Radioactive Effluents Research Articles

From Radioactive Effluent to Drinking Water: Efficient Removal of Trace 99TcO4 -/ReO4 - by Cationic Porous Aromatic Framework.

Efficient removal of 99TcO4 - from radioactive effluents while recovering drinking water remains a challenge. Herein, an excellent ReO4 - (a nonradioactive surrogate of 99TcO4 -) scavenger is presented through covalently bonding imidazolium poly(ionic liquids) polymers with an ionic porous aromatic framework (iPAF), namely iPAF-P67, following an adsorption-site density-addition strategy. It shows rapid sorption kinetics, high uptake capacity, and exceptional selectivity toward ReO4 -. Notably, the residual concentration of TcO4 -/ReO4 - in the radioactive wastewater after iPAF-P67 treatment is as low as 0.046 ppb, fully meeting the drinking water standards of World Health Organization (WHO, 0.159 ppb) and United States Environmental Protection Agency (U.S. EPA, 0.053 ppb). Density functional theory (DFT) calculations show that the imidazolium groups in iPAF-P67 provide stronger electrostatic interactions and higher binding energies between iPAF-P67 and TcO4 - anions, leading to its superior adsorption performance. Furthermore, the scale-up synthesized iPAF-P67 materials are shaped with polyethersulfone (PES) to fabricate PAF-P67/PES beads and nanofibers via phase inversion method and electrospinning technique, respectively. Both composites demonstrate outstanding ultra-purification abilities toward ReO4 - to meet the WHO criteria even after multiple dynamic adsorption/desorption cycles. This work develops a design strategy for adsorbents applicable in the sequestration of low-concentration radioactive pollutants.

Safety assessment of introducing radioactive waste incineration facilities in Korea: An off-site resident dose evaluation

As nuclear power technology advances, radioactive waste accumulation rises, necessitating measures to alleviate strain on disposal facilities and minimize waste management costs. Analysis of radioactive waste composition revealed that combustible waste comprised the largest proportion (45 %), with incineration demonstrating high reduction efficiency for this fraction. In order for a radioactive waste incineration facility to be introduced, it is necessary to evaluate the safety of gas radioactive effluent generated during city operation. Evaluation criteria have already been established and methodologies also exist, but these results greatly depend on the area where the incineration facilities are located, the waste to be treated, the operation method of the facilities. Accordingly, this study assumed annual throughput and radionuclide concentrations based on the radioactive waste stored and generated in Korea. The centralized operation method at a specific site was compared with the decentralized operation method employed at all sites. Post-incineration, the impact of radionuclides released from the facilities was analyzed against Nuclear Safety and Security Commission standards, confirming the discharge standards and doses for single facilities and entire sites.

Determination of Decay Tank Capacity and Minimum Storage Time for Liquid Radioactive Effluent in Nuclear Medicine Departments Based on Environmental Requirements

Determination of Decay Tank Capacity and Minimum Storage Time for Liquid Radioactive Effluent in Nuclear Medicine Departments Based on Environmental Requirements

Radioactive elements in wastewater and potable water: Sources, effects, and methods of analysis and removal.

Radioactive effluents, originating from nuclear power plants, medical-nuclear applications, and various extraction industries worldwide, present a significant and dangerous contamination challenge. The concentrations of radioactive substances in wastewater, surface water, and potable water vary widely depending on the source and location. For example, cesium-137 levels in wastewater from nuclear facilities can range from 0.1 to 10 Bq/L, while tritium concentrations in surface water near nuclear plants can reach up to 100 Bq/L. Regulatory guidelines, like the maximum contaminant level of 0.185 Bq/L for combined radium-226 and radium-228 in drinking water, are critical for ensuring safety and environmental protection. Specifically, in Fukushima, Japan, cesium-137 levels in surface water range from 0.1 to 10 Bq/L due to the nuclear accident. In contrast, regions with natural uranium deposits, like parts of the United States, have reported radium-226 concentrations in potable water up to 1 Bq/L. These variations highlight the necessity for focused monitoring and evaluation to protect water quality and community health. Among various methods, Gamma spectrometry and inductively coupled plasma mass spectrometry are precise for radionuclide quantification, scintillation detectors, and ion exchange, and adsorption techniques efficiently remove radioactive substances from water. This critical review examines the sources, adverse effects, and analysis and remediation strategies for various radioactive elements in wastewater. By thoroughly evaluating the origins and potential dangers associated with radioactive effluents, this report emphasizes the urgent need for rigorous monitoring and effective treatment practices to maintain the integrity of water resources and ecosystems. PRACTITIONER POINTS: Comprehensive analysis of the radioactive elements frequently found in wastewater and drinking water. Assess the negative effects of radioactive elements in water systems. Examine the treatment methods used to eliminate radioactive pollutants from water sources. Outline effective methods and tactics for addressing and controlling radioactive contamination occurrences. Analyze the latest advancements in technology, regulatory enhancements, and optimal methods to guarantee the safety of drinking water and the sustainable handling of radioactive substances in wastewater.

Methods to Track Effective Doses from Airborne Radioactive Emissions for Compliance with 40 CFR 61, SUBPART H.

US Department of Energy national laboratories can play an integral role in not only the advancement of science but also in the treatment of various medical conditions through research and development activities conducted at radioisotope production facilities. A project has been underway at Oak Ridge National Laboratory since 2016 whose mission is to produce and supply the radioisotope 227Ac, which is used in a radiopharmaceutical developed to treat certain types of prostate cancer and bone metastases. Production activities result in the environmental release of airborne radioactive emissions, which are governed by Clean Air Act regulations described in 40 CFR Part 61, Subpart H. Stack 3039, the source that emits radioactive effluents from 227Ac production, is subject to additional requirements outlined in American National Standards Institute (ANSI) N13.1-1969 due to its grandfathered status. Radioactive emissions are limited to levels below those that would cause annual compliance dose standards for members of the public to be exceeded and stack 3039 to lose its grandfathered status. To allow for maximum production of 227Ac without exceeding relevant dose limits, monthly tracking of project emissions and resulting CAP88-PC modeled effective doses to a maximally exposed individual have been implemented. Four years of tracking data were compiled and analyzed to identify additional methods that could be used to estimate project doses more frequently, potentially further optimizing 227Ac production while maintaining compliance with applicable regulations.

Analysis of carbon‐14 discharges from Korean nuclear power plants

AbstractThe routine practice accompanying the operation of nuclear facilities involves the discharge of radioactive effluents from nuclear power plants (NPPs). Regulation of this discharge to the environment hinges on three criteria: radioactivity concentration, public dose, and radioactivity. Among these, radioactive carbon‐14 holds particular significance as it possesses an extensive half‐life of 5730 years, making it a primary source of radiation dose to communities residing around NPPs. In Korea, the monitoring of carbon‐14 discharges from pressurized water reactors (PWRs) in gaseous effluents has been ongoing since 2012, whereas before 2012, monitoring exclusively focused on carbon‐14 discharges from pressurized heavy water reactors (PHWRs). Analysis of carbon‐14 discharges from Korean PHWRs indicates that their emission constituted less than 1% of total radioactive effluents over the past two decades. In the context of Korean PWRs, carbon‐14 discharge monitoring was absent from 2002 to 2011, resulting in an absence of data regarding such discharges during that period. After introducing carbon‐14 discharge monitoring in gaseous effluents from Korean PWRs, emissions from 2012 to 2021 contributed 3% of the total gaseous effluents. These findings indicate that despite being the primary contributor to public dose, carbon‐14 discharges from NPPs constitute a minor portion of the radioactive effluent discharge.

A Supramolecular Organic Framework‐Mediated Electrochemical Strategy Achieves Highly Selective and Continuous Uranium Extraction

AbstractThe integration of selectivity and electron transfer ability remains a primary challenge in developing electrode materials for uranium electroextraction. Herein, a phenanthroline‐based supramolecular organic framework (MPSOF) is elaborately constructed as a pioneering cathode material through the hydrogen bond‐driven self‐assembly of melamine and 1,10‐phenanthroline 2,9‐dicarboxylic acid (PDA) for selective and continuous electrochemical uranium extraction (EUE). PDA moieties selectively capture UO22+, while the hydrogen bond‐supporting frameworks provide an efficient electron transfer channel for the redox of UO22+. These structural features enable the rapid formation and spontaneous shedding of uranium precipitate from MPSOF, allowing for the regeneration of the selective adsorption sites. As a result, MPSOF‐mediated EUE exhibits a high extraction capacity of 7311 mg U g−1 at a low voltage of −3.5 V but does not reach equilibrium. Cyclic EUE is employed to uranium extraction from simulated high‐salt radioactive effluents and attains high selectivity for uranium. The electroextraction mechanism is confirmed, wherein uranium species transform into (UO2)O2·4H2O. This work not only provides an efficient electrode material for uranium electroextraction, but also presents a novel electrochemical strategy for separation and adsorption of other radionuclides and contaminant ions.

Optimized precipitation process for the treatment of radioactive effluents from Ni-alloy decontamination using a chemical oxidation reduction process

Nuclear power plays a major role in the generation of electricity with low carbon emissions. However, it generates significant amounts of radioactive waste, mainly from contaminated metallic components such as steam generators. Decontamination is essential for the safe handling and eventual recycling or disposal of these materials. Various decontamination techniques can be utilized but chemical processes are recommended for complex geometries such as the tubular parts of steam generators. COREMIX (Chemical Oxidation REduction using nitric permanganate and oxalic acid MIXture) is a process that is similar to the CORD (Chemical Oxidation Reduction Decontamination) process currently utilized in the industry which involves dissolving the contaminated oxide layers from metallic surfaces. This process generates a large quantity of radioactive effluent that requires appropriate treatment. The objective is to reduce metallic concentration and the radioactivity by precipitating metals in solution as hydroxides M(m-n)(OH)n (with m the oxidation number of the metal M). The optimization of a two-step precipitation protocol is presented here, with a study of the contact time (1–24 h) and the reagents used (NaOH and KOH). The resulting precipitates from this process are characterized using several techniques (FTIR, TGA and XRD). Tests were conducted on surrogate samples to demonstrate the viability of the process on more complex samples. Finally, the optimized protocols were implemented on radioactive Ni-alloy samples. Decontamination factors were calculated portraying the efficiency of both the COREMIX and the subsequent two-stage precipitation process. Characterization of the sludge produced during the process shows that the precipitate obtained at pH 8.5 consists mainly of iron (III) oxide-hydroxides, whereas the precipitate obtained at pH 12 is mainly composed of manganese (II,III) oxide. The optimization steps show that the contact time during the first precipitation and the choice of precipitants does not influence the efficiency of the protocol while the destruction of oxalic acid proves to be critical to quantitatively precipitate chromium. Ultimately, the COREMIX process can effectively decontaminate contaminated Ni-alloy samples, removing between 12% and 14% of the contamination in each cycle. Decontamination of effluent using the precipitation protocol results in a very high decontamination factor of between 3000 and 6000.

Features of Management with Biological Waste of Patients after Radioiodotherapy in Different Countries

The analysis of existing in different countries of the world approaches to the management of liquid radioactive waste (LRW) of patients generated during radionuclide therapy with 131I is carried out. The regulated values are given, on the basis of which criteria for the discharge of LRW containing 131I into a centralized urban sewage system are established for medical organizations in a number of countries. The most common strategies for the management of patients’ LRW after radiotherapy are considered. Compliance with the discharge criteria may be achieved by delaying radioactive effluents for decay in specially designed delay tanks or by its dilution with inactive effluents of a medical organization at the discharge point. The chosen strategy should be determined by the parameters characterizing the discharges of a particular organization, so as not to affect the capacity of the department and, as a result, the availability of the radiotherapy procedure to patients in the country. Defining a case-by-case treatment strategy or using the two strategies considered in combination with each other may be a more effective practice for treating patients with LRW. The latter may be relevant for medical organizations in Russia, where the discharge criteria is conservative, and at the legal level it is prohibited to use another strategy for handling LRW, except for storage for decay.

Uranium capture from aqueous solution using palm-waste based activated carbon: sorption kinetics and equilibrium

Carbonaceous materials produced from agricultural waste (palm kernel shell) by pyrolysis can be a proper type of low-cost adsorbent for wide uses in radioactive effluent treatment. In this context, the as-produced bio-char (labeled as PBC) and its sub-driven sulfuric acid and zinc oxide activated carbons (labeled as PBC-SA, and PBC-Zn respectively) were employed as adsorbents for uranium sorption from aqueous solution. Various analytical techniques, including SEM (Scanning Electron Microscopy), EXD (X-ray Diffraction), BET (Brunauer–Emmett–Teller), FTIR (Fourier Transform Infrared Spectroscopy), and Zeta potential, provide insights into the material characteristics. Kinetic and isotherm investigations illuminated that the sorption process using the three sorbents is nicely fitted with Pseudo-second-order-kinetic and Langmuir isotherm models. The picked data display that the equilibrium time was 60 min, and the maximum sorption capacity was 9.89, 16.8, and 21.9 mg/g for PBC, PBC-SA, and PBC-Zn respectively, which reflects the highest affinity for zinc oxide, activated bio-char, among the three adsorbents, for uranium taking out from radioactive wastewater. Sorption thermodynamics declare that the sorption of U(VI) is an exothermic, spontaneous, and feasible process. About 92% of the uranium-loaded PBC-Zn sorbent was eluted using 1.0 M CH3COONa sodium ethanoate solution, and the sorbent demonstrated proper stability for 5 consecutive sorption/desorption cycles.

Research on the Transboundary Environmental Damage Caused by the Discharge of Nuclear Wastewater in Japan

Neighboring nations voiced severe protests when Japan unilaterally declared on August 23, 2023, that it intended to release radioactive effluent stockpiled since the Fukushima nuclear accident in 2011 into the ocean. Japan clearly breaches international law by acting in a way that is contrary to its duties for reasonable risk prevention, notification, and transboundary environmental impact assessment. In the international community, the question of transboundary injury accountability and compensation has long been of concern. International conventions addressing transboundary pollution are mostly framework agreements with soft law provisions, which means that their substantive impact on contracting parties' behavior is minimal. This article examines the national and personal obligations that the party in control of this nuclear wastewater discharge should have by combining concepts of international law, including the principle of attribution, state sovereignty, and international environmental protection. It examines the characteristics of international transboundary damage liability and compensation schemes from the standpoint of governments taking on international environmental responsibility.

A hybrid model based on STL with simple exponential smoothing and ARMA for wind forecast in a Brazilian nuclear power plant site

In the event of a nuclear accident with release of radioactive effluents into the environment, the Environmental Control System (ECS) at the Central Nuclear Almirante Álvaro Alberto (CNAAA) nuclear complex estimates the movement of the radioactive plume produced and provides forecast for one and two hours ahead. The prediction is based on the current accident and atmospheric data collected from meteorological stations spread across the site. In this way, the ECS estimates the spatial dose and dose rates distribution at ground level. The one- and two-hour forecast made by the ECS use the naïve method, which repeats the last known value. Its results are satisfactory if the next value to be collected does not differ substantially from the last known value. However, observing real data, acquired in loco, this fact does not occur in practice, which can make the forecast considerably erroneous.The purpose of this work is to investigate new approaches to improve ECS forecasting method, making it more accurate in real situations. To this end, the Seasonal and Trend decomposition using Loess (STL) was used together with the Simple Exponential Smoothing (SES) method and the Autoregressive Moving Average (ARMA) model to forecast weather parameters at the Angra site. The STL method was chosen since it has a robust mathematical decomposition method, capable of satisfactorily dealing with time series that have a high frequency of acquisition, the so-called intraday series. This model uses the Loess method, which is a smoothing technique based on locally adjusted regressions. The SES method and ARMA model are the techniques that most adequately fit the trend and remainder components generated by the STL decomposition, respectively. In the scope of this work, the method is applied to forecast wind speed measurements made at one of the meteorological towers used by the ECS. Using the hybrid model developed, an increase the of 101.39% in the Mean Absolute Percentage Error (MAPE), was achieved when compared to the ECS forecast method.

Assessment of Radiation Doses to the General Public around Nuclear Power Plants Based on Representative Person Concept.

The International Commission on Radiological Protection recommended that the representative person concept should be used in radiation dose assessment of the general public to specify exposed individuals. The objective of this study is to assess radiation doses of the residents around nuclear power plants (NPPs) in relation to the introduction of the representative person concept. Critical group candidates and representative agro-livestock product producing areas were selected around a NPP site by considering radioactive effluents and regional meteorological data, geographical information, etc. A total of five exposure scenarios, including adult (non-fishery, fishery, and commuter), 10-y-old, and 1-y-old groups, were selected for the dose assessment. Generally, radiation doses were higher for 1-y-old, 10-y-old, and adult groups, in that sequence. There was no significant difference among the radiation doses by occupation in adult groups. Radiation dose results calculated by applying the representative person concept and dose assessment method currently used in Korea were compared. Application of the representative person concept results in lower radiation dose by 68.2% due to consideration of actual residential and agro-livestock product producing areas for the radiation dose assessment, by 13.3% due to the application method of habit data for dose calculation, and by 33.3% due to representative value of the dose results. Finally, considering all the factors above, radiation dose calculated by the current dose assessment method was 8.16 × 10 -2 mSv y -1 , while that calculated using the representative person concept was 1.40 × 10 -2 mSv y - 1 (82.8% lower). The results of this study can be used as reference data when introducing the representative person concept to the regulatory systems in Korea.

Study on the actual particle size, activity concentration, and migration process adsorption behavior of radioactive substances in liquid effluents from nuclear power plants

Radionuclides emitted by nuclear power plants may have effects on the environment and public health. At present, research on radioactive material effluent in the industry mainly focuses on the treatment of radioactive effluent and the particle size distribution of the primary circuit. There is little research on the particle size of radioactive material during the migration process outside the primary circuit system, as well as the flocculation precipitation and other enrichment phenomena during the collection process of effluent. Therefore, this study relies on the sampling of effluent from an in-service nuclear power plant to measure its radioactivity level by particle size range. At the same time, the mixing process of effluent is simulated in the laboratory to simulate the adsorption behavior of effluent during the migration process. It was found that in the activity concentration of detectable radioactive nuclides in the effluent samples, more than 95% of radioactive nuclides exist in the liquid with particle sizes less than 0.1μm, while particle sizes greater than 0.45 μm account for less than 5%. After the sample was filtered by the demineralizer, the radioactive activity decreased. The flocculation precipitation in the waste liquid of the waste water recovery system has a certain contribution to the enrichment of nuclides. With the extension of time, the enrichment of transition elements such as cobalt and manganese is particularly obvious, so that it is distributed in the liquid again with a large particle size. In addition, large particle size substances such as colloids in seawater have a certain adsorption effect on radionuclides, which will lead to its aggregation effect again.

Photocatalytic Th(IV) removal: Unleashing the potential of amidoxime-modified graphitic carbon nitride photocatalyst

g-C3N4-AX photocatalyst was synthesized using a hydrothermal approach, with urea as a precursor, for the removal of Th(IV) in aqueous solution. The results of the experiment indicated that the addition of amidoxime to g-C3N4 altered its photocatalytic characteristics, resulting in a narrower band gap reduced from 2.75 eV to 2.7 eV, and faster formation of electron-hole pairs. The g-C3N4-AX photocatalyst exhibited remarkable uptake capacity with 71.09 mg.g−1 within 120 min. The excellent performance of g-C3N4-AX was mainly attribute to its effective absorption of visible light, facilitated by the narrow band gap. Therefore, this study proposes the potential of g-C3N4-AX can be efficiently adapted as a visible light-responsive catalyst for the application in radioactive effluent treatment.

Layered metal sulfides with MaSbc- framework (M = Sb, In, Sn) as ion exchangers for the removal of Cs(Ⅰ) and Sr(Ⅱ) from radioactive effluents: a review.

Nuclear power has emerged as a pivotal contributor to the global electricity supply owing to its high efficiency and low-carbon characteristics. However, the rapid expansion of the nuclear industry has resulted in the production of a significant amount of hazardous effluents that contain various radionuclides, such as 137Cs and 90Sr. Effectively removing 137Cs and 90Sr from radioactive effluents prior to discharge is a critical challenge. Layered metal sulfides exhibit significant potential as ion exchangers for the efficient uptake of Cs+ and Sr2+ from aqueous solutions owing to their open and exchangeable frameworks and the distinctive properties of their soft S2- ligands. This review provides a detailed account of layered metal sulfides with MaSb c- frameworks (M = Sb, In, Sn), including their synthesis methods, structural characteristics, and Cs+ and Sr2+ removal efficiencies. Furthermore, we highlight the advantages of layered metal sulfides, such as their relatively high ion exchange capacities, broad active pH ranges, and structural stability against acid and radiation, through a comparative evaluation with other conventional ion exchangers. Finally, we discuss the challenges regarding the practical application of layered metal sulfides in radionuclide scavenging.

Bioremediation of uranium (Ⅵ) using a native strain Halomonas campaniensis ZFSY-04 isolated from uranium mining and milling effluent: Potential and mechanism

A significant surge in the exploitation of uranium resources has resulted in considerable amounts of radioactive effluents. Thus, efficient and eco-friendly uranium removal strategies need to be explored to ensure ecological safety and resource recovery. In this study, we investigated the resistance of Halomonas campaniensis strain ZFSY-04, isolated from an evaporation pool at a uranium mine site, and its potential mechanism of uranium (Ⅵ) removal. The results showed that the strain exhibited unique uranium tolerance and its growth was not significantly inhibited under a uranium concentration of 700 mg/L. It had a maximum loading capacity of 865.40 mg/g (dry weight), achieved following incubation under uranium concentration of 100 mg/L, pH 6.0, and temperature 30 °C, for 2 h, indicating that the removal of uranium by the strain was efficient and rapid. Combined with kinetic, isothermal, thermodynamic, and microspectral analyses, the mechanism of uranium loading by strain ZFSY-04 was metabolism-dependent and diverse, including, physical and chemical adsorption on the cell surface, extracellular biomineralisation, intracellular bioaccumulation, and biomineralisation. Our results highlight the unique properties of indigenous strains, including high resistance, high efficiency, rapid uranium removal, and various uranium removal strategies, which make it suitable as a new tool for in situ bioremediation and uranium-contaminated environmental resource recovery.

A multiparametric study on the behavior of mesoporous silica under electron irradiation

Grafted mesoporous silica is believed to be a candidate for the decontamination of radioactive effluents and the final storage of radionuclides. Under this condition, silica is subjected to continuous electron irradiation due to beta decay of radionuclides. This paper examined two mesoporous silica (SBA-15 and MCM-41) under high-energy electron beam irradiation (0.6 MeV <E < 2.4 MeV). The results showed that the pore structure of both mesoporous silica pellets shrank for all the samples (with 40 % < ΔVpores < 60 % at 8 × 1018 e-/cm2), while no significant damage was observed in the amorphous silica network. The main reason for the structural changes was attributed to electron beam radiation-induced fluidization. Additional experiments conducted with numerous incident electron energies provided more detailed support, confirming that the radiolytic process was the primary cause of fluidization. These findings contribute to a better understanding of electron-irradiation-induced damage and may lead to novel approaches for handling radionuclides with mesoporous materials.

Magnetic flocculants and selective adsorbents for the decontamination of radioactive and acidic soil-washing effluent

We demonstrate that radioactive 137Cs-suspended soil and 137Cs+ ions in the effluent can be sequentially removed, enabling the effluent to be reused or released. Specially synthesized coagulant-flocculants and adsorbents were used to remove Cs-suspended soils and Cs+ ions under strongly acidic conditions. Polyethyleneimine coated magnetic nanoparticles (PEI-MNPs) was found to be the best coagulant-flocculants for removing Cs-suspended soil among various coagulant-flocculants, including inorganic, organic, and organic-inorganic ones. To optimize the separation conditions, such as the dosage and composition of the coagulant-flocculants and adsorbents, a nickel potassium hexacyanoferrate -embedded polyacrylonitrile (NiFC/PAN)-3.5, defined as a NiFC/PAN weight ratio of 3.5, was used to successfully remove Cs+ ions in nonradioactive and radioactive tests, meeting the release criterion of 50 Bq L−1 (South Korea). In the first step, the radioactivity of the effluent was reduced from 380 to 300 Bq L−1 by separating 137Cs-suspended soils with PEI-MNP coagulant-flocculants. In the next step, 137Cs ions were substantially removed using NiFC/PAN, resulting in a decrease of the radioactivity from 300 to 20 Bq L−1, which meets the release criterion. These results suggest that the proposed process is a potentially useful and effective method for treating radioactive effluent after soil washing.

Polyphosphonate-segmented macroporous organosilicon frameworks for efficient dynamic enrichment of uranium with in-situ regeneration

Efficient separation and enrichment of uranium from radioactive effluents is of strategic significance for sustainable development of nuclear energy and environmental protection. Macropore structure of adsorbent is conducive to accessibility of the pore and transport of the adsorbate during dynamic adsorption. However, the low specific surface area results in fewer ligand sites and subsequently reduces the adsorption capacity. Herein, we present a novel strategy for efficient dynamic uranium enrichment using polyphosphonate-segmented macroporous organosilicon frameworks (PMOFs). PMOFs are constructed through the copolymerization of diethyl vinylphosphonate and triethoxyvinylsilane, followed by hydrolysis and condensation of the oligomers. The introduction of polyphosphonate segments into the frameworks endows PMOFs with a macroporous structure (31 µm) and a high ligand content (up to 72 wt%). Consequently, the optimized PMOF-3 demonstrated an ultrahigh dynamic adsorption capacity of 114.8 mg/g among covalently conjugated silicon-based materials. Additionally, PMOF-3 achieves a high enrichment factor (120) in the dynamic enrichment of uranium on a fixed bed column, which can be in-situ regenerated with 1 M NaHCO3 as the eluent. This work presents a new strategy for efficient dynamic enrichment of nuclides, which can be extended to the separation of other specific pollutants, shedding new light on adsorbent design and technical innovation.