Radiation Physics and Chemistry最新文献

{"title":"Deposition of radioactive admixture on aerosol nano particles","authors":"V.A. Zagaynov ,&nbsp;М.Е. Vasyanovich ,&nbsp;A.A. Lushnikov ,&nbsp;I.E. Agranovski ,&nbsp;A.A. Maslov ,&nbsp;V.V. Maksimenko ,&nbsp;V. Nagibin ,&nbsp;V. Krivosheev ,&nbsp;D.K. Zagaynov","doi":"10.1016/j.radphyschem.2026.113709","DOIUrl":"10.1016/j.radphyschem.2026.113709","url":null,"abstract":"<div><div>The paper develops a model of the process of radioactive impurities deposition on aerosol particles of various sizes. For this purpose, the following problem was solved; aerosol particles are introduced into a gas system in which there is a source of radioactivity and radioactive atoms are uniformly distributed over space. It is assumed that when these radioactive atoms collide with particles, these atoms are deposited on the particles and transfer their activity to them. These processes lead to the distribution of the radioactive impurity on the particles. To find this distribution function, a system of differential equations describing the process was solved by introduction generation function. The characteristic times for the systems to reach the stationary regime were determined, and the distributions for the stationary regime were obtained. To illustrate the results obtained, an example for monodisperse aerosol particles that collide with radioactive atoms with the same decay constant has been discussed. At the same time the distribution function was obtained by numerical methods. Numerical and exact solutions are coincided. It must also be noted that the problem can be generalized to particles with a polydisperse distribution and to a system of atoms with different decay constants using numerical solution. The proposed method can be used both for radioactive systems operating in normal mode and for emergency situations.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113709"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146146249","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 Radiological Parameters for boron oxide reinforced Glasses","authors":"Mucize Sarıhan ,&nbsp;Seher Polat ,&nbsp;Sabiha Anas Boussaa ,&nbsp;Iskender Akkurt","doi":"10.1016/j.radphyschem.2026.113706","DOIUrl":"10.1016/j.radphyschem.2026.113706","url":null,"abstract":"<div><div>Computer simulation is an important and valuable method to obtain any paramaters from engineering to medical sciences. Using radiation in technology required extra care in order not to be exposed especially for ionizing raidation. Monte Carlo simulation is an easy method to obtain radiation shielding properties of any materials. The glass materials are widely used and thus their some properties should be investigated. In the present work, the gamma-neutron shielding properties of boron-oxide glasses were calculated using Phy-X/PSD code. The composition of gass samples formualted as (45-x)SiO₂+xB₂O₃+24.5Na₂O+24.5CaO+6P₂O₅ (where x ranged from 0, 1, 3 and 5 mol% steps) and used in this study.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113706"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146146245","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":"Structure and radiation shielding properties of transparent Na2O–ZnO–B2O3 glass system modified by TiO2 addition","authors":"M.S. Al-Buriahi ,&nbsp;Marzoqa M. Alnairi ,&nbsp;Mine Kirkbinar ,&nbsp;Hind Saeed Alzahrani ,&nbsp;B. Alshahrani ,&nbsp;Beriham Basha ,&nbsp;Norah Alomayrah ,&nbsp;I.O. Olarinoye","doi":"10.1016/j.radphyschem.2026.113703","DOIUrl":"10.1016/j.radphyschem.2026.113703","url":null,"abstract":"<div><div>The characterization of substances reveals their useful attributes, weaknesses and potential technological applications. In this study, the influence of TiO₂ on the microstructural, hardness, density and radiation insulating features of transparent Na₂O–ZnO–B₂O₃ glass system was investigated with the aim of providing alternative, cheap and transparent glass shields for therapeutic and diagnostic medical facilities. Two glass batches coded as BNZ (73B₂O₃+13ZnO+14Na₂O) and BNZ-T (69B₂O₃+12ZnO+14Na₂O+5TiO₂) were prepared based on the melt-and-quench technology and analysed for their mechanical, microstructural, radiation (gamma-rays, fast, and thermal neutrons) shielding attributes. The microstructure and chemical element distribution within the glasses were investigated with the aid of a scanning electron microscope and the electron diffraction spectroscopy, respectively, while the mass attenuation coefficients (MACs) and effective atomic number <span><math><mrow><msub><mi>Z</mi><mrow><mi>e</mi><mi>f</mi><mi>f</mi></mrow></msub></mrow></math></span> of the glasses were estimated using the EPICS2017 interaction cross-section database for 59–1332 keV photons. The introduction of TiO₂ increased the density and hardness and introduced changes in the microstructure of BNZ. The MACs of BNZ and BNZ-T decreased from 0.3604 to 0.0536 cm²/g and 0.3664 to 0.0534 cm²/g, respectively as energy of gamma rays increased. Also, <span><math><mrow><msub><mi>Z</mi><mrow><mi>e</mi><mi>f</mi><mi>f</mi></mrow></msub></mrow></math></span> decreased from 12.81 to 8.45 for BNZ and 12.85 to 8.39 for BNZ-T for the 59.54–1332.49 keV energy spectrum. The fast neutron removal ability <span><math><mrow><msub><mi>Σ</mi><mi>R</mi></msub><mspace></mspace><mo>(</mo></mrow></math></span> cm⁻¹) of the glasses indicated that the introduction of TiO₂ to the structure of BNZ enhanced the ability of the glass to moderate fast neutrons by about 5%, but compromised the thermal neutron total cross section by 9%. The gamma-rays and neutron insulating properties of BNZ and BNZ-T compared well with traditional shielding substances within the investigated radiation energies. BNZ and BNZ-T glasses can be used as gamma and fast neutron radiation insulators, especially at photon energies used in medical applications.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113703"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146152633","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":"Application of ionizing radiation technology in agro-industrial waste: A review","authors":"J.P.A.A. Barros ,&nbsp;V. Spagnol ,&nbsp;L.M. Rondan-Flores ,&nbsp;B.G. Negrão ,&nbsp;V.F. Benedetti ,&nbsp;A.L.C.H. Villavicencio","doi":"10.1016/j.radphyschem.2026.113690","DOIUrl":"10.1016/j.radphyschem.2026.113690","url":null,"abstract":"<div><div>The world produces large quantities of raw materials from agriculture, aquaculture, forestry, and livestock. However, there are estimated losses of up to 50% of raw materials throughout the harvesting, slaughtering, transportation, processing, storage, and consumption stages. Due to its composition, agro-industrial waste may be slower to degradable, resulting in accumulation and negative environmental impact. Despite this, these residues retain considerable concentrations of important bioactive compounds that could be reincorporated into new formulations. Because of this, it is essential to identify applications to convert these wastes into high-value-added products. In this context, ionizing radiation has stood out as a promising technique among the current resources available for reusing waste and reducing microbial load, as it is a clean technology, does not generate additional waste, and does not raise the temperature during processing, the main limitation of conventional methods. With ionizing radiation, a new proposal for waste management emerges to reincorporate it into new products, reducing waste and reducing environmental impact. Thus, this review summarizes the most recent research on the application of nuclear energy as a viable solution and technological innovation for reusing agro-industrial waste, addressing its positive and negative effects on nutritional preservation and availability of bioactive compounds. In addition, it provides a brief analysis of the acceptability of this technology and the dissemination of information about the benefits of this process in food and waste.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113690"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134650","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":"Enhanced radon and thoron-barrier performance of ambient‒curable natural rubber latex for sustainable building material coatings","authors":"Worawat Poltabtim ,&nbsp;Suchart Kothan ,&nbsp;Tarika Thumvijit ,&nbsp;Chayanit Jumpee ,&nbsp;Siriprapa Somboon ,&nbsp;Benjamaporn Supawat ,&nbsp;Phannavich Malawan ,&nbsp;Kiadtisak Saenboonruang","doi":"10.1016/j.radphyschem.2026.113680","DOIUrl":"10.1016/j.radphyschem.2026.113680","url":null,"abstract":"<div><div>The release of radon and thoron from building materials is presently a concern as a source of indoor radiation exposure, which causes substantial long-term health risks to the public. This research presented a novel sustainable radon barrier based on natural rubber latex (NRL) emulsion coating, which was crosslinked using glutaraldehyde and filled with varying contents of silicon dioxide (SiO₂) or activated carbon (AC). The emulsion was coated (0.20 ± 0.10 mm dry thickness) on clay bricks and subsequently evaluated for their ability to mitigate radon and thoron exhalation. The results showed that the 10-phr SiO₂-filled sample achieved the highest radon mitigation efficiency of 60.3% in surface radon exhalation rate relative to the uncoated condition, while all formulations, including pristine NRL, achieved thoron suppression efficiencies greater than 92%. Furthermore, simulated dose assessments confirmed the coating's effectiveness in reducing annual effective dose (AED) from indoor radon, with further reductions to 0.10–0.15 mSv·y⁻¹ achieved under ventilated scenarios. Beyond radon and thoron barrier performance, SiO₂ incorporation markedly enhanced mechanical robustness and abrasion resistance, while AC improved coating elasticity, although high AC contents led to agglomeration and reduced film uniformity. These findings highlight the potential of sustainable, ambient-curable NRL coatings as effective practical and durable barriers against indoor radon and thoron for green building applications.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113680"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146089317","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":"Systematic investigation of the shielding performance of 26 types of concrete in three accelerator radiation environments: an 18-MeV proton medical cyclotron, a 250-MeV proton therapy machine, and a 400-MeV/u carbon-ion therapy machine","authors":"Po-Wen Fang ,&nbsp;Kah-Yeen Lim ,&nbsp;Rong-Jiun Sheu","doi":"10.1016/j.radphyschem.2026.113705","DOIUrl":"10.1016/j.radphyschem.2026.113705","url":null,"abstract":"<div><div>Different types of concrete have different compositions and therefore may exhibit greatly different shielding performances. This study systematically and quantitatively analyzed this problem by numerically simulating 26 types of concrete used as a shield against the radiation fields induced by three accelerators: an 18-MeV proton cyclotron for radioisotope production, a 250-MeV proton therapy machine, and a 400-MeV/u carbon-ion therapy machine. The results were compiled and explored from various perspectives to identify correlations with concrete properties such as density, average atomic number, hydrogen content, and heavy metal content. Among these properties, density was found to be optimal predictor of dose attenuation length in concrete. Best-fit parameters were determined for three accelerator radiation fields in the forward and lateral directions. The data present in this study can be used to quantify the effect of uncertainty in the modeling of concrete composition in shielding calculations.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113705"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146138540","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":"Monte Carlo evaluation of a novel functionally graded tri-layer composite system for MOX spent nuclear fuel casks","authors":"Ayman Abu Ghazal ,&nbsp;Rawand Alakash ,&nbsp;Feras Afaneh","doi":"10.1016/j.radphyschem.2026.113663","DOIUrl":"10.1016/j.radphyschem.2026.113663","url":null,"abstract":"<div><div>Spent nuclear fuel (SNF) transport and dry-storage containers are crucial for guaranteeing the safe confinement and radiation shielding of highly radioactive materials at the conclusion of the nuclear fuel cycle. This work presents a comprehensive Monte Carlo investigation of a novel Tri-Layer Adaptive Composite System (TACS) developed for radiation shielding in SNF transport and dry-storage casks. The proposed architecture adopts a functionally graded design composed of three optimized layers: a Refractory High-Entropy Alloy (RHEA) inner layer providing structural integrity and initial gamma attenuation, a Hydrogenated Boron Nitride (HBN) composite layer serving as the primary neutron moderator and absorber, and an outer Tungsten–Metallic Glass Matrix Composite (W-MGMC) layer delivering further suppression of residual gamma and neutron radiation. Radiation transport simulations were performed using MCNP5, modeling a homogenized pressurized water reactor (PWR) mixed-oxide (MOX) spent fuel assembly with a heavy-metal loading of 0.492 tHM and a representative burnup of 50 GWd tHM⁻¹. Conservative, bounding source terms were employed, assuming ¹³⁷Cs as the dominant gamma-emitting radionuclide and ²⁴⁴Cm as the primary neutron source via spontaneous fission, for cooling times up to 50 years. The results show smooth and monotonic attenuation of both photon and neutron fields across the multilayer system, with no localized dose-rate hot spots. Energy-dependent total microscopic photon cross-section analyses confirm substantial interaction probabilities in the high-Z RHEA and W-MGMC layers across the relevant energy range, explaining the rapid suppression of gamma flux and dose observed within these regions. At the same time, HBN exhibits minimal photon interaction consistent with its low-Z composition. Half-value layer (HVL) analysis further quantifies the shielding efficiency, revealing that RHEA and W-MGMC exhibit the smallest gamma HVLs (≈0.8 cm). In contrast, HBN provides the lowest neutron HVL (≈1.5 cm), confirming its dominant role in fast-neutron removal. At the cask surface, the TACS configuration achieves a total dose rate of approximately 0.10 mSv h⁻¹, corresponding to a safety margin of about 20 × below the IAEA SSR-6 transport limit. Comparative benchmarking against conventional Fe–PE–Pb and steel–air–concrete shielding configurations demonstrates the superior shielding efficiency and compactness of the proposed system, particularly for neutron-dominated, high-burnup MOX fuel inventories.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113663"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146047884","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 analysis of radiation shielding character in engineered bricks blended with CaO, Al2O3, and Fe2O3 additives: thermal stability and Phy-X simulation insights into attenuation characteristics","authors":"Anoud Saud Alshammari ,&nbsp;U. Rilwan ,&nbsp;Feras Alafer ,&nbsp;Marwan F.S.H. AL-Kamali ,&nbsp;Aml Almutery ,&nbsp;Atef El-Taher","doi":"10.1016/j.radphyschem.2026.113674","DOIUrl":"10.1016/j.radphyschem.2026.113674","url":null,"abstract":"<div><div>This study employed Phy-X software to investigate the radiation protection efficacy of different bricks fabricated from a mixture of clay, CaO (calcium oxide), Al₂O₃ (aluminum oxide), and Fe₂O₃ (iron oxide). As the oxide additives substituted clay, an increased in the density of the fabricated samples was noticed, with <strong>CL5Fe</strong> showcasing the superior value of 2.40 g/cm³. An improved linear attenuation coefficient (LAC) was also noticed, with <strong>CL5Fe</strong> demonstrating the greatest LAC value of 0.154 cm⁻¹ at 0.6 MeV, which could be associated to its superior density due to presence of Fe₂O₃. The 0.6 MeV energy was chosen as a representative 137Cs value within the Compton-dominant region. Shielding performance was further evaluated from 0.0459 to 1.46 MeV, covering photoelectric-to-Compton-dominated interactions. <strong>CL5Fe</strong> also outsmarted other samples in terms of thermal stability and structural integrity, making it the best choice for gamma radiation protection. Future studies should evaluate shielding performance across 1.47–15 MeV to assess material suitability for medical imaging, radiotherapy, and nuclear radiation environments.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113674"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134647","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":"Relationship between exposure index and radiographic noise under varying exposure conditions for chest and abdominal radiography","authors":"Nobukazu Tanaka ,&nbsp;Yongsu Yoon ,&nbsp;Tadamitsu Ideguchi","doi":"10.1016/j.radphyschem.2026.113676","DOIUrl":"10.1016/j.radphyschem.2026.113676","url":null,"abstract":"<div><div>Recently, flat-panel detector (FPD) systems have been developed to display exposure index (EI) values on the console immediately after exposure, thereby enhancing user comprehension. However, differences between examination rooms and bedside imaging can lead to discrepancies in EI values. This study aimed to investigate the relationship between EI and radiographic noise for an indirect-FPD system under varying exposure conditions in digital chest and abdominal radiography. For chest radiography, the following exposure conditions were used: 120 kV with an anti-scatter grid and 70 kV without a grid. For abdominal radiography, the exposure conditions were: 80 kV with a high-ratio (12:1) grid and 80 kV with a low-ratio (5:1) grid. Acrylic phantoms of different thicknesses were used for both chest and abdominal radiography. Radiographic noise was assessed using the Wiener spectrum (WS). For chest radiography, when the incident doses on the imaging detector were identical, the EI values displayed at 120 kV were significantly higher than those at 70 kV. At similar EI values, WS values were lower at 70 kV than at 120 kV. For abdominal radiography, when the incident doses on the imaging detector were identical, the displayed EI values with the high-ratio grid were considerably higher than those with the low-ratio grid. At similar EI values, WS values were lower with the low-ratio grid than with the high-ratio grid. Even when EI values are similar for the same anatomical regions, variations in exposure conditions, such as tube voltage and grid type, affect radiographic noise.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113676"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146072398","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":"EPR of neutron-radiation-induced defects in Gd3Ga5O12","authors":"Jekabs Cirulis,&nbsp;Uldis Rogulis,&nbsp;Nina Mironova-Ulmane,&nbsp;Guntars Zvejnieks,&nbsp;Andris Antuzevics","doi":"10.1016/j.radphyschem.2026.113664","DOIUrl":"10.1016/j.radphyschem.2026.113664","url":null,"abstract":"<div><div>Stable radiation-induced defects can have significant effects on materials usability in solid state lasers, scintillators, and other devices that may be exposed to ionising radiation. This study investigates several paramagnetic centres in gadolinium gallium garnet (<span><math><mrow><msub><mrow><mi>Gd</mi></mrow><mrow><mn>3</mn></mrow></msub><msub><mrow><mi>Ga</mi></mrow><mrow><mn>5</mn></mrow></msub><msub><mrow><mi>O</mi></mrow><mrow><mn>12</mn></mrow></msub></mrow></math></span>). Analysis of single-crystal electron paramagnetic resonance (EPR) spectra was performed after irradiation with fast neutron radiation. It was determined that paramagnetic centres with highly anisotropic g-factor values are formed and remain stable well above room temperature. The irregular defect symmetry suggests that one of the defects is formed along the direction of cubic lattice diagonal. This defect was attributed to Ge centres resulting from Ga neutron capture coupled with multiple oxygen vacancies. The origin of other paramagnetic centres is discussed based on unusual temperature dependencies of EPR spectra and ab initio calculations.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113664"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146071588","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}