Nuclear Engineering and Technology最新文献

{"title":"Phytoremediation of cesium-contaminated soils using Sorghum bicolor, Albizia falcataria, Amaranthus viridis, and Vetiveria zizanioides in tropical environments","authors":"Nuril Hidayati T.H ,&nbsp;Gustri Nurliati ,&nbsp;Mirawaty Mirawaty ,&nbsp;Zeni Anggraini ,&nbsp;Raden Sumarbagiono ,&nbsp;Sugeng Purnomo ,&nbsp;Suryantoro Suryantoro ,&nbsp;Ajrieh Setyawan ,&nbsp;Moch Romli ,&nbsp;Mukhamad Nurhasyim ,&nbsp;Sunardi Sunardi ,&nbsp;Dyah Sulistyani Rahayu ,&nbsp;Suhartono Suhartono ,&nbsp;Djarot Sulistio Wisnubroto ,&nbsp;Dadong Iskandar ,&nbsp;Susetyo Hario Putero ,&nbsp;Chalid Talib ,&nbsp;Indra Gunawan ,&nbsp;Nana Mulyana ,&nbsp;Irawan Sugoro ,&nbsp;Muhammad Yusuf","doi":"10.1016/j.net.2025.103871","DOIUrl":"10.1016/j.net.2025.103871","url":null,"abstract":"<div><div>Radioactive cesium (Cs-137) contamination in soil presents serious environmental and health concerns due to its long-lasting presence and high mobility. Conventional remediation techniques are often expensive and technically complex, prompting the need for more sustainable approaches. This study investigates the potential of phytoremediation as an environmentally friendly approach for soils contaminated with stable isotope Cs-133, using <em>Sorghum bicolor, Albizia falcataria, Amaranthus viridis,</em> and <em>Vetiveria zizanioides</em> under controlled conditions. The results indicate that a mong the four species studied, Amaranthus <em>viridis</em> and <em>Sorghum bicolor</em> achieved the higher bioaccumulation and translocation factors, with <em>Amaranthus viridis</em> producing a peak biomass of 125 g at 100 ppm and <em>Sorghum bicolor</em> reaching 180 g at 50 ppm. All species showed translocation factor values greater than 1, confirming their ability for phytoextraction. However, while bioaccumulation factor values exceeded 1 at cesium concentrations below 50 ppm, they decreased at higher concentrations, suggesting a threshold for effective uptake. These findings indicate that Amaranthus viridis and Sorghum bicolor are promising candidates for phytoremediation of cesium-contaminated soils, particularly at concentrations up to 50 ppm, offering valuable insights into sustainable radioactive waste management, especially in tropical settings.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103871"},"PeriodicalIF":2.6,"publicationDate":"2025-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145010861","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":"Reconstructing North Korea’s plutonium production history with Bayesian inference-based reprocessing waste analysis","authors":"Benjamin Jung ,&nbsp;Johannes Bosse ,&nbsp;Malte Göttsche","doi":"10.1016/j.net.2025.103849","DOIUrl":"10.1016/j.net.2025.103849","url":null,"abstract":"<div><div>Although North Korea’s nuclear program has been the subject of extensive scrutiny, estimates of its fissile material stockpiles remain fraught with uncertainty. In potential future disarmament agreements, inspectors may need to use nuclear archaeology methods to verify or gain confidence in a North Korean fissile material declaration. This study explores the potential utility of a Bayesian inference-based analysis of the isotopic composition of reprocessing waste to reconstruct the operating history of the 5<!--> <!-->MWe reactor and estimate its plutonium production history. We simulate several scenarios that reflect different assumptions and varying levels of prior knowledge about the reactor. The results show that correct prior assumptions can be confirmed and incorrect prior information (or a false declaration) can be detected. Model comparison techniques can distinguish between scenarios with different numbers of core discharges, a capability that could provide important insights into the early stages of operation of the 5 MWe reactor. Using these techniques, a weighted plutonium estimate can be calculated, even in cases where the number of core discharges is not known with certainty.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103849"},"PeriodicalIF":2.6,"publicationDate":"2025-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144913998","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":"Investigation on evolution characteristic of dynamic pore and reactive transport of leaching solute in uranium-bearing sandstone during in-situ alkaline leaching mining: An in-situ LF-NMR leaching experiment","authors":"Tong Zhang ,&nbsp;Xin Yang ,&nbsp;Liang Yuan ,&nbsp;Xuebin Su ,&nbsp;Zhiming Du ,&nbsp;Yihan Yang ,&nbsp;Ming Tang ,&nbsp;Chuanfei Zhang ,&nbsp;Peng Qiao ,&nbsp;Bingzhang Li","doi":"10.1016/j.net.2025.103864","DOIUrl":"10.1016/j.net.2025.103864","url":null,"abstract":"<div><div>In-situ uranium leaching involves complex physicochemical interactions critically influencing reservoir permeability and leaching efficiency. This study investigated microstructural changes in uranium-bearing sandstone during alkaline leaching mining through integrated column leaching experiments, real-time multi-pore geometry structure and leaching solution morphology was motored using online low-field nuclear magnetic resonance (LF-NMR), and uranium-bearing sandstone component and leaching agent was analyzed by scanning electron microscopy (SEM), X-ray diffraction (XRD) and X-ray fluorescence (XRF). The uranium-bearing sandstone predominantly comprises micropores (T₂ &lt; 2.5 ms), mesopores (2.5 ms &lt; T₂ &lt; 100 ms), and macropores (T₂ &gt; 100 ms), with the pore system mainly composed of quartz, clinochlore, kaoline, and orthoclase. The results demonstrate that permeability reduction of 48.6 % (from 0.976 to 0.502 mD), with total pore porosity increase of 2.44 % was primarily driven by a substantial micropore reduction of 5.98 %. A significant micropore clogging was induced by precipitation of secondary minerals (CaSO₄, Mg(OH)₂, and silica colloids) during late-stage leaching (156–363 PV). An innovative empirical relation model for microporosity and permeability was established, and enhanced the prediction accuracy of permeability evolution. These insights reveal that micropore dynamically influence permeability evolution and uranium recovery efficiency, which benefits the technology optimization in alkaline leaching mining.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103864"},"PeriodicalIF":2.6,"publicationDate":"2025-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144907637","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 core physics design and analysis of micro-modular lead cooled fast reactor (MMLFR) cores for autonomous ultra-long-life operation","authors":"Seungnam Lee,&nbsp;Ser Gi Hong","doi":"10.1016/j.net.2025.103874","DOIUrl":"10.1016/j.net.2025.103874","url":null,"abstract":"<div><div>Minimizing core size with keeping an ultra-long-life operation cycle is very interesting for improving the inherent safety and sustainability of nuclear energy systems. Additionally, minimizing the excess reactivity change to less than 1$ for the small core is very helpful to make the small nuclear reactor to be safer by removing the prompt critical accident and to make it easy for autonomous operation by minimizing the movements of the control rods. In this work, Micro-Modular Lead-cooled Fast Reactor (MMLFR) cores of 35 MWth are neutronically designed by using the superb neutronic properties of the lead coolant and considering simple two-region cores of different fuel compositions. The results of the analysis showed that the final candidate cores have cycle lengths longer than 30 EFPYs (Effective Full Power Years) over which the burnup reactivity swings are less than 1$, achieve high burnups exceeding 58 MWd/kgHM, and possess all negative reactivity coefficients except for reactivity coefficients by coolant expansion. Also, it was shown that the final candidate cores can maintain the integrity of fuel rods from point of view of DPA, peak cladding and fuel centerline temperatures, and internal pressure and hoop stress for the fission gas plenum over the operation life.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103874"},"PeriodicalIF":2.6,"publicationDate":"2025-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144904251","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":"Correction of the radon exhalation rate using the Kalman filtering to reduce measurement errors","authors":"Haoyu You ,&nbsp;Jianfeng Tang ,&nbsp;Zhongkai Fan ,&nbsp;Ruomei Xie ,&nbsp;Hongzhi Yuan ,&nbsp;Yanliang Tan","doi":"10.1016/j.net.2025.103868","DOIUrl":"10.1016/j.net.2025.103868","url":null,"abstract":"<div><div>The RAD7 detector is widely used for measuring the radon exhalation rate from the surfaces of media such as soil, rocks, and building materials. However, during the measurement process, the accuracy of the results is prone to interference due to the instrument's inherent statistical errors and environmental noise. To reduce these measurement errors, the Kalman filtering was introduced in this study to correct the radon exhalation rate, which was obtained through data fitting of radon concentration measured by the RAD7 detector. Ten verified experiments were performed with a radon exhalation standard device. The experimental result shows that 80 % of the radon exhalation rate, corrected by Kalman filtering, significantly approached the theoretical value of the standard device, compared to the uncorrected experimental results. It confirms the effectiveness of the Kalman filtering in correcting RAD7 measurements, thereby enhancing the accuracy of radon exhalation rate measurements. The proposed method provides a reference technical pathway for improving the measurement accuracy of similar radon measurement instruments.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103868"},"PeriodicalIF":2.6,"publicationDate":"2025-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144916628","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 comprehensive investigation of computational analysis on flow characteristics, stability and safe limits of a supercritical natural circulation loop for different heating power profiles","authors":"Santosh Kumar Rai ,&nbsp;Pardeep Kumar ,&nbsp;Vinay Panwar ,&nbsp;Mahesh Kumar Gupta ,&nbsp;Dhowmya Bhatt ,&nbsp;Dinesh Kumar ,&nbsp;Vipin Kumar Sharma ,&nbsp;Vikas Goyat ,&nbsp;Gyander Ghangas ,&nbsp;Arun Uniyal ,&nbsp;Mahiti Gupta","doi":"10.1016/j.net.2025.103858","DOIUrl":"10.1016/j.net.2025.103858","url":null,"abstract":"<div><div>The Generation IV International Forum (GIF) is a global organization focused on the research and advancement of next-generation nuclear reactor technologies. GIF-IV reactors particularly seek to improve the safety, efficiency, and sustainability of nuclear power, with an emphasis on developing cleaner and more renewable energy sources. Supercritical water reactors (SCWRs) and supercritical water natural circulations (SCWNCL) are one of the most advanced technologies developed by the GIF-IV for cooling the core of nuclear reactors. In this study,a thermal-hydraulic (TH) model has been developed based on the nonlinearly coupled equations of mass, momentum, and energy conservation, with an equation of state which depends on two independent thermodynamic characteristics pressure and enthalpy. The present model is first validated against literature result such as experimental and numerical which showed a good agreement, followed by a grid independence test (GIT) conducted for both steady state and transient conditions to ensure accurate predictions of the SCWNCL. Further, the simulations are carried out to examine loop behavior and ascertain thermal-hydraulic transient instability, along with determining the stable and safe limits of the SCWNCL. Additionally, numerous simulations have been conducted to ascertain the presence of static instability that occurs at extremely low enthalpy. Furthermore, dynamic instability has been seen in the loop at both low and high enthalpy using three different heating profiles like uniform, point and half sinusoidal profiles, resulting in the construction of the marginal stability map. Subsequently, comprehensive simulations have been conducted to forecast heat transfer deterioration within the loop from a material point of view, aiming to ascertain the stable and safe limits of the SCWNCL. Comparative studies have been conducted with and without the consideration of heating structure stability maps, demonstrating that the addition of the structure provides a higher stability zone compared to its absence.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103858"},"PeriodicalIF":2.6,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144921516","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":"Dose assessment in several accidental scenarios involving lithium leakage in three IFMIF-DONES lithium system rooms","authors":"J. Javier Martínez-Serrano ,&nbsp;Jorge Maestre ,&nbsp;Yuefeng Qiu ,&nbsp;Francesco Saverio Nitti","doi":"10.1016/j.net.2025.103855","DOIUrl":"10.1016/j.net.2025.103855","url":null,"abstract":"<div><div>This study assesses the radiological risks from potential failures in the lithium system of the IFMIF-DONES (International Fusion Materials Irradiation Facility - Demo Oriented NEutron Source<em>)</em> facility, focusing on critical components in the Lithium Loop Cell (LLC), Hot Trap (H-trap), and Cold Trap (C-trap) rooms. Seven lithium leak scenarios were analyzed: four in the LLC room (near the electromagnetic pump, Target Lithium TLIC inlet/outlet, and primary heat exchanger), one in the H-trap, and one in the C-trap. Lithium release volumes varied from 0.017 m³ to 3.8 m³. Ambient dose equivalent rates, H*(10), were calculated using the MCNP 5.1.40 radiation transport code for gamma-emitting radionuclides like ⁷Be and activation products. Simulations included structural features affecting gamma transport, and dose maps were generated at various heights and distances from leaks. The most severe radiological conditions arose from the Primary Heat Exchanger (PHX) rupture and C-trap leakage, with peak H*(10) rates of 94 mSv/h and 130 mSv/h, respectively. To meet annual dose limits (50 mSv/year), maximum allowable human intervention times ranged from 32 min (PHX rupture) to 714 min (H-trap failure). Post-leak access to the C-trap room is prohibited due to exceeding red zone thresholds. These results are essential for safety planning, remote handling, and accident mitigation strategies within the IFMIF-DONES lithium loop systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103855"},"PeriodicalIF":2.6,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144886135","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":"Investigation of a stable and saturated reference electrode using metal chlorides and oxides in eutectic LiCl-KCl molten salts","authors":"Carlos Mejia,&nbsp;Devin Rappleye","doi":"10.1016/j.net.2025.103875","DOIUrl":"10.1016/j.net.2025.103875","url":null,"abstract":"<div><div>Stable and reproducible reference electrodes (REs) are essential for electrochemical systems operating in high-temperature molten salts, where consistent control of potential is required. This study uses three different solutes to investigate the development and evaluation of REs in eutectic LiCl-KCl at 773 K. The solutes tested were NiCl₂, AgCl, and NiO, each prepared at multiple concentrations to assess stability, reproducibility, and saturation. Electrochemical stability was measured over three days using chronopotentiometry (CP), followed by open circuit potential (OCP), with cyclic voltammetry (CV) also integrated to monitor changes in electrochemical behavior over time. The CP-OCP approach established a Li⁺/Li redox potential, and CV was used to confirm the consistency of RE performance. REs containing NiCl₂ showed stable behavior at all concentrations, with saturation achieved at 15 mol% or greater. NiO-based REs also showed both stability and saturation at all concentrations tested, which can be attributed to the low solubility of NiO in LiCl-KCl. AgCl-based REs were stable at low concentrations but exhibited potential drift at 5 mol% after 35–40 h. These findings support the use of NiCl₂ and NiO above saturated concentrations for constructing reliable REs for future high-temperature electrochemical applications.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103875"},"PeriodicalIF":2.6,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144913994","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":"Fault identification and signal restoration of sensors based on artificial intelligence at nuclear power plants","authors":"Ji Woo Hong,&nbsp;Ji Hun Park,&nbsp;Man Gyun Na","doi":"10.1016/j.net.2025.103876","DOIUrl":"10.1016/j.net.2025.103876","url":null,"abstract":"<div><div>In nuclear power plants (NPPs), the reliability of sensor signals is important for operators’ situational awareness and for ensuring safe operation. Operators make decisions based on information collected from various instrumentation sensors, which serve as inputs for artificial intelligence (AI)-based operator support systems. However, signal faults caused by sensor malfunctions, aging, and environmental factors can occur in actual operating environments. These faults may delay accident recognition or cause misdiagnosis, increasing human error risk. Signal integrity is particularly important in emergency situations, where rapid decision-making is imperative. This study proposes an AI-based algorithm for effective identification and restoration of sensor signal faults during emergencies in NPPs. First, the algorithm verifies the input signals to detect faults. Subsequently, it selectively restores only faulty signals. The restored signals are then used for accident diagnosis, preventing performance degradation caused by faulty inputs. The algorithm was evaluated using artificially generated data for three types of faults: bias, drift, and stuck. Results demonstrated high accuracy in fault detection and restoration. Additionally, restored signals enabled accurate accident classification. This study is expected to enhance NPP safety and reliability by mitigating the impact of signal faults on AI-based operator support systems and decision-making.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103876"},"PeriodicalIF":2.6,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145004625","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":"Preliminary mechanical analysis of the CS coil design for a medium-sized tokamak","authors":"Jiandong Zhu ,&nbsp;Xiaogang Liu ,&nbsp;Xiang Gao ,&nbsp;Jie Zhang ,&nbsp;Lijuan Yu ,&nbsp;Fanping Ding ,&nbsp;Guoqiang Li","doi":"10.1016/j.net.2025.103872","DOIUrl":"10.1016/j.net.2025.103872","url":null,"abstract":"<div><div>A preliminary mechanical analysis has been conducted for the hybrid Central Solenoid coil, designed for a medium-sized tokamak aiming for a fusion power gain <em>Q</em> &gt; 1. To optimize magnetic flux, the CS coil integrates REBCO conductors in its high-field sub-coil and high-Jc Nb₃Sn conductors in the low-field sub-coil. The peak magnetic field reaches 18.3 T at a current of 39.5 kA, producing a magnetic flux of 54.6 V s at a major radius of 3.5 m. A static structural assessment has been undertaken to initially evaluate the integrity of the preload structure. Additionally, a 2D axisymmetric finite element model, incorporating cables, conductor jackets, turn insulations, insulation spacers, pancake insulations, ground insulations, and inter-module spacers, has been developed and simulated using ANSYS's coupled structural-thermal-electromagnetic solver. Given that the CS conductor jacket is subjected to cyclic loads due to electromagnetic forces during operation, estimating its fatigue life is crucial. The jacket fatigue life curves are derived from a fatigue crack growth analysis.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103872"},"PeriodicalIF":2.6,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144917405","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}