Nuclear Materials and Energy最新文献

{"title":"Characterization of detachment inferred from the Balmer line ratios in JET-ILW low-confinement mode plasmas","authors":"Vesa-Pekka Rikala ,&nbsp;M. Groth ,&nbsp;A.G. Meigs ,&nbsp;D. Reiter ,&nbsp;B. Lomanowski ,&nbsp;A. Shaw ,&nbsp;S. Aleiferis ,&nbsp;G. Corrigan ,&nbsp;I.S. Carvalho ,&nbsp;D. Harting ,&nbsp;N. Horsten ,&nbsp;I. Jepu ,&nbsp;J. Karhunen ,&nbsp;K.D. Lawson ,&nbsp;C. Lowry ,&nbsp;S. Menmuir ,&nbsp;B. Thomas ,&nbsp;D. Borodin ,&nbsp;D. Douai ,&nbsp;A. Huber","doi":"10.1016/j.nme.2025.101893","DOIUrl":"10.1016/j.nme.2025.101893","url":null,"abstract":"<div><div>Spectroscopic measurements of the hydrogenic Balmer-<span><math><mi>α</mi></math></span> and Balmer-<span><math><mi>γ</mi></math></span> line emission in JET-ILW low-confinement mode (L-mode) deuterium plasmas are used to assess the onset of volume recombination in the low-field side (LFS) divertor. The evolution of the EDGE2D-EIRENE predicted Balmer-<span><math><mi>γ</mi></math></span> to Balmer-<span><math><mi>α</mi></math></span> emission ratio from low-recycling to detached conditions is in qualitative agreement with the measured ratio. In low-recycling conditions the EDGE2D-EIRENE predicted line-emission is within 30% of measured emission, in high-recycling within 20%t, and in detached conditions lower by a factor of 2.5.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101893"},"PeriodicalIF":2.3,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143388227","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Demonstrating the impact of ro-vibrationally excited H2 on divertor detachment via population modelling","authors":"Richard C. Bergmayr ,&nbsp;Dirk Wünderlich ,&nbsp;Mathias Groth ,&nbsp;Liam H. Scarlett ,&nbsp;Dmitry V. Fursa ,&nbsp;Mark C. Zammit ,&nbsp;Igor Bray ,&nbsp;Ursel Fantz","doi":"10.1016/j.nme.2025.101895","DOIUrl":"10.1016/j.nme.2025.101895","url":null,"abstract":"<div><div>EDGE2D-EIRENE profiles characteristic for low recycling, high recycling and detached plasmas are postprocessed applying a vibrationally resolved collisional radiative (CR) model based on the Yacora solver to predict excited state densities and thus the molecular Lyman-, Werner- and Fulcher band emission intensities. These emission intensities are compared to predictions from the AMJUEL database standardly used in EIRENE. Lower Fulcher band and higher Lyman- and Werner band emission is predicted by the Yacora model in comparison to AMJUEL suggesting that inconsistent results from model based evaluation of measured spectra are expected depending on which model and molecular emission band is considered. The implications on detachment rate predictions are discussed.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101895"},"PeriodicalIF":2.3,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143388228","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"The influence of hydrogen and impurities on the work function of multilayer Cs atoms on the plasma grid: An ab-initio molecular dynamics study about negative hydrogen ion sources for neutral beam injection systems","authors":"Xin Zhang ,&nbsp;Heng Li ,&nbsp;Katsuyoshi Tsumori ,&nbsp;Yuhong Xu ,&nbsp;Mitsutaka Isobe ,&nbsp;Guangjiu Lei ,&nbsp;Sanqiu Liu ,&nbsp;Masaki Osakabe ,&nbsp;Haruhisa Nakano ,&nbsp;Akihiro Shimizu ,&nbsp;Shoichi Okamura ,&nbsp;Kunihiro Ogawa ,&nbsp;Hiromi Takahashi ,&nbsp;Zilin Cui ,&nbsp;Jun Hu ,&nbsp;Yiqin Zhu ,&nbsp;Xiaolong Li ,&nbsp;Xiaoqiao Liu ,&nbsp;Huaqing Zheng ,&nbsp;Shaofei Geng ,&nbsp;Changjian Tang","doi":"10.1016/j.nme.2025.101897","DOIUrl":"10.1016/j.nme.2025.101897","url":null,"abstract":"<div><div>We conducted ab-initio molecular dynamics simulations to investigate the migration of hydrogen and impurities (oxygen or copper) and their impact on the work function of cesiated surfaces under different cesium coverages. To ensure temperature and energy stability, all simulations were divided into pre-equilibrium and equilibrium phases, with more rigorous computations performed on equilibrium configurations. Our findings indicate that as the cesium coverage increases, the effects of hydrogen and impurities on the work function gradually diminish. When the cesium coverage reaches 20/16 <em>θ</em>, the work function without hydrogen and impurities is approximately 2.07 eV, and the presence of hydrogen and impurities causes a work function change of less than 0.05 eV. Additionally, when hydrogen and oxygen impurities are bound to the Mo (001) substrate (deposited underneath the cesium layer), the range of electron redistribution induced by hydrogen and impurities is limited, terminating at 1.03 Å above the dense cesium layer. When the cesium layer thickness is greater than dense layer, the electronic density perturbations caused by hydrogen and impurities vanish. The dynamic simulation with hydrogen and impurities initially positioned above the cesium layer reveals that they quickly enter the disordered Cs phase but stabilizes at a specific height, without penetrating the dense cesium layer. Impurities close to the top of disordered Cs phase cause electronic density perturbations that cannot be fully screened in this case. Furthermore, hydrogen and impurities remaining bound to the Mo (001) substrate are more energetically stable. This is attributed to the electron-rich environment below the dense cesium layer, which is particularly advantageous for oxygen impurities with strong electronegativity.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101897"},"PeriodicalIF":2.3,"publicationDate":"2025-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143403348","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Real-time helium bubble growth in tungsten by in-situ GISAXS","authors":"L. Corso ,&nbsp;S. Curiotto ,&nbsp;F. Cheynis ,&nbsp;P. Muller ,&nbsp;E. Bernard ,&nbsp;M. Cabie ,&nbsp;C. Martin ,&nbsp;F. Leroy","doi":"10.1016/j.nme.2025.101894","DOIUrl":"10.1016/j.nme.2025.101894","url":null,"abstract":"<div><div>Nuclear fusion, as a carbon-free energy source, is actively pursued by the international community. However, the irradiation by helium (He) of the walls facing the plasma can lead to important damages at the surface and deeper in the bulk, affecting the properties and life span of the materials. To address the effects of He irradiation, we have studied in real time, during He bombardment at 1273 K, the nucleation and growth of He bubbles nearby the surface of tungsten by grazing incidence small angle X-ray scattering (GISAXS). We could disentangle the surface and bubble contributions on the measured GISAXS patterns by adjusting the X-ray incident angle below and above the critical angle of total external reflection. The occurrence of tilted diffuse scattering rods proves the presence of facetted bubbles buried inside the tungsten matrix. The time evolution of the X-ray diffuse scattering has been used to evaluate the growth kinetics. A close comparison with analytical modelling of the growth process suggests a growth kinetics dominated by the migration-coalescence of bubbles during which the bubble motion is hindered by the nucleation of ledges at the bubble facet surface.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101894"},"PeriodicalIF":2.3,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143372478","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigating the role of divertor geometry on density build-up in the island divertor","authors":"N. Maaziz,&nbsp;F. Reimold,&nbsp;V.R. Winters,&nbsp;D. Bold,&nbsp;Y. Feng,&nbsp;V. Perseo,&nbsp;W7-X Team","doi":"10.1016/j.nme.2025.101886","DOIUrl":"10.1016/j.nme.2025.101886","url":null,"abstract":"<div><div>The island divertor has been proposed for power and particle exhaust in stellarators. It is investigated in the Wendelstein 7-X (W7-X) experiment. The divertor capabilities such as particle exhaust or radiative power dissipation scale with the divertor density. However, significantly lower divertor density has been obtained in W7-X in comparison to tokamaks and no high-recycling scaling is observed. To alleviate the impact of the complicated geometry, a simplified geometry model for the island divertor in EMC3-EIRENE is developed and used to investigate the effect of the divertor target geometry. We show that compared to the open divertor, a closed divertor geometry leads to higher achievable densities and in particular a much stronger scaling of the target density with respect to the separatrix density.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101886"},"PeriodicalIF":2.3,"publicationDate":"2025-02-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143343832","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D","authors":"M.G. Burke ,&nbsp;F. Scotti ,&nbsp;S.L. Allen ,&nbsp;W.H. Meyer ,&nbsp;A. Holm ,&nbsp;M. Zhao ,&nbsp;A.G. McLean ,&nbsp;M. Fenstermacher ,&nbsp;H.Q. Wang ,&nbsp;R. Wilcox","doi":"10.1016/j.nme.2025.101888","DOIUrl":"10.1016/j.nme.2025.101888","url":null,"abstract":"<div><div>This paper presents experimental measurements of the location of the impurity flow stagnation point in the scrape-off-layer (SOL) of a tokamak plasma. Coherence imaging of carbon-2+ emission (465 nm) is used to track the main-chamber impurity velocity of DIII-D L-mode plasmas with <span><math><mrow><mi>B</mi><mo>×</mo><mo>∇</mo><mi>B</mi></mrow></math></span> out of the divertor. The <span><math><msup><mrow><mi>C</mi></mrow><mrow><mn>2</mn><mo>+</mo></mrow></msup></math></span> flow stagnates near the top or crown of the plasma when an open divertor (no baffling) is used. In contrast, with matched conditions and using a divertor with baffling, the <span><math><msup><mrow><mi>C</mi></mrow><mrow><mn>2</mn><mo>+</mo></mrow></msup></math></span> flow stagnates near the outer divertor leg (X-point). The <span><math><msup><mrow><mi>C</mi></mrow><mrow><mn>2</mn><mo>+</mo></mrow></msup></math></span> poloidal emission is hollow, peaking near the divertor legs, in the open configuration. In contrast, in the closed configuration, the <span><math><msup><mrow><mi>C</mi></mrow><mrow><mn>2</mn><mo>+</mo></mrow></msup></math></span> emission is flat through most of the main-chamber SOL. Changing divertor dissipation from attached to detached conditions had only a minor effect on the main-chamber midplane impurity velocity. Numerical simulations using the multi-fluid edge transport code UEDGE including cross-field drifts show qualitative agreement with the open divertor experimental result.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101888"},"PeriodicalIF":2.3,"publicationDate":"2025-02-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143403221","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"The first application of flush probe arrays on HL-3 tokamak","authors":"Z.H. Huang ,&nbsp;L.W. Yan ,&nbsp;K.Y. Yi ,&nbsp;Na Wu ,&nbsp;W.J. Chen ,&nbsp;W.C. Wang ,&nbsp;Yu He ,&nbsp;J. Chen ,&nbsp;J. Cheng ,&nbsp;W. Zhao ,&nbsp;J.M. Gao ,&nbsp;L. Nie ,&nbsp;Z.B. Shi ,&nbsp;X.Q. Ji ,&nbsp;W.L. Zhong","doi":"10.1016/j.nme.2025.101892","DOIUrl":"10.1016/j.nme.2025.101892","url":null,"abstract":"<div><div>Newly flush-mounted Langmuir probe arrays are fabricated and applied in the HL-3 tokamak to investigate its advanced divertor physics such as snowflake and tripod divertors. Three sets of flush probe arrays are installed on toroidal ports 4, 10 and 18. Each port has 43 × 4 = 172 probe tips, which are composed of 43 triple and single probe arrays. Each array consists of 4 tips with the same major radius and height. A total of 516 CFC (carbon fiber composite) tips with diameter of <em>d</em>_p = 4 mm are mounted at 3 ports. Their minimum spatial separation is 1.8 cm poloidally, while temporal resolution for ion saturation currents is 1 μs. The toroidal separation of a triple probe is 1.8 ∼ 3.8 cm or 10.2 ∼ 14.8 cm. It gradually increases with major radius. A novel design of ceramic isolation ring with a labyrinth can ensure reliable electrical insulation between the CFC tip and the divertor target plate where plasma dust and impurities are continuously deposited into their gaps due to long experimental operation. A large spring washer improves the heat conduction from each tip through a ceramic insulator into a cooled divertor copper plate. Every probe body is embedded into a divertor plate then brazed to a copper wire to ensure good electrical connection, and finally fixed on a stainless-steel support. Forty-three signal wires at the same toroidal angle are combined into a manifold copper tube to vacuum feedthrough, which can dramatically shield noise and resist the high baking temperature of 300 °C. Moreover, the discharge monitoring and mode conversion between the triple and single probes could be freely performed via a remote-control workstation. The first application results indicate that the target probe arrays can measure highly temporal plasma parameters, including electron temperature and density, particle and heat fluxes in H-mode discharges on HL-3 tokamak. The tripod divertor configuration has been confirmed by the new flush probe arrays.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101892"},"PeriodicalIF":2.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143174243","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Grain orientation and temperature dependences of bubbles at tungsten surfaces upon helium plasma exposure","authors":"Mounir Alfazzaa ,&nbsp;Federica Pappalardo ,&nbsp;Andrea Campos ,&nbsp;Gilles Cartry ,&nbsp;Marco Minissale ,&nbsp;Céline Martin","doi":"10.1016/j.nme.2025.101883","DOIUrl":"10.1016/j.nme.2025.101883","url":null,"abstract":"<div><div>The impact of grain orientation and surface temperature on helium bubble growth at tungsten surfaces exposed to low-pressure helium plasmas was investigated by analyzing the nanoholes formed at the surface. Polycrystalline tungsten samples were exposed to a 2<!--> <!-->Pa RF plasma at 400<!--> <!-->W and 79<!--> <!-->eV positive ion bombardment energy. Through detailed SEM imaging before and after plasma exposure and a developed image analysis protocol, we assessed quantitatively the size and density of helium bubbles that have burst on the surface upon plasma exposure. The results demonstrate a clear temperature dependence, with surface bubble density and size increasing at higher temperatures, and a dependence on grain orientation, with the (111) orientation giving slightly larger and denser surfaces of burst bubbles.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101883"},"PeriodicalIF":2.3,"publicationDate":"2025-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143343831","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Boundary plasma studies for a spherical tokamak with lithium walls","authors":"A. Antony ,&nbsp;L. Carbajal ,&nbsp;T.D. Rognlien ,&nbsp;M.V. Umansky ,&nbsp;A. Froese ,&nbsp;S. Howard ,&nbsp;C. Ribeiro ,&nbsp;R. Ivanov ,&nbsp;C. Dunlea ,&nbsp;C.P. McNally","doi":"10.1016/j.nme.2025.101885","DOIUrl":"10.1016/j.nme.2025.101885","url":null,"abstract":"<div><div>Boundary plasma and plasma-material interactions are investigated for magnetised target fusion (MTF) applications. The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a cavity with liquid lithium walls that will subsequently be compressed to fusion conditions Laberge, J. Fusion Energy (2019) The Plasma Injector 3 (PI3) experiment at General Fusion is a non-compressing experiment with solid lithium walls that studies the formation and quasi-steady state operation of a CHI spherical tokamak Carbajal et al. (2023). An explorative study is carried out for wall-limited versus diverted configurations for PI3 using the fluid edge transport code UEDGE. Experimental edge temperature and density profiles from triple Langmuir probes are used to establish realistic temperature and density profiles in UEDGE Rognlien et al. (1992) by adjusting the transport coefficients. In UEDGE, we model the wall-limited plasma via a thin limiter with various insertion depths. It is found that limiter depth and location are key parameters in determining radial profiles and sputtered lithium behaviour. Furthermore, it is found that the total sputtering of the limiter is significantly lower than the sputtering of the wall in some of the limiter configurations studied. Lithium ions and neutral behaviour are compared between limited and diverted configurations.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101885"},"PeriodicalIF":2.3,"publicationDate":"2025-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143174235","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"First-principles calculations for the effect of irradiation-induced point defects on the hydrogen dissolution and diffusion in γ-Al2O3","authors":"Xin-Dong Pan ,&nbsp;Xiao-Chun Li ,&nbsp;Jing Wang ,&nbsp;Rongmei Yu ,&nbsp;Chunying Pu ,&nbsp;Hai-Shan Zhou ,&nbsp;Guang-Nan Luo","doi":"10.1016/j.nme.2025.101890","DOIUrl":"10.1016/j.nme.2025.101890","url":null,"abstract":"<div><div>FeAl/Al₂O₃ is considered the most promising candidate material for tritium permeation barrier (TPB) due to numerous advantages. γ-Al₂O₃ phase structure is commonly found in FeAl/Al₂O₃, and is crucial to its effectiveness. In fusion reactors, high-energy neutrons generate a large number of irradiation-induced defects, significantly affecting the performance of γ-Al₂O₃. The underlying mechanism is still unclear. This study focuses on the influence of irradiation-induced point defects on the dissolution and diffusion of H in γ-Al₂O₃ using first-principles theory. Our results show that the irradiation-induced point defect exhibit a strong ability to capture dissolved H atoms, leading to higher hydrogen retention. When dissolved H atoms are captured by vacancy-type defects, the diffusion barrier becomes so high that isolated vacancy-type irradiation-induced point defects can hinder the diffusion of H atoms. This in turn enhances the effectiveness of TPB in preventing H permeation. Furthermore, the impediment effect of Al vacancies on H diffusion in γ-Al₂O₃ is higher than that in α-Al₂O₃, whereas O vacancies have the opposite effect, impeding H diffusion in γ-Al₂O₃ less than in α-Al₂O₃. However, the diffusion barrier of O interstitial atoms and H as a bound entity is only 0.11 eV, which is even far lower than that in α-Al₂O₃ (0.44 eV). Therefore, O interstitial atoms can accelerate the diffusion process of H, which can reduce the efficiency of protection against H permeation through γ-Al₂O₃ TPB. The accelerating effect in γ-Al₂O₃ is higher than that in α-Al₂O₃. These findings provide valuable insights into the influence of irradiation-induced point defects on H behavior in γ-Al₂O₃, which is essential for improving the efficiency of FeAl/Al₂O₃ tritium permeation barriers.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101890"},"PeriodicalIF":2.3,"publicationDate":"2025-01-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173087","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}