Journal of Nuclear Materials最新文献

{"title":"Short communication: Characterization of Mo-rich precipitates in δ-ferrite of thermally aged Mo-bearing cast austenitic stainless steel","authors":"Shoaib Mehboob ,&nbsp;Hyun Joon Eom,&nbsp;Chaewon Jeong,&nbsp;Changheui Jang","doi":"10.1016/j.jnucmat.2025.155747","DOIUrl":"10.1016/j.jnucmat.2025.155747","url":null,"abstract":"<div><div>Long-term operation of cast austenitic stainless steels (CASSs) at high temperatures in nuclear power plants results in embrittlement due to δ-ferrite hardening from nanoscale precipitates, with Mo addition further accelerating the embrittlement through enhanced spinodal decomposition and G-phase precipitation. Meanwhile, the formation of distinct Mo-rich precipitates in δ-ferrite during thermal aging are occasionally reported, but they were not clearly characterized. Here, we characterized the Mo-rich precipitates in δ-ferrite formed during thermal aging at 400 °C using high-resolution TEM images and electron diffraction patterns. Based on the detailed analysis, the Mo-rich precipitates were identified as hexagonal ω-phase.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155747"},"PeriodicalIF":2.8,"publicationDate":"2025-03-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143619292","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}

{"title":"Phase transformation and precipitation of Zr-Sn-Nb-Fe alloys at different cooling rates","authors":"Boran Tao ,&nbsp;Dailin Zhong ,&nbsp;Risheng Qiu ,&nbsp;Zhongni Liao","doi":"10.1016/j.jnucmat.2025.155742","DOIUrl":"10.1016/j.jnucmat.2025.155742","url":null,"abstract":"<div><div>The phase transformation mechanisms and elemental precipitation behaviors in Zr−1.0Sn−1.0Nb−0.3Fe (N1) and Zr−1.0Sn−0.3Nb−0.3Fe (N2) alloys under varying cooling rates were systematically investigated. As the cooling rates decrease from water cooling (WC) to liquid nitrogen cooling (LNC), air cooling (AC), and finally furnace cooling (FC), the phase transformation progressively shifts from a non-diffusional martensitic mechanism to a diffusional mechanism, accompanied by increasing Nb and Fe segregation. Rapid cooling (WC) retains metastable (β+ω)-Zr phases with limited Fe enrichment. Intermediate cooling rates (LNC/AC) promote semi-diffusional transformations, leading to the formation of binary Zr-Fe precipitates (Zr₂Fe, Zr₃Fe). Slow furnace cooling (FC) allows for complete elemental diffusion, resulting in residual β-Zr and equilibrium Zr(Nb,Fe)₂ phases. Notably, Zr₂Fe persists in the low-Nb N2 alloy under these conditions. Phase transformations and precipitate phases nucleate and grow along the low-index habit planes of the parent phase. In addition to the Burgers orientation relationship between α-Zr phase and β-Zr phase, the orientation relationships between Zr₂Fe and Zr(Nb,Fe)₂ and the matrix, designated as <span><math><mrow><mo>&lt;</mo><mn>0001</mn><mo>&gt;</mo><mrow><mi>α</mi><mo>/</mo><mo>/</mo><mo>&lt;</mo><mn>001</mn><mo>&gt;</mo><mtext>Zr</mtext><mn>2</mn><mtext>Fe</mtext></mrow></mrow></math></span>, <span><math><mrow><mo>{</mo><mover><mrow><mn>1</mn></mrow><mo>‾</mo></mover><mn>100</mn><mo>}</mo><mrow><mi>α</mi><mo>/</mo><mo>/</mo><mo>{</mo><mn>110</mn><mo>}</mo><mtext>Zr</mtext><mn>2</mn><mtext>Fe</mtext></mrow></mrow></math></span> and <span><math><mrow><mo>&lt;</mo><mn>011</mn><mrow><mo>&gt;</mo><mi>β</mi><mo>/</mo><mo>/</mo><mo>&lt;</mo></mrow><mover><mrow><mn>2</mn></mrow><mo>‾</mo></mover><mrow><mn>110</mn><mo>&gt;</mo><mtext>Zr</mtext><mo>(</mo><mtext>Nb</mtext><mo>,</mo><mtext>Fe</mtext><mo>)</mo><mn>2</mn></mrow></mrow></math></span>, <span><math><mrow><mo>{</mo><mn>21</mn><mover><mrow><mn>1</mn></mrow><mo>‾</mo></mover><mrow><mo>}</mo><mi>β</mi><mo>/</mo><mo>/</mo><mo>{</mo><mn>0002</mn><mo>}</mo><mtext>Zr</mtext><mo>(</mo><mtext>Nb</mtext><mo>,</mo><mtext>Fe</mtext><mo>)</mo><mn>2</mn></mrow></mrow></math></span>, have also been characterized.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"608 ","pages":"Article 155742"},"PeriodicalIF":2.8,"publicationDate":"2025-03-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143591961","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}

{"title":"Chemical interaction and compatibility of uranium mononitride and alumina forming austenitic stainless steel","authors":"Andre Broussard ,&nbsp;Dong Zhao ,&nbsp;Kevin Yan ,&nbsp;Bruce A. Pint ,&nbsp;Jiheon Jun ,&nbsp;Erofili Kardoulaki ,&nbsp;Jie Lian","doi":"10.1016/j.jnucmat.2025.155748","DOIUrl":"10.1016/j.jnucmat.2025.155748","url":null,"abstract":"<div><div>Uranium mononitride (UN) and alumina forming austenitic (AFA) stainless steel are a potential fuel-cladding combination for the lead-cooled fast reactor (LFR). Chemical compatibility between UN and AFA steel needs to be verified before implementation in a nuclear reactor. Diffusion couple experiments at 823 K and 1023 K were conducted for nonirradiated UN samples in contact with as-cast (no thermally grown Al₂O₃) and preoxidized (with thermally grown Al₂O₃) AFA for 500 and 1000 h in an inert environment. Preoxidized AFA exhibited little to no interaction with all UN samples tested at both 823 K and 1023 K, displaying the stability and capability of the Al₂O₃ layer to prevent chemical interaction and inter-diffusion with UN. Chemical interaction occurs between UN and as-cast AFA. At 1023 K, an aluminum and nitrogen rich phase (likely AlN) formed along the interface of as-cast AFA and UN samples. At 823 K the AlN phase was not prominently observed due to the reduced diffusivity of aluminum through AFA. The aluminum and nitrogen-enriched phase was also observed in a high temperature pressure-assisted test sample of UN and as-cast AFA thermally treated at 1373 K. In UN samples doped with a low weight percent of UO₂ (&lt; 3 wt%), AlN was not detected along the interface at either temperatures, and an Al₂O₃ layer likely formed along the interface and prevented further chemical interaction between UN and as-cast AFA.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155748"},"PeriodicalIF":2.8,"publicationDate":"2025-03-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143629962","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}

{"title":"Ab initio investigation of energetics and stability of vacancy clusters in the FCC high-entropy alloy FeCrCoNi","authors":"Binrong Luo ,&nbsp;Xianli Ren ,&nbsp;Xianyun Feng ,&nbsp;Liuhai Gong ,&nbsp;Guigui Peng","doi":"10.1016/j.jnucmat.2025.155744","DOIUrl":"10.1016/j.jnucmat.2025.155744","url":null,"abstract":"<div><div>The energetics and stability of divacancy, trivacancy, and tetravacancy of the face-centered cubic (FCC) high entropy alloy (HEA) FeCrCoNi in random solid solutions have been investigated by first-principles calculations and ab initio molecular dynamics simulations. Both the formation energy and the binding energy of the vacancy clusters exhibit a broad and overlapping energy distribution. Unlike pure metals, the local lattice distortion induced by the vacancy defects is irregular, displaying both local volume expansion and contraction in our calculations. According to the results of ab initio molecular dynamics (AIMD) simulations, the examined alloy has a higher probability of defect cluster dissociation compared to pure Ni. The tetravacancies decompose into two smaller vacancy defects of (divacancy+divacancy) in the HEA and (monovacancy+trivacancy) in Ni, respectively. Such characteristics for the small vacancy cluster in the HEA are anticipated to significantly influence aggregation, diffusion, and dissociation in the microstructural evolution of defects under irradiation.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155744"},"PeriodicalIF":2.8,"publicationDate":"2025-03-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682845","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}

{"title":"Improving helium bubble models in tungsten: Refined structural and energetic insights","authors":"Chi Song ,&nbsp;Xiang-Shan Kong ,&nbsp;Jie Hou ,&nbsp;C.S. Liu ,&nbsp;Z.M. Xie","doi":"10.1016/j.jnucmat.2025.155743","DOIUrl":"10.1016/j.jnucmat.2025.155743","url":null,"abstract":"<div><div>Tungsten, a key plasma-facing material for fusion reactors, forms bubbles under helium ion fluxes, causing compromising reactor stability. The nucleation and growth of bubbles are linked to helium aggregation at nanovoids, but critical atomistic information, such as the bubble structure and energetics, remains poorly understood, which hinders a thorough understanding of bubbling behavior. Here, we conducted a systematic investigation on the structural and energetic properties of helium-vacancy complexes in tungsten using <em>ab initio</em> molecular dynamics and first-principal static calculations. The structure of helium clusters in nanovoids was characterized in detail using liquid structure analysis techniques. Our energetic calculations validate the robustness of the existing physical model whilst also revealing the inherent shortcomings of the model. By adjusting the gap width and revising the void formation energy, our revised model shows better agreement with DFT calculations, especially for larger nanovoids. Based on this revised model, we can conclude that as the size increases, the He/V ratios of thermodynamically stable bubbles range between 1.5 and 3, whereas the critical He/V ratios for trap mutation lie between 5 and 6.5. Furthermore, our assessment of the available empirical potentials for the W-He system highlights the limitations of these potentials. These findings provide critical insights into bubble nucleation and growth, offer essential parameters for mesoscopic-scale simulations and advance the development of new W-He empirical potentials.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"608 ","pages":"Article 155743"},"PeriodicalIF":2.8,"publicationDate":"2025-03-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143609515","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}

{"title":"Chemical states and reactions of typical nuclides in the primary circuit under normal conditions of HTR-PM","authors":"Jingni Guo ,&nbsp;Yu Wang ,&nbsp;Feng Xie ,&nbsp;Jianzhu Cao ,&nbsp;Jiejuan Tong ,&nbsp;Qian Ma ,&nbsp;Wenting Jia ,&nbsp;Minghua Lyu ,&nbsp;Peng Li","doi":"10.1016/j.jnucmat.2025.155741","DOIUrl":"10.1016/j.jnucmat.2025.155741","url":null,"abstract":"<div><div>The chemical states of nuclides significantly affect their behaviors in multicomponent and multiphase systems, including adsorption, desorption, deposition, diffusion, migration, and chemical reactions. Based on the design and operating parameters of the world's first pebble-bed modular high-temperature gas-cooled reactor demonstration power plant (HTR-PM), the chemical states and potential reactions of 14 typical nuclides in the primary circuit under normal operating conditions of HTR-PM were investigated under a thermodynamic framework and a newly developed two-dimensional projected phase diagram. A correlation matrix was used to quantitatively analyze the factors influencing the chemical states, including the temperature, pressure, and amount of impurity elements (C, H, O, and N). The results showed that the temperature had the greatest effect on the chemical states of the nuclides, while the pressure and N content had negligible effects. A mirror-symmetry relationship was discovered between the effects of C and O on the chemical states of typical nuclides. The phase boundary caused by this symmetry was largely influenced by the chemical states and contents of the compounds of minor elements. This study systematically provides the chemical states and reactions for typical nuclides in the primary circuit of HTR-PM, which is of great significance for research into the behaviors of fission products in advanced nuclear energy systems. The developed technologies and methods are also widely applicable to multicomponent and multi-phase chemical systems.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"608 ","pages":"Article 155741"},"PeriodicalIF":2.8,"publicationDate":"2025-03-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143577241","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}

{"title":"MX precipitate behavior in an irradiated advanced Fe-9Cr steel: Helium sequestration and cavity swelling performance","authors":"T.M. Kelsy Green ,&nbsp;Tim Graening ,&nbsp;Weicheng Zhong ,&nbsp;Ying Yang ,&nbsp;Kevin G. Field","doi":"10.1016/j.jnucmat.2025.155727","DOIUrl":"10.1016/j.jnucmat.2025.155727","url":null,"abstract":"<div><div>This work is the third and final part in an initial series on addressing the behavior of MX precipitate stability in an advanced Fe-9Cr reduced activation ferritic/martensitic (RAFM) alloy under fusion-relevant ion irradiation conditions. Here, the helium trapping properties of MX precipitates are investigated across varying damage levels (15–100 dpa), temperatures (400–600 °C), and helium doses (10–25 appm He/dpa) using sophisticated dual ion beam experiments and electron microscopy. Results indicate that individual MX precipitates efficiently sequester helium in the form of nanoscale bubbles at the precipitate-matrix interfaces near the peak swelling temperature (∼5 bubbles/precipitate at 500 °C). Swelling was primarily due to matrix cavities. The Fe-9Cr alloy reached 2% swelling by 100 dpa, suggesting a shift to steady-state swelling around 50 dpa at 500 °C. However, MX precipitate dissolution beginning at 15 dpa did not coincide with this onset of steady-state swelling.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155727"},"PeriodicalIF":2.8,"publicationDate":"2025-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143629957","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}

{"title":"Defect study in Xe-irradiated UO2 by XRD, TEM and PAS","authors":"C. Onofri ,&nbsp;M. Gérardin ,&nbsp;G. Carlot ,&nbsp;V. Klosek ,&nbsp;C. Bachelet ,&nbsp;M.F. Barthe ,&nbsp;P. Desgardin ,&nbsp;R. Belin ,&nbsp;D. Drouan ,&nbsp;N. Tarisien ,&nbsp;M. Cabié ,&nbsp;M. Angleraud ,&nbsp;T. Grenèche ,&nbsp;H. Palancher","doi":"10.1016/j.jnucmat.2025.155740","DOIUrl":"10.1016/j.jnucmat.2025.155740","url":null,"abstract":"<div><div>Transmission electron microscopy (TEM), X-ray diffraction (XRD) and positron annihilation spectroscopy (PAS) characterizations were combined on polycrystalline UO₂ disks, implanted with low energy xenon ions, to probe the microstructural transformations due to irradiation by taking advantage of their different sensitivities to radiation damage.</div><div>While XRD provides information on elastic strain (and thus free swelling) and microstrains, PAS is sensitive to vacancy defects and TEM allows the direct observation of extended defects (dislocations and vacancy objects).</div><div>These data were gathered in order to understand mechanisms involved in the damage build up in UO₂. At a very low damage level, an increase of the free swelling is highlighted along with first vacancy defects, and then with interstitials dislocation loops. At a higher damage level, dislocation lines appear through loop interactions, inducing a small free swelling relaxation associated with an increase of microstrains. The results of this extensive experimental study are then discussed in the light of literature data.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155740"},"PeriodicalIF":2.8,"publicationDate":"2025-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143629960","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}

{"title":"Integrated multiscale experiment and model analysis of radially resolved microstructure and thermal conductivity in mixed oxide fuel","authors":"Joshua Ferrigno ,&nbsp;Tsvetoslav Pavlov ,&nbsp;Pierre-Clément Simon ,&nbsp;Mathew Goodson ,&nbsp;Ethan Hisle ,&nbsp;Stephen Novascone ,&nbsp;Fabiola Cappia ,&nbsp;Marat Khafizov","doi":"10.1016/j.jnucmat.2025.155739","DOIUrl":"10.1016/j.jnucmat.2025.155739","url":null,"abstract":"<div><div>The thermal conductivity of mixed oxide (MOX) fuel depends on complex microstructural, chemical, and thermomechanical processes. Due to large thermal variations across the annular fuel pellet of sodium fast reactors, many significant microstructural alterations occur across short distances, which greatly impact local thermal conductivity. Using novel experimental methods that provide high spatial resolution enables capturing these localized microstructural trends affecting the thermo-physical properties of nuclear fuel. In this study, radial measurements of porosity, elemental composition, and thermal conductivity of mixed oxide nuclear fuel pellets at various burnups (6 - 19 % FIMA) have been acquired and are analyzed with a multiphysics fuel performance model. The model includes equations capturing heat generation and diffusion, porosity evolution, grain growth, fission gas behavior, and microstructure dependent thermal conductivity. This coupled experimental and modeling effort provides insight into how burnup and irradiation temperature lead to intricate microstructure evolution impacting the properties of the nuclear fuel. We quantify and discuss the accuracy of the implemented models. The porosity and dissolved fission product profiles resulting from burnup were identified as having the most significant impact on thermophysical properties. Validity of the overall multiphysics model was assessed using radially resolved experimental data revealing central void evolution, porosity, grain growth, dissolved fission gas, and thermal conductivity. This work provides a pathway for improving localized thermal conductivity models and the predictive capabilities of fuel performance codes.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155739"},"PeriodicalIF":2.8,"publicationDate":"2025-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143629961","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}

{"title":"Effect of Mg and Ni impurities on tritium diffusion in lithium ceramics through cluster dynamics simulations","authors":"Ankit Roy ,&nbsp;Krishna Chaitanya Pitike ,&nbsp;Christopher Matthews ,&nbsp;David A. Andersson ,&nbsp;Andrew M. Casella ,&nbsp;Ram Devanathan ,&nbsp;David J. Senor","doi":"10.1016/j.jnucmat.2025.155736","DOIUrl":"10.1016/j.jnucmat.2025.155736","url":null,"abstract":"<div><div>This study investigates the impact of Mg and Ni doping on tritium diffusion in LiAlO₂ and LiAl₅O₈ ceramics, that are used in tritium-producing burnable absorber rods (TPBARs). Utilizing Centipede simulations across a broad temperature range (500 K to 1250 K), we explore the interplay between defect dynamics, cluster formation, and tritium mobility. In LiAlO₂, Mg doping significantly enhances tritium diffusivity by increasing tritium interstitial concentrations and diffusion coefficients of key species, thereby doubling the overall tritium diffusivity. Ni doping, while shifting the dominant defect to Li vacancies, maintains high tritium mobility due to the low binding energy of Li vacancy-tritium complexes, which ensures effective tritium migration. In LiAl₅O₈, Mg and Ni doping results in a slight reduction in the diffusion coefficients of key species, yet the dramatic increase in tritium interstitial concentrations compensates, leading to a net small increase in tritium diffusivity. The findings highlight the critical role of defects in tritium transport and the effect of Mg and Ni defects on the performance of these ceramics in demanding nuclear environments.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"608 ","pages":"Article 155736"},"PeriodicalIF":2.8,"publicationDate":"2025-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143591959","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}