Nuclear Engineering and Technology最新文献

Electrorefining of HANA-4 cladding scrap in LiCl-KCl salts for volumetric decontamination of irradiated cladding containing Nb-94 含Nb-94辐照包层体积净化用氯化氯化钾电解提纯HANA-4包层废料

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

Nuclear Engineering and Technology

Pub Date : 2026-07-01 Epub Date: 2026-03-07 DOI: 10.1016/j.net.2026.104252

Sungjune Sohn , Jungho Hur , Jaeyeong Park , Pyeonghwa Kim , Il Soon Hwang

Nb-94, an activation product in irradiated cladding, is a major concern in geological disposal. As Nb-94 is distributed throughout the cladding, volumetric decontamination should be applied for separation between Zr and Nb. In this study, the radiological characteristics of irradiated HANA-4 cladding were investigated using the ORIGEN-ARP code to derive a decontamination factor for Nb-94, 11. The electrochemical behavior of Nb was evaluated by cyclic voltammetry using low NbCl₅ concentrations (0.15 and 0.5 wt %) in LiCl-KCl at 773 K. Nb exhibits complex redox behaviors, but it was found that the nobler tendency could be utilized for Zr electrorefining. Two electrorefining tests were performed by applying constant potentials of −0.85 V and −1.2 V (vs. Ag/AgCl 1 wt %) at the anode and cathode, respectively. From the anodic test, Zr metal was obtained at the bottom of the salt, by two-step reactions among Zr⁴⁺, Zr²⁺, and Zr. Meanwhile, ZrCl and Zr were co-recovered as deposits in the cathodic test. The results revealed good separation performance between Zr and Nb. The Nb concentrations were 2.1 and 20.3 ppm in the products from the anodic and cathodic tests, respectively, supporting the feasibility of satisfying the radioactivity concentration limits of the Gyeongju Disposal Facility.

铌-94是辐照覆层中的一种活化产物，是地质处置中的一个重要问题。由于Nb-94分布在整个包层中，Zr和Nb之间的分离应采用体积净化。在这项研究中，使用ORIGEN-ARP代码研究辐照HANA-4包层的放射学特性，以得出nb - 94,11的去污因子。在773 K时，采用低NbCl5浓度（0.15 wt %和0.5 wt %）的LiCl-KCl，用循环伏安法评价Nb的电化学行为。Nb表现出复杂的氧化还原行为，但发现更优的倾向可以用于Zr电精炼。在阳极和阴极分别施加- 0.85 V和- 1.2 V （vs. Ag/AgCl 1 wt %）的恒定电位进行了两次电精炼试验。在阳极试验中，通过Zr4+、Zr2+和Zr的两步反应，在盐的底部得到金属Zr。同时，在阴极试验中，ZrCl和Zr作为沉积物被共回收。结果表明，Zr和Nb具有良好的分离性能。在阳极和阴极试验的产物中，铌的浓度分别为2.1 ppm和20.3 ppm，证明了满足庆州处理设施放射性浓度限值的可行性。

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引用次数: 0

A CFD SSTk−ω−kθ−εθ four parameter heat transfer turbulence model for the 19-pin fuel assembly in LBE cooled reactors LBE冷却堆19针燃料组件的SSTk−ω−kθ−εθ四参数传热湍流模型

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

Nuclear Engineering and Technology

Pub Date : 2026-07-01 Epub Date: 2026-03-10 DOI: 10.1016/j.net.2026.104253

YaoDi Li , Mei Huang , Yiyuan Du , Shiju Jin

Liquid lead-bismuth eutectic (LBE) alloy exhibits excellent thermo-hydraulic properties and chemical inertness as a coolant for fast reactors. Unlike conventional fluids such as water and air, LBE has a lower Prandtl number (

\Pr

), and its local turbulent Prandtl number (

\Pr_{t}

) is nonlinear. Therefore, the constant turbulent Prandtl number is difficult to satisfy complex turbulent heat transfer calculations. Thus, developing a high-precision

k_{θ} - ε_{θ}

two parameter turbulent heat transfer model for lead bismuth alloys has significant engineering value. This study systematically derives the

S S T k - ω - k_{θ} - ε_{θ}

four parameter turbulence heat transfer model and its boundary conditions under constant heat flux boundary. Based on the open source CFD software OpenFOAM, a four parameter heat transfer turbulence solver named LBEHMTFoam is developed to enhance the prediction accuracy of turbulent heat and mass transfer in liquid lead-bismuth alloys. The accuracy of the model is validated by comparing the simulation results of planar flow heat transfer with direct numerical simulation (DNS) data. Furthermore, heat and mass transfer simulations are conducted for LBE fuel assemblies and compared with empirical correlations. This study provides an effective tool for accurately predicting the thermo-hydraulic coupled corrosion behavior in LBE systems and holds significant reference value.

液态铅铋共晶（LBE）合金作为快堆冷却剂具有优良的热工性能和化学惰性。与水和空气等常规流体不同，LBE具有较低的普朗特数（Pr），其局部湍流普朗特数（Prt）是非线性的。因此，恒定的湍流普朗特数很难满足复杂的湍流换热计算。因此，建立高精度的kθ−εθ双参数铅铋合金湍流传热模型具有重要的工程价值。本文系统地推导了SSTk−ω−kθ−εθ四参数湍流换热模型及其在恒热流密度边界下的边界条件。基于开源CFD软件OpenFOAM，开发了四参数传热湍流求解器LBEHMTFoam，提高了液态铅铋合金湍流传热传质的预测精度。通过将平面流动换热模拟结果与直接数值模拟（DNS）数据进行比较，验证了模型的准确性。此外，对LBE燃料组件进行了传热传质模拟，并与经验相关性进行了比较。该研究为准确预测LBE体系热-液耦合腐蚀行为提供了有效工具，具有重要的参考价值。

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引用次数: 0

Influence of double-beam design on nuclear waste transmutation performance for CiADS-like reactor 双束设计对类ciads反应堆核废料嬗变性能的影响

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

Nuclear Engineering and Technology

Pub Date : 2026-07-01 Epub Date: 2026-03-05 DOI: 10.1016/j.net.2026.104246

Tiqi Chen , JiaLi Huang , Hui Guo , Long Zhu , Shaojun Yan , Yanjun Chen , Leyi Wu , Jun Su

This study establishes neutronics models of both single-beam and double-beam driven ADS subcritical reactors based on the CiADS core geometry using the OpenMC code, systematically comparing their performance in terms of power distribution, neutron flux, transmutation of long-lived fission products (LLFPs), and breeding of plutonium. Comparison shows that the discrepancy in the effective neutron multiplication factor between the model and reference results is within

\pm

0.003, and the neutron energy spectra agree well in the range of

1 0^{- 4} MeV

to 10 MeV. The results indicate that the double-beam design significantly improves the axial power distribution uniformity, with the full width at half maximum increasing from 58.8 cm in the single-beam system to 60.5 cm in the double-beam system, along with a general increase in neutron flux within fuel assemblies. Regarding transmutation performance, the double-beam system enhances the transmutation rate of ¹³⁵Cs in LLFP assemblies by 58% and significantly promotes the breeding of ²³⁹Pu. These findings demonstrate that the double-beam design offers clear advantages in improving power flattening, enhancing transmutation efficiency, and promoting actinide conversion in ADS systems, providing neutronic insights for future engineering conceptual design of multi-beam ADS configurations.

本研究基于CiADS堆芯几何形状，利用OpenMC代码建立了单束和双束驱动ADS亚临界堆的中子模型，系统比较了它们在功率分布、中子通量、长寿命裂变产物嬗变和钚增殖等方面的性能。结果表明，模型与参考结果的有效中子倍增因子差异在±0.003以内，在10−4MeV ~ 10 MeV范围内中子能谱吻合良好。结果表明，双束设计显著改善了轴向功率分布的均匀性，半最大全宽度从单束系统的58.8 cm增加到双束系统的60.5 cm，同时燃料组件内的中子通量普遍增加。在嬗变性能方面，双光束系统使LLFP组件中135Cs的嬗变率提高了58%，并显著促进了239Pu的繁殖。这些研究结果表明，双光束设计在改善ADS系统的功率平坦化、提高嬗变效率和促进锕系元素转换方面具有明显的优势，为未来多光束ADS配置的工程概念设计提供了中子见解。

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引用次数: 0

Improving the impermeability of nuclear graphite towards molten lead-bismuth eutectic in lead-cooled fast reactor by precursor impregnation and pyrolysis processes 采用前驱体浸渍和热解工艺改善铅冷快堆中核石墨对熔融铅铋共晶的不渗透性

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

Nuclear Engineering and Technology

Pub Date : 2026-07-01 Epub Date: 2026-03-06 DOI: 10.1016/j.net.2026.104250

Zhao He , Jinliang Song , Zhanjun Liu

The permeation of molten lead-bismuth eutectic (LBE) in graphite coolant channel material is a big issue that influences the stable operation of lead-cooled fast reactor (LFR). In this study, a modification process is conducted on a commercial nuclear graphite to improve its impermeability to molten LBE used in LFR by impregnation and pyrolysis with polycarbosilane solution. Mercury and static molten LBE infiltration experiments are performed on pristine graphite and modified graphite to investigate and compare their differences in structural compactness and infiltration resistance to molten LBE. The experimental results demonstrate that the modification process can significantly improve the structural compactness of graphite substrate and thereby effectively enhance its infiltration resistance to molten LBE. Particularly, the infiltration amount of molten LBE into modified graphite is much less than that into pristine graphite under all infiltration pressures. Additionally, the dense SiC coating derived from polycarbosilane shows robust durability to stand up to the test of molten LBE infiltration experiments. These results preliminarily demonstrate that the modification process employed in this work is a feasible method to obtain graphite coolant channel material amenable to LFR.

铅铋共晶熔融体在石墨冷却剂通道材料中的渗透是影响铅冷快堆稳定运行的一个重要问题。本研究采用聚碳硅烷溶液浸渍和热解的方法，对一种商用核石墨进行改性，以提高其对LFR中熔融LBE的不渗透性。对原始石墨和改性石墨进行了汞和静态熔融LBE渗透实验，研究并比较了它们在结构致密性和抗熔融LBE渗透性能方面的差异。实验结果表明，改性工艺可以显著提高石墨基体的结构致密性，从而有效增强其抗熔融LBE渗透能力。特别是在所有渗透压力下，熔融LBE对改性石墨的渗透量都远远小于对原始石墨的渗透量。此外，由聚碳硅烷衍生的致密SiC涂层具有强大的耐久性，可以经受熔融LBE渗透实验的测试。这些结果初步表明，本文所采用的改性工艺是获得适合LFR的石墨冷却剂通道材料的一种可行方法。

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引用次数: 0

A data-efficient physics-informed neural network framework for reliable irradiation hardening assessment in nanocrystalline materials 一个数据高效的物理信息神经网络框架，用于可靠的纳米晶体材料辐照硬化评估

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

Nuclear Engineering and Technology

Pub Date : 2026-07-01 Epub Date: 2026-03-09 DOI: 10.1016/j.net.2026.104256

Kai Liu , Xin Leng , Ting Liu , Wangwang Liao , Weipeng Li , Xiangyun Long

This paper proposes a novel Physics-Informed Neural Network (PINN) framework for assessing ion irradiation hardening in nanocrystalline materials. A key innovation lies in the deep integration of irradiation hardening mechanisms into the neural network via a composite loss function, which imposes physical laws as hard constraints. During network training, key parameters of the physical model are simultaneously optimized, enabling adaptive matching to the microstructural characteristics of different materials. This integration ensures that the model's predictions are both consistent with experimental data and physically plausible. Compared with conventional methods, this framework significantly reduces data dependence, overcomes the limitations of pure physical models under ill-posed conditions, and addresses the poor generalizability of purely data-driven approaches. Validation through multi-condition irradiation experiments on Ni-Mo-Cr alloys with two different grain sizes demonstrates that the model achieves a prediction error of less than 5% for the nanocrystalline alloy and maintains an error of approximately 10% for conventional alloy, with robust stability in extrapolation tests. Its evaluation accuracy and robustness are significantly superior to those of traditional physical models and purely data-driven methods. This study provides a physically interpretable, data-efficient, and highly generalizable paradigm for the assessment of irradiation hardening.

本文提出了一种新的物理信息神经网络（PINN）框架，用于评估纳米晶材料的离子辐照硬化。一个关键的创新在于通过复合损失函数将辐射硬化机制深度集成到神经网络中，该函数将物理定律作为硬约束。在网络训练过程中，同时优化物理模型的关键参数，实现对不同材料微观结构特征的自适应匹配。这种整合确保了模型的预测既与实验数据一致，又在物理上是可信的。与传统方法相比，该框架显著降低了数据依赖性，克服了纯物理模型在病态条件下的局限性，解决了纯数据驱动方法泛化性差的问题。通过对两种不同晶粒尺寸的Ni-Mo-Cr合金的多条件辐照实验验证，该模型对纳米晶合金的预测误差小于5%，对常规合金的预测误差保持在10%左右，在外推试验中具有良好的稳定性。其评估精度和鲁棒性明显优于传统的物理模型和纯数据驱动方法。本研究为辐照硬化的评估提供了一种物理上可解释的、数据效率高的、高度可推广的范式。

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引用次数: 0

Seismic fragility analysis of NPP cabinets considering high-frequency excitations using an efficient numerical model 考虑高频激励的核电厂柜体地震易损性分析

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

Nuclear Engineering and Technology

Pub Date : 2026-06-01 Epub Date: 2026-02-09 DOI: 10.1016/j.net.2026.104188

Shariful Islam, Towhid Ahmed, Dong Van Nguyen, Dookie Kim

Electrical cabinets are critical for the reliable operation of nuclear power plants (NPPs), yet their seismic fragility under high-frequency ground motions remains insufficiently addressed. This study develops a computationally efficient three-dimensional finite element model for an anchored NPP electrical cabinet that explicitly accounts for excitation frequency relative to cabinet dynamics. The cabinet is idealized with beam and shell elements, while omitted panel masses are represented by an equivalent lumped mass whose location is optimized using Response Surface Methodology. The optimized model reproduces shaking-table-identified fundamental frequencies with a maximum error of 1.99% and accurately matches measured top-of-cabinet acceleration histories. Seismic fragility is evaluated through incremental dynamic analysis using two controlled suites of motions: a low-frequency set dominated below the fundamental mode and a high-frequency set concentrated near the first-mode frequency. High-frequency excitation produces a consistent leftward shift of fragility curves, indicating earlier exceedance of a functional acceleration limit, and reduces the HCLPF capacity by about 22% compared with low-frequency excitation. These findings demonstrate that excitation frequency relative to cabinet dynamics critically influences seismic vulnerability, and neglecting high-frequency effects can yield unconservative capacity estimates. The proposed framework provides an efficient basis for frequency-sensitive seismic fragility evaluation of NPP cabinets.

电气柜是核电站可靠运行的关键，但其在高频地震动下的地震易碎性仍未得到充分解决。本研究开发了一个计算效率高的锚定核电站电气柜三维有限元模型，该模型明确地说明了相对于机柜动力学的激励频率。箱体采用梁和壳单元，而省略的面板质量由等效集总质量表示，其位置使用响应面方法进行优化。优化后的模型以1.99%的最大误差再现了振动台识别的基频，并准确匹配了测量到的机柜顶部加速度历史。地震易损性是通过增量动力分析来评估的，该分析使用两组受控运动：低频组占主导地位，低于基本模态，高频组集中在第一模态频率附近。高频激励产生脆性曲线一致的左移，表明较早超过功能加速度极限，与低频激励相比，HCLPF容量降低了约22%。这些研究结果表明，相对于机柜动力学的激励频率对地震易损性有重要影响，忽略高频效应会产生不保守的容量估计。该框架为核电厂机柜的频率敏感地震易损性评估提供了有效的依据。

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引用次数: 0

Baseline radiological environmental monitoring and impact assessment of radioactive waste storage facilities in Thailand 泰国放射性废物储存设施的基线辐射环境监测和影响评估

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

Nuclear Engineering and Technology

Pub Date : 2026-06-01 Epub Date: 2026-02-10 DOI: 10.1016/j.net.2026.104185

Anan O-Manee , Suwisa Sudchawa , Chalit Muanglay , Panuwat Srimork , Archara Phattanasub , Ritiron Samran , Wutthikrai Kulsawat , Phatchada Nochit , Waleeporn Pongkua

Radiation monitoring was conducted at two sites of the RWSF in Thailand. The activity concentration of tritium was assessed in the surface water, while gross alpha/beta radioactivity levels were measured additionally in soil and sediment. Gamma-ray spectroscopy was obtained the radioactivity concentrations for all environmental samples, and the external gamma-ray exposure dose rate was estimated. No tritium activity was detected at either site and showed no influence from nuclear-related activities. The average gross alpha/beta levels were found to be low, approximately 0.06-0.50 Bq/L, indicating that these levels are within safe limits. The activity concentrations of K-40, Th-232, and U-238 radionuclides in soil samples were 239.38 ± 21.75, 57.95 ± 1.56, and 50.34 ± 0.56 Bq/kg, respectively, while those in water samples were 17.15 ± 1.31, 0.69 ± 0.13, 0.32 ± 0.05 Bq/L, respectively. These natural radionuclides do not exceed the recommended limits. Related artificial radionuclides, including Cs-137, Co-60, and I-131 were not detected in any sample. Additionally, no radionuclides were detected in airborne dust samples, possibility of effective air ventilation in the sampling area. Moreover, the external gamma-ray exposure rate approximately 0.3-0.5 μSv/h, within the natural background radiation level. This routine monitoring has been strictly in accordance with international regulations, confirming that the RWSFs pose no radiological risk to nearby living organisms.

辐射监测工作在泰国的两个地点进行。评估了地表水中氚的活度浓度，同时还测量了土壤和沉积物中的总α / β放射性水平。通过伽玛能谱法获得了各环境样品的放射性浓度，并估算了外部伽玛射线照射剂量率。在这两个地点均未检测到氚活性，也未显示出受核相关活动的影响。平均总α / β水平较低，约为0.06-0.50 Bq/L，表明这些水平在安全范围内。土壤样品中K-40、Th-232和U-238放射性核素活性浓度分别为239.38±21.75、57.95±1.56和50.34±0.56 Bq/kg，水样中K-40、Th-232和U-238放射性核素活性浓度分别为17.15±1.31、0.69±0.13、0.32±0.05 Bq/L。这些天然放射性核素没有超过建议限量。在任何样本中均未检测到相关的人工放射性核素，包括Cs-137、Co-60和I-131。此外，在空气中的粉尘样本中未检测到放射性核素，这可能是采样区域有效的空气通风。此外，外部γ射线暴露率约为0.3-0.5 μSv/h，在自然本底辐射水平之内。这一例行监测是严格按照国际规定进行的，证实了再生水处理厂不会对附近的生物构成辐射风险。

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引用次数: 0

A synergistic experimental–theoretical study of radiation attenuation in locally manufactured Iraqi glasses 伊拉克本地玻璃辐射衰减的协同实验-理论研究

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

Nuclear Engineering and Technology

Pub Date : 2026-06-01 Epub Date: 2026-02-05 DOI: 10.1016/j.net.2026.104180

Mohsin Hasan Ali , Mohamed Y. Hanfi , Mushtaq Abed Al-Jubbori , M.I. Sayyed , Mutaz Salih Hasan Aljuboori , Abedelmoneim Saleh

In this context, we examine the physical, structural, and gamma-ray shielding properties of six Iraqi traditional glass samples (S1–S6). The elemental composition was analyzed using Energy Dispersive X-Ray Fluorescence (EDXRF) while the Archimedes' principle were used for density measurement. In addition, gamma-ray attenuation tests were performed with an NaI(Tl) scintillation detector across photon energies of 60–662 keV. Different shielding parameters including linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), tenth-value layer (TVL), transmission factor (TF and effective atomic number (Z_eff) were determined and compared to theoretical predictions from Phy-X software. The densities of the glass samples ranging from 2.41 to 2.475 g/cm³. At 60 keV, the LAC values ranged from 0.471 to 0.645 cm⁻¹, while at higher energies (609–662 keV) it was about 0.176 and 0.188 cm⁻¹ respectively. Among the samples, S2 showed the best shielding efficiency due to higher contents of sodium and magnesium, achieving the lowest HVL (1.075 cm) and an RPE of about 72% at a thickness of 2 cm at lower photon energies. The experimental MAC values of about 0.072 to 0.075 cm²/g aligned closely with Phy-X calculations and compared with ordinary and commercial concrete.

在这种情况下，我们研究了六种伊拉克传统玻璃样品（S1-S6）的物理、结构和伽马射线屏蔽性能。用能量色散x射线荧光（EDXRF）分析了元素组成，并用阿基米德原理测量了密度。此外，用NaI（Tl）闪烁探测器在60-662 keV的光子能量范围内进行了伽马射线衰减测试。测定了不同的屏蔽参数，包括线性衰减系数（LAC）、质量衰减系数（MAC）、半值层（HVL）、平均自由程（MFP）、十值层（TVL）、透射系数（TF）和有效原子序数（Zeff），并与物理- x软件的理论预测结果进行了比较。玻璃样品的密度范围为2.41 ~ 2.475 g/cm3。60 keV时LAC值为0.471 ~ 0.645 cm−1,609 ~ 662 keV时LAC值分别为0.176和0.188 cm−1。其中，由于钠和镁含量较高，S2表现出最好的屏蔽效率，在较低光子能量下，厚度为2 cm时的HVL最低（1.075 cm）， RPE约为72%。实验MAC值约为0.072至0.075 cm2/g，与Phy-X计算结果一致，并与普通混凝土和商品混凝土进行了比较。

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引用次数: 0

Nuclear and radiological characterization of a 226Ra-Be neutron irradiator at INFISA-UNMSM, Peru, using Monte Carlo simulation with the OpenMC code 秘鲁INFISA-UNMSM的226Ra-Be中子辐照器的核和放射特性，使用蒙特卡罗模拟和OpenMC代码

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

Nuclear Engineering and Technology

Pub Date : 2026-06-01 Epub Date: 2026-02-10 DOI: 10.1016/j.net.2026.104158

P. Tataje , Abdessamad Didi , A. Arroyo , S. Daza

A neutron irradiator consisting of a²²⁶Ra-Be source with a 3 mCi activity of radium, used for the early teaching of neutron activation experiments, belonging to the INFISA-UNMSM, was characterized using the relatively new open-source framework OpenMC. The ²²⁶Ra-Be source is located inside a hermetically sealed nickel-soldered cylinder filled with activated carbon. This cylinder, in turn, is inside a larger cylinder filled with paraffin wax, with seven irradiation channels. These channels were characterized for axial and radial neutron flux, prompt gamma flux, and dose equivalent rate (H∗₍₁₀₎) both inside the irradiation channels and on the exterior of the cylinder.

利用相对较新的开放源代码框架OpenMC对用于中子活化实验早期教学的中子辐照体进行了表征，该中子辐照体由镭活度为3mci的226ra - be源组成。226Ra-Be源位于一个密封的镍焊气缸内，气缸内填充活性炭。这个圆柱体，反过来，是在一个更大的圆柱体充满石蜡，有七个辐照通道。这些通道的特征是轴向和径向中子通量，提示伽马通量和剂量等效率（H *(10)）在辐照通道内和柱体的外部。

引用次数: 0

Simulating transport of uranium series radionuclides in fractured rock of Beishan area: The use of multi-channel model and the influence of parameters 模拟北山地区裂隙岩中铀系放射性核素输运：多通道模型的应用及参数的影响

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

Nuclear Engineering and Technology

Pub Date : 2026-06-01 Epub Date: 2026-02-03 DOI: 10.1016/j.net.2026.104182

Shuo Meng , Hai Wang , Longcheng Liu

In this work, the multi-channel model is applied to simulate transport of radionuclides for uranium series in Beishan area of China. In the model, the mechanisms of advection, velocity dispersion, surface retardation, matrix diffusion and sorption, and radioactive decay are considered. The simulation results show that the normalized concentration of U-238 has the largest value of

\sim 10^{- 5}

at about

10^{3}

yr, while the highest concentration of all daughter nuclides is in the range of

\sim 10^{- 12}

. Moreover, it is found that a decrease in mean aperture of the ensemble of channels causes an earlier arrival of U-238, because of the increase of the fluid velocity of each channel. Similarly, a higher mean flowrate or a smaller average width also leads to an earlier arrival. In addition, it is also observed that early-time behaviors are significantly different, provided that the amount of flow-paths is limited. An increased amount will reduce the difference, since the realization mean flowrate is closer to the statistical mean value of the infinite amount case. Likewise, the effect of heterogeneity of rock matrix on radionuclide transport is also dependent on the number of flow-paths.

本文采用多通道模式模拟了中国北山地区铀系放射性核素的输运。在模型中考虑了平流、速度色散、表面延迟、基体扩散和吸附以及放射性衰变等机理。模拟结果表明，铀-238的归一化浓度在约103年时最大，为~ 10−5，而所有子核素的最高浓度在~ 10−12范围内。此外，还发现由于各通道流体速度的增加，通道集合平均孔径的减小会导致U-238提前到达。同样，较高的平均流量或较小的平均宽度也会导致较早到达。此外，我们还观察到，在流道数量有限的情况下，早期行为有显著差异。增加的流量将减小差异，因为实现的平均流量更接近无限大情况下的统计平均值。同样，岩石基质的非均质性对放射性核素输运的影响也取决于流动路径的数量。

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引用次数: 0