Nuclear Engineering and Technology最新文献

Dual-purpose borate based glasses: optical features and Monte Carlo simulations of gamma radiation shielding 双用途硼酸盐基玻璃：伽马辐射屏蔽的光学特性和蒙特卡罗模拟

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-20 DOI: 10.1016/j.net.2025.103752

M.I. Sayyed , K.A. Mahmoud , Shrikant Biradar , U. Rilwan , Laith Ahmed Najam

{"title":"Dual-purpose borate based glasses: optical features and Monte Carlo simulations of gamma radiation shielding","authors":"M.I. Sayyed , K.A. Mahmoud , Shrikant Biradar , U. Rilwan , Laith Ahmed Najam","doi":"10.1016/j.net.2025.103752","DOIUrl":"10.1016/j.net.2025.103752","url":null,"abstract":"<div><div>The study uses the melt quenching method for fabrication of a new series of borate based glasses according to the chemical formula of (9+x) PbO<sub>2</sub>+20 BaO+11 CaO+ (60-x-y-z) B<sub>2</sub>O<sub>3</sub>+y Eu<sub>2</sub>O<sub>3</sub>+z Pr<sub>6</sub>O<sub>11</sub>; x = 0, 3, 6, and 9 mol% and y = z = 0.25, 0.5, 0.75, and 1 mol%. The aforementioned borate-based glass series is being fabricated with the dual purpose of serving as radiation shielding and optical materials. The substitution of PbO<sub>2</sub>, Eu<sub>2</sub>O<sub>3</sub>, and Pr<sub>6</sub>O<sub>11</sub> for the B<sub>2</sub>O<sub>3</sub> enhances the density of fabricated glasses (4.023–4.680 g/cm<sup>3</sup>) when the PbO<sub>2</sub>+Eu<sub>2</sub>O<sub>3</sub>+Pr<sub>6</sub>O<sub>11</sub> raised from concentrations of 9.5 mol% to 20 mol%. Increase in concentration of PbO<sub>2</sub>+Eu<sub>2</sub>O<sub>3</sub>+Pr<sub>6</sub>O<sub>11</sub> (9.5–20 mol.%) causes decrease in the energy band gap (direct transition) from 3.080 to 2.964 eV. The refractive index was enhanced (2.486–2.529) when the doping compounds were raised within the prepared glasses. The Monte Carlo simulation results over energy interval of 0.015–15 MeV showed that, increase in concentration of PbO<sub>2</sub>+Eu<sub>2</sub>O<sub>3</sub>+Pr<sub>6</sub>O<sub>11</sub> (9.5–20 mol%) enhances the LAC values from 6.899 to 9.690 cm<sup>−1</sup> (at 0.08 MeV), 0.248–0.293 cm<sup>−1</sup> (at 1 MeV), and 0.134–0.178 cm<sup>−1</sup> (at 15 MeV).</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103752"},"PeriodicalIF":2.6,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144322604","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}

引用次数: 0

Uncertainty quantification of steady state depeltion solution using multi-physics coupling code system based on nodal diffusion code RAST-K 基于节点扩散码RAST-K的多物理场耦合码系统对稳态耗尽解的不确定性量化

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-13 DOI: 10.1016/j.net.2025.103751

Jinsu Park , Yeongseok Kang , Deokjung Lee

{"title":"Uncertainty quantification of steady state depeltion solution using multi-physics coupling code system based on nodal diffusion code RAST-K","authors":"Jinsu Park , Yeongseok Kang , Deokjung Lee","doi":"10.1016/j.net.2025.103751","DOIUrl":"10.1016/j.net.2025.103751","url":null,"abstract":"<div><div>This study presents the uncertainty quantification results of steady-state depletion simulations using a multi-physics coupling framework based on the nodal diffusion code RAST-K. Developed for the analysis and optimization of pressurized water reactors, RAST-K integrates advanced methodologies and diverse engineering capabilities, consistently demonstrating strong agreement with measured data and commercial nuclear design codes. High-fidelity core simulations are conducted through the multi-physics coupling of RAST-K with the subchannel thermal-hydraulic code CTF and the fuel performance code FRAPCON. Notably, the consideration of dynamic gap conductance and thermal conductivity degradation in fuel performance calculations highlights discrepancies in pin-wise fuel temperature predictions. Uncertainty quantification is performed using stochastic sampling methods by perturbing both input parameters and nuclear data. The results indicate that uncertainties in global reactor design parameters, such as critical boron concentration, axial shape index, and peaking factor, are primarily driven by nuclear data perturbations, while thermal-hydraulic uncertainties are influenced by both input and nuclear data variations.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103751"},"PeriodicalIF":2.6,"publicationDate":"2025-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144314443","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}

引用次数: 0

Continuous cryogenic adsorption adjustments of radon in air using carbon-based microporous adsorbents 碳基微孔吸附剂对空气中氡的连续低温吸附调节

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-12 DOI: 10.1016/j.net.2025.103704

Xu Feng , HuiJia Long , Chengtao Yue , ShouKang Qiu , Quan Tang , LongCheng Liu

{"title":"Continuous cryogenic adsorption adjustments of radon in air using carbon-based microporous adsorbents","authors":"Xu Feng , HuiJia Long , Chengtao Yue , ShouKang Qiu , Quan Tang , LongCheng Liu","doi":"10.1016/j.net.2025.103704","DOIUrl":"10.1016/j.net.2025.103704","url":null,"abstract":"<div><div>In underground low-background laboratories (LRBL), minimizing radon concentration is crucial. This study developed a cryogenic Rn adsorption system, which operated for more than 5 h at a flow rate of 60 L/min. The dynamic adsorption coefficients (<span><math><mrow><msub><mi>K</mi><mi>d</mi></msub></mrow></math></span>) of Rn on four carbon-based adsorbents were measured at 293 K, 243 K and 223 K. Combined with the results of N<sub>2</sub>-adsorption and desorption,XPS, FTIR and SEM test results indicated that the larger the micropore volume within the 0.5–0.7 nm range, the higher the the <span><math><mrow><msub><mi>K</mi><mi>d</mi></msub></mrow></math></span> of Rn adsorption of the adsorbent, and this difference becomes more obvious with the decrease of adsorption temperature. CarbosieveS-III exhibited the highest <span><math><mrow><msub><mi>K</mi><mi>d</mi></msub></mrow></math></span> at 223 K (436 L/g). Adsorption penetration curves of each component of Rn-containing air on activated carbon were measured using an infrared gas analyzer and a RAD7 radon meter. The CO<sub>2</sub> concentration gradient was adjusted, and the <span><math><mrow><msub><mi>K</mi><mi>d</mi></msub></mrow></math></span> of all adsorbents (including reduced carbon molecular sieves) were measured. Experimental results revealed that CO<sub>2</sub> acts as the dominant competitive adsorbate for radon capture when water vapor interference was eliminated.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103704"},"PeriodicalIF":2.6,"publicationDate":"2025-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144270833","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}

引用次数: 0

In-Situ Diagnosis of Heat Loads on Divertor Tungsten Targets Using Laser Speckle Digital Image Correlation 利用激光散斑数字图像相关技术对导流钨靶热负荷进行原位诊断

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-11 DOI: 10.1016/j.net.2025.103748

Zhang Dale , Jiang Menglai , Li Ledi , He Shengnan , Li Hang , Pan Zhiwei , Huang Shenghong , W.A.N.G. Weihua , Su Yong

{"title":"In-Situ Diagnosis of Heat Loads on Divertor Tungsten Targets Using Laser Speckle Digital Image Correlation","authors":"Zhang Dale , Jiang Menglai , Li Ledi , He Shengnan , Li Hang , Pan Zhiwei , Huang Shenghong , W.A.N.G. Weihua , Su Yong","doi":"10.1016/j.net.2025.103748","DOIUrl":"10.1016/j.net.2025.103748","url":null,"abstract":"<div><div>Based on a high heat flux (∼300MW) comprehensive experimental platform, this study used the laser speckle digital image correlation (LS-DIC) method to measure the thermal strain of the tungsten target plates from 190°C–2952°C, that was used to invert the temperature field distribution and heat loads of the target plates, realizing the synchronous in-situ measurement of the strains, temperatures and heat loads of the tungsten target plates under extreme high temperature. By comparing with the tungsten thermal strains in literature, the average relative errors of LS-DIC measurement results in different temperature ranges are 2% within 190–1100°C and 6% within 1040–2952°C. The feasibility and accuracy of using LS-DIC to diagnose temperature field and heat loads were verified, the inversion results were compared with Ansys simulation results and actual loading data of heat loads, and the error rates of temperature and heat loads inversion were less than 6% and 7%, respectively. The LS-DIC method proposed in this study is expected to be applied to the non-contact, in-situ measurement of material strain and temperature under extreme environments as well as the inversion of heat loads.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103748"},"PeriodicalIF":2.6,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144322682","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}

引用次数: 0

Radiological safety assessment for water treatment facility due to radon inhalation in Korea 韩国水处理设施吸入氡的放射性安全评价

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-11 DOI: 10.1016/j.net.2025.103727

Seung Beom Yoo, Shin Dong Lee, Jeong Woo Lee, Chang Hee Han, Kwang Pyo Kim

{"title":"Radiological safety assessment for water treatment facility due to radon inhalation in Korea","authors":"Seung Beom Yoo, Shin Dong Lee, Jeong Woo Lee, Chang Hee Han, Kwang Pyo Kim","doi":"10.1016/j.net.2025.103727","DOIUrl":"10.1016/j.net.2025.103727","url":null,"abstract":"<div><div>Water treatment facilities are facilities that use groundwater to produce potable water. Groundwater can contain radon which is a naturally occurring radionuclide, and water treatment facility workers who directly handle groundwater are at risk of internal exposure from radon inhalation. The objective of this study is to assess the internal radiation dose from radon inhalation in water treatment facility workers in Korea. To achieve this, we analyzed work processes in 6 water treatment facilities in Korea, and main process areas were investigated through interviews with workers. The airborne radon concentration was measured in the main process areas using the RAD 7 and Raduet radon detector. Radon concentrations measured in the main process areas ranged from 16.6 to 756 Bq m<sup>−3</sup>, which is below the ICRP's reference level of 1,000 Bq m<sup>−3</sup>. The internal radiation dose due to radon inhalation ranged from 0.193 to 5.80 mSv y<sup>−1</sup>. This is about half of the ICRP's reference level of 10 mSv y<sup>−1</sup> for radon inhalation. This study can be used as technical data for radiological safety management of NORM industries in Korea.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103727"},"PeriodicalIF":2.6,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144263785","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}

引用次数: 0

An experimental approach to the calculate of air-to-water dose ratio in Tehran Research Reactor (TRR) spent fuel using TL dosimeter 用TL剂量计计算德黑兰研究堆（TRR）乏燃料空气水剂量比的实验方法

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-11 DOI: 10.1016/j.net.2025.103728

R. Adeli

{"title":"An experimental approach to the calculate of air-to-water dose ratio in Tehran Research Reactor (TRR) spent fuel using TL dosimeter","authors":"R. Adeli","doi":"10.1016/j.net.2025.103728","DOIUrl":"10.1016/j.net.2025.103728","url":null,"abstract":"<div><div>The Tehran Research Reactor (TRR) is a reliable neutron source in Iran. Dealing with the spent fuel (SF) is one of the most challenging issues in the peaceful use of nuclear technology, both in protecting the public and the environment from the hazardous effects of ionization radiation.</div><div>In this experimental research work the GR-200 as a thermoluminescence-dosimeter (TLD) was used for measuring the dose rate of this high dose rate item in water and air environments. To overcome the challenge of air dose assessment, a waterproof polymer tube was designed and placed in front of a low burn-up SF. Also, a thick stainless steel slab was fabricated to both immerse the dry channel in water and prevent the TLD saturation. The distances of 20, 50 and 100 cm were considered to measure the dose rate in the air and the distances of 10, 20 and 50 cm were chosen to measure the dose rate in the water environment. Accordingly, the air-to-water dose rate ratio (100 cm of air and 20 cm of water) is 0.11. The obtained dose rate ratios matrix at different distances in these two environments will enable us to measure the dose rate in water and then calculate the dose rate in air without any direct measurement.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103728"},"PeriodicalIF":2.6,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144263786","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}

引用次数: 0

Influence of oversized atoms X = Ti, Ta, W, Mo on the dynamics of native defects under annealing in Fe35Cr35V20Cu5-(X) HEA studied by positron annihilation spectroscopy (PAS) 正电子湮没光谱（PAS）研究了超大原子X = Ti, Ta， W， Mo对Fe35Cr35V20Cu5-(X) HEA退火过程中缺陷动力学的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-10 DOI: 10.1016/j.net.2025.103743

R. Domínguez-Reyes , M.A. Monge , A. Rodríguez-López , Y. Ortega , B. Savoini

{"title":"Influence of oversized atoms X = Ti, Ta, W, Mo on the dynamics of native defects under annealing in Fe35Cr35V20Cu5-(X) HEA studied by positron annihilation spectroscopy (PAS)","authors":"R. Domínguez-Reyes , M.A. Monge , A. Rodríguez-López , Y. Ortega , B. Savoini","doi":"10.1016/j.net.2025.103743","DOIUrl":"10.1016/j.net.2025.103743","url":null,"abstract":"<div><div>The dynamics of native defects in the high entropy alloy family produced by arc melting Cu<sub>5</sub>Cr<sub>35</sub>Fe<sub>35</sub>V<sub>20</sub>X<sub>5</sub> (at. %), where X = Ti, Ta, W or Mo corresponds to oversized atoms, were studied using positron annihilation lifetime spectroscopy (PALS) and coincidence Doppler broadening (CDB) spectroscopy. Isochronal annealing from room temperature (RT) to 900 °C revealed three stages common to all HEAs. The first stage (RT- 300 °C) corresponds to the stabilization of the native defects. This is followed by a second recovery stage (400–600 °C, or 700 °C for W-containing HEAs), involving the onset of diffusion and recombination of the defects. The final stage, up to the upper annealing temperature, is characterized by the interaction of the thermal vacancies produced during isochronal annealing with the precipitates. Cu precipitation, driven by its high mixing enthalpy with Fe and Cr, dominates the chemical environment of positron annihilation sites initially and, later, by the coarsening of the Cu precipitates at high temperatures. Oversized atoms like Ti and Ta suppress void growth, as revealed by combining PAS results with microstructural analysis. These results provide insights into defect behavior and stability in HEAs, emphasizing the role of oversized atoms in enhancing resistance to void growth.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103743"},"PeriodicalIF":2.6,"publicationDate":"2025-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144322603","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}

引用次数: 0

Study on the performance of membrane reactor using steam methane reforming for hydrogen production heated by HTGR HTGR加热蒸汽甲烷重整制氢膜反应器性能研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-10 DOI: 10.1016/j.net.2025.103744

Chengye Wu, Baozhi Wu, Huang Zhang, Huaqiang Yin

{"title":"Study on the performance of membrane reactor using steam methane reforming for hydrogen production heated by HTGR","authors":"Chengye Wu, Baozhi Wu, Huang Zhang, Huaqiang Yin","doi":"10.1016/j.net.2025.103744","DOIUrl":"10.1016/j.net.2025.103744","url":null,"abstract":"<div><div>Using High-Temperature Gas-cooled Reactor (HTGR) for hydrogen production through steam methane reforming (SMR) offers advantages such as high hydrogen yield, methane savings, relatively low cost, and ease of scale-up. However, due to the limitation of the temperature of the heating helium gas, the methane conversion ratio of SMR using HTGR is much lower than that of traditional SMR. The membrane reactor (MR), with its high conversion efficiency, compact structure, and low cost, is a suitable way to improve the methane conversion ratio. This study establishes a one-dimensional reaction flow model for MR heated by the helium gas from HTGR. And the model is validated and applied to analyze the performance of MR. The results show that, compared to the original reformer tube, MR demonstrates superior performance, especially at higher methane conversion ratio and hydrogen yield. And the significant impact of sweep gas and membrane thickness on the performance of MR is discussed in detail. This work offers a new insight into highly enhancing the efficiency of SMR for hydrogen production using HTGR.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103744"},"PeriodicalIF":2.6,"publicationDate":"2025-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144314444","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}

引用次数: 0

Investigations on effect of primary mass flow change rate on flow instability among parallel U-tubes of steam generator 一次质量流量变化率对蒸汽发生器并联u型管流动不稳定性影响的研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-09 DOI: 10.1016/j.net.2025.103747

Jianli Hao , Wenzhen Chen , Houqi Lv , Junjie Ma , Yanping Huang , Lei Yu

引用次数: 0

Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system 新型mw级紧凑型核电系统被动余热排出系统的设计与分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-09 DOI: 10.1016/j.net.2025.103746

Leqi Yuan, Junli Gou, Zhenlan Wang, Bo Zhang, Jianqiang Shan

{"title":"Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system","authors":"Leqi Yuan, Junli Gou, Zhenlan Wang, Bo Zhang, Jianqiang Shan","doi":"10.1016/j.net.2025.103746","DOIUrl":"10.1016/j.net.2025.103746","url":null,"abstract":"<div><div>The heat pipe-cooled reactor is an ideal power source for unmanned underwater vehicles (UUVs) due to its compact design, simple structure, and high safety features. However, a heat sink loss accident may lead to reactor damage, requiring a passive residual heat removal system (PRHRS) for emergency cooling. This study presents a novel compact heat pipe reactor with a PRHRS that uses natural circulation to cool the heat pipes' adiabatic sections. A steady-state CFD simulation optimized the geometry, and a transient analysis code was developed in FORTRAN and validated with CFD results. The findings show a sharp increase in fuel temperature immediately after the accident, followed by a decrease as natural circulation cools the reactor. Throughout the accident, component temperatures stayed within permissible limits, with the maximum fuel and heat pipe temperatures not exceeding 965.13 K and 972.5 K, respectively. No boiling occurred in the PRHRS cooling water. This confirms that the PRHRS effectively removes residual heat, ensuring reactor safety during both steady-state and accident conditions, and lays the groundwork for the design of new MW-class compact heat pipe reactors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103746"},"PeriodicalIF":2.6,"publicationDate":"2025-06-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144280584","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}

引用次数: 0