Amount Of Uranium Research Articles

Trace elements and the environmental factors influencing early life-growth of the squid, Uroteuthis duvaucelii

The early growth of Indian squid, Uroteuthis duvaucelii, was examined in specimens with sizes ranging from 41 – 215 mm ML from fisheries catches in coastal waters of Central Philippines. The linear relationship between mantle length and statolith radial length indicates that statolith growth is proportional to body size growth. At 60 days after hatching in different months, growth trajectories revealed high individual growth variability. At this age, monsoons influenced the growth variation and seasonality of U. duvaucelii, revealing the squid’s high growth plasticity and adaptability towards changes in environmental conditions. During the first 40 days, the growth of female U. duvaucelii was significantly influenced by ambient temperature and food availability, indicating that these factors play a crucial role in the survival of their young. Hatching occurs continuously throughout the year, with prominent peaks in July and October. The lateral dome of the statolith contains significant amounts of trace elements, including strontium (Sr), uranium (U), magnesium (Mg), barium (Ba), and sodium (Na), which are known to be correlated with environmental conditions, habitat, and physiology of squids.

The Impact of Induced Industrial and Urban Toxic Elements on Sediment Quality

Abstract: The increasing population has subjected rivers and streams to high levels of both industrial and domestic pollution. Significant environmental challenges have been brought about by their effects, particularly with regard to biota, ecosystem processes, soil quality, and groundwater pollution. This study examined the effects of human activity by applying pollution index models to evaluate the input of toxic elements in river sediments. Prior to sediment quality analysis, the total amount of arsenic (As), lead (Pb), cadmium (Cd), mercury (Hg), thorium (Th), and uranium (U) was determined in the concentration range of 1.09–10.0 mg/kg, 8.53–475 mg/kg, 0.12–0.16 mg/kg, 4.85–77.5 mg/kg, 3.14–5.9 mg/kg and 0.93–2.86 mg/kg, respectively. The enrichment factor, contamination factor, pollution load index, and geo-accumulation index revealed alarmingly high levels of Pb and Hg contamination at some sampling points, which are related to possible human input, ranging from severe enrichment to considerable contamination. The low ranges of pollution indices of some toxic elements suggest enrichment through the natural weathering process and atmospheric deposition. The Pearson correlation coefficient revealed a significant correlation between Pb-Fe and As-Fe, suggesting the possibility of acid mine contamination. Continual monitoring of river sediment is essential to minimize the impact of toxic elements to sustain sediment health and quality.

Bioremediation of uranium enriched coal fly ash based on microbially induced calcite precipitation

Coal fly ash (CFA) is an essential raw material in brickmaking industry worldwide. There are some coal mines with a relatively high content of uranium (U) in the Xinjiang region of China that are yet understudied. The CFA from these coal mines poses substantial environmental risks due to the concentrated uranium amount after coal burning. In this paper, we demonstrated a calcifying ureolytic bacterium Halomonas sp. SBC20 for its biocementation of U in CFA based on microbially induced calcite precipitation (MICP). Rectangle-shaped CFA bricks were made from CFA using bacterial cells, and an electric testing machine tested their compressive strength. U distribution pattern and immobility against rainfall runoff were carefully examined by a five-stage U sequential extraction method and a leaching column test. The microstructural changes in CFA bricks were characterized by FTIR and SEM-EDS methods. The results showed that the compressive strength of CFA bricks after being cultivated by bacterial cells increased considerably compared to control specimens. U mobility was significantly decreased in the exchangeable fraction, while the U content was markedly increased in the carbonate-bound fraction after biocementation. Much less U was released in the leaching column test after the treatment with bacterial cells. The FTIR and SEM-EDX methods confirmed the formation of carbonate precipitates and the incorporation of U into the calcite surfaces, obstructing the release of U into the surrounding environments. The technology provides an effective and economical treatment of U-contaminated CFA, which comes from coal mines with high uranium content in the Xinjiang region, even globally.

Zircon Internal Deformation and Its Effect on U-Pb Geochronology: A Case Study from the Himalayan High-Pressure Eclogites

Zircon, with a chemical formula of ZrSiO4, is a widely used mineral for determining the crystallization age of igneous rocks. It is also used to constrain the timing of metamorphic events from its overgrowth or recrystallized domains. Furthermore, detrital zircon grains can provide information on the sedimentary provenance. Due to the trace amounts of uranium (parent) which decays into its daughter element (Pb), it is a prime geochronometer for the majority of magmatic and metamorphic rocks. With high-precision analytical instruments, such as TIMS, SIMS, and LA-ICP-MS, huge amounts of geochronological and trace element data from zircon have been generated around the globe to date. Target domains within zircon grains are analyzed to extract geochemical and geochronological records using spatially resolved techniques such as ion probes or laser ablation coupled with mass spectrometry. Before any such analysis, the zircon grains are examined for internal structures, growth zoning, and the presence of tiny inclusions. However, many researchers analyze multiple domains within single zircon grains for U-Pb isotope analysis with little regard for their internal structures, particularly crystallographic orientations. Hence, they may obtain mixed ages with variable discordance, leading to imprecise interpretation especially when the growth domains are not well-identified. Particularly, zircon grains that contain multi-growth domains or have local internal deformations within a single grain may not produce geologically meaningful age results if the analyses are conducted on mixed domains. This study presents a brief review on zircon geochronology, how to identify and visualize micro-deformations in metamorphic zircons through the EBSD analysis, and the effects of micro-deformation on age results. Examples from a case study conducted on zircons hosted in the Himalayan high-pressure eclogites are presented that show intra-grain plastically deformed domains and their effects on the corresponding age results.

Behavior of uranium(VI) in the presence of a geomaterial: an aquifer sediment

Sediments from aquatic environments can be contaminated with uranium from natural and anthropogenic sources; the behavior of U(VI) was investigated in two natural (SPT and DS) and gamma-irradiated (SPT-I) aquifer sediments in batch systems. Sediments were characterized, and quartz, albite, and kaolinite were mainly found in both sediments by X-ray diffraction. The points of zero charge were 5.4, 5.3, and 5.5, and the organic matter percentages were 48.0, 46.0, and 4.7% for SPT, SPT-I, and DS, respectively. Uranyl nitrate solutions were put in contact with each sediment considering different parameters (pH, contact time, initial concentration of uranium, and temperature). DS sediment did not adsorb any quantity of uranium at different pH values; SPT and SPT-I, attained the highest q e values at pH 3.5–4. The results show chemisorption on homogenous materials and endothermic processes. Desorption behavior of U(VI)/SPT showed a hundred percent desorption with nitric acid and humic acid solutions; in the last case, it is due to the high stability constant of the complex of uranium with the humic acids. The results help to understand the contamination and decontamination processes of sediments with uranium, the bioavailability of uranium, the ecological risk of U-contaminated sediments, and remediation. Doses of 1 MGy of Co-60 gamma radiation did not affect the uranyl ions behavior in the aquifer sediment.

Radiological Risk Assessment of Uranium, Thorium and Potassium in Siluriformes and Oreochromis Niloticus in Baga, Borno State

The study of radiological risk assessment plays a crucial role in understanding the potential impact of radioactive elements on the environment and human health. Uranium, thorium, and potassium are naturally occurring radioactive elements commonly found in various geological formations worldwide. Their presence in aquatic ecosystems, such as rivers, lakes, and reservoirs, raises concerns regarding potential exposure and associated risks to aquatic organisms and humans (Ajayi et al., 2018; Syarbaini et al., 2014; Hamidalddin et al., 2016). In October 2023, two fish samples were obtained from Baga, Kukawa, Borno State. Sample A was catfish, while Sample B was tilapia. The amounts of uranium, thorium, and potassium were the main topics of the radiological risk assessment performed on the samples. Following a seven-day sun-drying process, the fish were ground into a powder and carefully sent to the Obafemi Awolowo University's Centre for Energy Research and Development in Ile-Ife, Osun State. The findings showed that both catfish and tilapia contain certain radionuclides (uranium, thorium, and potassium), their anticipated annual effective dose rates from consumption are relatively modest. It was discovered that the computed dose rates for tilapia (Sample B) and catfish (Sample A) were significantly lower than the global average for the yearly effective dosage limit for the general public, which is normally set at 1 millisievert (mSv) annually. In particular, the estimated annual effective dose rate were 3.190758 μSv/year and 4.021574 μSv/year for Sample A and B respectively. These results imply that eating tilapia and catfish is unlikely to expose the general public to radiation levels higher than dose recommended by international agreements. The investigation concludes that eating tilapia and catfish is compliant with international standards for radiation exposure from food. Nevertheless, maintaining ongoing food safety procedures depends on constant observation and adherence to changing regulations.

STUDY OF THE EFFECTIVENESS OF METHODS FOR INCREASING THE PRODUCTIVITY OF URANIUM THROUGH PRELIMINARY FORECASTING

A study was conducted of the effectiveness of methods for increasing the productivity of uranium through preliminary forecasting. The objective of this study is to analyze and optimized the technological block currently in production. To analyze the performance of a block or cell different performance indexes are used: Tracer cut, Tracer in Place, Acid in place. Several scenarios of optimization have been tested using the HYTEC reactive transport program and modeling the uranium mining process. These scenarios involved new wells and the impact of "chemical well treatment" that increases the productivity of well. This work focused on improving the production of block. Three different scenarios were performed. Among the three scenarios, the third produced the highest amount of uranium 133 tons out of 154 tons of reserves. During optimization it is better to get the right efficiency value for each well's last trend in the cleaning action excel file. After chemical treatment of the well it was possible to increase the area where pH<1.85. This shows the importance of optimization and chemical treatment of the well.

A study of the concentration of uranium in soil samples was evaluated using the CR_39 detector in the south of Amara Governorate

The quantity of uranium in soil samples taken from various residential, industrial, and agricultural areas in southern Iraq's Southern Omara governorate was evaluated using the neutron activation technique for solid-state nuclear track detectors CR-39. Uranium values in soil samples varied from 0.77 ppm to 1.94 ppm, according to the findings. Soil samples were collected at a depth of 10 cm. The outcomes were compared to publicly available data and found to be within acceptable ranges.

Sensitive 236U/238U Isotopic Analysis of Trace Uranium in Safeguards Environmental Samples Using Multicollector Inductively Coupled Plasma Mass Spectrometry.

A sensitive analytical technique was developed for determining a 10-7 level low 236U/238U ratio using multicollector inductively coupled plasma mass spectrometry. This analytical technique can determine the subnanogram amount of uranium in safeguards environmental samples. To increase the sensitivity of the 236U/238U ratio, (1) the feed solution was concentrated to one-tenth of that in the conventional method and (2) data acquisition was started from the beginning of the solution uptake until all of the solution was exhausted. All signal intensities were recorded. This technique was applied to the IRMM-184 uranium isotopic standard solution with a 1.2410 × 10-7 236U/238U ratio. The IRMM-184 uranium solution (0.2 mL of 1 ng g-1 uranium) was prepared, and the 236U/238U ratios were determined using our new data collection method. The 236U/238U ratios were in agreement with the certified value within the uncertainty (k = 2) evaluated using the Guide to the Expression of Uncertainty in Measurement (GUM) workbench. The uncertainties obtained with this new technique (32% on average) were revised to be 10 times smaller than those obtained with the conventional method using 0.1 ng g-1 IRMM-184. The tailing effect from the 238U intense peak was determined using 10 times higher concentrations of NBL CRM U0002 uranium isotopic standard solution (10 ng g-1 uranium) to improve its uncertainty. Approximately 1-2% of the uncertainties of 236U/238U could be further reduced using this improved correction factor.

Absorbed dose rates and biological consequences of discrete alpha-emitting particles embedded in tissue

This study calculates dose rate in Gy y-1 for individual dust, soil, and sediment particles that contain significant amounts of alpha-emitting uranium or thorium. When inhaled or ingested, these particles deliver radiation dose to organs where they embed. The presented method uses X-ray microscopy to measure alpha emitting elements in environmental microparticles, followed by calculation of dose rates delivered to the targeted volume of tissues that surround embedded microparticles. The example calculations use a real-world, 89% uranium house dust particle.

Mineralogical and geochemical studies on the Qianjiadian deposit, Songliao Basin, NE China: Insights into multiple metallogenic processes in the sandstone-type uranium deposit

Sandstone-type uranium deposits usually exhibit a range of metallogenic mechanisms. To gain insights into the nature, genetic relationships, and mineralization mechanisms of uranium and associated minerals, representative samples from the Qianjiadian uranium deposit in the Songliao Basin were investigated through detailed mineralogical, elemental geochemical, and in-situ sulfur isotopic analyses. The results provided invaluable information on the various stages of uranium mineralization. During the early diagenetic stage, uranium mineralization occurred in the local organic matter (OM)-enriched sites (TOC = 0.70 ∼ 2.05 %) in the Yaojia Formation. The paragenetic relationship revealed that uranium was firstly precipitated as pitchblende along with the biogenetic framboidal pyrite (δ34S values ranging from −44.1 ‰ to −1.8 ‰) through bacterial sulfate reduction (BSR) process. Simultaneously, organic acids generated through biodegradation of OM caused an acidic fluid condition and subsequent dissolution of feldspars, resulting in the production of kaolinite intergrowth with pitchblende. During the late diagenetic stage, the ore-forming fluid turned alkaline, leading to the conversion of pitchblende into coffinite, with elevated elements such as Si, P, Ca, Zr, and Y in the altered phase. In addition to the contribution of OM and sulfate-reducing bacteria (SRB), pyrite was confirmed as a reducing agent manifested by its replacement by uranium minerals and the Fe-oxide produced along the boundaries. The diagenetic uranium enrichment is mainly hosted in the gray sandstone that experienced reduced alteration of deep hydrocarbons, resulting in pervasive kaolinization and promotion of reduction potential. A significant amount of uranium was fixed by adsorption, as evidenced by the rare observation of independent uranium minerals, but the higher whole-rock U content (U = 133.5 ∼ 394.0 ppm) and the detection of U signal in micro-XRF analysis and EPMA data (U content in representative kaolinite ranges from bld to 0.74 wt%). Overall, the formation of sandstone-type uranium deposits is a long-term and multi-stage process. The early enriched uranium during synsedimentary-diagenetic stages is non-negligible and can even result in an appreciable amount of mineralization, further serving as an important source for the subsequent secondary enrichment.

Impact of Dilute Amounts of Fission Products on the Mechanical Behavior of Ni.

Fission products may interact with structural materials in various nuclear energy applications and cause their mechanical performance to deteriorate. Therefore, it is important to study the effects of different fission products on the mechanical properties of structural materials. In this work, nickel was chosen as a model structural material system and dilute amounts of uranium and fission product impurities X = (Tc, Te, Sb, Ce, Eu, and U) up to 4 at % were used. Density functional theory (DFT) calculations were utilized to assess the effects of these substitutional impurities on the elastic behavior of the metal. Additionally, DFT was used to investigate some aspects of plastic response by computing the generalized stacking fault energies on the {111} ⟨112⟩ slip system for all alloying elements and at varying distances away from the stacking fault plane. None of the dopants satisfied the Pugh or Pettifor criteria for embrittlement, and alloying with Tc led to a slight increase in the elasticity of nickel. The phenomenon of Suzuki segregation was observed for all alloying elements, and there was consequently a significant reduction in the intrinsic stacking fault energy. Finally, and based on the analysis of the stacking fault energies, dopants generally led to softening the nickel (except for Tc and Ce), and all of the dopants were correlated with a loss of ductility (except Eu). These findings may be useful to consider in the design of next-generation reactors and nuclear waste management systems.

MAPPING RADIOACTIVITY IN CONTINENTAL TERMINAL 3 (CT3) FORMATIONS: THE CASE OF THE THREE SISTERS, NIAMEY REGION (EASTERN EDGE OF THE WEST AFRICAN CRATON, ILLUMMEDEN BASIN)

The Continental Terminal 3 (Ct3) formations, which rest in major unconformity on the Birimian basement of the West African Craton, correspond to the last filling deposits of the Iullemmeden basin in the Niamey region (West, Niger). The general objective of this study is to produce a surface radiometric map of the Niamey Three Sisters Hills area. The methodology used included field and laboratory work, with radiometric data processed using Surfer software. Radioactivity values in the Three Sisters area ranged from 5 to 25 shocks per second (C/s). High radioactivity values (15 to 25 c/s) are recorded in the upper terms, corresponding to the breastplates. Low values of radioactivity (5 to 15 c/s) are measured in the basal layers, corresponding to clays and alluvium. This radioactivity is thought to be due to trace amounts of uranium in these outcrops.

Optimization of conceptual design on the lead-based modular nuclear power reactor core loaded with U-10Zr alloy fuel

As one of the forth-generation nuclear energy system reactor types, lead fast reactor has good safety and economical properties due to the stable chemical properties of the coolant and the proliferation characteristics of the fuel, and modular nuclear power faster reactor designed for nuclear plant can further improve the economics of the reactor. In this article, the conceptual design of the lead-based modular power reactors with different power levels loaded with uranium alloy fuel is found to be found that when reactor core size increased to a certain level, the proliferation performance is too high due to the increase of the reactor core size under a specific core life such as 2000EFPD, so at the end of core life, the reactor core still has a large remaining reactivity. The proliferation advantage of the core cannot be fully released during the current core life time. Based on this phenomenon, in this article, we optimized the conceptual design of lead-based modular nuclear power reactor core loaded with uranium alloy fuel, and proposed to choose the appropriate rod to diameter ratio and effective density of fuel based on the power level and life time of the core. By adjusting the amount of uranium and 235U per unit volume, the proliferation performance of the core can be changed to match the power level and life time of the core. So the reactivity of core during the life period does not change, which not only reduce the difficulty of the reactivity control, but also make full use of the proliferation performance of the core. And at the same time, the reasonable rod to diameter ratio can provide safety and design margin for the analysis of thermal and hydraulic safety, and effectively improve the economy and safety of the core.

Rapid and non-destructive quantification of trace to minor concentrations of Uranium in ores, minerals and reference materials by instrumental neutron activation analysis using high-flux pneumatic carrier facility of Dhruva reactor

ABSTRACT Rapid and non-destructive determination of trace quantities of Uranium in “as received” solid samples using a suitable analytical method is a challenging task. Uranium can be quantified by Instrumental Neutron Activation Analysis (INAA) using both short lived (239U) and medium-lived (239Np from decay of 239U) activation products. In the present work, INAA method has been optimised in terms of sample mass, duration of irradiation, lesser decay period and faster counting to acquire reasonable counts (peak area) under the peak of interest. Pneumatic Carrier Facility (PCF), high neutron flux (5 × 1013 n/cm2 /s at 50 MW power) at Dhruva research reactor, has been advantageously utilised for short duration irradiation (1 min) of the samples. Quantification of Uranium utilising 239U short-lived activation product (23.5 min half-life) formed after short irradiation, makes the methodology faster without any longer decay time. Immediately after 1 min of irradiation, the short-lived 239U activation product showed higher analytical sensitivity compared to that of medium-lived activation product (239Np) having gamma-rays at 106 and 277 keV. The detection limit of uranium was found to be much lower when it was calculated using 239U activation product. A comparative study was carried out between the short and medium lived activation products of 238U. The method was applied for determination of trace quantities of total Uranium in ores and minerals like Zircon, Ilmenite and Rutile having complex matrices. INAA method was validated by analysing USGS CRMs like STM-1, RGM-1 and AGV-1 and IAEA RM RGU-1. The detection limit was found to be around 1 ppb for the analysed solid samples (ores and minerals).

Multi-functional microparticles constructed by steerable phase separation process for synchronous uranium selective extraction and heat storage

Nuclear wastewater contains large amounts of uranium and waste heat, and hence synchronous uranium selective extraction and heat storage from nuclear wastewater are of prime importance. Herein, a series of distinctive dual-functional absorbents, such as P(St-VA)-1, P(St-VA)-2, P(St-VA)-3, were developed through photoinitiated interfacial polymerization via emulsion templates, using styrene and ethylene phosphate as co-monomers. The P(St-VA) has dual-functions, i.e., waste heat storage and uranium extraction. The uranium extraction feature is derived from the phosphoric acid group, while paraffin was encapsulated inside the P(St-VA). The concentration of sodium dodecyl sulfate (SDS) determines the rate and extent of phase separation between styrene and paraffin via tuning the size and stability of the emulsion, and hence the morphology and functionality of the P(St-VA). The P(St-VA) demonstrates excellent uranium adsorption performance with prominent selectivity. Furthermore, the P(St-VA) underwent multiple phase transitions between 25℃ and 70℃, displaying endothermic and exothermic behaviours and great heat storage potential. This study has provided an innovative path for the synchronous recycling of uranyl ions and waste heat from nuclear wastewater for practical applications.

A marine bacteria-inspired electrochemical regulation for continuous uranium extraction from seawater and salt lake brine.

Oceans and salt lakes contain vast amounts of uranium. Uranium recovery from natural water not only copes with radioactive pollution in water but also can sustain the fuel supply for nuclear power. The adsorption-assisted electrochemical processes offer a promising route for efficient uranium extraction. However, competitive hydrogen evolution greatly reduces the extraction capacity and the stability of electrode materials with electrocatalytic activity. In this study, we got inspiration from the biomineralisation of marine bacteria under high salinity and biomimetically regulated the electrochemical process to avoid the undesired deposition of metal hydroxides. The uranium uptake capacity can be increased by more than 20% without extra energy input. In natural seawater, the designed membrane electrode exhibits an impressive extraction capacity of 48.04 mg-U per g-COF within 21 days (2.29 mg-U per g-COF per day). Furthermore, in salt lake brine with much higher salinity, the membrane can extract as much uranium as 75.72 mg-U per g-COF after 32 days (2.37 mg-U per g-COF per day). This study provides a general basis for the performance optimisation of uranium capture electrodes, which is beneficial for sustainable access to nuclear energy sources from natural water systems.

Distribution of U and 210PO in groundwater of Kodagu district, Karnataka, India.

Trace amounts of uranium along with its decay products are found in varying levels in natural soil, rocks, water and air. They are a matter of significant concern due to their carcinogenic nature. In the present work, the distribution of U and 210Po in groundwater of Kodagu District, Karnataka, India, was studied. The concentration of total U in groundwater samples was estimated using LASER and LED fluorimeter, and the activity of 210Po in groundwater was studied using electrochemical deposition followed by alpha counting method. The concentration of U and 210Po varied from 0.4 to 8.8 μgl-1 and 0.47 to 4.35 mBql-1, respectively. The ingestion dose due to U and 210Po in groundwater varied from 0.33 to 7.17 and 0.41 to 3.81μSv y-1, respectively. The estimated U activity was found to be well below the standard safe limits of 30 μgl-1 in drinking water, as recommended by WHO and USEPA. The 210Po activity was low compared with the recommended 100 mBql-1 standard of WHO.

Substantially excess uranium in the waters of an intertidal salt marsh: A case study of eastern Chongming Beach

Knowledge of the geochemical behavior of uranium is key to an accurate tracing of the decay chain of the uranium series nuclides for material transportation processes on different temporal scales. However, direct observations for understanding dissolved uranium input in tidal water are very limited. Therefore, dissolved uranium was measured in tidal creek water, overlying water, and pore water collected from the central cross section of eastern Chongming Beach, Changjiang Estuary, from November 2012 to October 2013, to observe the spatiotemporal distribution of uranium. The results indicated that the behavior of dissolved uranium is conservative in the tidal creek waters during the flooding process, and an excess of dissolved uranium is observed during the ebbing process; excess uranium phenomena are dominant in the overlying and pore waters throughout the year, particularly at the middle and high tidal flats. The element concentration profiles in pore water showed that uranium release follows Mn oxide reduction in the subsurface suboxic zone. Hence, the exchange process between tidal water and pore water, coupled with ebb tide, represents a potential path for uranium release into the estuary. The three-end-member (Changjiang River, seawater, and pore water) model estimates that 35% of the amount of uranium in ebbing water is derived from pore water. The exchange rate between tidal water and pore water is 196.4 nmol/(cm2·d), with an export flux of 2.34 × 104 mol/a. We suggest that the release of uranium from intertidal salt marshes is an important uranium source in estuarine and coastal regions.

Screening and signifying the uranium remediation level of Alternanthera philoxeroides and Eichhornia crassipes from aquatic medium.

Uranium is causing a hazardous impact on the human population throughout the globe. Different methods of remediation have been documented but the approach of phytoremediation has been praised throughout the globe. The bioaccumulation of uranium especially as a hyper-accumulator, has been documented in limited plant species. Therefore the current studies were conducted to elaborate on the overall U accumulation, biochemical and photochemical reactions in Alternanthera philoxeroides and Eichhornia crassipes to different concentrations of Uranium. The results showed that the accumulation of U in A.philoxeroides is higher; followed by E.crassipes; with maximum amounts of roots accumulation. Overall A.philoxeroides and E.crassipes accumulate as much as 948.88 mg/kg and 801.87 mg/kg on a dry weight basis. The biochemical results showed that Superoxide dismutase (SOD) decreased in the leaves and stem of A.philoxeroides; whereas an increase has been seen in E.crassipes in response to all treatments. peroxidase (POD) and Catalase (CAT) showed irregular response to all treatments; where the main increase was observed at T3 (120 μmol/L) and 72 h up to 138 μ/g-FW (POD) and 178 μ/g-FW (CAT) in A.philoxeroides and 1870 μ/g-FW (POD) and 73 μ/g-FW (CAT) in E.crassipes, respectively. The correlation coefficient between the fluorescence ratio Fv/Fm and the concentrations of U-treatment was significantly negative. It is concluded from the results that Uranium halted the biochemical and photochemical reaction but the plants resisted its impact while accumulating a good amount of uranium which is a good prospect for future interventions for the in-situ remediation of uranium-affected sites.