Progress in Nuclear Energy最新文献

{"title":"Thermo-mechanical response of SiCf/SiC composite cladding: Effect of loss-of-coolant accident duration","authors":"Shuang Liang ,&nbsp;Chong Wei ,&nbsp;Bowen Qiu ,&nbsp;Cheng Zhang ,&nbsp;Haoyu Liao ,&nbsp;Xingjie Ren ,&nbsp;Zhong Xiao","doi":"10.1016/j.pnucene.2025.105681","DOIUrl":"10.1016/j.pnucene.2025.105681","url":null,"abstract":"<div><div>SiC_f/SiC composite is one of the candidate materials for fuel cladding in Generation IV advanced nuclear reactors. However, there are still few risks under accident conditions, such as large physical property changes and poor thermal conductivity, the performance of the cladding remains to be studied especially in extreme accident conditions (loss-of-coolant accident, LOCA and reactivity-insertion accident, RIA). In this study, the thermo-mechanical responses of SiC_f/SiC composite cladding under different LOCA durations were investigated by a meso-macroscopic coupling finite element simulation method. At mesoscopic scale, we present a mathematical model between the longitudinal tensile ultimate strength and temperature (200K∼2000K), which enables us to define the failure of macroscopic cladding. At macroscopic scale, the established mathematical model was applied to the failure analysis of macroscopic cladding, then the temperature and hoop stress of the inner and outer surfaces of the cladding were studied under different LOCA durations of 200s, 300s and 400s. The results showed that under LOCA condition, the hoop stress difference between the inner and external surfaces of the SiC_f/SiC composite cladding increases about 200% compared with that under normal service conditions. Meanwhile, the hoop stress difference increases slowly with the increase of LOCA duration, and the maximum increment can reach about 2.8%. In addition, the peak temperature increases with the increase of LOCA duration, which the maximum increment can reach about 5.6%, while the peak temperature difference between the inner and external surfaces increases slowly with the increase of LOCA duration, and the maximum increment can reach about 5.1%.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105681"},"PeriodicalIF":3.3,"publicationDate":"2025-02-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143471152","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigation of heat transfer characteristics of carbon dioxide transcritical flow in a reactor channel","authors":"Mao Luo ,&nbsp;Hui Bao ,&nbsp;Fulong Zhao ,&nbsp;Ruibo Lu ,&nbsp;Sichao Tan ,&nbsp;Ruifeng Tian","doi":"10.1016/j.pnucene.2025.105670","DOIUrl":"10.1016/j.pnucene.2025.105670","url":null,"abstract":"<div><div>The fourth generation of supercritical carbon dioxide (S-CO₂) cooled advanced reactor has the characteristics of compact volume and high efficiency, and is widely used in space reactors and small reactors. For the purpose of the heat transfer characteristics of S-CO₂ under transcritical conditions, the effects of changing inlet velocity, inlet CO₂ fluid temperature, CO₂ fluid operating pressure and wall heat flux on <em>h</em> and <em>Nu</em> in a single cylinder without gravity were analyzed by numerical simulation. The influence of different inlet flow rates on transcritical conditions under horizontal tube gravity is analyzed, and the temperature and velocity distributions of normal transcritical conditions and heat transfer deterioration conditions are compared. The consequence show that the rise of wall heat flux and the decrease of pressure will make the critical position move towards the inlet end. Reducing the inlet rate and increasing the inlet temperature will also shift the critical position towards the inlet end and result the heat transfer to worsen at the inlet end. In the horizontal pipe, when the heat transfer deteriorates, the CO₂ fluid temperature differences between the top and lower parts exceeds 20 K, and the coefficient of heat transfer at underside is 2.5 times that at the top. When the deterioration degree of heat transfer deepens, the difference of heat transfer coefficients between the upper and lower parts of the channel will also increase due to ascent the temperature difference. Finally, the heat transfer deterioration can be attributed to the dual effects of the near-wall CO₂ fluid criticality and the increase in the CO₂ fluid mainstream thermal conductivity.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105670"},"PeriodicalIF":3.3,"publicationDate":"2025-02-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143471153","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Influence of the accumulation of TODGA degradation compounds in the separation of Americium from Curium by the AmSel process","authors":"Pablo Vacas-Arquero ,&nbsp;Iván Sánchez-García ,&nbsp;Hitos Galán","doi":"10.1016/j.pnucene.2025.105677","DOIUrl":"10.1016/j.pnucene.2025.105677","url":null,"abstract":"<div><div>N,N,N′,N′-tetraoctyldiglycolamide (TODGA) is considered one of the most promising extractants for achieving the actinides recovery in the advanced nuclear fuel cycles due to its good extraction properties and resistance to degradation against the harsh process conditions, <em>i.e.</em> a high radiation field and high nitric acid concentrations where the spent nuclear fuel is dissolved. While its stability has been very well studied and its degradation products characterized, their impact on separating americium (Am) and curium (Cm) hasn't been fully investigated. This study presents from fundamental investigations to more realistic scenarios on how the accumulation of the degradation compounds of TODGA could affect the Am and Cm separation under <em>Americium Selective</em> (AmSel) process conditions. This study also considers some possibility of solving the problems caused by the accumulation of those compounds by adjusting different parameters in the stripping step of the AmSel process such as the concentration of SO₃-Ph-BTBP or HNO₃ in the aqueous phase.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105677"},"PeriodicalIF":3.3,"publicationDate":"2025-02-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143464085","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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":"Microgrid control incorporated with Small Modular Reactor (SMR)-based power productions in the university campus","authors":"Tae Ho Woo ,&nbsp;Yun Il Kim","doi":"10.1016/j.pnucene.2025.105678","DOIUrl":"10.1016/j.pnucene.2025.105678","url":null,"abstract":"<div><div>Microgrids, comprised of a diverse portfolio of efficient energy sources, present a promising approach to managing localized power systems, exemplified by university campuses. The successful implementation of such microgrids necessitates a rigorous and multifaceted analytical framework. Given the dynamic and computationally intensive nature of the modeling process, which involves numerous interdependent variables, System Dynamics (SD) was adopted as the analytical methodology. A fifty-year SD model was developed to harness the computational power of this approach. The accompanying figure depicts the SD model, encompassing key components such as Microgrid Control, Distributed Resources, and Small Modular Reactor (SMR)-based Nuclear Energy. Nuclear energy availability exhibited a fluctuating trajectory in the initial three decades, subsequently gaining significant prominence due to its zero-carbon emissions and high energy efficiency. Other energy sources demonstrated a gradual increase in availability, while \"Marketing &amp; Power Plant\" and \"Microgrid Control\" exhibited cyclical patterns of growth. The significance of energy efficiency within university campuses cannot be overstated, as the associated cost savings can directly support and enhance educational and research initiatives.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105678"},"PeriodicalIF":3.3,"publicationDate":"2025-02-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143464084","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Lithium isotopic analysis in depleted lithium salts","authors":"Kirby Hobbs ,&nbsp;Sean R. Scott ,&nbsp;Johnny Williams ,&nbsp;Sara Mastromarino ,&nbsp;Norbert Gajos ,&nbsp;Christian Berry ,&nbsp;Ian Anderson ,&nbsp;Kali Melby ,&nbsp;Alan Kruizenga","doi":"10.1016/j.pnucene.2025.105674","DOIUrl":"10.1016/j.pnucene.2025.105674","url":null,"abstract":"<div><div>Lithium isotope separation processes require characterization of the isotopic compositions of the different output phases of the process. While considerable effort to develop isotope separation methods has been ongoing for decades, the analytical methods associated with these analyses are rarely provided. In this work three types of mass spectrometers (Q-ICP-MS, MC-ICP-MS, TIMS) were tested for the ability to measure depleted lithium salts that are relevant materials for isotopic separations. Results indicate that, once stabilized, the Q-ICP-MS can provide equal precision for Li isotopic samples compared to TIMS or MC-ICP-MS. However, MC-ICP-MS consistently provides the highest precision for salts with natural isotopic abundances, whereas Q-ICP-MS provides equal or better precision in the depleted salts. These data demonstrate that Q-ICP-MS is an appropriate choice for analysis of depleted lithium salts, especially when rapid analyses are desired for near-online process monitoring.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105674"},"PeriodicalIF":3.3,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143464082","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental evidences and quantum chemical insights into the extraction of plutonium from sulfate medium using diamylhydrogen Phosphonate","authors":"B. Shiva Rama Krishna ,&nbsp;Diganta Raychaudhuri ,&nbsp;P. Rajani ,&nbsp;Balija Sreenivasulu ,&nbsp;Gopinadhanpillai Gopakumar ,&nbsp;C.V.S. Brahmananda Rao ,&nbsp;G. Srinivasa Rao ,&nbsp;N.R. Jawahar ,&nbsp;N. Sivaraman","doi":"10.1016/j.pnucene.2025.105679","DOIUrl":"10.1016/j.pnucene.2025.105679","url":null,"abstract":"<div><div>Recovery of plutonium from aqueous streams containing sulfate ions has been examined using Diamylhydrogen Phosphonate (DAHP) by both experimentally and computation. The distribution ratios (<em>D</em>) for Pu(IV) with 1.1 M DAHP/<em>n</em>-DD are found to decrease with an increase in sulfuric acid concentration and <em>D</em> values are significantly higher for DAHP system than TBP system under identical conditions. The percentage extraction of Pu(IV) rises with a rise in DAHP concentration. Quantitative extraction (&gt;98%) of Pu(IV) from actual analytical waste was observed in one contact with 2 M DAHP/<em>n</em>-DD. Stripping of Pu(IV) from the organic phase has been performed with 0.8 M oxalic acid with various organic to aqueous ratio (O/A). Striping was found to be effective when the O/A ratio is 1:4. To gain insights into the mechanism of complex formation of Pu(IV) with DAHP, density functional theory (DFT) calculations were applied on the corresponding Pu metal complexes. The acid-dependent dual extraction mechanism for DAHP has been examined both experimentally and by DFT computations. Probable structures and binding abilities of plutonium with DAHP and TBP have been inferred from electronic structure calculations. The calculated extraction behavior of Pu with DAHP and TBP is in agreement with the results attained by experimental distribution ratios and provided further insights into the extraction mechanism.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105679"},"PeriodicalIF":3.3,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143464083","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Enhancing accuracy and efficiency of RMC/SUBCHAN neutronics and thermal-hydraulics coupling system for BEAVRS simulation","authors":"Hao Luo ,&nbsp;Kaiwen Li ,&nbsp;Jie Li ,&nbsp;Zhaoyuan Liu ,&nbsp;Jingang Liang ,&nbsp;Jiyang Yu ,&nbsp;Shanfang Huang ,&nbsp;Kan Wang","doi":"10.1016/j.pnucene.2025.105666","DOIUrl":"10.1016/j.pnucene.2025.105666","url":null,"abstract":"<div><div>High-fidelity whole-core multi-cycle simulations, incorporating coupled neutronics performance analyses and thermal-hydraulics feedback, play a crucial role in understanding the complex behavior of operating nuclear power reactors. This paper presents a high-performance neutronics and thermal-hydraulics (N-TH) coupling system between RMC and SUBCHAN developed for the large-scale, multi-physics analyses of the pressurized water reactors (PWRs). The new coupling system was validated using a two-cycle whole-core depletion benchmark BEAVRS, comparing criticality boron concentration (CBC) and assembly-wise detector signals with measurements. The accuracy of RMC/SUBCHAN solutions in terms of CBC falls within the range of [-50.83 ppm, 1.5ppm] for cycle1 and [-8.53 ppm, 12.89ppm] for cycle 2. The root mean square (RMS) relative errors of the detector signals are in the [1.58%, 4.56%] range for both cycles, demonstrating great agreements with the measurements. Two acceleration techniques were employed in the coupling, achieving a 16.8% speedup for each depletion step. Finally, an explicit heat generation scheme was presented and analyzed, which features more accurate prediction of energy deposition distribution in different regions and materials and improves the accuracy of the thermal-hydraulics solutions.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105666"},"PeriodicalIF":3.3,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143453016","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A general correlation for saturated flow boiling heat transfer in vertical narrow rectangular channel based on test data from specialized experiment","authors":"Bo Kuang ,&nbsp;Pengfei Liu ,&nbsp;Jian Deng ,&nbsp;Shuhua Ding ,&nbsp;Dan Wu","doi":"10.1016/j.pnucene.2025.105668","DOIUrl":"10.1016/j.pnucene.2025.105668","url":null,"abstract":"<div><div>Due to the special geometry of narrow rectangular channels, their heat transfer characteristics differ from conventional channels. Heat transfer data and visualization images within a wide parameter range are obtained in this study, through heat transfer tests and visualization tests. The boiling curves of rectangular narrow channel under different parameter conditions are given, and the effect of parameters on the heat transfer coefficient is analyzed. It is indicated that mass flux, pressure, and gap size have an impact on the heat transfer coefficient. In addition, the boiling heat transfer mechanism exhibits a dominant mode transition from nucleate boiling to forced convective vaporization. In response to the asymmetric confinement effect on the vapor phase in narrow rectangular channels, the vapor velocity correction coefficient and vapor size correction coefficient are obtained through vapor force balance analysis, to characterize the effects of convection in liquid film evaporation and asymmetric bubble growth, respectively. By combining the liquid film confinement number and mechanism transition function applicable to rectangular narrow channels, a heat transfer correlation suitable for rectangular narrow channels is obtained, and the results showed that the new equation was in good agreement with the experimental results.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105668"},"PeriodicalIF":3.3,"publicationDate":"2025-02-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143445640","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of novel oval-twisted helical tube once-through steam generator: Part I: Single-phase laminar flow","authors":"Scott Wahlquist ,&nbsp;Amir Ali ,&nbsp;Kyle Schroeder ,&nbsp;Su-Jong Yoon ,&nbsp;Piyush Sabharwall","doi":"10.1016/j.pnucene.2025.105667","DOIUrl":"10.1016/j.pnucene.2025.105667","url":null,"abstract":"<div><div>The Helically coiled tube Once-Through Steam Generator (H-OTSG) offers enhanced overall thermal performance due to its high surface area per unit volume and secondary flow generation. The H-OTSG design (circular cross-sectional flow area) is considered for various Small Modular Reactor (SMR) designs due to its compactness, practical manufacturability, and higher thermal efficiency than current OTSG technologies (e.g., shell and tube). A novel conceptual H-OTSG tube design, known as the Oval-Twisted Helically coiled tube Once-Through Steam Generator (OTH-OTSG), is proposed for nuclear applications. The concept is a helically twisted coil with an oval cross-sectional flow area. The OTH-OTSG geometry simultaneously enhances the heat transfer performance through double-induced secondary flow. One through the tube twist generated swirling flow, and the second by the centrifugal force offered by the helical shape. Technology development requires two significant steps. The first is investigating the thermal performance of single-phase flow, which is the focus of this study, to develop heat transfer and friction loss models. In this step, the single-phase heat transfer performance is evaluated and compared with the H-OTSG. The OTH-OTSG and H-OTSG are evaluated for various mean coil diameters (<span><math><mrow><msub><mi>D</mi><mi>c</mi></msub></mrow></math></span> = 75–225 mm), laminar single-phase flow regime (<span><math><mrow><mi>R</mi><mi>e</mi></mrow></math></span> = 200–2000), and isothermal wall conditions (<span><math><mrow><msub><mi>T</mi><mrow><mi>w</mi><mi>a</mi><mi>l</mi><mi>l</mi></mrow></msub></mrow></math></span> = 320–350 K). Over the range of investigated parameters, the new proposed OTH-OTSG geometry shows an enhanced heat transfer rate (<span><math><mrow><msub><mi>q</mi><mi>o</mi></msub></mrow></math></span>/ <span><math><mrow><msub><mi>q</mi><mi>C</mi></msub></mrow></math></span> = 28.29–59.78%), heat transfer coefficient (<span><math><mrow><msub><mrow><mi>N</mi><mi>u</mi></mrow><mi>o</mi></msub><mo>/</mo><msub><mrow><mi>N</mi><mi>u</mi></mrow><mi>c</mi></msub></mrow></math></span> = 19.14–39.06%) and increased friction coefficient (<span><math><mrow><msub><mi>f</mi><mi>o</mi></msub><mo>/</mo><msub><mi>f</mi><mi>c</mi></msub></mrow></math></span> = 15.07–41.84%) over the single-phase flow in H-OTSG with a circular cross-sectional flow area. The presented heat transfer (<span><math><mrow><mi>N</mi><mi>u</mi></mrow></math></span>) and friction loss (<span><math><mrow><mi>f</mi></mrow></math></span>) models are within <span><math><mrow><mo>±</mo></mrow></math></span> 9 and <span><math><mrow><mo>±</mo></mrow></math></span> 13% with all data, respectively. The heat transfer and hydrodynamic models developed through this stage will be implemented in a two-phase flow study for the single-phase flow regime at the early stage of the innovative OHT-OTSG study, which is the next step in the development process.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105667"},"PeriodicalIF":3.3,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143438230","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design of fuzzy adaptive fractional-order controller for total power control of AHWR","authors":"Devbrat Gupta ,&nbsp;Jitendra Kumar ,&nbsp;Vishal Goyal ,&nbsp;K.N.V. Sairam","doi":"10.1016/j.pnucene.2025.105641","DOIUrl":"10.1016/j.pnucene.2025.105641","url":null,"abstract":"<div><div>In this article, a fuzzy adaptive fractional-order proportional plus derivative controller for total power control of an Advanced Heavy Water Reactor is designed in the presence of thermal hydraulics feedback. In addition to a conventional Fuzzy Logic Control layer (FLC), the proposed controller uses a self-tuning FLC layer for run-time adaption of the controller output. A genetic algorithm (GA) based optimization method is used for tuning the controller parameters. Transient Simulation studies are carried out to demonstrate the efficacy of the proposed controller for set-point changes and feedwater temperature disturbances. Results of the proposed controller are compared with those of the traditional proportional plus derivative (PD) and fractional-order proportional plus derivative (FOPD) controllers using standard performance indices. It is observed that the AFOPD controller has 13.99% performance improvement over the FOPD controller and 20.53% improvement over the PD controller for considered objective function. At various operating conditions also, the AFOPD controller shows similar superiority over FOPD and PD controllers.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"183 ","pages":"Article 105641"},"PeriodicalIF":3.3,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143438231","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}