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

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

{"title":"Electrorefining of HANA-4 cladding scrap in LiCl-KCl salts for volumetric decontamination of irradiated cladding containing Nb-94","authors":"Sungjune Sohn , Jungho Hur , Jaeyeong Park , Pyeonghwa Kim , Il Soon Hwang","doi":"10.1016/j.net.2026.104252","DOIUrl":"10.1016/j.net.2026.104252","url":null,"abstract":"<div><div>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 NbCl<sub>5</sub> 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 Zr<sup>4+</sup>, Zr<sup>2+</sup>, 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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 7","pages":"Article 104252"},"PeriodicalIF":2.6,"publicationDate":"2026-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147388316","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

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

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

{"title":"A CFD SSTk−ω−kθ−εθ four parameter heat transfer turbulence model for the 19-pin fuel assembly in LBE cooled reactors","authors":"YaoDi Li , Mei Huang , Yiyuan Du , Shiju Jin","doi":"10.1016/j.net.2026.104253","DOIUrl":"10.1016/j.net.2026.104253","url":null,"abstract":"<div><div>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 (<span><math><mrow><mi>Pr</mi></mrow></math></span>), and its local turbulent Prandtl number (<span><math><mrow><msub><mi>Pr</mi><mi>t</mi></msub></mrow></math></span>) is nonlinear. Therefore, the constant turbulent Prandtl number is difficult to satisfy complex turbulent heat transfer calculations. Thus, developing a high-precision <span><math><mrow><msub><mi>k</mi><mi>θ</mi></msub><mo>−</mo><msub><mi>ε</mi><mi>θ</mi></msub></mrow></math></span> two parameter turbulent heat transfer model for lead bismuth alloys has significant engineering value. This study systematically derives the <span><math><mrow><mi>S</mi><mi>S</mi><mi>T</mi><mspace></mspace><mi>k</mi><mo>−</mo><mi>ω</mi><mo>−</mo><msub><mi>k</mi><mi>θ</mi></msub><mo>−</mo><msub><mi>ε</mi><mi>θ</mi></msub></mrow></math></span> 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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 7","pages":"Article 104253"},"PeriodicalIF":2.6,"publicationDate":"2026-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147388317","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 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

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

{"title":"Influence of double-beam design on nuclear waste transmutation performance for CiADS-like reactor","authors":"Tiqi Chen , JiaLi Huang , Hui Guo , Long Zhu , Shaojun Yan , Yanjun Chen , Leyi Wu , Jun Su","doi":"10.1016/j.net.2026.104246","DOIUrl":"10.1016/j.net.2026.104246","url":null,"abstract":"<div><div>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 <span><math><mo>±</mo></math></span>0.003, and the neutron energy spectra agree well in the range of <span><math><mrow><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mo>−</mo><mn>4</mn></mrow></msup><mspace></mspace><mi>MeV</mi></mrow></math></span> 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 <sup>135</sup>Cs in LLFP assemblies by 58% and significantly promotes the breeding of <sup>239</sup>Pu. 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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 7","pages":"Article 104246"},"PeriodicalIF":2.6,"publicationDate":"2026-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147388320","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

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

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

{"title":"Improving the impermeability of nuclear graphite towards molten lead-bismuth eutectic in lead-cooled fast reactor by precursor impregnation and pyrolysis processes","authors":"Zhao He , Jinliang Song , Zhanjun Liu","doi":"10.1016/j.net.2026.104250","DOIUrl":"10.1016/j.net.2026.104250","url":null,"abstract":"<div><div>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 <span><span>impregnation and pyrolysis with polycarbosilane</span><svg><path></path></svg></span> 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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 7","pages":"Article 104250"},"PeriodicalIF":2.6,"publicationDate":"2026-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147388318","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

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

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

{"title":"A data-efficient physics-informed neural network framework for reliable irradiation hardening assessment in nanocrystalline materials","authors":"Kai Liu , Xin Leng , Ting Liu , Wangwang Liao , Weipeng Li , Xiangyun Long","doi":"10.1016/j.net.2026.104256","DOIUrl":"10.1016/j.net.2026.104256","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 7","pages":"Article 104256"},"PeriodicalIF":2.6,"publicationDate":"2026-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147388319","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

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

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

{"title":"Seismic fragility analysis of NPP cabinets considering high-frequency excitations using an efficient numerical model","authors":"Shariful Islam, Towhid Ahmed, Dong Van Nguyen, Dookie Kim","doi":"10.1016/j.net.2026.104188","DOIUrl":"10.1016/j.net.2026.104188","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 6","pages":"Article 104188"},"PeriodicalIF":2.6,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146154230","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

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

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

{"title":"Baseline radiological environmental monitoring and impact assessment of radioactive waste storage facilities in Thailand","authors":"Anan O-Manee , Suwisa Sudchawa , Chalit Muanglay , Panuwat Srimork , Archara Phattanasub , Ritiron Samran , Wutthikrai Kulsawat , Phatchada Nochit , Waleeporn Pongkua","doi":"10.1016/j.net.2026.104185","DOIUrl":"10.1016/j.net.2026.104185","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 6","pages":"Article 104185"},"PeriodicalIF":2.6,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146154259","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

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

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

{"title":"A synergistic experimental–theoretical study of radiation attenuation in locally manufactured Iraqi glasses","authors":"Mohsin Hasan Ali , Mohamed Y. Hanfi , Mushtaq Abed Al-Jubbori , M.I. Sayyed , Mutaz Salih Hasan Aljuboori , Abedelmoneim Saleh","doi":"10.1016/j.net.2026.104180","DOIUrl":"10.1016/j.net.2026.104180","url":null,"abstract":"<div><div>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<sub>eff</sub>) 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/cm<sup>3</sup>. At 60 keV, the LAC values ranged from 0.471 to 0.645 cm<sup>−1</sup>, while at higher energies (609–662 keV) it was about 0.176 and 0.188 cm<sup>−1</sup> 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 cm<sup>2</sup>/g aligned closely with Phy-X calculations and compared with ordinary and commercial concrete.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 6","pages":"Article 104180"},"PeriodicalIF":2.6,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146193133","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

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

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

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

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

{"title":"Simulating transport of uranium series radionuclides in fractured rock of Beishan area: The use of multi-channel model and the influence of parameters","authors":"Shuo Meng , Hai Wang , Longcheng Liu","doi":"10.1016/j.net.2026.104182","DOIUrl":"10.1016/j.net.2026.104182","url":null,"abstract":"<div><div>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 <span><math><mrow><mo>∼</mo><msup><mn>10</mn><mrow><mo>−</mo><mn>5</mn></mrow></msup></mrow></math></span> at about <span><math><mrow><msup><mn>10</mn><mn>3</mn></msup></mrow></math></span> yr, while the highest concentration of all daughter nuclides is in the range of <span><math><mrow><mo>∼</mo><msup><mn>10</mn><mrow><mo>−</mo><mn>12</mn></mrow></msup></mrow></math></span>. 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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 6","pages":"Article 104182"},"PeriodicalIF":2.6,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146154228","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