Journal of Nuclear Materials最新文献_第6页

Reaction behavior of molten 316L stainless steel with B4C at 1450℃ during a core melt accident of BWR

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-18 DOI: 10.1016/j.jnucmat.2025.155705

Tatsuya Kanno , Takayuki Iwama , Takumi Sato , Ayumi Itoh , Yuji Nagae , Ryo Inoue , Shigeru Ueda

{"title":"Reaction behavior of molten 316L stainless steel with B4C at 1450℃ during a core melt accident of BWR","authors":"Tatsuya Kanno , Takayuki Iwama , Takumi Sato , Ayumi Itoh , Yuji Nagae , Ryo Inoue , Shigeru Ueda","doi":"10.1016/j.jnucmat.2025.155705","DOIUrl":"10.1016/j.jnucmat.2025.155705","url":null,"abstract":"<div><div>In the severe accident at the Fukushima Daiichi Nuclear Power Station, molten core material migrated downward and generated fuel debris at the bottom of the containment vessel and other locations. The composition of the generated melt changes as it moves because it reacts with structural materials. The composition of fuel debris is determined by the initial melt composition and reactions during migration. In this study, the reaction rate between molten 316 L stainless steel and B<sub>4</sub>C at 1450 °C was experimentally investigated, assuming that control rods would melt and stainless steel-based melts would stagnate in the lower plenum in boiling water reactors. The effect of H<sub>2</sub>O gas on the reaction between the molten metal and B<sub>4</sub>C was investigated, and an estimation of the rate-limiting process of the reaction and the rate of B₄C was carried out. The rate-limiting process of the reaction changed from the dissolution reaction of B<sub>4</sub>C to the diffusion of alloying elements and the precipitation of carbon as the reaction proceeded. Including these rate-limiting processes, an overall dissolution rate of B₄C melting in the B₄C/molten stainless steel reaction at 1450 °C was obtained.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155705"},"PeriodicalIF":2.8,"publicationDate":"2025-02-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143487304","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Development of SiC encapsulation for thulium oxide targets as potential nuclear batteries

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-17 DOI: 10.1016/j.jnucmat.2025.155700

Brandon Shaver , Kip Wheeler , Caen Ang

{"title":"Development of SiC encapsulation for thulium oxide targets as potential nuclear batteries","authors":"Brandon Shaver , Kip Wheeler , Caen Ang","doi":"10.1016/j.jnucmat.2025.155700","DOIUrl":"10.1016/j.jnucmat.2025.155700","url":null,"abstract":"<div><div>The design, fabrication and properties of encapsulations for radioisotope fuel targets (<sup>169</sup>Tm) were assessed. Elemental analysis and phase identification by X-ray Fluorescence and X-ray Diffraction showed a SiC encapsulation of a thulium oxide ceramic. Microhardness testing of the encapsulation showed a relatively consistent hardness of 32.2 ± 4.7 GPa across the vertices and walls, with a mid-plane join hardness of 30.1 ± 5.4 GPa. Manufacturing tolerances followed a normal distribution with a standard deviation (σ) of σ <sub>OD</sub> = ± 0.014 mm and σ<sub>ID</sub> = ± 0.037 mm for Tm<sub>2</sub>O<sub>3</sub> and SiC. The design of the target emphasizes robust, radiation-tolerant, high-strength SiC, but heat transfer is likely axially asymmetric because contact between Tm<sub>2</sub>O<sub>3</sub>-SiC is limited. Tm<sub>2</sub>O<sub>3</sub>-SiC chemical compatibility testing was investigated, indicating a possible reaction-limited process below 1873 K, and a possible diffusion-limited process above 1873 K. At higher temperatures, thulium containment for this concept is limited by chemical compatibility.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"608 ","pages":"Article 155700"},"PeriodicalIF":2.8,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143534750","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Mechanistic insights into spinodal L12 nanostructures in mitigating radiation defect growth in Al0.5Cr0.9FeNi2.5V0.2 high-entropy alloys

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-16 DOI: 10.1016/j.jnucmat.2025.155703

Zhengxiong Su, Jianqiang Wang, Jinxue Yang, Ping Zhang, Rui Gao, Chenyang Lu

{"title":"Mechanistic insights into spinodal L12 nanostructures in mitigating radiation defect growth in Al0.5Cr0.9FeNi2.5V0.2 high-entropy alloys","authors":"Zhengxiong Su, Jianqiang Wang, Jinxue Yang, Ping Zhang, Rui Gao, Chenyang Lu","doi":"10.1016/j.jnucmat.2025.155703","DOIUrl":"10.1016/j.jnucmat.2025.155703","url":null,"abstract":"<div><div>High-entropy alloys with high-content L1<sub>2</sub> nanoprecipitates formed through phase separation have recently demonstrated outstanding mechanical properties across a wide temperature range, making them suitable structural materials for advanced nuclear systems. This study investigates the irradiation response of a high-entropy alloy composed of Al<sub>0.5</sub>Cr<sub>0.9</sub>FeNi<sub>2.5</sub>V<sub>0.2</sub> with varying volumes of L1<sub>2</sub> nanostructures. High-temperature He ion irradiation was performed, and its effects on defect evolution were analyzed using transmission electron microscopy and nanoindentation. The results show that the spinodal order-disorder L1<sub>2</sub> network structure effectively suppresses irradiation-induced defects, as evidenced by reduced dislocation loop size, lower He bubble swelling, and decreased irradiation hardening in alloys with higher L1<sub>2</sub> volume fractions. This is primarily because the L1<sub>2</sub> structure, with its low-misfit coherent interface, undergoes the reversible order-disorder transition that reduces early irradiation point defects and suppresses defect nucleation and growth. Furthermore, the spinodal order-disorder L1<sub>2</sub> nanostructure impedes defect cluster movement by providing diffuse obstacles and forming antiphase boundaries, thereby slowing the growth of defects and He bubbles. This work provides an alloy design strategy to improve irradiation tolerance by exploiting the self-healing and structural complexity of the L1<sub>2</sub> structure.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155703"},"PeriodicalIF":2.8,"publicationDate":"2025-02-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143444729","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Interaction between dislocations and cavities in tungsten during tensile test in a TEM at 723 K

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-14 DOI: 10.1016/j.jnucmat.2025.155701

Kouichi Tougou , Maoto Fukui , Ken-ichi Fukumoto , Ryoya Ishigami

引用次数: 0

Air oxidation kinetics of erbium trihydride and hydrogen permeation mechanism in Er2O3 layer

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-14 DOI: 10.1016/j.jnucmat.2025.155702

Mingwang Ma, Xing Wang, Zhoushilin Ruan, Han Wang, Lei Wang, Binghua Tang, Xiaohua Tan

{"title":"Air oxidation kinetics of erbium trihydride and hydrogen permeation mechanism in Er2O3 layer","authors":"Mingwang Ma, Xing Wang, Zhoushilin Ruan, Han Wang, Lei Wang, Binghua Tang, Xiaohua Tan","doi":"10.1016/j.jnucmat.2025.155702","DOIUrl":"10.1016/j.jnucmat.2025.155702","url":null,"abstract":"<div><div>The hydrogen permeation barrier is crucial in minimizing the loss of hydrogen isotopes from structural components, particularly in applications such as hydrogen storage systems and fusion reactors. In this study, Er<sub>2</sub>O<sub>3</sub> layers were synthesized on erbium trihydride (ErH<sub>3</sub>) powder surfaces through air oxidation. Oxidation kinetics were examined within the temperature range of 100 to 300 °C, and the kinetic parameters were identified, leading to the suggestion of grain boundary diffusion controlling mechanism. Focused ion beam scanning electron microscope (FIB-SEM), X-ray photoelectron spectroscopy (XPS) and X-ray diffraction (XRD) were employed to analyze the cross-sectional microstructure, crystal structure and chemical composition of the pre-oxidized samples. Thermal desorption spectroscopy (TDS) observations suggested that the low-temperature peak was affected by hydrogen diffusion through the Er<sub>2</sub>O<sub>3</sub> layer, whereas the high-temperature desorption peak associated with β-ErH<sub>2</sub> decomposition was unaffected due to the dissolution and reduction of oxide layer. A hydrogen permeation model was introduced to calculate the activation energy for hydrogen permeation through the Er<sub>2</sub>O<sub>3</sub> layer formed on ErH<sub>3</sub>.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155702"},"PeriodicalIF":2.8,"publicationDate":"2025-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143444728","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

High dose ion irradiation response of large strain extrusion machined ultrafine grain HT-9 steel

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-12 DOI: 10.1016/j.jnucmat.2025.155697

Hyosim Kim , Jonathan G. Gigax , Matthew R. Chancey , Mert. Efe , Jon K.S. Baldwin , Yongqiang Wang , Stuart A. Maloy , Osman El Atwani

{"title":"High dose ion irradiation response of large strain extrusion machined ultrafine grain HT-9 steel","authors":"Hyosim Kim , Jonathan G. Gigax , Matthew R. Chancey , Mert. Efe , Jon K.S. Baldwin , Yongqiang Wang , Stuart A. Maloy , Osman El Atwani","doi":"10.1016/j.jnucmat.2025.155697","DOIUrl":"10.1016/j.jnucmat.2025.155697","url":null,"abstract":"<div><div>Grain size refinement is one of the many methods to improve radiation resistance of steels. In this study, ultrafine grain HT-9 steel (grain size < ∼270 nm), a potential candidate material for future nuclear fission reactor designs, was manufactured by large strain extrusion machining (LSEM). Radiation resistance of this ultrafine grain HT-9 steel was tested for the first time at high dose using a 3.5 MeV Fe ion beam up to 500 peak displacements-per-atom (dpa) at 450 °C. Results were characterized using a transmission electron microscopy (TEM). Although previous study on the pristine LSEM HT-9 showed that ultrafine grains are thermally stable up to 700 °C, irradiation induced grain growth was observed after 200 peak dpa. Grain boundary carbides were stable after 200 peak dpa with notable dissolution into the matrix in between 200 and 300 peak dpa. The grain size remained in the ultrafine regime (<350 nm) even after the 500 peak dpa irradiation indicating superior grain stability. LSEM HT-9 showed only 0.14 % swelling after 300 peak dpa (181 average local dpa) but showed a steeper rise after 400 peak dpa (242 average local dpa) reaching 1.57 %. However, the rate of swelling between 300 and 400 peak dpa and 400–500 peak dpa decreased significantly from 0.014 to 0.003 %/dpa. The LSEM HT-9 void swelling trend was compared with the void swelling data of other ion and neutron irradiated HT-9 alloys, and the result was discussed with respect to the irradiation induced grain growth, chemical segregation at the grain boundary and precipitation.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155697"},"PeriodicalIF":2.8,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143454720","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Lanthanide electrodeposition in aqueous ammonium acetate: A surrogate approach for actinide film fabrication

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-12 DOI: 10.1016/j.jnucmat.2025.155698

Jonathan Morrison , Robert Sacci , Kristian Myhre , Jisue Moon Braatz

{"title":"Lanthanide electrodeposition in aqueous ammonium acetate: A surrogate approach for actinide film fabrication","authors":"Jonathan Morrison , Robert Sacci , Kristian Myhre , Jisue Moon Braatz","doi":"10.1016/j.jnucmat.2025.155698","DOIUrl":"10.1016/j.jnucmat.2025.155698","url":null,"abstract":"<div><div>Electrodeposition is a key technique for preparing actinide thin films, which are used in applications such as alpha spectroscopy, accelerator beam bombardments, irradiation studies, and as radioactive sources. In this study, we investigate the electrodeposition of actinides using three nonradioactive lanthanide surrogates: lanthanum, samarium, and lutetium. Using cyclic voltammetry, chronopotentiometry, pH evolution measurements, and imaging, we examine the electrodeposition mechanisms driven by local pH changes at the electrode surface, caused by cathodic reactions that form hydroxide species. While all three lanthanides produced similar thin film morphologies, lutetium showed a stronger preference for deposition at lower currents compared to lanthanum and samarium. This difference suggests that the unique properties of lanthanide hydroxides influence the deposition process. These findings underscore the importance of accounting for the variability in lanthanide and actinide hydroxides as the range of actinides used in electrodeposition continues to expand.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155698"},"PeriodicalIF":2.8,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143421684","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Origins of radiation-induced optical attenuation in neutron-irradiated single-crystal sapphire at elevated temperatures

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-12 DOI: 10.1016/j.jnucmat.2025.155695

Yan-Ru Lin, Sabrina Calzada, Chad M. Parish, Christian M. Petrie

{"title":"Origins of radiation-induced optical attenuation in neutron-irradiated single-crystal sapphire at elevated temperatures","authors":"Yan-Ru Lin, Sabrina Calzada, Chad M. Parish, Christian M. Petrie","doi":"10.1016/j.jnucmat.2025.155695","DOIUrl":"10.1016/j.jnucmat.2025.155695","url":null,"abstract":"<div><div>Sapphire (α-Al<sub>2</sub>O<sub>3</sub>) is a candidate fiber-optic sensor material for extreme temperature environments, potentially including those of nuclear reactors. However, its optical transmission under high-dose neutron irradiation is not well understood compared with that of conventional fused silica. This study examined dimensional changes, optical transmission, and irradiation-induced defects in neutron-irradiated α-Al<sub>2</sub>O<sub>3</sub> at temperatures of 298 °C to 688 °C and doses of 3.2 to 12 dpa. Although previous studies attributed radiation-induced attenuation (RIA) at the highest irradiation temperatures to increased optical scattering from radiation-induced voids, our findings indicate that scattering from neither voids nor dislocation loops can explain the measured attenuation. Instead, absorption due to aluminum vacancy centers appears more likely based on a comparison of the spectral features of the measured optical attenuation with previous literature. Significant <em>c</em>-axis swelling (5.51 % ± 0.83 %) was observed in the 12 dpa, 592 °C irradiated sample, much higher than earlier measurements, suggesting temperature sensor drift of 543 °C to 1,140 °C. Void patterning was predominantly observed along the <em>a</em>-axis, differing from previous studies on polycrystalline samples, which showed <em>c</em>-axis patterning. Dislocation loops evolved into network dislocations with increasing temperature and dose; voids formed within these structures, showing no size or density changes, indicating an atypical growth mechanism.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155695"},"PeriodicalIF":2.8,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143421687","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Construction of wear-resistant and anti-corrosion composite coatings on uranium surface by laser surface nitriding and texture coupled with solid lubrication

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-11 DOI: 10.1016/j.jnucmat.2025.155696

Zhanpeng Ye , Tingwen Yan , Jie Shi , Ruilong Yang , Yongbin Zhang , Xiangcheng Shi , Zhilei Chen , Hui Rong , Bin Bai , Kezhao Liu , Yin Hu , Xiaobin Yue

{"title":"Construction of wear-resistant and anti-corrosion composite coatings on uranium surface by laser surface nitriding and texture coupled with solid lubrication","authors":"Zhanpeng Ye , Tingwen Yan , Jie Shi , Ruilong Yang , Yongbin Zhang , Xiangcheng Shi , Zhilei Chen , Hui Rong , Bin Bai , Kezhao Liu , Yin Hu , Xiaobin Yue","doi":"10.1016/j.jnucmat.2025.155696","DOIUrl":"10.1016/j.jnucmat.2025.155696","url":null,"abstract":"<div><div>Uranium metal has attracted considerable attention due to its unique physicochemical properties and has generated widespread interest in the field of nuclear power. However, the uranium surface is prone to wear and corrosion, leading to performance degradation. In addition, the high chemical reactivity and strong radioactivity of metallic uranium pose challenges to the long-term stability of traditional protective coatings on its surface. In recent years, significant research progress has been made in improving the wear resistance and corrosion resistance of uranium substrates through surface alloying or laser shock processing techniques. Nevertheless, the problem of wear and corrosion of the modified layer on the uranium surface under a prolonged harsh environment remains unresolved. This study proposes a ternary synergistic strategy of “two-dimensional solid lubrication, micro-texture friction reduction, and nitrided layer hardening passivation” to prepare a modified layer on the uranium surface with robust radiation resistance and reliable protection. The composite modified layer not only effectively improves the wear-resisting and anti-corrosion of the uranium surface but also resists robust radiation. The research shows that the modified coating prepared retains its silver-white metallic sheen following 48 h of accelerated corrosion testing in pure water vapor at 338.15 K. Additionally, friction coefficient measurements from wear experiments reveal that the modified layer exhibits a coefficient of friction below 0.05. The ternary synergistic strategy provides crucial theoretical guidance and a technical roadmap for enhancing the wear and corrosion resistance of uranium materials in the atmospheric environment.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155696"},"PeriodicalIF":2.8,"publicationDate":"2025-02-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143402913","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Liquid feed vitrification of high-level nuclear waste: Description and modeling of chemical reactions

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-02-10 DOI: 10.1016/j.jnucmat.2025.155688

E. Sauvage , S. Schuller , Z. Nabyl , R. Podor , J. Lautru , P. Benigni , J. Klouzek , S. Mure , V. Benavent

{"title":"Liquid feed vitrification of high-level nuclear waste: Description and modeling of chemical reactions","authors":"E. Sauvage , S. Schuller , Z. Nabyl , R. Podor , J. Lautru , P. Benigni , J. Klouzek , S. Mure , V. Benavent","doi":"10.1016/j.jnucmat.2025.155688","DOIUrl":"10.1016/j.jnucmat.2025.155688","url":null,"abstract":"<div><div>In order to take into account the thermal effects associated with the decomposition of precursors (glass frit and waste, without prior calcination) in the multiphysics CFD (Computational Fluid Dynamics) simulations developed for cold crucible vitrification, mathematical modeling of denitration kinetics is proposed. On the basis of a run-rerun method applied to DTA-TGA analysis carried out at different temperature ramps (10 to 40°C/minute), the degrees of conversion of the reactions have been determined and the kinetic parameters described by taking into account a weighted sum of 7 elementary reactions of order n, whose rate constant follows an Arrhenius law. This global approach makes it possible to describe the overall kinetics of each endothermic event satisfactorily, without having to consider the complexity of the decomposition reactions of the initial pure compounds. However, analysis of the gases emitted during the reactions using thermogravimetric analysis coupled with mass spectrometry (TGA-MS) and characterization by environmental scanning electron microscopy (ESEM) correlated with literature data enabled to describe the main chemical reactions associated with thermal events. This global approach can be transposed to other systems if the reactions are thermally activated.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155688"},"PeriodicalIF":2.8,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143377877","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0