Nuclear Materials and Energy最新文献

{"title":"Effect of welding speed on the microstructure and corrosion resistance of laser deep penetration welded joints of nuclear-grade 316H stainless steel","authors":"Cui Jing ,&nbsp;Wang Annan ,&nbsp;Mei Xiangchen ,&nbsp;Li Dongjie ,&nbsp;Yang Guangfeng","doi":"10.1016/j.nme.2025.101974","DOIUrl":"10.1016/j.nme.2025.101974","url":null,"abstract":"<div><div>A single-pass laser self-melting welding of nuclear-grade 316H stainless steel plate welding experiments, the study of different welding speed under the molten pool morphology and weld corrosion resistance of the changing law. The results show that with the increase of welding speed, the δ ferrite content in the weld gradually decreases, and the corrosion resistance of the weld shows a trend of increasing and then decreasing. When the welding parameters are laser power 9 kW, welding speed 1.6 m/min, and out-of-focus amount −5 mm, the weld corrosion resistance is the best.SEM observation shows that the increase of welding speed promotes the transformation of weld organization from columnar crystals to fine and uniform equiaxial crystals, and the formation of equiaxial crystals significantly improves the corrosion resistance of the weld.EDS analysis shows that the elements of Cr and Mo diffuse at high temperatures, enrich in grain boundaries, and promote ferrite and ferrite. at grain boundaries, promoting ferrite nucleation and growth, and forming coarse ferrite regions at lower welding speeds, while at higher welding speeds, rapid cooling limits element diffusion and ferrite generation, and the microstructure prefers the formation of fine equiaxed crystals.XRD analysis shows that high heat input and high temperature residence time at low welding speeds lead to the precipitation of carbon as metal carbides from the FCC lattice, and at the same time, the accumulation of carbides at grain boundaries further affects the microstructure of the weld. Carbides further affect the microstructure and corrosion resistance of the weld.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101974"},"PeriodicalIF":2.7,"publicationDate":"2025-07-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144739716","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Enhanced vacancy-interstitial annihilation via sliding, rotation and emission of the interstitial in tungsten","authors":"Yi Hu ,&nbsp;Xiaolin Li ,&nbsp;Fangqing Qian ,&nbsp;He Tong ,&nbsp;Changjie Ding ,&nbsp;Shifeng Chen ,&nbsp;Yange Zhang ,&nbsp;Yichun Xu ,&nbsp;Xiang-Yan Li ,&nbsp;Xuebang Wu ,&nbsp;C.S. Liu","doi":"10.1016/j.nme.2025.101973","DOIUrl":"10.1016/j.nme.2025.101973","url":null,"abstract":"<div><div>Experimental studies have demonstrated that introducing alloying elements into bulk tungsten effectively mitigates radiation-induced swelling. This improvement is attributed to enhanced annihilation between vacancies and self-interstitial atoms (SIAs) facilitated by alloying elements. However, the precise atomic-scale mechanisms governing this process remain unclear. In this work, we investigated the dynamic annihilation mechanisms of vacancies with both free and alloying-elements-pinned SIA clusters through combined molecular statics and dynamics simulations. Motivated by the high-energy intermediate state of a SIA cluster motion, we analysed the relevant atomic trajectories and energy landscapes, and identified three key processes driving SIA-mediated vacancy annihilation: sliding, rotation and emission of the interstitial. These processes collectively extend the effective annihilation region of SIAs beyond the limited spatial range predicted by static lattice stability calculations. Crucially, the dynamic coupling between vacancy hopping and these SIA behaviours further amplifies the annihilation volume, offering a mechanistic basis for the large annihilation radii hypothesized in rate theory. This work provides atomic-level insights into vacancy annihilation dynamics and reveals that the radiation-induced SIA clusters, when stabilized by alloying elements, act as efficient vacancy scavengers. These findings establish a framework for optimizing radiation-resistant materials through synergistic strategies of alloy design and grain refinement.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101973"},"PeriodicalIF":2.3,"publicationDate":"2025-07-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144714572","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000 °C)","authors":"Santiago Bermudez ,&nbsp;Furkan Erdogan ,&nbsp;Victoria Davis ,&nbsp;Jessika V. Rojas ,&nbsp;Rajnikant V. Umretiya","doi":"10.1016/j.nme.2025.101972","DOIUrl":"10.1016/j.nme.2025.101972","url":null,"abstract":"<div><div>Despite their widespread application, FeCrAl alloys face several challenges in maintaining performance under high thermal cycling and extreme oxidation conditions. Following the 2011 Fukushima Daiichi accident, there has been a growing interest on developing of accident tolerant fuel (ATF) cladding materials, as well as modifications to existing ones, for advanced nuclear reactors. This study investigates the role of nickel in enhancing the high-temperature oxidation resistance of FeCrAl alloys, which are being considered as potential replacements for zirconium alloys. Specifically, the oxidation behavior of FeCrAl alloys with 17 wt% chromium and varying nickel contents Fe-17Cr-5.5Al, Fe-17Cr-5.5Al-1Ni, and Fe-17Cr-5.5Al-3Ni were examined under steam environment at 1000 °C for 5000 s. The oxide layer thickness and compositional changes were characterized using X-ray diffraction (XRD), scanning electron microscopy (SEM-EDX) and transmission electron microscopy (TEM). The results indicate that low nickel concentrations significantly improve the oxidation resistance of FeCrAl alloys, making them more suitable for accident-tolerant fuel cladding applications in advanced nuclear reactors. This study provides valuable insights in optimizing FeCrAl alloy compositions to improve their oxidation resistance under extreme conditions.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101972"},"PeriodicalIF":2.3,"publicationDate":"2025-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144711392","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Neutron shielding and activation estimation of Bismuth doped glasses (60-x) B2O3–20SiO2–x Bi2O3–12ZnO–8BaO","authors":"Sachin Shet ,&nbsp;Ashwitha Nancy Dsouza ,&nbsp;M.I. Sayyed ,&nbsp;Aljawhara H. Almuqrin ,&nbsp;Nagaraj Kamath ,&nbsp;Srinivas Shenoy Heckadka ,&nbsp;Sudha Kamath","doi":"10.1016/j.nme.2025.101971","DOIUrl":"10.1016/j.nme.2025.101971","url":null,"abstract":"<div><div>Neutron shielding materials play a critical role in nuclear reactors, radiation therapy, and other environments where neutron radiation is present. This study uses theoretical analysis and the Monte Carlo N-Particle (MCNP) simulation tool to investigate the neutron shielding properties of various doped glass materials. In this study, we investigated the neutron shielding properties and activation characteristics of heavy metal oxide glass with the composition (60-x) B₂O₃–20SiO₂–xBi₂O₃–12ZnO–8BaO, where x represents the concentration of Bi₂O₃ varied at 0 and 12 mol%. The primary focus was evaluating the neutron shielding performance with the Monte Carlo MCNP tool. MCNP was employed to perform neutron transport simulations to determine shielding properties.</div><div>Additionally, we explored neutron activation within the glass matrix to assess its feasibility for neutron shielding applications. The results showed that increasing the Bi₂O₃ content reduced the neutron shielding efficiency as it was replaced with a high neutron scattering Boron element. The activation produced in the glass was assessed for thermal neutrons, and the results indicated the glass composite produced a minimal amount of activation. This makes it suitable for the neutron field, considering sufficient cooling time and adequate chemical process needed to eliminate the toxic species produced during irradiation.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101971"},"PeriodicalIF":2.3,"publicationDate":"2025-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144662092","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermal neutron shielding properties of rare-earth nickel alloy materials","authors":"Junze Lin ,&nbsp;Deyang Cui ,&nbsp;Xiaoxiao Li ,&nbsp;Chunyan Zou ,&nbsp;Jianhui Wu ,&nbsp;Cuilan Ren ,&nbsp;Jingen Chen","doi":"10.1016/j.nme.2025.101969","DOIUrl":"10.1016/j.nme.2025.101969","url":null,"abstract":"<div><div>The thermal neutron shielding performance of rare-earth nickel alloys are investigated, specifically focusing on the influence of various rare-earth elements and their concentrations on neutron transmission coefficients. The nickel-based alloy GH3535, with a thickness of 0.5 cm, was doped with mono or binary rare-earth elements. The thermal neutron transmission coefficients were assessed using Monte Carlo simulation methods. Key parameters analyzed included macroscopic absorption and scattering cross-sections, secondary gamma dose, and displacement radiation damage from recoil electrons. The results reveal that thermal neutrons in GH3535 primarily lose energy through scattering, allowing for a high transmission coefficient of 7.24 × 10⁻¹. The incorporation of gadolinium (Gd), a rare-earth element with the largest thermal neutron microscopic absorption cross-section, into GH3535 forms a mono rare-earth nickel alloy, Gd-Ni. The introduction of Gd significantly enhanced the Gd-Ni alloy’s absorption capacity, achieving a transmission coefficient of 2.52 × 10⁻⁶ at 1.50 wt% Gd, with a secondary gamma dose of 2.32 × 10⁻⁵ pSv·s⁻¹. Further doping of binary Gd-Ni alloys with other rare-earth elements, such as samarium (Sm), europium (Eu), and dysprosium (Dy), formed binary rare-earth nickel alloys Gd-Re-Ni and substantially improved shielding effectiveness. Compared to the Gd-Ni alloy (1.5 wt% Gd), the thermal neutron transmission coefficients were reduced by 64.47 % (1.0 wt% Sm), 54.68 % (1.0 wt%, Eu), and 15.13 % (1.0 wt%, Dy). The secondary gamma dose varied with different dopants and Eu notably minimized gamma exposure yielding a dose of 2.29 × 10⁻⁵ pSv·s⁻¹ at 1.0 wt% Eu. Meanwhile, doping with Eu, Sm and Dy reduced the displacement per atom (DPA) in the Gd-Re-Ni alloy, thereby enhancing its resistance to irradiation damage. The study demonstrates that the incorporation of rare-earth elements, particularly Eu and Dy, significantly enhances the thermal neutron shielding capabilities of nickel alloys while reducing secondary gamma radiation and irradiation damage. These findings provide essential theoretical support for the design and application of advanced neutron shielding materials.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101969"},"PeriodicalIF":2.3,"publicationDate":"2025-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144655742","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Irradiation induced structural changes in the coating layers of TRISO fuel","authors":"Janne Heikinheimo ,&nbsp;Yanling Ge ,&nbsp;Zuzanna M. Krajewska-Travar ,&nbsp;Janne Pakarinen","doi":"10.1016/j.nme.2025.101967","DOIUrl":"10.1016/j.nme.2025.101967","url":null,"abstract":"<div><div>The impact of 160 keV Ne ion irradiation on TRISO fuel surrogate samples was investigated, focusing on structural transformations in the buffer, transition, and the IPyC layers. Using various TEM techniques we analyzed the structural changes in the vicinity of the buffer-IPyC interface. The anisotropy texture analysis was based on the orientation distribution of the carbon (002) planes, determined from angular intensity variations along the (002) diffraction rings in SAED patterns, for both unirradiated and irradiated buffer, transition, and IPyC layers. We observed increasing texture up to 25-35 DPA followed by amorphization above 35-40 DPA. Using energy dispersive spectroscopy we observed a distinctive double peak in the Ne concentration profile within the buffer layer. The results indicate that the structure evolves significantly during irradiation and that these changes likely induce different ion penetration depths resulting abnormal Ne concentration profile. SRIM simulations provide complementary insights into the depth-dependent Ne concentration and DPA profiles. This research highlights the significant structural changes induced by Ne ion irradiation and the unique characteristics of the buffer layer’s response.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101967"},"PeriodicalIF":2.7,"publicationDate":"2025-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144724738","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigation of thermoplastic deformation behavior and microstructural evolution of CLF-1 steel for fusion blankets","authors":"Xu Shen ,&nbsp;Gang Yao ,&nbsp;Xiao-Yong Zhu ,&nbsp;Jia-Qin Liu ,&nbsp;Lai-Ma Luo ,&nbsp;Yu-Cheng Wu","doi":"10.1016/j.nme.2025.101966","DOIUrl":"10.1016/j.nme.2025.101966","url":null,"abstract":"<div><div>Reduced Activation Ferritic/Martensitic (RAFM) steel is widely recognized as the preferred structural material for fusion blanket modules. Among China’s primary candidate materials, Chinese Low-Activation Ferritic/Martensitic (CLF-1) steel requires further investigation of its thermomechanical behavior, which is crucial for its application in fusion reactor blankets. This study examines the effects of temperature and strain rate on the deformation behavior of CLF-1 steel. By using a hot processing map, microstructural evolution analysis, and energy efficiency evaluation, the optimal stable deformation conditions for CLF-1 steel at a strain of 0.2 are identified. These conditions correspond to a strain rate of 0.1 to 5 s⁻¹ and a temperature range of 1273 to 1373 K. The identification of these stable deformation parameters provides a theoretical foundation for optimizing the hot-working process of critical CLF-1 steel.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101966"},"PeriodicalIF":2.3,"publicationDate":"2025-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144604694","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental and analytical investigations to reduce MHD pressure drop for liquid LiPb fusion blanket systems: use of ODS-FeCrAl alloys with electrically insulating α-Al2O3 layer in optimal flow channel geometry","authors":"Ryunosuke Nishio ,&nbsp;Masatoshi Kondo ,&nbsp;Teruya Tanaka ,&nbsp;Naoko Oono-Hori","doi":"10.1016/j.nme.2025.101965","DOIUrl":"10.1016/j.nme.2025.101965","url":null,"abstract":"<div><div>The magnetohydrodynamic (MHD) pressure drop in a liquid–metal breeder blanket of magnetic confinement fusion reactors was studied under conditions in which an α-Al₂O₃ layer functioned as an electrically insulating layer on flow channel walls. The α-Al₂O₃ layers had a compact microstructure and uniform thicknesses up to 3.2 μm, which were formed on oxide-dispersion-strengthened FeCrAl alloys SP10 (Fe-15Cr-7Al) and NF12 (Fe-12Cr-6Al) by the oxidation treatment in air atmosphere at 1273 K and 1373 K. The electrical conductivities of the α-Al₂O₃ layers were measured and formulated in the temperature range from 291 K to 1073 K. The electrical conductivity of the layer which was formed on SP10 at 1373 K was 9.4 × 10⁻⁹ S/m at 773 K. This value was lower than those of other oxides such as ZrO₂ and Er₂O₃. The MHD pressure drop in a rectangular flow channel with an α-Al₂O₃ layer was analytically obtained under the conditions of <em>Re</em> = 2.9 × 10⁴ and <em>Ha</em> = 5.9 × 10³. The α-Al₂O₃ layer can significantly reduce the MHD pressure drop. The aspect ratio of width to height of the rectangular channel was varied from 10⁻⁵ to 10⁵ under the magnetic field applied horizontally to the channel. The additional reduction of MHD pressure drop by 74 % can be achieved when the aspect ratio changes from 1 to 16 at the cross-sectional area of 2500 mm².</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101965"},"PeriodicalIF":2.3,"publicationDate":"2025-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144631544","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Studies of material deposition during boronization using quartz crystal microbalance in EAST","authors":"Yuming Liu ,&nbsp;Rong Yan ,&nbsp;Lei Mu ,&nbsp;Baoguo Wang ,&nbsp;Qian Long ,&nbsp;Zhaohui Wang ,&nbsp;Yefan Zhu ,&nbsp;Yuxian Wen ,&nbsp;Zengjie Li ,&nbsp;Shuyue Sun ,&nbsp;Rui Ding ,&nbsp;Junling Chen","doi":"10.1016/j.nme.2025.101964","DOIUrl":"10.1016/j.nme.2025.101964","url":null,"abstract":"<div><div>Boronization is a widely employed technique for controlling fuel recycling and suppressing impurities. It is expected to be a routine wall conditioning method in the fully tungsten (W) wall configuration of the International Thermonuclear Experimental Reactor (ITER). To evaluate boron (B) performance under ITER-relevant metal wall conditions, ion cyclotron range of frequency (ICRF)-assisted boronizations were conducted in the Experimental Advanced Superconducting Tokamak (EAST) from 2023 to 2024. Quartz crystal microbalances (QMBs) installed at the mid-plane of ports C (C-QMB) and J (J-QMB), positioned well beyond the limiter, were utilized for in-situ and real-time measurements of material deposition rates during boronization using sublimation of carborane. Deposition rates ranged from 0.31 to 3.40 μg cm^-2h⁻¹ at C-QMB and 0.04 to 16.95 μg cm^-2h⁻¹ at J-QMB, exhibiting more spatially uniform profiles than lithium (Li) coatings. Deposition behavior was systematically studied and found to depend on the locations of the carborane sublimation oven and ICRF antenna, the temperatures of both the oven and substrate, and the substrate material. Higher deposition rates were associated with elevated plasma parameters in closer proximity to the ICRF antenna, denser gaseous carborane near the oven, and increased oven temperature. In contrast, deposition was reduced on high-Z substrate (W) and at elevated first wall temperature (70 °C). These findings provide further information for the optimization of boronization strategies in future fusion devices.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101964"},"PeriodicalIF":2.3,"publicationDate":"2025-06-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144514219","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Evaluation of a boron nitride–boron pebble aggregate material for renewable plasma-facing surfaces in magnetic fusion devices","authors":"Erick Martinez-Loran ,&nbsp;Daisuke Nishijima ,&nbsp;Marlene Patino ,&nbsp;Angelica Ottaviano ,&nbsp;Lucy Tang ,&nbsp;Santhosh Kumar ,&nbsp;Jose Boedo ,&nbsp;Eric Hollmann","doi":"10.1016/j.nme.2025.101962","DOIUrl":"10.1016/j.nme.2025.101962","url":null,"abstract":"<div><div>We demonstrate a new renewable boron aggregate material that can withstand heat loads of 40<!--> <!-->MW<!--> <!-->m^-2 without cooling and featuring low sublimation of below 100<!--> <!-->Torr-L/s/m² and sputtering yield of 0.04 from 40<!--> <!-->eV D, similar to solid boron. The retention of deuterium (D) is 3.2 × 10²⁰ <!-->D/m², 200<span><math><mo>×</mo></math></span> less than solid boron, 100<span><math><mo>×</mo></math></span> less than carbon, and comparable to tungsten at similar fluence and energy. The material sheds under high heat loads, at a rate of 0.35<!--> <!-->cm/s, exposing the cool surface to the plasma, allowing heat removal and tritium extraction away from the plasma and eliminating the need for cooling channels. This recession rate can be compensated for, as the material can be extruded from a paste at a rate of 1<!--> <!-->cm/s.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101962"},"PeriodicalIF":2.3,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144502012","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}