Nuclear Engineering and Technology最新文献_第4页

Analytical derivation of steady-state delayed neutron precursor distribution and effective delayed neutron fraction in a molten salt reactor 熔盐堆中稳态延迟中子前体分布和有效延迟中子分数的解析推导

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-23 DOI: 10.1016/j.net.2026.104160

Jae Jun Jeong , Yun Je Cho

In liquid-fueled molten salt reactors (MSRs), the nuclear fuel is dissolved in a molten salt mixture that circulates through the primary loop. For system-scale simulations of MSRs, a point kinetics model (PKM) is commonly employed to describe the core neutronic behavior. In this model, flow-related terms are added to the delayed neutron precursor (DNP) balance equation by simplifying the reactor system into two lumped regions - a reactor core and an external loop. This simplified approach is, however, inadequate for a realistic MSR system with complex flow paths. To overcome this limitation, a DNP transport equation can be incorporated into the PKM in place of the DNP balance equation, enabling a more accurate representation of the DNP distribution throughout the reactor system.

In this study, a one-dimensional thermal-hydraulic model is assumed for MSR system simulations, and the axial power distribution in the reactor core is considered to be either uniform or sinusoidal. Analytical solutions to the steady-state DNP transport equation are then derived to obtain one-dimensional DNP profiles in the core and the corresponding effective delayed neutron fraction. These analytical results can serve as reference solutions for verifying thermal-hydraulic system codes developed for MSRs.

在液体燃料熔盐反应堆（MSRs）中，核燃料溶解在通过主回路循环的熔盐混合物中。对于MSRs的系统尺度模拟，通常采用点动力学模型（PKM）来描述堆芯中子行为。在该模型中，通过将反应堆系统简化为堆芯和外环两个集总区域，将流动相关项加入到延迟中子前体（DNP）平衡方程中。然而，这种简化的方法对于具有复杂流路的实际MSR系统来说是不够的。为了克服这一限制，可以在PKM中加入DNP输运方程来代替DNP平衡方程，从而能够更准确地表示整个反应堆系统中的DNP分布。本研究采用一维热-水力模型进行MSR系统仿真，认为堆芯内的轴向功率分布为均匀分布或正弦分布。然后导出稳态DNP输运方程的解析解，得到堆芯内DNP的一维剖面和相应的有效延迟中子分数。这些分析结果可作为验证为msr开发的热液系统规范的参考解决方案。

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引用次数: 0

Neutron and γ-ray shielding properties of magnetite-serpentine concrete based on Geant4 simulation 基于Geant4模拟的磁铁矿蛇纹混凝土中子和γ射线屏蔽性能

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-12 DOI: 10.1016/j.net.2026.104127

Jun Liu , Hongfei Chen , Weizhuo Zhang , Renjie Niu , Ertao Li , Yuyang Chen

Serpentine concrete is an excellent neutron shielding material, and the addition of magnetite aggregate can enhance the γ-ray shielding performance of concrete. In this study, the Geant4 software was used to simulate and analyze five different concrete mix designs where magnetite aggregate replaced serpentine aggregate at varying concentrations. To ensure the reliability of the simulation results, the study compared them with the calculated data obtained from the Phy-X/PSD program. For both neutrons and γ-rays, several shielding parameters including linear attenuation coefficient (μ), half-value layer (HVL) and effective atomic number (Z_eff) as well as effective electron density (N_eff) were systematically calculated. Penetration rate and neutron energy spectrum analyses were also conducted. The results show that with the increase of magnetite doping, the γ-ray shielding performance of concrete is significantly enhanced, but the neutron shielding ability decreases. Based on a comprehensive evaluation of various performance indicators, the optimal proportion of magnetite aggregate was determined to be 25 %. The neutron shielding performance of this admixture is similar to that of pure serpentine concrete, while its γ-ray shielding performance is significantly improved.

蛇纹石混凝土是一种优良的中子屏蔽材料，添加磁铁矿骨料可提高混凝土的γ射线屏蔽性能。在这项研究中，使用Geant4软件模拟和分析了五种不同的混凝土配合比设计，其中磁铁矿骨料取代了不同浓度的蛇纹石骨料。为了保证仿真结果的可靠性，将仿真结果与Phy-X/PSD程序的计算数据进行了比较。对中子和γ射线进行了线性衰减系数μ、半值层HVL、有效原子序数Zeff和有效电子密度Neff等屏蔽参数的系统计算。并进行了穿透速率和中子能谱分析。结果表明：随着磁铁矿掺量的增加，混凝土的γ射线屏蔽性能显著增强，但中子屏蔽能力下降；在综合评价各项性能指标的基础上，确定磁铁矿骨料的最佳配比为25%。该掺合料对中子的屏蔽性能与纯蛇纹石混凝土相当，对γ射线的屏蔽性能有明显提高。

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引用次数: 0

Benchmark analysis of SPERT III E-core critical experiments using the STREAM neutronics code 使用STREAM中子码对SPERT III E-core临界实验进行基准分析

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2025-12-31 DOI: 10.1016/j.net.2025.104112

Anisur Rahman , Saisundar Mohanty , Deokjung Lee

This study delivers a high-fidelity neutronic analysis of the SPERT III E-Core, a pressurized-water experimental reactor designed to probe fundamental transient behavior during reactivity-initiated accidents (RIAs). Using the advanced 3D transport code STREAM, we construct a detailed full-core representation—including fuel assemblies, cruciform transient control rods, control rod followers, and flux suppressors, to simulate both steady-state operation and rapid power excursions. Eigenvalue predictions at cold and hot zero-power conditions agree with measurements within 400 pcm, while simulated RIA responses, including reactivity evolution, peak power, and energy release, remain within 10 % of experimental observations. These results demonstrate that STREAM reliably captures fast transient dynamics in complex reactor configurations. Beyond validating a modern deterministic tool against historically important pulse-reactor experiments, this work establishes a foundation for next-generation transient modeling, supporting enhanced safety assessment, performance optimization, and informed regulatory decision-making in advanced reactor systems.

这项研究提供了SPERT III E-Core的高保真中子分析，这是一种压水实验反应堆，旨在探测反应性引发事故（ria）期间的基本瞬态行为。使用先进的3D传输代码STREAM，我们构建了一个详细的全核心表示-包括燃料组件，十字形瞬态控制棒，控制棒跟随器和通量抑制器，以模拟稳态运行和快速功率漂移。冷、热零功率条件下的特征值预测与400 pcm以内的测量结果一致，而模拟的RIA响应，包括反应性演化、峰值功率和能量释放，与实验观测值的误差仍在10%以内。这些结果表明STREAM可靠地捕获了复杂反应堆结构中的快速瞬态动力学。除了通过历史上重要的脉冲反应堆实验验证现代确定性工具之外，这项工作还为下一代瞬态建模奠定了基础，支持先进反应堆系统中增强的安全评估、性能优化和知情的监管决策。

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引用次数: 0

Seismic behavior of electrical cabinets with cast-in-place anchors: influence of concrete cracks and multi-bay installation 现浇锚杆电柜抗震性能：混凝土裂缝和多槽安装的影响

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-16 DOI: 10.1016/j.net.2026.104144

Bub-Gyu Jeon , Sung-Wan Kim , Dong-Uk Park , Chae-Been Lee , DaeGi Hahm , Hong-Pyo Lee

Electrical cabinets are typically assembled in a multi-bay configuration, connecting two or more modules, and the structural implications of this setup must be carefully addressed. Concrete foundation cracks, often observed during field investigations at power plants, represent a common form of support deterioration. This study fabricated concrete foundations to simulate intact conditions and cracked conditions with 0.5 mm and 1.0 mm wide cracks at anchor locations. A simplified electrical cabinet model was constructed in single-bay, two-bay, and three-bay configurations and anchored to the concrete foundations using cast-in-place anchors to consider the effects of multi-bay configuration and support deterioration. Three-axis shaking table tests were conducted, including resonant frequency search and seismic fragility tests. The results indicated that cracks at the anchor locations can increase the uncertainty in the cabinet's resonant frequency. Specifically, when the concrete foundation was intact, seismic performance improved as the number of connected bays increased. However, cracks up to 1.0 mm in width degraded the seismic performance of multi-bay configurations but had a negligible impact on the single-bay cabinet. Moreover, distinct damage modes were observed between single-bay and multi-bay conditions.

电柜通常以多机柜配置组装，连接两个或更多模块，必须仔细处理这种设置的结构含义。在电厂现场调查中经常观察到混凝土基础裂缝，这是一种常见的支护劣化形式。本研究制作混凝土基础，模拟锚固位置0.5 mm和1.0 mm宽裂缝的完整条件和开裂条件。建立了简化的电柜模型，分为单仓、双仓和三仓三种构型，考虑多仓构型和支座劣化的影响，采用现浇锚杆将电柜锚固在混凝土基础上。进行了三轴振动台试验，包括共振频率搜索和地震易损性试验。结果表明，锚固位置的裂缝会增加箱体谐振频率的不确定性。具体而言，在混凝土基础完整的情况下，随着连接槽数量的增加，抗震性能有所提高。然而，宽度为1.0 mm的裂缝会降低多机柜的抗震性能，但对单机柜的影响可以忽略不计。此外，在单舱和多舱条件下观察到不同的损伤模式。

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引用次数: 0

Development of frictional pressure drop models for single- and two-phase flows in a helically coiled tube 螺旋管内单相和两相流动摩擦压降模型的建立

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-12 DOI: 10.1016/j.net.2026.104134

Oktari Zaidi, Byong Jo Yun, Jae Jun Jeong

Helically coiled tubes (HCTs) are widely employed in small modular reactors (SMRs), due to their compact geometry and superior heat transfer performance. Accurate prediction of frictional pressure drop for single-phase and two-phase flows in HCTs is crucial for the design and safety analysis of SMRs. In this study, the characteristics of frictional pressure drop in HCTs were investigated using an experimental database comprising 1489 single-phase and 876 two-phase data points. A systematic physics-based model development framework was applied, including key parameters identification and statistically supported modeling to ensure the significance and independence of all selected parameters. Through this, dominant factors influencing frictional pressure drop in HCTs were determined. It was found that, in addition to the well-known flow variables, centrifugal force induced by main axial flow has a significant impact on pressure drop. Based on the finding, new empirical correlations were developed by explicitly incorporating a dimensionless centrifugal force number. The final formulation is designed to preserve asymptotic consistency with straight tube when the curvature effect vanishes. Assessment results indicate that the proposed correlations reduce the root mean square errors by 7.0 %, 9.1 %, and 15.0 %, respectively, compared to the best-performing existing models for single-phase laminar, single-phase turbulent, and two-phase flows.

螺旋盘管（hct）由于其紧凑的几何结构和优越的传热性能而广泛应用于小型模块化反应器（smr）中。准确预测高压混凝土中单相流和两相流的摩擦压降对小型反应器的设计和安全性分析至关重要。在这项研究中，使用包含1489个单相和876个两相数据点的实验数据库研究了hct的摩擦压降特性。采用了系统的基于物理的模型开发框架，包括关键参数识别和统计支持建模，以确保所选参数的重要性和独立性。由此确定了影响hct摩擦压降的主要因素。研究发现，除了众所周知的流量变量外，主轴流引起的离心力对压降也有显著的影响。基于这一发现，通过明确地纳入无量纲离心力数，开发了新的经验相关性。最后的公式被设计成在曲率效应消失时与直管保持渐近一致性。评估结果表明，与现有的单相层流、单相湍流和两相流的最佳模型相比，所提出的相关性分别将均方根误差降低了7.0%、9.1%和15.0%。

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引用次数: 0

A variable universe fuzzy control method for the HCOTSG feedwater system of small pressurized water reactor 小型压水堆HCOTSG给水系统的变域模糊控制方法

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-05 DOI: 10.1016/j.net.2026.104116

Zhihui Yan , Xuan She , Shijia Yang , Wenjie Zeng , Zhifeng Li

Helical-Coil Once-Through Steam Generator (HCOTSG) is a key energy conversion component in the secondary circuit system of Small Pressurized Water Reactor (SPWR), exhibiting lower heat storage capacity and great difficulty in steam pressure regulation. The traditional fuzzy control method adopts a fixed domain of discourse, which has limited adaptability under load change conditions, and it is difficult to meet the requirements of HCOTSG for high precision control. Therefore, this paper proposes a variable universe fuzzy control (VUFC) method for the HCOTSG feedwater system, with the nonlinear mathematical model of the secondary circuit, the real-time adjustment domain of the scaling factor based on fuzzy rules is used to realize the online adaptive control of HCOTSG feedwater system. Simulation results of the SPWR under step load changes show that the VUFC offers faster response speed, smaller overshoot and stronger robustness than traditional fuzzy control, which mitigates the impacts of steam pressure on secondary circuit equipment and improves the operation safety of SPWR.

螺旋盘管式蒸汽发生器（HCOTSG）是小型压水堆（SPWR）二次回路系统中关键的能量转换部件，其蓄热能力较低，蒸汽压力调节难度较大。传统的模糊控制方法采用固定的话语域，对负载变化条件的适应性有限，难以满足HCOTSG高精度控制的要求。为此，本文提出了一种HCOTSG给水系统的变域模糊控制（VUFC）方法，结合二次回路的非线性数学模型，利用基于模糊规则的比例因子实时调整域，实现了HCOTSG给水系统的在线自适应控制。负荷阶跃变化下的SPWR仿真结果表明，与传统模糊控制相比，VUFC具有更快的响应速度、更小的超调量和更强的鲁棒性，减轻了蒸汽压力对二次回路设备的影响，提高了SPWR的运行安全性。

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引用次数: 0

Long-term corrosion behavior of a cold-spray copper-SiC composite coating for spent nuclear fuel disposal canisters 废核燃料处理罐用冷喷涂铜-碳化硅复合涂层的长期腐蚀行为

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-23 DOI: 10.1016/j.net.2026.104159

Minsoo Lee, Junhyuk Jang, Nakkyu Chae, Jin Seop Kim

A novel copper-silicon carbide (Cu-SiC) metal matrix composite (MMC) was fabricated using cold spray coating and evaluated as a corrosion-resistant barrier for spent nuclear fuel disposal canisters. The Cu-SiC MMC exhibited superior properties compared to pure copper, including reduced oxygen content and a more noble corrosion potential. To assess its long-term performance, a 3690-day corrosion test was conducted under simulated deep geological conditions at the KAERI Underground Research Tunnel (KURT), while embedded in Ca-type bentonite and exposed to 70 °C aerobic groundwater. After over a decade, the Cu-SiC MMC showed an average corrosion depth of only 4.02 ± 1.72 μm. The corrosion kinetics followed a distinct “S-shaped” pattern, attributed to long-term changes at the bentonite-copper interface. Post-test characterization, including surface profilometry and FIB-SEM analysis, confirmed that the chemically inert SiC particles effectively acted as a physical barrier, significantly reducing corrosion penetration. These findings demonstrate the excellent durability and corrosion resistance of Cu-SiC MMC, validating its potential for enhancing the long-term integrity of nuclear waste disposal canisters.

采用冷喷涂技术制备了一种新型的Cu-SiC金属基复合材料（MMC），并对其作为乏燃料处理罐的耐腐蚀屏障进行了评价。与纯铜相比，Cu-SiC MMC表现出更优越的性能，包括氧含量降低和更高贵的腐蚀电位。为了评估其长期性能，在KAERI地下研究隧道（KURT）的模拟深层地质条件下进行了3690天的腐蚀测试，同时埋在ca型膨润土中，暴露于70°C的好氧地下水中。10多年后，Cu-SiC MMC的平均腐蚀深度仅为4.02±1.72 μm。腐蚀动力学遵循明显的“s”型模式，归因于膨润土-铜界面的长期变化。测试后的表征，包括表面轮廓分析和FIB-SEM分析，证实了化学惰性的SiC颗粒有效地起到了物理屏障的作用，显著降低了腐蚀渗透。这些发现证明了Cu-SiC MMC优异的耐久性和耐腐蚀性，验证了其提高核废料处理罐长期完整性的潜力。

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引用次数: 0

Enhancing quality control in radiography systems through automated algorithms 透过自动演算法，加强射线照相系统的品质控制

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-22 DOI: 10.1016/j.net.2026.104156

Herdi Firdaus Jamal , Mohammad Wasef Marashdeh , Muhammad Kabir Abdulkadir , Mohd Ilyas Sazali , Hanan Fawaz Akhdar , Muhamad Zabidi Ahmad , Mohd Zahri Abdul Aziz

Quality control (QC) in radiography systems is essential for ensuring imaging accuracy and radiation safety. Traditional QC methods are time-consuming and prone to human error. Automated algorithms offer a potential solution by streamlining QC assessments. The aim of this study was to develop and evaluate the performance of an automated QC algorithm tailored for radiography systems in accordance with Malaysian regulatory requirements by comparing its efficiency, accuracy, and reliability against manual methods. QC algorithms were developed using Microsoft Excel for a comprehensive list of QC tests delineated by the Ministry of Health, Malaysia. These algorithms were designed to automate the input of measured data, execute necessary calculations, and deliver a pass/fail outcome based on established regulatory criteria. The performance of the algorithms was evaluated through data collected from 100 radiography machines across various locations and models. The study compared the time efficiency, accuracy and errors of algorithm-based QC assessments and manual calculations. The algorithm significantly (p < 0.001) reduced QC assessments time by 90 % and eliminated all calculation errors, outperforming manual assessments that occurred 64 times. This is the first Excel-based QC algorithm validated against Malaysian regulations, providing low-cost alternative to commercial systems.

射线照相系统的质量控制（QC）对于确保成像精度和辐射安全至关重要。传统的质量控制方法耗时长，容易出现人为错误。自动化算法通过简化QC评估提供了一个潜在的解决方案。本研究的目的是根据马来西亚的监管要求，通过将其效率、准确性和可靠性与手动方法进行比较，开发和评估为放射照相系统量身定制的自动QC算法的性能。QC算法是使用Microsoft Excel开发的，用于马来西亚卫生部划定的QC测试的综合清单。这些算法旨在自动输入测量数据，执行必要的计算，并根据既定的监管标准提供合格/不合格的结果。通过从不同地点和型号的100台x光机收集的数据来评估算法的性能。该研究比较了基于算法的QC评估和人工计算的时间效率、准确性和误差。该算法显著（p < 0.001）减少了90%的QC评估时间，消除了所有的计算错误，优于64次的人工评估。这是第一个根据马来西亚法规验证的基于excel的QC算法，为商用系统提供了低成本的替代方案。

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引用次数: 0

Tracking simulation of third-integer resonant extraction for Fermilab’s Mu2e experiment Fermilab Mu2e实验中第三整数共振提取的跟踪仿真

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2025-12-31 DOI: 10.1016/j.net.2025.104097

Chong Shik Park

The Mu2e experiment at Fermilab requires acceleration and transport of intense proton beams in order to deliver stable, uniform particle spills to the production target. To meet the experimental requirement, particles will be extracted slowly from the Delivery Ring to the external beamline. Using Synergia2, we have performed multi-particle tracking simulations of third-integer resonant extraction in the Delivery Ring, including space charge effects, physical beamline elements, and apertures. A piecewise linear ramp profile of tune quadrupoles was used to maintain a constant averaged spill rate throughout extraction. To study and minimize beam losses, we implemented and introduced a number of features, beamline element apertures, and septum plane alignments. Dynamic bumps are also implemented for local orbit corrections in which septum entrance angles are controlled to reduce angular spreads of extracted beams.

费米实验室的Mu2e实验需要加速和传输强质子束，以便向生产目标提供稳定、均匀的粒子泄漏。为了满足实验要求，粒子将从输送环缓慢地提取到外部光束线。利用协同效应a2，我们在传递环中进行了第三整数共振提取的多粒子跟踪模拟，包括空间电荷效应、物理光束线元素和孔径。在整个提取过程中，采用分段线性四极斜坡剖面来保持恒定的平均泄漏率。为了研究和最小化光束损耗，我们实现并引入了许多功能，光束线元件孔径和隔膜平面对齐。动态颠簸也实现了局部轨道修正，其中隔膜入口角被控制，以减少提取光束的角扩散。

引用次数: 0

Preparation and characterization of metakaolin-based Ag0-containing sorbent beads for iodine capture 偏高岭土基含ag0吸附珠的制备及性能研究

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-19 DOI: 10.1016/j.net.2026.104149

Jae Won Lee, Byoungjin So, Seok-Min Hong, Namcheol Kim, Ju Ho Lee, Yung Zun Cho, Chang Hwa Lee

We report metakaolin (MK)-based sorbents with high metallic silver(Ag⁰) content for maximizing iodine uptake per unit volume. Spherical beads were fabricated by a droplet method using slurries with various Na/M (M = Na + Al + Si) and H₂O/Na₂O molar ratios. Subsequent Ag/Na ion exchange and thermal reduction produced Ag⁰-loaded beads with a dense outer layer and porous core. Increasing the Na/M ratio enhanced the maximum silver loading, total iodine capture capacity, and packing density, while the crushing strength decreased with increasing Na/M and H₂O/Na₂O ratios. The resulting Ag⁰MK sorbents exhibited pore sizes larger than the kinetic diameters of relevant iodine species (I₂, HI, CH₃I). As a result, their gravimetric iodine uptake reached 0.612 g-I/g-sorbent, demonstrating high efficiency. These findings suggest that Ag⁰MK sorbents are highly effective for iodine capture and hold strong potential for application in off-gas treatment in nuclear fuel reprocessing and reactor systems.

我们报道了高金属银（Ag0）含量的偏高岭土（MK）基吸附剂，可以最大限度地提高单位体积的碘吸收率。采用不同Na/M （M = Na + Al + Si）和H2O/Na2O摩尔比的浆料，采用液滴法制备了球形微球。随后的Ag/Na离子交换和热还原产生了具有致密外层和多孔核的ag0负载珠。增大Na/M比可提高最大载银量、总碘捕获能力和堆积密度，但破碎强度随Na/M比和H2O/Na2O比的增大而降低。所得Ag0MK吸附剂的孔径大于相关碘（I2， HI, CH3I）的动力学直径。吸附剂的重量碘吸收量达到0.612 g-I/g，吸附剂的吸收率较高。这些发现表明Ag0MK吸附剂对碘的捕获非常有效，在核燃料后处理和反应堆系统的废气处理中具有很大的应用潜力。

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引用次数: 0