Annals of Nuclear Energy最新文献

{"title":"Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding","authors":"Reda Abdel-Hameed ,&nbsp;Nagah Abourashed ,&nbsp;Ashraf Ashmawy ,&nbsp;Eshraqa Ali ,&nbsp;Bader Huwaimel ,&nbsp;M. Abdallah ,&nbsp;Ali Hydaya ,&nbsp;Esraa H. Abdel-Gawad ,&nbsp;Mohamed.Elsafi","doi":"10.1016/j.anucene.2025.111384","DOIUrl":"10.1016/j.anucene.2025.111384","url":null,"abstract":"<div><div>The mechanical and radiation shielding performance of lead-borate-based glass samples <span><math><mrow><mn>45</mn><msub><mi>B</mi><mn>2</mn></msub><msub><mi>O</mi><mn>3</mn></msub><mo>:</mo><mn>25</mn><mi>P</mi><mi>b</mi><mi>O</mi><mo>:</mo><mfenced><mrow><mn>25</mn><mo>-</mo><mi>x</mi></mrow></mfenced><mi>C</mi><mi>a</mi><mi>O</mi><mo>:</mo><mi>x</mi><mi>B</mi><mi>a</mi><mi>O</mi><mfenced><mrow><mi>x</mi><mo>=</mo><mrow><mn>5</mn><mo>,</mo><mn>10</mn><mo>,</mo><mn>15</mn></mrow><mo>&amp;</mo><mn>20</mn><mi>m</mi><mi>o</mi><mi>l</mi><mo>%</mo></mrow></mfenced></mrow></math></span> were evaluated<span><math><mo>.</mo></math></span> The density values range from <span><math><mrow><mn>4.510</mn><mi>g</mi><mo>.</mo><msup><mrow><mi>cm</mi></mrow><mrow><mo>-</mo><mn>3</mn></mrow></msup></mrow></math></span> for BPCB-5 to <span><math><mrow><mn>4.815</mn><mi>g</mi><mo>.</mo><msup><mrow><mi>cm</mi></mrow><mrow><mo>-</mo><mn>3</mn></mrow></msup></mrow></math></span> for BPCB-20. Makishima-Mackenzie’s theory was applied, and mechanical moduli were derived. The increase in BaO content made the microhardness, shear modulus, and Young’s modulus slightly decreased. Simultaneously, radiation shielding parameters were assessed within energies <span><math><mrow><mn>0.662</mn></mrow></math></span>, <span><math><mrow><mn>1.173</mn></mrow></math></span> and <span><math><mrow><mn>1.333</mn></mrow></math></span> <span><math><mrow><mi>MeV</mi></mrow></math></span>. The results of BPCB-20 sample surpasses all other samples in terms of radiation shielding capabilities. The half value layer at <span><math><mrow><mn>0.662</mn><mi>M</mi><mi>e</mi><mi>V</mi></mrow></math></span> were <span><math><mrow><mn>1.662</mn><mo>,</mo><mn>1.635</mn><mo>,</mo><mn>1.610</mn></mrow></math></span> and <span><math><mrow><mn>1.587</mn><mi>c</mi><mi>m</mi></mrow></math></span> for BPCB-5, BPCB-10, BPCB-15 and BPCB-20, respectively. The samples BPCB-5 and BPCB-20 have separate radiation shielding effectiveness measurements of <span><math><mrow><mn>56.585</mn></mrow></math></span> and <span><math><mrow><mn>58.262</mn><mo>%</mo></mrow></math></span> for <span><math><mrow><mn>20</mn><mi>m</mi><mi>m</mi></mrow></math></span> thickness of the sample. These glass samples are superior to commercial glass that is being adopted in the market such as RS-360, since the HVL for RS-360 at <span><math><mrow><mn>0.662</mn><mi>M</mi><mi>e</mi><mi>V</mi></mrow></math></span> is.<span><math><mrow><mn>2.166</mn><mi>c</mi><mi>m</mi><mo>.</mo></mrow></math></span></div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111384"},"PeriodicalIF":1.9,"publicationDate":"2025-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682651","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":"Predicting time-correlated leakage rates of double-sealed hatch under accident conditions in a nuclear power plant","authors":"Xiaoming Huang ,&nbsp;Lei He ,&nbsp;Ming Li ,&nbsp;Xing Fang ,&nbsp;Jiawei Wang ,&nbsp;Guoliang Xu","doi":"10.1016/j.anucene.2025.111354","DOIUrl":"10.1016/j.anucene.2025.111354","url":null,"abstract":"<div><div>A gaseous circuit model is proposed for predicting the time-correlated leakage rate of double-sealed structures used in the large diameter hatches, which are considered to be the most vulnerable parts of the containment systems. The core task of the model is the determination of the instantaneous dual O-ring flow resistance, deduced from existing interfacial leakage mechanisms and combined with the effect of large flange deflection. After validation by comparison with experimental measurements, the model is used to quantitatively investigate the leakage behavior of a double-sealed hatch under various air source excitations. It is found that, the leakage related parameters all vary exponentially with time under constant pressure excitation, with higher pressures corresponding to faster system stabilization rates. However, under a dynamic accident scenario, the leakage related parameters follow the internal pressure, and a significant lag in parasitic pressure and outer leakage can be observed during the pressure decay phase.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111354"},"PeriodicalIF":1.9,"publicationDate":"2025-03-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143643012","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":"Reactor multi-physics internal coupling method based on STL unified dynamic mesh","authors":"Yungeng LI ,&nbsp;Qingquan PAN ,&nbsp;Xiaojing LIU","doi":"10.1016/j.anucene.2025.111377","DOIUrl":"10.1016/j.anucene.2025.111377","url":null,"abstract":"<div><div>The Monte Carlo method is widely used in reactor multi-physics analysis due to its superior accuracy. However, it faces geometry incompatibility with multi-physics software. Traditional coupling relies on external interfaces and approximates geometric deformation. This study develops a high-fidelity Monte Carlo multi-physics coupling method; it has the following characteristics: (1) internal coupling between multi-physics fields; (2) a unified mesh for all physical fields; (3) dynamic mesh capabilities for geometric deformations; (4) partition adaptive STL model. Based on the irradiation neutronics platform <strong>Light</strong>, we develop a multi-physics coupling module, <strong>LightMP</strong>. It is internally coupled with the Monte Carlo neutronics module <strong>LightMC</strong>. This integration realizes high-fidelity “Neutronic-Thermal-Mechanical” coupling within a unified dynamic mesh. We tested it on a single channel and a 3 × 3 bundle of PWR. The results agreed with the reference values, proving the accuracy and robustness of this method.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111377"},"PeriodicalIF":1.9,"publicationDate":"2025-03-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642126","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":"Adjoint-based path length stretching in a Woodcock framework with SIRS angular biasing","authors":"David Legrady,&nbsp;Marton Pukler,&nbsp;Gabor Tolnai","doi":"10.1016/j.anucene.2025.111255","DOIUrl":"10.1016/j.anucene.2025.111255","url":null,"abstract":"<div><div>The development of an adjoint-based path-stretching scheme within a non-analog Woodcock (delta-tracking) framework is predicated on zero-variance formalism. The derivation of an ideal cross-section stretching factor is possible from the incident and the outgoing adjoint collision densities. The incorporation of this bias into the virtual collision decision probability necessitates time-consuming oversampling (high sampling cross section) to achieve low variance. Conversely, a similar effect can be achieved by stretching the sampling cross section, which, however, results in a considerable increase in variance, even for minor discrepancies between the actual local and the sampling cross sections. To mitigate this, a combination of the two bias methods is necessary. Nevertheless, sensitivity to the difference between sampling and actual cross sections persists, which limits the maximum efficiency gain. To address this challenge, a Sampling Importance Resampling (SIRS) scheme was devised for angular biasing, as both transport and collision kernels necessitate biasing for a significant enhancement in efficiency. The efficacy of the algorithm is demonstrated through numerical examples for source-detector systems, employing realistic geometries and utilizing the GUARDYAN code.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111255"},"PeriodicalIF":1.9,"publicationDate":"2025-03-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143643706","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":"Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: Applying novel methodologies","authors":"Mohamed Mira ,&nbsp;O. El Hajjaji ,&nbsp;Jordi Freixa ,&nbsp;T. El Bardouni ,&nbsp;H. Boukhal ,&nbsp;Y. Boulaich ,&nbsp;Tarik El Ghalbzouri","doi":"10.1016/j.anucene.2025.111353","DOIUrl":"10.1016/j.anucene.2025.111353","url":null,"abstract":"<div><div>The Doppler effect, commonly referred to as fuel temperature coefficient (<span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>T</mi></mrow></msub></math></span>), is a critical parameter that quantifies the reactivity feedback resulting from changes in fuel temperature. Understanding and accurately quantifying <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>T</mi></mrow></msub></math></span> is essential for evaluating and adopting innovative fuel compositions. In this study, we present a comprehensive evaluation of <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>T</mi></mrow></msub></math></span> for transuranic (TRU)-based Moroccan TRIGA Mark II reactor, employing advanced simulation techniques and methodologies based on the OpenMC code. Two novel methods are introduced and validated. The first method analyzes the contributions of the fast fission factor (<span><math><mi>ϵ</mi></math></span>), resonance escape probability factor (<span><math><mi>p</mi></math></span>), thermal utilization factor (<span><math><mi>f</mi></math></span>), and reproduction factor (<span><math><mi>η</mi></math></span>) to <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>T</mi></mrow></msub></math></span>. The second evaluates the Upscattering and isotope-wise contributions to gain deeper insights into the behavior of these factors. Additionally, <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>T</mi></mrow></msub></math></span> is evaluated as a function of fuel burnup. For comparative purposes, the standard U-ZrH_1.65 fuel is also analyzed to benchmark the behavior of the TRU-based fuel against conventional fuel types.</div><div>The results reveal that TRU-based fuel, despite its high fissile content, it maintains a negative <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>T</mi></mrow></msub></math></span> across the operational temperature range and throughout the reactor’s lifetime. This negative reactivity feedback is attributed to the significant thermal capture resonances of TRU-based isotopes, such ²⁴⁰Pu, and ²⁴²Pu, and the unique properties of the zirconium hydride matrix ZrH_1.65. Although the magnitude of <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>T</mi></mrow></msub></math></span> for TRU-based fuel is less negative compared to the standard U-ZrH_1.65 fuel, it remains sufficiently negative to guarantee safe reactor operation.</div><div>These findings are promising and suggest that further exploration of TRU-based fuels could support the development of reliable, clean, and sustainable nuclear energy systems.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111353"},"PeriodicalIF":1.9,"publicationDate":"2025-03-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143643707","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 newly and efficient virtual mesh based CMFD acceleration method for pebble-bed HTGR with cylindrical geometry","authors":"Yuchen Wen,&nbsp;Chen Hao,&nbsp;Yizhen Wang","doi":"10.1016/j.anucene.2025.111349","DOIUrl":"10.1016/j.anucene.2025.111349","url":null,"abstract":"<div><div>Three-dimensional method of characteristic (3D-MOC) codes have been developed to conduct neutronic simulation for pebble-bed high temperature gas-cooled rector (HTGR). Although parallel strategy such as domain decomposition and acceleration method such as coarse mesh finite difference (CMFD) are applied in these codes, whole core simulation still faces huge computational burden which needs more efficient acceleration method to enhance simulation efficiency. Moreover, considering the cylindrical geometry of pebble-bed HTGR, differential length of coarse meshes will gradually increase along radial direction which will lead convergence problem in conventional CMFD method. In this paper, a virtual mesh based CMFD method is proposed to overcome this issue. Virtual coarse meshes are generated by further dividing CMFD coarse meshes along circumferential direction to reduce the optical thickness of peripheral coarse meshes. The performance of proposed virtual coarse mesh based CMFD acceleration method is verified in a simplified cylindrical pebble-bed model and HTR-10 whole core problem. Numerical results show that virtual coarse mesh based CMFD method can reduce around 30% source iterations of MOC compared with original CMFD method.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111349"},"PeriodicalIF":1.9,"publicationDate":"2025-03-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143632043","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":"Object-oriented petri nets for reliability assessment and sensitivity analysis of safety-critical nuclear power plant systems","authors":"Kabiratna Behera ,&nbsp;Vinay Kumar ,&nbsp;Binod Kumar Singh","doi":"10.1016/j.anucene.2025.111364","DOIUrl":"10.1016/j.anucene.2025.111364","url":null,"abstract":"<div><div>A Safety-critical system (SCS) is a complex system consisting of various components functioning cooperatively that demands rigorous analysis to ensure reliability and effectiveness in mitigating potential hazards. In several previous studies, the ordinary Petri net (PN) models are used to model and analyze the reliability of SCSs. However, these models lack modularity and flexibility and have state explosion problems. On the other hand, the application of Object-Oriented Petri Nets (OOPNs) in the field of dependability analysis of SCSs is limited. Thus, we propose a framework using OOPNs to model the complex SCSs and perform reliability and sensitivity analysis of such systems. Unlike ordinary PN models, the OOPN models offer better modularity and flexibility and also reduce the state explosion problems. We apply our framework to the Reactor Core Isolation Cooling (RCIC) system in Nuclear Power Plants (NPPs) to demonstrate its effectiveness. We have validated our framework and achieved an accuracy of 99.97% in reliability prediction, which proves its efficacy.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111364"},"PeriodicalIF":1.9,"publicationDate":"2025-03-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642125","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":"Toward environmental sustainability: What role does Russian nuclear technology play?","authors":"Shujaat Abbas","doi":"10.1016/j.anucene.2025.111368","DOIUrl":"10.1016/j.anucene.2025.111368","url":null,"abstract":"<div><div>Nuclear energy technology has enormous untapped potential to generate stable and clean energy required to achieve net-zero carbon emissions. This study explores the impact of Russian nuclear technology exports on environmental sustainability in 21 major nuclear power-consuming countries from 2002 to 2021. This objective is realized by using panel inverse quantile and instrumental variable quantile with smoothed generalized methods of moments technique. The estimated result reveals that Russian nuclear technology exports have a significant negative impact on GHG emissions in all quantiles. Similarly, environmental policy stringency has also emerged as an important policy instrument to enhance environmental sustainability in lower quantiles (Qtile-10 to Qtile-50), while insignificant impact is observed in higher quantiles. Furthermore, rapid urbanization has emerged as a major contributor to GHG emissions and environmental degradation, while the increase in economic globalization is instrumental in enhancing environmental sustainability only at higher quantiles.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111368"},"PeriodicalIF":1.9,"publicationDate":"2025-03-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143632041","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":"Assessing sensitivity and uncertainty in rod ejection accidents: A combined PCE-POD approach","authors":"Yijun Zhang ,&nbsp;Wenhuai Li ,&nbsp;Sitao Peng ,&nbsp;Jinggang Li ,&nbsp;Ting Wang ,&nbsp;Qingyun He ,&nbsp;Tao Wang ,&nbsp;Haoliang Lu ,&nbsp;Zeng ling","doi":"10.1016/j.anucene.2025.111362","DOIUrl":"10.1016/j.anucene.2025.111362","url":null,"abstract":"<div><div>This study investigates the sensitivity and uncertainty of outcomes related to rod ejection accidents in nuclear reactors, focusing on the impact of perturbations in neutron parameters. By perturbing the macroscopic cross-sections of fuel assemblies, we assess how these variations influence reactor dynamics during transient events. We employ Polynomial Chaos Expansion (PCE) combined with Proper Orthogonal Decomposition (POD) to create an efficient analytical framework for quantifying uncertainty. Using Monte Carlo simulations as a benchmark, we demonstrate that PCE can accurately estimate the mean and variance of global peaking parameters with significantly fewer samples than traditional methods. Our findings reveal that only a limited number of POD modes can capture the majority of the energy distribution, facilitating a more streamlined analysis. This research enhances our understanding of reactor behavior under uncertainty and contributes to improving safety assessments in nuclear engineering.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111362"},"PeriodicalIF":1.9,"publicationDate":"2025-03-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143632042","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":"Analysis of a new on-site semi-passive design to improve the safety of Generation II/II+ Pressurized water reactors","authors":"Wei Li ,&nbsp;Zhenhua Wu ,&nbsp;Chengcheng Deng ,&nbsp;Junmei Wu","doi":"10.1016/j.anucene.2025.111370","DOIUrl":"10.1016/j.anucene.2025.111370","url":null,"abstract":"<div><div>Generation II/II+ (Gen II/II+) Pressurized Water Reactors (PWRs) still account for a significant proportion of nuclear reactors worldwide. However, some Gen II/II+ PWR plants face a significant safety risk, as current accident management typically covers Station BlackOut (SBO) or Total Loss of FeedWater (TLFW) accidents individually. It is challenging to address the combination of SBO and TLFW (TMLB’), which can occur under extreme circumstances. Numerical simulations of severe accidents have indicated that this combination can lead to reactor core melting in as little as 2.5 h after the accident. To enhance the safety of Gen II/II+ PWRs during TMLB’, a new strategy called semi-passive cyclic cooling was proposed. This approach aims to delay accident progression by fully utilizing on-site resources, such as the cooling water inside the deaerator, the high-pressure steam in the Steam Generators (SG) as the driving force, and the feedwater pipeline in the secondary loop. This paper presents an uncertainty and sensitivity analysis of the semi-passive cyclic cooling performance during TMLB’. The fundamental characteristics of the semi-passive cyclic cooling strategy were studied using a best-estimate thermal–hydraulic model for the CPR1000, an improved Chinese Gen II/II+ PWR. An uncertainty analysis was then performed to assess the impact of various operating parameters of the reactor system and the semi-passive cyclic cooling system on the safety benefit, specifically in terms of delayed reactor core uncovery. Sobol sequence sampling-based simulations demonstrated that the semi-passive cyclic cooling system can significantly delay reactor core uncovery, with delays of 9.3173 to 9.606 h for the 5th percentile value, depending on the mode of deaerator pressurization (1,000 samples for each mode). Finally, a sensitivity analysis with both local and global methods indicated that the initial water level in the deaerator is the most critical parameter affecting the time to reactor core uncovery.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111370"},"PeriodicalIF":1.9,"publicationDate":"2025-03-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143632070","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}