ZnO films grown on sapphire substrates are implanted with lO0-keV Li ions up to a total dose of 1 × 10^16 cm^-2. Vacancy-type defects, mostly vacancy dusters, are observed by positron annihilation measurements af...ZnO films grown on sapphire substrates are implanted with lO0-keV Li ions up to a total dose of 1 × 10^16 cm^-2. Vacancy-type defects, mostly vacancy dusters, are observed by positron annihilation measurements after implantation. Upon annealing, they first have an agglomeration process which leads to the growth in the vacancy size. After anneling at about 500℃, vacancy clusters grow into microvoids, which is indicated by the positronium formation. With annealing temperature increases to above 500℃, the microvoids begin to recover, and finMly M1 the implantation-induced vacancy defects are removed at 1000℃. No Li nanoclusters can be observed after Li^+ implantation.展开更多
An anomalous phenomenon of wave energy deposition and its evolution were noticed in the beginning phases of lower hybrid wave injection in JT-60U experiments. It was found that the driven currents are always formed in...An anomalous phenomenon of wave energy deposition and its evolution were noticed in the beginning phases of lower hybrid wave injection in JT-60U experiments. It was found that the driven currents are always formed in the central region of the plasma column in the first several hundred milliseconds of the wave pulses, no matter what N|| spectrum of the waves is. Then the driven current profile will change to their normal situation gradually, which depends on N|| spectrum closely.展开更多
The central post is one of the critical components for the low aspect ratio tokamak, which endures not only a tremendous ohmic heating because it carries a rather high current, but also a large neutron heating and irr...The central post is one of the critical components for the low aspect ratio tokamak, which endures not only a tremendous ohmic heating because it carries a rather high current, but also a large neutron heating and irradiation owing to the plasma operation. The DS copper alloy Glidcop AL-25[8] was chosen as the conductor material for its adequate mechanical properties and physics properties. The central post has a cylindrical structure with lots of cooling channels. The length of the central post for the next generation of nuclear fusion spherical tokamaks will be more than 10 m or 20 m. The structural stability is very crucial. When the applied load is larger than the structure critical buckling load, the device will lose its stability and collapse. In order to calculate the critical buckling load, a 1/6-segment finite element model was used and the force acting on the central post was simulated. The results showed that the vertical compressive stresses mainly affect the stability of the central post. The linear buckling analysis results with finite element method based on small deformation theory were given in this paper. The relation curves and functions for buckling factor, depending on the different lengths and the radius of the central post, the diameter of cooling channel and the maximum allowable current density, were also shown.展开更多
Magnetic properties were investigated for the rare-earth 3d-transition metal oxides with the perovskite structure. Intriguing magnetic phenomena were reviewed for a few systems:magnetization peak effect in the titanat...Magnetic properties were investigated for the rare-earth 3d-transition metal oxides with the perovskite structure. Intriguing magnetic phenomena were reviewed for a few systems:magnetization peak effect in the titanates, magnetization reversal in the chromites and metallic ferromagnetism in the cobaltites. The results suggest an important role of the rare-earth ions for the magnetic properties of such complex oxides.展开更多
A simple Core-SOL-Divertor (C-S-D) model has been developed to investigate qualitatively the overall features of the operational space for the integrated core and edge plasma. To construct the simple C-S-D model, a ...A simple Core-SOL-Divertor (C-S-D) model has been developed to investigate qualitatively the overall features of the operational space for the integrated core and edge plasma. To construct the simple C-S-D model, a simple core plasma model of ITER physics guidelines and a two-point SOL-divertor model are used. The simple C-S-D model is applied to the study of the EAST operational space with lower hybrid current drive experiments under various kinds of trade-off for the basic plasma parameters. Effective methods for extending the operational space are also presented, From this study for the EAST operational space, it is evident that the C-S-D model is a useful tool for understanding qualitatively the overall features of the plasma operational space.展开更多
Thin films of VO_(2)single-crystalline on(0001)sapphire substrates have been prepared by visible pulsed laser ablation technique.The crystal quality and properties of the films are evaluated through electrical resista...Thin films of VO_(2)single-crystalline on(0001)sapphire substrates have been prepared by visible pulsed laser ablation technique.The crystal quality and properties of the films are evaluated through electrical resistance measurement,x-ray diffraction(XRD),and Rutherford-backscattering spectroscopy/channeling(RBS/C)analysis.The dependence of the surface electrical resistance of the films on the temperature shows semiconductor-to-metal transitions with the resistance change of 7×10^(3)-2×10^(4).The hysteresis widths are from less than 1 to 3 K.XRD and RBS/C data reveal that the films prepared in particular conditions are single-crystalline VO_(2)with the(010)planes parallel to the surface of the sapphire substrate.展开更多
Recent progress in the physics and engineering design study for themodification programme of JT-60 is presented. In order to achieve a steady state high-βplasmaoperation, which is the dominant issue of this programme...Recent progress in the physics and engineering design study for themodification programme of JT-60 is presented. In order to achieve a steady state high-βplasmaoperation, which is the dominant issue of this programme, physics design for the MHD control and thestability analysis is investigated. Engineering design and the R & D for the superconducting coils,irradiation shield are performed well towards the mission of programme.展开更多
The search for the ri_(13/2) vi_(13/2 ) band in ^(178)Ir has been conducted through the ^(152)Sm(^(31) P, 5nγ)^( 178)Ir reaction and the excitation functions, x-γ and γ-γ-t coincidence measurements. Five rotationa...The search for the ri_(13/2) vi_(13/2 ) band in ^(178)Ir has been conducted through the ^(152)Sm(^(31) P, 5nγ)^( 178)Ir reaction and the excitation functions, x-γ and γ-γ-t coincidence measurements. Five rotational bands have been newly identified. The low-spin signature inversion in the πi13/2 vi13/2 band has been confirmed by the observations of linking transitions and signature crossing at I = 25.5 h. The inversion phenomenon in rh11/2 vi_(13/2), rh9/2 vi_(13/2) and ri_(13/2) vi13/2 structures in ^(178)Ir provides a unique testing ground for different theoretical interpretations.展开更多
Recent results of JT-60U towards establishment of physics basis for ITER andadvanced tokamak operation are presented. Progress in high integrated performance is achieved withimprovement of N-NB and ECRF heating system...Recent results of JT-60U towards establishment of physics basis for ITER andadvanced tokamak operation are presented. Progress in high integrated performance is achieved withimprovement of N-NB and ECRF heating systems. In the next experimental campaign 2003~2004,discharge duration with 17 MW heating will be extended up to 30s for sustaining high-beta plasmalonger than the current diffusion time. Superconducting modification of JT-60 is planned todemonstrate high-beta plasma sustainment exceeding ideal MHD instability limit without wallstabilization.展开更多
Low activation materials have to be developed toward fusion demonstrationreactors. Ferritic steel, vanadium alloy and SiC/SiC composite are candidate materials of the firstwall, vacuum vessel and blanket components, r...Low activation materials have to be developed toward fusion demonstrationreactors. Ferritic steel, vanadium alloy and SiC/SiC composite are candidate materials of the firstwall, vacuum vessel and blanket components, respectively. Although changes of mechanical-thermalproperties owing to neutron irradiation have been investigated so far, there is little data for theplasma material interactions, such as fuel hydrogen retention and erosion. In the present study,deuterium retention and physical sputtering of low activation ferritic steel, F82H, wereinvestigated by using deuterium ion irradiation apparatus. After a ferritic steel sample wasirradiated by 1.7 keV D^+ ions, the weight loss was measured to obtain the physical sputteringyield. The sputtering yield was 0.04, comparable to that of stainless steel. In order to obtain theretained amount of deuterium, technique of thermal desorption spectroscopy (TDS) was employed to theirradiated sample. The retained deuterium desorbed at temperature ranging from 450 K to 700 K, inthe forms of DHO, D_2, D_2O and hydrocarbons. Hence, the deuterium retained can be reduced by bakingwith a relatively low temperature. The fluence dependence of retained amount of deuterium wasmeasured by changing the ion fluence. In the ferritic steel without mechanical polish, the retainedamount was large even when the fluence was low. In such a case, a large amount of deuterium wastrapped in the surface oxide layer containing O and C. When the fluence was large, the thickness ofsurface oxide layer was reduced by the ion sputtering, and then the retained amount in the oxidelayer decreased. In the case of a high fluence, the retained amount of deuterium became comparableto that of ferritic steel with mechanical polish or SS 316 L, and one order of magnitude smallerthan that of graphite. When the ferritic steel is used, it is required to remove the surface oxidelayer for reduction of fuel hydrogen retention. Ferritic steel sample was exposed to the environmentof JFT-2M tokamak in JAERI and after thatthe deuterium retention was examined. The result wasroughly the same as the case of deuterium ion irradiation experiment.展开更多
The center post is the most critical component as an inboard part of the toroidal field coil for the low aspect ratio tokamak. During the discharge it endures not only a tremendous ohmic heating owing to its carrying ...The center post is the most critical component as an inboard part of the toroidal field coil for the low aspect ratio tokamak. During the discharge it endures not only a tremendous ohmic heating owing to its carrying a rather high current but also a large nuclear heating and irradiation owing to the plasma operation. All the severe operating conditions, including the structure stress intensity and the stability of the structure, largely limit the maximum allowable current density. But in order to contain a very high dense plasma, it is hoped that the fusion power plant system can operate with a much high maximum magnetic field BT ≥12 T-15 T in the center post. A new method is presented in this paper to improve the maximum magnetic field up to 17 T and to investigate the possibility of the normal conducting center post to be used in the future fusion tokamak power plant.展开更多
Th/s article deals with the determination of the adsorption properties of metal ions and humic acid in wa- ter on crosslinked chitosan derivatives (carboxymethylchitosan) which were formed using the irradiation techni...Th/s article deals with the determination of the adsorption properties of metal ions and humic acid in wa- ter on crosslinked chitosan derivatives (carboxymethylchitosan) which were formed using the irradiation technique without any additives.The solubility test of these crosslinked materials were investigated in acidic,alkaline media, distilled water,and certain organic solvents.Scanning electron microscopic (SEM) images showed that the crosslinked chitosan derivatives possessed a porous morphological structure.Charged characteristic analyses demon- strated typically pH-dependent properties of the crosslinked materials.The adsorption studies were carried out by the batch method at room temperature.Adsorption of heavy metal ions (such as Cu^(2+),Cd^(2+)) and humic acid onto crosslinked samples was found to be strongly pH-dependent.Adsorption kinetic studies indicated the rapid removal of metal ions,and humic acid from the aqueous solutions.Moreover,isothermal adsorption data revealed that Cu^(2+),Cd^(2+), and humic acid were removed by these crosslinked materials with high efficiency.Adsorption isothermal data were interpreted well by the Langmuir equation.These crosslinked carboxymethylated chitosan derivatives indicate favor- able adsorption of metal ions and humic acid.展开更多
Plasma control on high-β_N steady-state operation for JT-60 superconductingmodification is discussed. Accessibility to high-β_N exceeding the free-boundary limit isinvestigated with the stabilising wall of reduced-a...Plasma control on high-β_N steady-state operation for JT-60 superconductingmodification is discussed. Accessibility to high-β_N exceeding the free-boundary limit isinvestigated with the stabilising wall of reduced-activated ferritic steel and the active feedbackcontrol of the ill-vessel non-axisymmetric field coils. Taking the merit of superconducting magnet,advanced plasma control for steady-state high performance operation could be expected.展开更多
High spin states in ^174Re have been investigated via the ^152Sm (^27 Al, 5nγ) ^174Re reaction. Gamma-ray excitation functions, x-γ and γ-γ coincidences have been measured. Two rotational bands built on the πh9...High spin states in ^174Re have been investigated via the ^152Sm (^27 Al, 5nγ) ^174Re reaction. Gamma-ray excitation functions, x-γ and γ-γ coincidences have been measured. Two rotational bands built on the πh9/2 × vi13/2 and πh11/2 × vi13/2 configurations have been identified and extended up to high-spin states. The relative spin and parity of the band levels have been unambiguously fixed due to observations of several inter-band transitions. Both the bands show the low-spin signature inversion, which is consistent with systematic expectations for the high-j two-quasiparticle bands in the A = 170 mass region.展开更多
A new experimental regime has recently been studied for achieving high fraction of the bootstrap current in the JT-60U hydrogen discharges.The high poloidal beta(βp~3.61)plasma was obtained by high-power neutral beam...A new experimental regime has recently been studied for achieving high fraction of the bootstrap current in the JT-60U hydrogen discharges.The high poloidal beta(βp~3.61)plasma was obtained by high-power neutral beam injection heating at very high edge safety factor(Ip=0.3 MA,Bt=3.65 T,qeff=25-35)region,and the bootstrap current fraction(fBS)was about 40%using the ACCOME code calculation.It was observed that there were no magnetohydrodynamics instabilities to retard the increase ofβp and fBS parameters in the new regime.展开更多
The Excited states of ^(88)Sr have been produced in the reaction ^(16)O(^(82)Se,4p6n)and studied using the in-beam γ spectroscopy techniques.Two high-spin level structures have been observed and established up to 8.5...The Excited states of ^(88)Sr have been produced in the reaction ^(16)O(^(82)Se,4p6n)and studied using the in-beam γ spectroscopy techniques.Two high-spin level structures have been observed and established up to 8.5 MeV and 7.9 MeV excitation energy,respectively.Based on the measurements of the directional correlations ofγ-rays de-exciting oriented states and anisotropic factors ofγ-rays,spin values of the excited states have been assigned up to the highest levels observed.展开更多
A transport simulation has been done by using a i.5D time dependent transportcode to reproduce a formation of the ITB on electron temperature Profile during the long pu1seLHCD in JT-60U tokamak. The transport coeffici...A transport simulation has been done by using a i.5D time dependent transportcode to reproduce a formation of the ITB on electron temperature Profile during the long pu1seLHCD in JT-60U tokamak. The transport coefficients were assumed to reduce with a reversedmagnetic shear and the LH driven current profile was evaluated by fitting dynamic change inthe measured current profile. The gradual increase in the central electron temperature could beexplained by the change in the current profile during LHCD in the present simulation model. Theestimated LH-driven current profile by the transport code analysis shows a finite current densityat the plasma center. Analysis of transport simulation suggests some mechanisms for broadeningthe LH-driven current profile at the central region of the plasma.展开更多
文摘ZnO films grown on sapphire substrates are implanted with lO0-keV Li ions up to a total dose of 1 × 10^16 cm^-2. Vacancy-type defects, mostly vacancy dusters, are observed by positron annihilation measurements after implantation. Upon annealing, they first have an agglomeration process which leads to the growth in the vacancy size. After anneling at about 500℃, vacancy clusters grow into microvoids, which is indicated by the positronium formation. With annealing temperature increases to above 500℃, the microvoids begin to recover, and finMly M1 the implantation-induced vacancy defects are removed at 1000℃. No Li nanoclusters can be observed after Li^+ implantation.
文摘An anomalous phenomenon of wave energy deposition and its evolution were noticed in the beginning phases of lower hybrid wave injection in JT-60U experiments. It was found that the driven currents are always formed in the central region of the plasma column in the first several hundred milliseconds of the wave pulses, no matter what N|| spectrum of the waves is. Then the driven current profile will change to their normal situation gradually, which depends on N|| spectrum closely.
基金supported by National Natural Science Foundation of China (No.10405024)the Ministry of Education,Culture,Sports,Science and Technology (MEXT) Nuclear Researchers Exchange Programme of Japan
文摘The central post is one of the critical components for the low aspect ratio tokamak, which endures not only a tremendous ohmic heating because it carries a rather high current, but also a large neutron heating and irradiation owing to the plasma operation. The DS copper alloy Glidcop AL-25[8] was chosen as the conductor material for its adequate mechanical properties and physics properties. The central post has a cylindrical structure with lots of cooling channels. The length of the central post for the next generation of nuclear fusion spherical tokamaks will be more than 10 m or 20 m. The structural stability is very crucial. When the applied load is larger than the structure critical buckling load, the device will lose its stability and collapse. In order to calculate the critical buckling load, a 1/6-segment finite element model was used and the force acting on the central post was simulated. The results showed that the vertical compressive stresses mainly affect the stability of the central post. The linear buckling analysis results with finite element method based on small deformation theory were given in this paper. The relation curves and functions for buckling factor, depending on the different lengths and the radius of the central post, the diameter of cooling channel and the maximum allowable current density, were also shown.
文摘Magnetic properties were investigated for the rare-earth 3d-transition metal oxides with the perovskite structure. Intriguing magnetic phenomena were reviewed for a few systems:magnetization peak effect in the titanates, magnetization reversal in the chromites and metallic ferromagnetism in the cobaltites. The results suggest an important role of the rare-earth ions for the magnetic properties of such complex oxides.
基金supported in part by the JSPS-CAS Core-University Program in the field of Plasma and Nuclear Fusionalso carried out as a joint project under the Facility Utilization Program of JAERI.
文摘A simple Core-SOL-Divertor (C-S-D) model has been developed to investigate qualitatively the overall features of the operational space for the integrated core and edge plasma. To construct the simple C-S-D model, a simple core plasma model of ITER physics guidelines and a two-point SOL-divertor model are used. The simple C-S-D model is applied to the study of the EAST operational space with lower hybrid current drive experiments under various kinds of trade-off for the basic plasma parameters. Effective methods for extending the operational space are also presented, From this study for the EAST operational space, it is evident that the C-S-D model is a useful tool for understanding qualitatively the overall features of the plasma operational space.
文摘Thin films of VO_(2)single-crystalline on(0001)sapphire substrates have been prepared by visible pulsed laser ablation technique.The crystal quality and properties of the films are evaluated through electrical resistance measurement,x-ray diffraction(XRD),and Rutherford-backscattering spectroscopy/channeling(RBS/C)analysis.The dependence of the surface electrical resistance of the films on the temperature shows semiconductor-to-metal transitions with the resistance change of 7×10^(3)-2×10^(4).The hysteresis widths are from less than 1 to 3 K.XRD and RBS/C data reveal that the films prepared in particular conditions are single-crystalline VO_(2)with the(010)planes parallel to the surface of the sapphire substrate.
文摘Recent progress in the physics and engineering design study for themodification programme of JT-60 is presented. In order to achieve a steady state high-βplasmaoperation, which is the dominant issue of this programme, physics design for the MHD control and thestability analysis is investigated. Engineering design and the R & D for the superconducting coils,irradiation shield are performed well towards the mission of programme.
基金Supported by the National Natural Science Foundation of China under Grant Nos.10025525 and 19605008the Japan STA Scientist Exchange Programme,the JSPS Invitation Fellowship Programme for Research in Japan under Grant No.L00515the Major State Basic Research Development Programme of China(Contract No.G2000077400).
文摘The search for the ri_(13/2) vi_(13/2 ) band in ^(178)Ir has been conducted through the ^(152)Sm(^(31) P, 5nγ)^( 178)Ir reaction and the excitation functions, x-γ and γ-γ-t coincidence measurements. Five rotational bands have been newly identified. The low-spin signature inversion in the πi13/2 vi13/2 band has been confirmed by the observations of linking transitions and signature crossing at I = 25.5 h. The inversion phenomenon in rh11/2 vi_(13/2), rh9/2 vi_(13/2) and ri_(13/2) vi13/2 structures in ^(178)Ir provides a unique testing ground for different theoretical interpretations.
文摘Recent results of JT-60U towards establishment of physics basis for ITER andadvanced tokamak operation are presented. Progress in high integrated performance is achieved withimprovement of N-NB and ECRF heating systems. In the next experimental campaign 2003~2004,discharge duration with 17 MW heating will be extended up to 30s for sustaining high-beta plasmalonger than the current diffusion time. Superconducting modification of JT-60 is planned todemonstrate high-beta plasma sustainment exceeding ideal MHD instability limit without wallstabilization.
文摘Low activation materials have to be developed toward fusion demonstrationreactors. Ferritic steel, vanadium alloy and SiC/SiC composite are candidate materials of the firstwall, vacuum vessel and blanket components, respectively. Although changes of mechanical-thermalproperties owing to neutron irradiation have been investigated so far, there is little data for theplasma material interactions, such as fuel hydrogen retention and erosion. In the present study,deuterium retention and physical sputtering of low activation ferritic steel, F82H, wereinvestigated by using deuterium ion irradiation apparatus. After a ferritic steel sample wasirradiated by 1.7 keV D^+ ions, the weight loss was measured to obtain the physical sputteringyield. The sputtering yield was 0.04, comparable to that of stainless steel. In order to obtain theretained amount of deuterium, technique of thermal desorption spectroscopy (TDS) was employed to theirradiated sample. The retained deuterium desorbed at temperature ranging from 450 K to 700 K, inthe forms of DHO, D_2, D_2O and hydrocarbons. Hence, the deuterium retained can be reduced by bakingwith a relatively low temperature. The fluence dependence of retained amount of deuterium wasmeasured by changing the ion fluence. In the ferritic steel without mechanical polish, the retainedamount was large even when the fluence was low. In such a case, a large amount of deuterium wastrapped in the surface oxide layer containing O and C. When the fluence was large, the thickness ofsurface oxide layer was reduced by the ion sputtering, and then the retained amount in the oxidelayer decreased. In the case of a high fluence, the retained amount of deuterium became comparableto that of ferritic steel with mechanical polish or SS 316 L, and one order of magnitude smallerthan that of graphite. When the ferritic steel is used, it is required to remove the surface oxidelayer for reduction of fuel hydrogen retention. Ferritic steel sample was exposed to the environmentof JFT-2M tokamak in JAERI and after thatthe deuterium retention was examined. The result wasroughly the same as the case of deuterium ion irradiation experiment.
基金The project supported by the Ministry of Education, Culture, Sports, Science and Technology (MEXT) Nuclear Researchers Exchange Program of Japan
文摘The center post is the most critical component as an inboard part of the toroidal field coil for the low aspect ratio tokamak. During the discharge it endures not only a tremendous ohmic heating owing to its carrying a rather high current but also a large nuclear heating and irradiation owing to the plasma operation. All the severe operating conditions, including the structure stress intensity and the stability of the structure, largely limit the maximum allowable current density. But in order to contain a very high dense plasma, it is hoped that the fusion power plant system can operate with a much high maximum magnetic field BT ≥12 T-15 T in the center post. A new method is presented in this paper to improve the maximum magnetic field up to 17 T and to investigate the possibility of the normal conducting center post to be used in the future fusion tokamak power plant.
文摘Th/s article deals with the determination of the adsorption properties of metal ions and humic acid in wa- ter on crosslinked chitosan derivatives (carboxymethylchitosan) which were formed using the irradiation technique without any additives.The solubility test of these crosslinked materials were investigated in acidic,alkaline media, distilled water,and certain organic solvents.Scanning electron microscopic (SEM) images showed that the crosslinked chitosan derivatives possessed a porous morphological structure.Charged characteristic analyses demon- strated typically pH-dependent properties of the crosslinked materials.The adsorption studies were carried out by the batch method at room temperature.Adsorption of heavy metal ions (such as Cu^(2+),Cd^(2+)) and humic acid onto crosslinked samples was found to be strongly pH-dependent.Adsorption kinetic studies indicated the rapid removal of metal ions,and humic acid from the aqueous solutions.Moreover,isothermal adsorption data revealed that Cu^(2+),Cd^(2+), and humic acid were removed by these crosslinked materials with high efficiency.Adsorption isothermal data were interpreted well by the Langmuir equation.These crosslinked carboxymethylated chitosan derivatives indicate favor- able adsorption of metal ions and humic acid.
文摘Plasma control on high-β_N steady-state operation for JT-60 superconductingmodification is discussed. Accessibility to high-β_N exceeding the free-boundary limit isinvestigated with the stabilising wall of reduced-activated ferritic steel and the active feedbackcontrol of the ill-vessel non-axisymmetric field coils. Taking the merit of superconducting magnet,advanced plasma control for steady-state high performance operation could be expected.
文摘High spin states in ^174Re have been investigated via the ^152Sm (^27 Al, 5nγ) ^174Re reaction. Gamma-ray excitation functions, x-γ and γ-γ coincidences have been measured. Two rotational bands built on the πh9/2 × vi13/2 and πh11/2 × vi13/2 configurations have been identified and extended up to high-spin states. The relative spin and parity of the band levels have been unambiguously fixed due to observations of several inter-band transitions. Both the bands show the low-spin signature inversion, which is consistent with systematic expectations for the high-j two-quasiparticle bands in the A = 170 mass region.
文摘A new experimental regime has recently been studied for achieving high fraction of the bootstrap current in the JT-60U hydrogen discharges.The high poloidal beta(βp~3.61)plasma was obtained by high-power neutral beam injection heating at very high edge safety factor(Ip=0.3 MA,Bt=3.65 T,qeff=25-35)region,and the bootstrap current fraction(fBS)was about 40%using the ACCOME code calculation.It was observed that there were no magnetohydrodynamics instabilities to retard the increase ofβp and fBS parameters in the new regime.
基金Supported by the National Natural Science Foundation of China under Grant Nos.19705011 and 19635030the Chinese Academy of Sciences,and RIKEN Radiation Laboratory。
文摘The Excited states of ^(88)Sr have been produced in the reaction ^(16)O(^(82)Se,4p6n)and studied using the in-beam γ spectroscopy techniques.Two high-spin level structures have been observed and established up to 8.5 MeV and 7.9 MeV excitation energy,respectively.Based on the measurements of the directional correlations ofγ-rays de-exciting oriented states and anisotropic factors ofγ-rays,spin values of the excited states have been assigned up to the highest levels observed.
文摘A transport simulation has been done by using a i.5D time dependent transportcode to reproduce a formation of the ITB on electron temperature Profile during the long pu1seLHCD in JT-60U tokamak. The transport coefficients were assumed to reduce with a reversedmagnetic shear and the LH driven current profile was evaluated by fitting dynamic change inthe measured current profile. The gradual increase in the central electron temperature could beexplained by the change in the current profile during LHCD in the present simulation model. Theestimated LH-driven current profile by the transport code analysis shows a finite current densityat the plasma center. Analysis of transport simulation suggests some mechanisms for broadeningthe LH-driven current profile at the central region of the plasma.