Radiation Physics and Chemistry最新文献

{"title":"Synthesis, physical, structure, mechanical and ionizing radiation shielding properties of some bismuth-based alloys: Comparative investigation","authors":"Abdelmoneim Saleh ,&nbsp;Nermin Ali Abdelhakim","doi":"10.1016/j.radphyschem.2025.112510","DOIUrl":"10.1016/j.radphyschem.2025.112510","url":null,"abstract":"<div><div>Due to the harmful effects of X-rays, gamma rays, neutrons, and heavy charged ions (such as protons and alpha particles) caused by radiation exposure, scientific investigation is still needed to find and develop materials that can act as radiation shields. Four Bi-based alloys (Bi–10Zn, Bi–10Sn, Bi–10In and Bi–10Ag) have been prepared utilizing melt-spinning technique. These alloys were composed of high purity elements such as Bi, Zn, Sn, In and Ag. Utilizing X-ray diffraction, the crystal structure of the prepared alloys was examined. The mechanical features in terms of Vickers hardness Hv and the creep behavior have been determined using Vickers microhardness test machine for the prepared alloys. The rapid solidification process had positive effects on the Vickers hardness Hv of the alloys due to several factors, including the refinement of grain size, enhanced alloy homogeneity, elimination of grain boundary segregation, increased solubility of solute elements, and the formation of new metastable crystalline structures, as well as a reduction in the degree of order. The WinXCom program was used to evaluate the shielding efficiency of various Bi-alloys against X/gamma radiation in the energy range of 0.015–15 MeV. Compared to other typical shielding materials and recently researched substances, the studied alloys demonstrate effective gamma shielding properties. The Sn–50Ag alloy exhibit superior mechanical and shielding against gamma rays performance. Consequently, the Bi–10Ag alloy strike a favorable balance between shielding and mechanical performance, making them suitable for radiation protection. Additionally, when compared to all other prepared alloys, conventional neutron shielding materials, and recently studied substances, the Bi–10Zn and Bi–10Ag alloys possesses the highest capability for absorbing neutrons. Lastly, the Bi–10Ag alloy demonstrates exceptional performance in attenuating protons (H⁺¹) and alpha particles (He⁺²) in terms of projected range (PR) and stopping power (MSP). These findings indicate that the Bi–10Ag alloy offer excellent nuclear shielding and mechanical performance, making it well-suited for various applications, including nuclear waste storage, industrial processes, and medical applications.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112510"},"PeriodicalIF":2.8,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967849","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"A comparative study on the radiological properties of PEEK and titanium alloy implant materials with extended HU CT imaging","authors":"Suvankar Das ,&nbsp;Thepuzhoyi Medeo ,&nbsp;Pranav Sharad Sapkal ,&nbsp;Hema Anukula ,&nbsp;Paul Ravindran B","doi":"10.1016/j.radphyschem.2025.112515","DOIUrl":"10.1016/j.radphyschem.2025.112515","url":null,"abstract":"<div><h3>Introduction</h3><div>This study compares the radiological properties of Polyether Ether Ketone (PEEK) and titanium Alloy (Ti6Al4V) implant materials in reconstructive surgery for head and neck cancer patients undergoing radiotherapy. It focuses on attenuation, scatter in water, dose build-up, and dose near heterogeneity, measured and calculated with the Treatment Planning System using 12-bit and extended HU CT images.</div></div><div><h3>Methods</h3><div>PEEK and Ti6Al4V slabs were 3D-printed at various thicknesses, and their radiological properties were measured using a Plane Parallel chamber on a Varian UNIQUE linear accelerator with 6 MV photons. Scatter measurements in a water phantom with 3D-printed holders were performed for both materials. The Eclipse TPS was used for dosimetric analysis with the AAA. TPS analysis utilized 12-bit and extended HU CT image sets of the water phantom with slabs.</div></div><div><h3>Results</h3><div>PEEK showed minimal scattering effects (&lt;1%) and no dose enhancement. Ti6Al4V resulted in 1.5% dose enhancement and 9.1% dose reduction. CT scans with Ti6Al4V exhibited artefacts, causing 4.5% underestimation of dose. HU maximum value for Ti6Al4V was about 6916 in extended HU CT images, saturating at 3017 in 12-bit depth CT. Depth dose curves from TPS for both CT image sets showed no significant variation with AAA, with a dose enhancement of about 2.5% at the slab entrance.</div></div><div><h3>Conclusion</h3><div>PEEK could be a viable alternative to Ti6Al4V due to its minimal impact on dose distribution. Enhanced radiation effects near Ti6Al4V and high-density artefacts suggest the need for alternatives to high-density materials, making PEEK as a suitable implant material.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112515"},"PeriodicalIF":2.8,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142990278","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Simulation of a suitable neutron and gamma shield for IECF device in different working modes by MCNPX code and studying its lithium production","authors":"Hadi Zanganeh,&nbsp;M.N. Nasrabadi","doi":"10.1016/j.radphyschem.2024.112495","DOIUrl":"10.1016/j.radphyschem.2024.112495","url":null,"abstract":"<div><div>In this work, the IECF device using the MCNPX code was simulated and parameters such as lethargy as well as cross-sections, changes in neutron flux and dosimetry and suitable multi-layer shields were studied. To secure the device from radiation hazards at different work intensities and in addition to the role of shielding, the role of producing materials such as lithium, the required simulations were done and the necessary shield thicknesses were determined. From the intensity of <span><math><mrow><msup><mn>10</mn><mn>6</mn></msup><msup><mi>s</mi><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span> which is used for nuclear laboratories in universities up to neutron production <span><math><mrow><msup><mn>10</mn><mn>12</mn></msup><msup><mi>s</mi><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span> which is used for the BNCT method, an optimal shield thickness is required. For the first layer, a material with an average mass number was chosen to absorb the highest amount of energy and produce the lowest amount of gamma in inelastic scattering with fast neutrons. The produced gammas are also absorbed by concrete. For the thickness changes of different layers, in addition to measuring the remaining energies in the neutron flux, the cross-sections corresponding to those energies were also measured in order to calculate the required shield thicknesses for different powers of the device in different working conditions. After determining the type of different materials suitable for shielding, dosimetry was performed according to the ICRP60 standard and by making the necessary changes in the thickness of the layers, the neutron and gamma doses were reduced to the standard level. Also, the fluxes of thermal, epithermal and fast neutrons were measured in different shielding layers. Finally, for all calculated neutron production intensities, the necessary shielding thickness was determined for safe operation of the device. As a result of this study, by modifying and improving the method of determining the required thickness of the shield for different intensities, the smaller and more suitable thickness for the intensity of 10⁹ <span><math><mrow><msup><mi>s</mi><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span> was determined. This improvement and reduction in the thickness of the shield caused a reduction in the weight of the total shield and a reduction in the cost of shield construction while maintaining radiation safety according to ICRP60 standards. The idea of lithium production by IECF device using the materials of this shielding was simulated by MCNPX code. Boric acid was investigated and studied as a suitable material for lithium production. After performing the simulation and calculations, the amount of 1 Kg of lithium per month of device working for 8 h per day was obtained which is a valuable amount and it is possible to increase its production.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112495"},"PeriodicalIF":2.8,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967741","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Voxel-based internal dose prediction using machine learning with organ-specific features and Monte Carlo simulations","authors":"Khaled Belkadhi ,&nbsp;Nabil Chaabane ,&nbsp;Kais Manai ,&nbsp;Omrane Kadri","doi":"10.1016/j.radphyschem.2024.112497","DOIUrl":"10.1016/j.radphyschem.2024.112497","url":null,"abstract":"<div><div>Estimation of internal dose is a critical task in nuclear medicine and radiation protection. New organ-specific features are included to construct a machine learning model capable of predicting the internal dose in the UF/NCI voxel phantoms, ranging from newborn to pediatric and adult of both genders. The dosimetry data is generated using the Monte Carlo simulation toolkit, Gate. Multiple source organs were utilized to train and validate the predictive models. Results demonstrate high accuracy, with less than 2% Root Squared Error in predicting the internal dose in most organs using the XGBoost machine learning model. This research can help nuclear medicine and radiation protection researchers and practitioners refine internal dose predictions based on anatomical and physiological characteristics of patients.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112497"},"PeriodicalIF":2.8,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967851","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Mn concentration dependence on dosimetric properties of Mn-doped ZnAl2O4 transparent ceramics","authors":"Satoshi Honjo,&nbsp;Kensei Ichiba,&nbsp;Yusuke Endo,&nbsp;Takumi Kato,&nbsp;Daisuke Nakauchi,&nbsp;Noriaki Kawaguchi,&nbsp;Takayuki Yanagida","doi":"10.1016/j.radphyschem.2025.112513","DOIUrl":"10.1016/j.radphyschem.2025.112513","url":null,"abstract":"<div><div>We synthesized the 0.01, 0.05, 0.1, and 0.5% Mn-doped ZnAl₂O₄ transparent ceramics of a spinel structure by the spark plasma sintering method and evaluated their optical, scintillation, and dosimetric properties. The XRD patterns confirmed that ZnAl₂O₄ was successfully synthesized. Photoluminescence spectra showed a broad emission band due to the 3d-3d transitions of Mn²⁺ ions. In the thermally stimulated luminescence (TSL) properties, TSL glow peaks of the Mn-doped ZnAl₂O₄ transparent ceramics were detected at 160, 320, and 490 °C. TSL spectra of all the samples heated at 160 °C showed the emission peak at 520 nm due to the Mn²⁺ ions. The TSL and OSL intensities of the 0.05% Mn-doped samples were the highest in all the samples. In the 0.05% Mn-doped sample, the TSL and OSL dose response functions exhibited a linear response at 0.01–100 and 1–100 mGy, respectively.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112513"},"PeriodicalIF":2.8,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967850","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Synthesis of irradiation-modified triphenylphosphine resins and study of the extraordinary enrichment behaviour of rhenium at low concentrations against a high uranium background","authors":"Haonan Li ,&nbsp;Yuxin Liao ,&nbsp;Yuanzhe Jia ,&nbsp;Wei Zhao ,&nbsp;Yonghuan Huang ,&nbsp;Rong Hua ,&nbsp;Xuebin Su","doi":"10.1016/j.radphyschem.2025.112511","DOIUrl":"10.1016/j.radphyschem.2025.112511","url":null,"abstract":"<div><div>In order to recover the trace rhenium resources in the background environment of high uranium leach solution, we synthesized a resin suitable for the efficient adsorption of rhenium in a low concentration environment by using electron-accelerator irradiation grafting technology and high-density solidification of triphenylphosphine on the surface of styrene chlorine sphere skeleton, which can circumvent the internal diffusion process in ion exchange, and investigated the adsorption and desorption performance of the material in static and dynamic adsorption modes. The adsorption and desorption properties of the materials were investigated by static and dynamic adsorption. It is shown that the new resin has good enrichment ability for rhenium between pH = 1–10 and basically does not adsorb uranium resin saturated adsorption capacity of up to 233.58 mg/g, the maximum uranium-rhenium separation coefficient β (Re/U) is calculated to be 1840.6, the dynamic adsorption equilibrium time of 256 s. Scanning electron microscopy (SEM), Fourier-transform infrared spectroscopy (FT-IR), and X-ray photoelectron spectroscopy (XPS), and density-functional theory (DFT) were applied to investigate the adsorption and desorption effects and mechanisms of the new material. The adsorption and desorption effects and mechanisms were characterized, dynamic adsorption showed that the resin reached adsorption penetration at 270 BV (resin bed volume) and adsorption saturation at 520 BV, with a saturation-to-penetration ratio V_e/V_b (ratio of the saturation point to the penetration point volume) of 1.92, the saturated resin can be completely desorbed by 4 mol/L NH₄SCN at 100 BV, and the poor resin can be effectively regenerated by concentrated hydrochloric acid, and the exchange capacity of the resin can be restored over 91%, which has an important application prospect.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112511"},"PeriodicalIF":2.8,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142989177","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Iodine K- and L-edge X-ray absorption spectra of HI: The effect of molecular orbitals and core subshells","authors":"R. Hauko ,&nbsp;J. Padežnik Gomilšek ,&nbsp;A. Kodre ,&nbsp;I. Arčon ,&nbsp;U. Luin","doi":"10.1016/j.radphyschem.2025.112509","DOIUrl":"10.1016/j.radphyschem.2025.112509","url":null,"abstract":"<div><div>Analysis of the recently measured absorption spectra of molecular HI at <em>K</em> and <em>L</em> edges of iodine, in parallel with previously measured spectra of noble gas Xe and the <em>K</em> edge spectrum of atomic I, is presented. A strong dependence of some valence multielectron photoexcitation features on the orbital momentum of the core vacancy is found, attributed to the change of the symmetry of the HI molecule: the shake-up coexcitation of a valence electron to a free molecular orbital is much stronger at <em>L</em>₃ than <em>L</em>₁ edge. The effect of angular momentum of the core hole on the shake processes of deeper multielectron photoexcitations is found negligible. Both HI and Xe exhibit a much weaker one-electron transition [1<em>s</em>]6<em>p</em> than monatomic I. At the <em>K</em> edge, the strength of coexcitations of 4<em>d</em>, 4<em>p</em> and 3<em>d</em> subshells in atomic I is close to the HI and Xe. The same is found for HI and Xe at the <em>L</em> edges, due to a weak contribution of the additional free molecular orbital in HI.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112509"},"PeriodicalIF":2.8,"publicationDate":"2025-01-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967852","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Postulated nuclear power plant accident in the Po valley (Italy) and application of the ICRP publication 146 recommendations","authors":"Sergio Biancotto ,&nbsp;Marco D'Arienzo","doi":"10.1016/j.radphyschem.2024.112490","DOIUrl":"10.1016/j.radphyschem.2024.112490","url":null,"abstract":"<div><div>A large release of radioactive material, consequence of a supposed nuclear power plant (NPP) accident, is simulated in the densely populated and productive area of the Italian Po Valley, using wind speed and atmospheric stability conditions characteristic of the region. The first step of the analysis is the evaluation of the dose received by the public during the plume passage through the HotSpot code. The second step is the calculation of dose in the years following the accident through the RESRAD-ONSITE code, considering soil and food-chain contamination. The third step is the dose reduction obtained with protective actions, mainly iodine prophylaxis and shelter in place. Recommendations contained in the International Commission on Radiological Protection (ICRP) Publication 146 are applied, with the goal of maintaining the public dose below the ICRP recommended Reference Levels. The influence of the height of the release is also analyzed. Without implementing protective measures, the public may be exposed to a dose of up to 2.9 × 10² mSv, although this is confined to a fairly restricted area. However, the dose can be greatly reduced by appropriate and preplanned protective actions. The use of ICRP Reference Levels is of overwhelming importance in guiding protective actions and helping authorities to make balanced decisions.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112490"},"PeriodicalIF":2.8,"publicationDate":"2025-01-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967853","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Is blast furnace slag suitable for the production of radiation shielding glass?","authors":"Cansu Karakaya,&nbsp;Ediz Ercenk,&nbsp;Senol Yilmaz","doi":"10.1016/j.radphyschem.2024.112496","DOIUrl":"10.1016/j.radphyschem.2024.112496","url":null,"abstract":"<div><div>This study examined the physical and radiation shielding properties of compounds formed by adding 0–50 wt % Bi₂O₃ to blast furnace slag. Physical properties: density included molar volume, oxygen molar volume, and oxygen packing density were calculated. The radiation protection properties of the prepared glasses were calculated theoretically using Phy-X/PSD software. Experimental shielding measurements were also made at some energy levels to verify the shielding values. The addition of Bi₂O₃ increased the composition density from 2.87 to 4.54 g/cm³. Mass attenuation coefficient (MAC) results showed increased radiation shielding performance with adding Bi₂O₃. While the highest MAC value for the pure composition was 1.222 cm²/g, the lowest was calculated as 0.054 cm²/g for the sample with 50% Bi₂O₃ added by weight. In addition, effective atomic charge (Z_eff) and electron densities (N_eff) were also determined, and it was observed that these values increased significantly with the addition of Bi₂O₃. Fast neutron removal cross-section values of the compositions were determined and compared with some commercial/alternative shielding materials.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112496"},"PeriodicalIF":2.8,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142925297","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Polyethylene composite doped with cadmium and tungsten oxide for neutron-gamma multilayer shielding","authors":"Chin Lok Sheng ,&nbsp;Muhammad Arif Sazali ,&nbsp;Asyraf Arif Abu Bakar ,&nbsp;Ahmad Hambali Ismail ,&nbsp;Roslan Yahya ,&nbsp;Muhammad Syahir Sarkawi ,&nbsp;Nur Syazwani Mohd Ali ,&nbsp;Khairulnadzmi Jamaluddin","doi":"10.1016/j.radphyschem.2024.112506","DOIUrl":"10.1016/j.radphyschem.2024.112506","url":null,"abstract":"<div><div>Radiation shielding is crucial to ensuring the safety of the people and the environment. Concrete and lead are common materials with great shielding properties against gamma and neutron radiation, yet they have drawbacks such as being harmful to human health, high cost, and seismic vulnerability. Therefore, the aim of this study is to develop polyethylene (PE)-based composites doped with cadmium (Cd) and tungsten oxide (WO₃), to determine the neutron-gamma shielding properties of the composites, and to compare the radiation shielding performance of multilayer shielding of the composites and the base PE. The composites were fabricated using the melt-mixing and hot-pressing methods. They were characterized using X-ray diffraction, micro-computed tomography scanning, and field emission scanning electron microscopy to observe the dispersion of filler particles in the PE matrix. Results show that the filler elements have good distribution in the composite. Their shielding performance was evaluated using the ²⁴¹Am/Be neutron and ¹³⁷Cs gamma sources at the Malaysian Nuclear Agency. The results show that the PE+20% WO₃ has the highest values of neutron removal macroscopic cross-section and gamma linear attenuation coefficient for single-layer shielding. For multilayer configuration, PE+10%Cd with PE+10% WO₃ (Cd10/W10) has the best mixed neutron-gamma radiation attenuation performance. The results will help in the development of alternative materials for better radiation protection.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112506"},"PeriodicalIF":2.8,"publicationDate":"2024-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142925298","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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}