the threshold energy neutron analysis(TENA)technique to introduce the world's first active interrogation system to detect special nuclear materials(SNMs),including U-235 and Pu-239.The system util...Herein,we employ the threshold energy neutron analysis(TENA)technique to introduce the world's first active interrogation system to detect special nuclear materials(SNMs),including U-235 and Pu-239.The system utilizes a DD neutron generator based on inertial electrostatic confinement(IEC)to interrogate suspicious objects.To detect secondary neutrons produced during fission reactions induced in SNMs,a tensioned metastable fluid detector(TMFD)is employed.The current status of the system's development is reported in this paper,accompanied by the results from experiments conducted to detect 10 g of highly enriched uranium(HEU).Notably,the experimental findings demonstrate a distinct difference in the count rates of measurements with and without HEU.This difference in count rates surpasses two times the standard deviation,indicating a confidence level of more than 96% for identifying the presence of HEU.The paper presents and extensively discusses the proof-of-principle experimental results,along with the system's planned trajectory.展开更多
Two pairs of high-frequency magnetic probes were installed in the Large Helical Device （LHD）. During the injection of a perpendicular neutral beam, ion cyclotron emissions （ICEs） with the fundamental frequency cor...Two pairs of high-frequency magnetic probes were installed in the Large Helical Device （LHD）. During the injection of a perpendicular neutral beam, ion cyclotron emissions （ICEs） with the fundamental frequency corresponding to the ion cyclotron frequency at the plasma edge were detected, which are the same type of ICE as measured with the former spare ion cyclotron range of frequencies （ICRF） heating antennas. This type of ICE was further investigated with regard to the phase and intensity of signals. Another type of ICE was found in the LHD, and these ICEs were synchronized with bursts of toroidicity induced Alfv^n eigenmodes （TAE） and the rise of intensity of lost ion flux. Therefore the source of these ICEs was thought to be the particles transferred from the core to the outer region of plasma by the TAE bursts. The frequency of ICEs induced by the TAE bursts increases linearly with the magnetic field strength, since the ion cyclotron frequency increases with the magnetic field strength.展开更多
The preparation for an experimental soft x-ray tomography study on the Heliotron J (H-J) machine is carried out,with the objectives of evaluating the capability of the current soft x-ray tomographic system in terms of...The preparation for an experimental soft x-ray tomography study on the Heliotron J (H-J) machine is carried out,with the objectives of evaluating the capability of the current soft x-ray tomographic system in terms of the identification of different mode structures and their poloidal rotation,and the axis shift with different plasma and machine parameters,and fixing the physics goals for the experimental study.These preparations were carried out via a simulated soft x-ray data set arising from different plasma conditions,such as magnetic islands,low beta and high beta.Soft x-ray tomography (SXT) is performed by the discrete pixel method including singular value decomposition and Phillips-Tikhonov regularization,to obtain clear and smooth images.The H-J soft x-ray tomography results from simulated soft x-rays for the equilibrium H-J plasma sensed the magnetic axis shift clearly and an estimate was also achieved.Successful reconstruction for mode structure m =1/n =1 was obtained along with the realization of the poloidal rotation of the structure.The reconstruction for the m =2/n =1 mode was not very clear for the current soft x-ray diagnostic design.Effective mode identification was not possible due to the lack of measurements.The SXT from the current soft x-ray diagnostic on H-J,the magnetic axis shift can be estimated and the m =1/n =1 mode can be studied.Study of higher poloidal modes is difficult with the current design.展开更多
A fast video camera is verified to be a powerful t0ol for observation of filaments/blobs near the last closed flux surface （LCFS）. In order to extract the fluctuation component from the raw data of the fast camera, ...A fast video camera is verified to be a powerful t0ol for observation of filaments/blobs near the last closed flux surface （LCFS）. In order to extract the fluctuation component from the raw data of the fast camera, a pre-processing technique, sliding time window averaging subtraction （STWAS） has been developed to remove the background of slowly varying emission from the bulk plasma. By using this pre-processing technique, the fast camera data are analyzed. A method to identify the filaments in the pre-processed image is also discussed.展开更多
A new high repetition rate Nd：YAG Thomson scattering system is developed for the Heliotron J helical device. A main purpose of installing the new system is the temporal evolution measurement of a plasma profile for i...A new high repetition rate Nd：YAG Thomson scattering system is developed for the Heliotron J helical device. A main purpose of installing the new system is the temporal evolution measurement of a plasma profile for improved confinement physics such as the edge transport barrier （H-mode） or the internal transport barrier of the helical plasma. The system has 25 spatial points with -10 mm resolution. Two high repetition Nd：YAG lasers （〉 550 m J@ 50 Hz） realize the measurement of the time evolution of the plasma profile with ~10 ms time intervals. Scattered light is collected by a large concave mirror （D----800 mm, f/2.25） with a solid angle of -100 mstr and transferred to interference filter polychromators by optical fiber bundles in a staircase form. The signal is amplified by newly designed fast preamplifiers with DC and AC output, which reduces the low frequency background noise. The signals are digitized with a multi-event QDC, fast gated integrators. The data acquisition is performed by a VME-based system operated by the CINOS.展开更多
Specimens of an oxide dispersion strengthened（ODS） ferritic steel（15 Cr-4 Al-0.6 Zr-0.1 Ti） are implanted with multiple-energy He ions at room temperature to create a damage plateau of 0.4 dpa for the average（cor...Specimens of an oxide dispersion strengthened（ODS） ferritic steel（15 Cr-4 Al-0.6 Zr-0.1 Ti） are implanted with multiple-energy He ions at room temperature to create a damage plateau of 0.4 dpa for the average（corresponding to an He concentration of about 7000 appm） from the near surface to a depth about 1 um. The specimen is subsequently thermally annealed at 800°C for 1 h in a vacuum so that simple defects can be formed in the as-implanted state that has undergone significant recombination, meanwhile helium bubbles at nano-scale are formed. Hardness of the specimens are tested with the nano-indentation technique. A hardening by 25% is observed. Microstructures of the specimen after irradiation/annealing are investigated with transmission electron microscopy. Helium bubbles are generally located at dislocations and grain boundaries. Using the dispersed barrier strength model, the strength factor of helium bubbles in the ODS ferritic steel is estimated to be between0.1 and 0.26, which is close to that of helium bubbles in austenitic steels.展开更多
Investigation of experimental configuration for the electron Bernstein wave （EBW） heating by using the existing electron cyclotron heating （ECH） antennas on LHD was performed. By using an antenna installed in the ...Investigation of experimental configuration for the electron Bernstein wave （EBW） heating by using the existing electron cyclotron heating （ECH） antennas on LHD was performed. By using an antenna installed in the lower port, direct oblique launching of the extraordinary （X-） mode from the high magnetic field side （HFS） is available. Since the parallel component of the refractive index （NIF） varies during propagation because of the inhomogeneity of the magnetic field, NH can be zero when the launched X-mode crosses the fundamental electron cyclotron resonance （ECR） layer even NⅡ is noonzero initially. In such a condition, if the electron density is above a certain level the obliquely launched X-mode can pass the fundamental ECR layer without being damped out and can be mode-converted to EBW that is absorbed at the Doppler shifted ECR layer. By using an antenna installed in the horizontal port, oblique launching from the lower magnetic field side （LFS） toward the over-dense plasma is available. Excitation of EBW via the mode conversion process of ordinary mode（O）-extraordinary mode（X）-electron Bernstein wave （B） is expected with the O-mode launching toward an appropriate direction. The O-X-B mode conversion rate and the region of power deposition were surveyed by varying the magnetic field strength and the launching direction. The results of the survey suggest that efficient heating in the core region is difficult by using the existing antenna. Rearrangement of the final mirror of the launching antenna may be needed.展开更多
The possibility of driving poloidal flows by use of ion Bernstein wave is assessed for Heliotron J and EAST devices by means of ray tracing analysis. Sheared poloidal flow is expected to suppress plasma turbulences du...The possibility of driving poloidal flows by use of ion Bernstein wave is assessed for Heliotron J and EAST devices by means of ray tracing analysis. Sheared poloidal flow is expected to suppress plasma turbulences due to the decorrelation of the waves. In Heliotron J and EAST plasma, the rays of Ion Bernstein Wave travel into the central region with oscillations along the magnetic lines of force and their power is absorbed by ions at the cyclotron resonance layers. The momentum input has been estimated by calculating the momentum change of rays and the poloidal flow has been estimated using neoclassical viscosities. The wave momentum changes its sign as it propagates inward, depositing sheared momentum to the plasma, and therefore causes sheared poloidal flows.展开更多
To investigate the potential of utilizing visible spectral imaging for controlling the plasma boundary shape during stable operation of plasma in future tokamak, a D_α band symmetric visible light diagnostic system w...To investigate the potential of utilizing visible spectral imaging for controlling the plasma boundary shape during stable operation of plasma in future tokamak, a D_α band symmetric visible light diagnostic system was designed and implemented on the Experimental Advanced Superconducting Tokamak(EAST). This system leverages two symmetric optics for joint plasma imaging. The optical system exhibits a spatial resolution less than 2 mm at the poloidal cross-section, distortion within the field of view below 10%, and relative illumination of 91%.The high-quality images obtained enable clear observation of both the plasma boundary position and the characteristics of components within the vacuum vessel. Following system calibration and coordinate transformation, the image coordinate boundary features are mapped to the tokamak coordinate system. Utilizing this system, the plasma boundary was reconstructed, and the resulting representation showed alignment with the EFIT(Equilibrium Fitting) results. This underscores the system's superior performance in boundary reconstruction applications and provides a diagnostic foundation for boundary shape control based on visible spectral imaging.展开更多
SiC with fiber-reinforced composites, which are presently considered as the primary structural materials in some fusion reactor conceptual designs, are more attractive and competitive for structural materials in a fus...SiC with fiber-reinforced composites, which are presently considered as the primary structural materials in some fusion reactor conceptual designs, are more attractive and competitive for structural materials in a fusion energy system because of its excellent chemical and mechanical properties such as high fracture toughness, induced-low activation, afterheat under 14MeV neutron irradiation environment at elevated temperature, and good compatibility with coolant and breeder materials. Thus it is important to investigate the research progress of advanced SiC composite, including transmuted helium gas, radiation swelling, radiation effects on mechanical properties, irradiation-enhanced creep, fatigue, physical properties associated with fusion design and their critical issues. This report summarized these results and addressed the major critical issues under irradiation conditions.展开更多
In advanced nuclear reactors,helium can inevitably be produced via(n,)reaction and may precipitate into nano-scale helium bubbles in materials,and can causes degradation of material properties.In the present study,eff...In advanced nuclear reactors,helium can inevitably be produced via(n,)reaction and may precipitate into nano-scale helium bubbles in materials,and can causes degradation of material properties.In the present study,effects of helium bubbles formation in an oxide dispersion strengthened(ODS)steel is studied.Specimens of an ODS ferritic steel(15Cr-4Al-0.6Zr-0.1Ti)were implanted with mutiple-energy He ions at room temperature at the terminal of the 320 kV High-voltage Platform in IMP,to create a damage plateau of 0.4 dpa for average(corresponding to an He concentration of about 7000 appm)from the near surface to a depth about 1m.The specimen was subsequently thermally annealed at 800℃for 1 h in vacuum so that simple defects formed in the as-implanted state underwent significant recombination,meanwhile helium bubbles at nano-scale were formed.展开更多
文摘Influence of the nanoscale oxide particles on mechanical properties and irradiation resistance of oxide-dispersionstrengthened(ODS)ferritic steels is of critical importance for the use of the material in fuel cladding or blanket components in advanced nuclear reactors.In the present work,impact of structures of oxide dispersoids on the irradiation hardening of ODS ferritic steels was studied.Specimens of three kinds of high-Cr ODS ferritic steels containing oxide dispersoids with different number density and average size were irradiated with high-energy Niions at about−50℃.The energy of the incident Ni ions was varied from 12.73 to 357.86 MeV by using an energy degrader at the terminal so that a plateau of atomic displacement damage(∼0.8 dpa)was produced from the near surface to a depth of 24m in the specimens.
文摘The progress of research going on in Group of Energy Materials (GEM), Material Research Center, in 2014 isin the following three aspects.1. Facility developmentIn order to push forward our study on fusion reactor materials, we upgraded the irradiation terminal (128#)of the sector focused cyclotron (SFC) at HIRFL, by developing a new specimen stage specific for irradiation withlow-fluence scattered ions. So far the terminal is capable of irradiation to both very low fluences (106 ions/cm2) andvery high fluences (typically 1016 ions/cm2) for various materials. Specimen temperature can be readily controlledusing the L-N2 cooling stage or the the high-T stage (up to 600 oC). Our recent investigation with transmissionelectron microscopy (TEM) of the defects produced by high-energy Ne ions in steel specimens provides a clearevidence that defects were produced uniformly along the depth in the specimen, indicating that the energy degraderof the terminal works effectively to disperse the ion energy in a wide range. A photo of the terminal together witha SRIM estimate of depth profiles of damage in an 8% Cr reduced activation ferritic/martensitic steel (RAFMS) isshown in Fig. 1.
文摘Aluminum-added Oxide-Dispersion-Strengthened(ODS)ferritic steel is the prime candidate for the fuel cladding of the accident-tolerant fuel technology.Under in-pile condition,the fuel cladding has to endure the intensive radiation from fast neutrons.
基金the Natural Science Foundation of Tianjin(No.06YFJMJC05000).
文摘By hydrolysing titanium isopropoxide in a long hydrocarbon chain surfactant-containing solution, TiO2 fine particles with a diversity of well-defined morphologies was synthesized in this study by a hydrothermal route. The structural change during the formation process was monitored by scanning electron microscopy, transmission electron microscopy and X-ray diffraction analysis. TiO2 with various morphologies such as particle, sheet, rod, tube and flower-like shape was obtained by carefully controlling the preparation conditions. The experimental results show that the pH value is crucial for shape control of the produced TiO2 because it can change the charge state of the surfactant in the solution and the adsorption potential of the surfactant on the TiO2 surface. The shape evolvement of anatase TiO2 was elucidated by quenching the reaction at different stage and the formation mechanism of different shaped TiO2 was suggested.
基金partially supported by the ZE Research Program,IAE(ZE31B-23)the joint usage/research program,c LPS(19022)。
文摘In this study,the effects of the fluid cooling and electric field line deformation were investigated in a dielectric barrier discharge(DBD)plasma source.The DBD plasma jet is improved by covering the ground electrode and a power electrode with insulating oil.We obtained positive results as insulating oil prevents arc formation,while it improved the supplied power and plasma jet length,and increased radical production.Radical production of this nonthermal plasma jet is studied with polyvinyl alcohol-potassium iodide liquid.
基金The project partially supported by the Grant-in-Aid for Science Research of MEXT in Japan and by the Collaboration Program of the Laboratory for Complex Energy ProcessesIAEKyoto University
文摘Spontaneous transition of the plasma confinement mode was observed in thehelical-axis heliotron device 'Heliotron J' for three different plasma heating schemes, i.e.ECH-only, NBI-only and the combination of ECH and NBI. The transition seems to occur above a certaincritical density. In addition to the confinement transition, a spontaneous shift of the hittingposition of the divertor plasma flux on the wall was observed. This shift could be related with thechange of the edge field topology caused by non-inductive toroidal currents.
基金support of the National Magnet Confinement Fusion Energy Research Program(Grand No.2013GB108001)
文摘Oxide dispersion strengthened （ODS） steels can be used as the structural materials in the future fusion reactors and the fuel cladding materials in the advanced fission reactors. However, the weldability of ODS steels is a severe problem. In the present study, defect-free joints of the 15Cr-ODS ferritic steel were achieved by friction stir welding at different rotation speeds. The recrystallization, hardness and tensile properties are highly related with the rotation speed of the stir tool. The higher rotation speed results in coarser grains in the top SZ, while the grain size exhibits more complicated relation with the rotation speed in the SZ center. The joint welded at 250 rpm exhibits a maximum tensile strength of 974 MPa that reaches about 84% of that of the base metal.
基金supported by Special Coordination Funds for Promoting Science and Technology,sponsored by Japan’s Ministry of Education,Culture,Sports,Science and Technology(MEXT).
文摘Herein,we employ the threshold energy neutron analysis(TENA)technique to introduce the world's first active interrogation system to detect special nuclear materials(SNMs),including U-235 and Pu-239.The system utilizes a DD neutron generator based on inertial electrostatic confinement(IEC)to interrogate suspicious objects.To detect secondary neutrons produced during fission reactions induced in SNMs,a tensioned metastable fluid detector(TMFD)is employed.The current status of the system's development is reported in this paper,accompanied by the results from experiments conducted to detect 10 g of highly enriched uranium(HEU).Notably,the experimental findings demonstrate a distinct difference in the count rates of measurements with and without HEU.This difference in count rates surpasses two times the standard deviation,indicating a confidence level of more than 96% for identifying the presence of HEU.The paper presents and extensively discusses the proof-of-principle experimental results,along with the system's planned trajectory.
基金supported by NIFS budgets NIFS10ULRR003,NIFS11ULRR703,and NIFS11PLRR302
文摘Two pairs of high-frequency magnetic probes were installed in the Large Helical Device （LHD）. During the injection of a perpendicular neutral beam, ion cyclotron emissions （ICEs） with the fundamental frequency corresponding to the ion cyclotron frequency at the plasma edge were detected, which are the same type of ICE as measured with the former spare ion cyclotron range of frequencies （ICRF） heating antennas. This type of ICE was further investigated with regard to the phase and intensity of signals. Another type of ICE was found in the LHD, and these ICEs were synchronized with bursts of toroidicity induced Alfv^n eigenmodes （TAE） and the rise of intensity of lost ion flux. Therefore the source of these ICEs was thought to be the particles transferred from the core to the outer region of plasma by the TAE bursts. The frequency of ICEs induced by the TAE bursts increases linearly with the magnetic field strength, since the ion cyclotron frequency increases with the magnetic field strength.
文摘The preparation for an experimental soft x-ray tomography study on the Heliotron J (H-J) machine is carried out,with the objectives of evaluating the capability of the current soft x-ray tomographic system in terms of the identification of different mode structures and their poloidal rotation,and the axis shift with different plasma and machine parameters,and fixing the physics goals for the experimental study.These preparations were carried out via a simulated soft x-ray data set arising from different plasma conditions,such as magnetic islands,low beta and high beta.Soft x-ray tomography (SXT) is performed by the discrete pixel method including singular value decomposition and Phillips-Tikhonov regularization,to obtain clear and smooth images.The H-J soft x-ray tomography results from simulated soft x-rays for the equilibrium H-J plasma sensed the magnetic axis shift clearly and an estimate was also achieved.Successful reconstruction for mode structure m =1/n =1 was obtained along with the realization of the poloidal rotation of the structure.The reconstruction for the m =2/n =1 mode was not very clear for the current soft x-ray diagnostic design.Effective mode identification was not possible due to the lack of measurements.The SXT from the current soft x-ray diagnostic on H-J,the magnetic axis shift can be estimated and the m =1/n =1 mode can be studied.Study of higher poloidal modes is difficult with the current design.
文摘A fast video camera is verified to be a powerful t0ol for observation of filaments/blobs near the last closed flux surface （LCFS）. In order to extract the fluctuation component from the raw data of the fast camera, a pre-processing technique, sliding time window averaging subtraction （STWAS） has been developed to remove the background of slowly varying emission from the bulk plasma. By using this pre-processing technique, the fast camera data are analyzed. A method to identify the filaments in the pre-processed image is also discussed.
基金supported by the Collaboration Program of the Laboratory for Complex Energy Processes,IAE,Kyoto Universitythe NIFS Collaborative Research Program (NIFS10KUHL030,NIFS09KUHL028,NIFS10KUHL033)
文摘A new high repetition rate Nd：YAG Thomson scattering system is developed for the Heliotron J helical device. A main purpose of installing the new system is the temporal evolution measurement of a plasma profile for improved confinement physics such as the edge transport barrier （H-mode） or the internal transport barrier of the helical plasma. The system has 25 spatial points with -10 mm resolution. Two high repetition Nd：YAG lasers （〉 550 m J@ 50 Hz） realize the measurement of the time evolution of the plasma profile with ~10 ms time intervals. Scattered light is collected by a large concave mirror （D----800 mm, f/2.25） with a solid angle of -100 mstr and transferred to interference filter polychromators by optical fiber bundles in a staircase form. The signal is amplified by newly designed fast preamplifiers with DC and AC output, which reduces the low frequency background noise. The signals are digitized with a multi-event QDC, fast gated integrators. The data acquisition is performed by a VME-based system operated by the CINOS.
基金Supported by the National Natural Science Foundation of China under Grant No U1532262the National Magnetic Confinement Fusion Program of China under Grant No 2011GB108003
文摘Specimens of an oxide dispersion strengthened（ODS） ferritic steel（15 Cr-4 Al-0.6 Zr-0.1 Ti） are implanted with multiple-energy He ions at room temperature to create a damage plateau of 0.4 dpa for the average（corresponding to an He concentration of about 7000 appm） from the near surface to a depth about 1 um. The specimen is subsequently thermally annealed at 800°C for 1 h in a vacuum so that simple defects can be formed in the as-implanted state that has undergone significant recombination, meanwhile helium bubbles at nano-scale are formed. Hardness of the specimens are tested with the nano-indentation technique. A hardening by 25% is observed. Microstructures of the specimen after irradiation/annealing are investigated with transmission electron microscopy. Helium bubbles are generally located at dislocations and grain boundaries. Using the dispersed barrier strength model, the strength factor of helium bubbles in the ODS ferritic steel is estimated to be between0.1 and 0.26, which is close to that of helium bubbles in austenitic steels.
基金the budget codes NIFS07ULRR501-3,518,NIFS07KLRR303a grant-in-aid for scientific research of MEXT JAPAN,2008 19740347the JSPS-CAS Core-University program in the field of Plasma and Nuclear Fusion
文摘Investigation of experimental configuration for the electron Bernstein wave （EBW） heating by using the existing electron cyclotron heating （ECH） antennas on LHD was performed. By using an antenna installed in the lower port, direct oblique launching of the extraordinary （X-） mode from the high magnetic field side （HFS） is available. Since the parallel component of the refractive index （NIF） varies during propagation because of the inhomogeneity of the magnetic field, NH can be zero when the launched X-mode crosses the fundamental electron cyclotron resonance （ECR） layer even NⅡ is noonzero initially. In such a condition, if the electron density is above a certain level the obliquely launched X-mode can pass the fundamental ECR layer without being damped out and can be mode-converted to EBW that is absorbed at the Doppler shifted ECR layer. By using an antenna installed in the horizontal port, oblique launching from the lower magnetic field side （LFS） toward the over-dense plasma is available. Excitation of EBW via the mode conversion process of ordinary mode（O）-extraordinary mode（X）-electron Bernstein wave （B） is expected with the O-mode launching toward an appropriate direction. The O-X-B mode conversion rate and the region of power deposition were surveyed by varying the magnetic field strength and the launching direction. The results of the survey suggest that efficient heating in the core region is difficult by using the existing antenna. Rearrangement of the final mirror of the launching antenna may be needed.
基金supported in part by the JSPS-CAS Core University Program in the field of Plasma and Nuclear Fusion
文摘The possibility of driving poloidal flows by use of ion Bernstein wave is assessed for Heliotron J and EAST devices by means of ray tracing analysis. Sheared poloidal flow is expected to suppress plasma turbulences due to the decorrelation of the waves. In Heliotron J and EAST plasma, the rays of Ion Bernstein Wave travel into the central region with oscillations along the magnetic lines of force and their power is absorbed by ions at the cyclotron resonance layers. The momentum input has been estimated by calculating the momentum change of rays and the poloidal flow has been estimated using neoclassical viscosities. The wave momentum changes its sign as it propagates inward, depositing sheared momentum to the plasma, and therefore causes sheared poloidal flows.
基金supported by the National MCF Energy R&D Program of China (Nos. 2018YFE0302103 and 2018YFE 0302100)National Natural Science Foundation of China (Nos. 12205195 and 11975277)。
文摘To investigate the potential of utilizing visible spectral imaging for controlling the plasma boundary shape during stable operation of plasma in future tokamak, a D_α band symmetric visible light diagnostic system was designed and implemented on the Experimental Advanced Superconducting Tokamak(EAST). This system leverages two symmetric optics for joint plasma imaging. The optical system exhibits a spatial resolution less than 2 mm at the poloidal cross-section, distortion within the field of view below 10%, and relative illumination of 91%.The high-quality images obtained enable clear observation of both the plasma boundary position and the characteristics of components within the vacuum vessel. Following system calibration and coordinate transformation, the image coordinate boundary features are mapped to the tokamak coordinate system. Utilizing this system, the plasma boundary was reconstructed, and the resulting representation showed alignment with the EFIT(Equilibrium Fitting) results. This underscores the system's superior performance in boundary reconstruction applications and provides a diagnostic foundation for boundary shape control based on visible spectral imaging.
基金The project supported by the 21st COE research program of Kyoto University on the establishment of sustainable energy system
文摘SiC with fiber-reinforced composites, which are presently considered as the primary structural materials in some fusion reactor conceptual designs, are more attractive and competitive for structural materials in a fusion energy system because of its excellent chemical and mechanical properties such as high fracture toughness, induced-low activation, afterheat under 14MeV neutron irradiation environment at elevated temperature, and good compatibility with coolant and breeder materials. Thus it is important to investigate the research progress of advanced SiC composite, including transmuted helium gas, radiation swelling, radiation effects on mechanical properties, irradiation-enhanced creep, fatigue, physical properties associated with fusion design and their critical issues. This report summarized these results and addressed the major critical issues under irradiation conditions.
文摘In advanced nuclear reactors,helium can inevitably be produced via(n,)reaction and may precipitate into nano-scale helium bubbles in materials,and can causes degradation of material properties.In the present study,effects of helium bubbles formation in an oxide dispersion strengthened(ODS)steel is studied.Specimens of an ODS ferritic steel(15Cr-4Al-0.6Zr-0.1Ti)were implanted with mutiple-energy He ions at room temperature at the terminal of the 320 kV High-voltage Platform in IMP,to create a damage plateau of 0.4 dpa for average(corresponding to an He concentration of about 7000 appm)from the near surface to a depth about 1m.The specimen was subsequently thermally annealed at 800℃for 1 h in vacuum so that simple defects formed in the as-implanted state underwent significant recombination,meanwhile helium bubbles at nano-scale were formed.
