Isotopes 238U Research Articles

The Effect of Nanofluid Coolant and Thorium-added Fuel on Burnup Dependent Isotopic Compositions in VVER-1000 Reactor

Recently, the use of nanofluids has gained importance in studies aimed at increasing reactor efficiency while also addressing safety concerns in nuclear technology. Various studies have investigated the effects of adding nanoparticles of different types and proportions to the coolant water on the thermal and neutronic characteristics of power reactors using conventional UO2 fuels. Given the abundance of thorium compared to uranium, research on thorium-based fuels has become increasingly significant. In this study, the criticality and isotope changes in a VVER-1000 reactor loaded with 5% ThO2 and 95% UO2 by mass as fuel, and 0.1% by volume of Al2O3, CuO, and TiO2 nanoparticles as the coolant, were investigated. Neutronic analysis was performed using the MCNP5 and MONTEBURNS2.0 codes. The analysis results indicated that the operational lifespan of the reactor with only water coolant and thorium-based fuel was shortened due to the presence of nanoparticles. Furthermore, it was observed that while there was no significant change in the amount of fissile 235U and fertile 238U isotopes, the consumption of fertile 232Th isotope in the reactor increased with the insertion of nanoparticles into the coolant.

Natural radioactivity of the crust as an important factor of the chemical evolution of the early Earth

The long-lived (billions of years) 40K, 235U, 238U, and 232Th isotopes have a high energy capacity and represent a potent internal source of energy. Together with the external action of the Sun, the natural radioactivity was apparently an important component of evolution of the early Earth and development of Earth's life. The decay of isotopes initiated radiation chemical reactions involving water, which were accompanied by the formation of hydrogen and oxygen and the transformation of Earth's inorganic matter into organic compounds, including prebiotic molecules. Water radiolysis in the Earth's crust continuously produces H2, which is now considered as the main electron donor (food) for microorganisms several kilometers below the Earth's surface. Here we calculate the initial radioactivity of the early Earth's crust from the relative abundances of elements and dynamics of variation of the radioactivity and energy release upon the decay of particular radioactive isotopes. The energy released upon the decay of heavy 235U, 238U, and 232Th throughout the existence of the Earth (4.6 billion years) was 4.5 × 1030 J, while the energy released upon the decay of 40K was approximately 1.0 × 1030 J. The energy release per year during the first billion years decreased from 3.0 × 1021 J to 1.5 × 1021 J for heavy isotopes and from 0.70 × 1021 J to 0.45 × 1021 J for 40K. Over the last billion years, the energy decreased approximately threefold. Analysis of the data on the radiation chemical formation of hydrogen in the wet components of the Earth's crust (cements, zeolites, geopolymers, and other) and bottom sediments indicates that hydrogen is formed upon direct action of radiation on water in yields characteristic of pure water. According to calculations, over the past 4 billion years, approximately 1.7 × 1022 M of hydrogen was formed. Furthermore, ∼93 % of H2 was due to the decay of uranium and thorium, while the contribution of 40K did not exceed 7 %. The global rate of hydrogen formation in the Earth's crust is ∼ 1.5 × 1012 mol per year. A mechanism involving ionic and radical products of water radiolysis was proposed to describe the formation of prebiotic molecules (amino acids, sugars, etc.) from carbon-, nitrogen-, and sulfur-containing inorganic compounds.

Uranium concentrations and its isotopes in baby food of Iraq

Abstract This study determines uranium concentrations and isotopes (238U, 235U, and 234U) in baby food samples collected from Iraqi markets using solid-state nuclear track detector technical (CR-39). Also, some radiological hazard parameters such as annual committed effective dose (E U) and risk of an excess cancer fatality per million persons (RECFPMP) for the same study samples were calculated using theoretical equations. The samples in the present study were classified into three varieties: cereals and cereal products, vegetables and fruits, and biscuits. The results show that the average uranium concentration (mg/kg or ppm) values in cereals and cereal products, vegetables and fruits, and biscuits were 0.71 ± 0.01, 0.81 ± 0.04, and 0.72 ± 0.031, respectively. At the same time, the average values of 238U, 235U, and 234U in all samples of the present study were 9.08 ±0.17 Bq/kg, 0.42 ± 0.0081 Bq/kg, and 9.33 ± 0.18 Bq/kg, respectively. The total average of E U (mSv/y) due to all uranium isotopes (238U, 235U, and 234U) in cereals and cereal products, vegetables and fruits, and biscuits were 0.042 ± 0.0006, 0.039 ± 0.001, and 0.034 ± 0.001, respectively. Moreover, it was found that the average values of RECFPMP were 0.159 ± 0.002 in cereals and cereal products samples, 0.154 ± 0.007 in vegetables and fruits samples, and 0.130 ± 0.005 in biscuits samples. Uranium concentrations and the total annual committed effective dose in all baby food samples comply with the worldwide limits approved by UNSCEAR, which state safe limitations (1.7 mg/kg) and (0.32 mSv/y), respectively. So, one may conclude that there is no danger of uranium concentrations in the case of baby consumption.

Effective dose evaluation for external exposure from surface soil by using resrad-onsite code

An annual effective dose evaluation from Dong Nai surface soil (45 samples) to humans was carried out in this work. ResRad-Onsite software has been applied to estimate the maximum exposure dose by considering different exposure levels across an area of ​​5905.7 km2 with a topsoil thickness of 20 cm. The calculation grid used in ResRad Onsite software is divided in the form of a circle of radius 3, 5, 10, 20, and 30 km, respectively, calculated from the circle center in terms of 16 wind directions. A high-purity germanium detector (HPGe) was used to determine 238U, 232Th, 226Ra, 137Cs, and 40K isotopes. The range activity concentrations of them were found to be 6.46 ÷ 48.11; 13.95 ÷ 58.75; 5.71 ÷ 35.27; 0.15 ÷ 1.23 and 6.7 ÷ 222; mBq/g, respectively. The isotope 239,240Pu was determined by the radiochemical separation method, measured on the alpha spectrometer system, and the calculated value range is 0.009 ÷ 0.073 mBq/g. The activity of 90Sr was determined by separation technique, measured on a low-background alpha/beta total counting system (MPC 9300) with a calculated value range of 0.10 ÷ 0.83 mBq/g. By ResRad-Onsite code, the external effective dose derived from the ground (excluding Radon’s contribution) is calculated to be 170 ÷ 658 µSv/year with an average value is 368.6 µSv/year. The external dose from the soil is 136.5 µSv/year (accounting for 37%). The results showed that the annual radiation dose distribution derived from the ground equivalent to the average of some different regions in the territory of Vietnam and the world. In addition, the external effective dose from the ResRad-Onsite code tended to be about 1.36 times smaller than the practical measured due to the library’s different dose conversion coefficients.

In-depth Study of Radioactive Isotope Profiles 234U, 235U, and 238U in Earth Samples from the Missour Region, Morocco: A Detailed Exploration of Nuclear Activity

In-depth Study of Radioactive Isotope Profiles 234U, 235U, and 238U in Earth Samples from the Missour Region, Morocco: A Detailed Exploration of Nuclear Activity

Energy-Dependent Fission-Product Yields in the Region of Second-Chance Fission

The energy dependence of high-yield fission products has been measured using quasi-monoenergetic neutron beams at energies between 5.5 and 11.0 MeV. The absolute number of fissions during the irradiation period was determined via dual-fission ionization chambers, while the fission products were measured via direct g-ray spectroscopy. This paper presents absolute fission product yields from neutron-induced fission of 235U, 238U, and 239Pu isotopes for five incident energies in the second chance fission region.

Long term activity measurement of the primary circuit water on the LVR-15 research reactor

Activity measurement of the primary circuit water of fission reactors is one method that can provide early detection of a damaged fuel assembly in the reactor core. This is an important aspect in the safe operation of the reactor and for radiation protection of staff. Radionuclides in the primary circuit water are produced by the activation of stable nuclides and the fission of fissile nuclides, mainly the isotope 235U. In the LVR-15 research reactor, measurement of the activity of the primary circuit water has been regularly undertaken since 1996. A water sample is taken from the primary circuit every week and the activities are measured four days later using gamma spectrometry. The results of these long-term measurements from 1996 to 2022 are presented. The activity time dependences of the individual radionuclides are discussed in relation to fuel assembly damage and for events connected to contamination of the water by objects inserted into the primary circuit during experiments carried out near the reactor core.

Sensitivity and uncertainty analysis of effective multiplication factor of KRITZ-1 benchmark using ENDF/B-VIII.0 and JEFF3-3 nuclear data libraries

Sensitivity and uncertainty analysis have been performed to estimate the uncertainty in the effective neutron multiplication factor, keff, of the KRITZ-1 benchmark and to identify which nuclear reactions and isotopes of interest could be significantly influencing it. First, the adjoint-weighted perturbation method using the KSEN card of the MCNP6 code is applied to compute the sensitivity vectors for 235U, 238U, 1H, 16O, and 10B isotopes with the JEFF-3.3 and ENDF/B-VIII.0 nuclear data libraries. Then, the sensitivity vectors and covariance matrices were combined to calculate the uncertainty in keff due to uncertainties in nuclear data. The 44 group covariance matrices have been processed with the NJOY21 system.It was found that the uncertainty in keff is mostly due to uncertainties on ν‾p , fission cross section of 235U, the capture cross section of the two isotopes 238U and 1H in the aforementioned data libraries

Uranium isotopes content in the certain types of foodstuffs. Optimization of the analytical method

An article contents the results of investigation of natural uranium isotopes content in the certain types of foodstuffs sampled in the kitchen gardens located in Leningrad region and bought in the trade network of Saint-Petersburg. More suitable and simple for realization than existing method is given for uranium isotopes (238U, 234U, 235U) content investigation in the foodstuffs from a sample with not more than 1,0 kg weight with minimal detectable activity not more than 0,02 Bq. Radiochemical investigations were carried out in 2018-2020. Estimation of potential average annual population internal exposure dose (Eint) have been carried out due to 238U and 234U content in the bread foodstuffs, black leaf tea, spicy herbs and salad greenery consumed by the local population. It is demonstrated that population internal exposure dose from uranium isotopes in the investigated types of foodstuffs could be about 0,0000022 mSv/ year. Estimated dose value is only small part of population internal exposure dose from uranium and even more so from total composition of natural radionuclides in the foodstuffs. At the same time toxic effect from soluble uranium as a chemical element prevails over its radiation effect.

X-ray absorption fine structure (XAFS)-based radionuclide research at the KIT Light Source

Abstract. In the past two decades, X-ray absorption spectroscopy (XAS) and related synchrotron-based radionuclide speciation techniques have become indispensable, supporting open issues in fundamental radiochemistry and nuclear waste disposal alike. Physicochemical structure information – encoded in the element-specific X-ray absorption fine structure (XAFS) – is obtained by the precise determination of the linear mass absorption coefficient μ(E) of a specimen in an X-ray energy window ΔE encompassing an electronic bonding level of a selected atom type. The characteristic modulations of μ(E) in the vicinity of an “absorption edge” (i.e., the steeply rising absorption probability of photons tuned to the binding energy of inner shell “core” electrons) are attributed to electronic transitions into unoccupied states due to the photoelectric effect. While absorption features close to the edge (arising from excitations into molecular orbitals or empty band structure levels close to the Fermi level) are generally denoted as an X-ray absorption near-edge structure (XANES), the scattering states at higher excitation energies are causing the well-known extended X-ray absorption fine structure (EXAFS). EXAFS oscillations of the post-edge μ(E) are caused by the periodicity of the constructive and destructive interference of outbound and backscattered inbound photoelectron waves (superimposing at the absorbing atom site) when continuously increasing the excitation energy. Quantitative analysis of EXAFS data based on electron scattering theory is a well-established short-range structural probe, providing precise values of interatomic distances (between the absorber atom and its neighbors) and additional information on the type, number, and ordering of neighbor atoms within a local cluster. Recent significant advancements in the quantum theoretical description of core-excited final states have been successful in overcoming persisting ambiguities in XANES data interpretation. Meanwhile, although there are more than 50 synchrotron radiation centers operational in the world, facilities with specialized beamline infrastructure and safety protocols to allow experiments on radioactive samples with activities beyond the exemption limits are still scarce. At the KIT Light Source (at the Karlsruhe Institute of Technology, Karlsruhe, Germany), the Institute for Nuclear Waste Disposal (Institut für Nukleare Entsorgung, INE) operates two beamline end-stations dedicated to the investigation of radionuclide materials by XAFS spectroscopy and related techniques, i.e., the INE-Beamline (operational since 2005) and the ACT station of the CAT-ACT (CATalysis and ACTinide) wiggler beamline (operational since 2016). Samples with total activities amounting to 1.0×106 times the isotope specific exemption limits and 200 mg of fissile isotopes 235U and 239Pu are feasible at both beamlines. Highly versatile detection systems and sample holders – generally avoiding extensive shielding or sample handling in a glove box – have been conceived since the initial commissioning of the beamlines and have enabled unique XAFS measurements such as the first ever investigation of aqueous technetium species at the Tc L3 edge. Investigations of highly radioactive specimens (e.g., spent nuclear fuel or nuclear waste glass fragments) are feasible, regardless of the actual contact dose rate if the radiation field is limited to a few microsieverts per hour at the edge of the experimental table.

Spatially Resolved Characterisation of Low Mass Fraction Uranium Glass Working Reference Materials

We present the results of a study to generate reference glasses that reflect an environment analogous to historic nuclear fallout samples of interest for post‐detonation nuclear forensics. The glasses were generated by melting and then quenching SiO2, Al2O3 and CaCO3 powders. Two suites of glasses with three distinct U isotopic ratios were successfully made with enrichments in the 235U isotope (~ natural [0.72%], ~ 53% and 94%), but the bulk elemental data showed heterogeneity (~ 10% RSD) with U mass fractions ranging from 331.47 to 373.63 μg g‐1. Spatially resolved U isotopic measurements were performed using three mass spectrometry techniques (secondary ion mass spectrometry‐single stage accelerator mass spectrometry [SIMS‐SSAMS], large geometry [LG] ‐ SIMS, and laser ablation‐inductively coupled plasma‐mass spectrometry [LA‐ICP‐MS]) across five National Laboratories. The results showed good agreement with the bulk U isotopic data for the low, medium, and high U mass fractions. We conclude that despite elemental heterogeneity, these samples can serve as useful working reference materials for spatially resolved nuclear fallout analyses, as well as for other related spatially resolved analyses.

Application of peak based-Bayesian statistical method for isotope identification and categorization of depleted, natural and low enriched uranium measured by LaBr3:Ce scintillation detector

Todays, medium energy resolution detectors are preferably used in radioisotope identification devices(RID) in nuclear and radioactive material categorization. However, there is still a need to develop or enhance « automated identifiers » for the useful RID algorithms. To decide whether any material is SNM or NORM, a key parameter is the better energy resolution of the detector. Although masking, shielding and gain shift/stabilization and other affecting parameters on site are also important for successful operations, the suitability of the RID algorithm is also a critical point to enhance the identification reliability while extracting the features from the spectral analysis. In this study, a RID algorithm based on Bayesian statistical method has been modified for medium energy resolution detectors and applied to the uranium gamma-ray spectra taken by a LaBr3:Ce detector. The present Bayesian RID algorithm covers up to 2000 keV energy range. It uses the peak centroids, the peak areas from the measured gamma-ray spectra. The extraction features are derived from the peak-based Bayesian classifiers to estimate a posterior probability for each isotope in the ANSI library. The program operations were tested under a MATLAB platform.The present peak based Bayesian RID algorithm was validated by using single isotopes(241Am, 57Co, 137Cs, 54Mn, 60Co), and then applied to five standard nuclear materials(0.32–4.51% at.235U), as well as natural U- and Th-ores. The ID performance of the RID algorithm was quantified in terms of F-score for each isotope. The posterior probability is calculated to be 54.5–74.4% for 238U and 4.7–10.5% for 235U in EC-NRM171 uranium materials. For the case of the more complex gamma-ray spectra from CRMs, the total scoring (ST) method was preferred for its ID performance evaluation. It was shown that the present peak based Bayesian RID algorithm can be applied to identify 235U and 238U isotopes in LEU or natural U–Th samples if a medium energy resolution detector is was in the measurements.

Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination

The low rate at which some fissile isotopes, such as 235U, 233U, and 239Pu, undergo spontaneous fission leads to a weak signal, resulting in a high-uncertainty in applying passive neutron counting techniques. Stimulating fission through active neutron interrogation can overcome this issue. At Canadian Nuclear Laboratories, a 252Cf and a deuterium-deuterium neutron source are available. In this study, a neutron counting system was designed to perform passive measurements and active neutron interrogation for a search of special nuclear material. The detection system consists of a cylindrical cavity surrounded by a polyethylene moderator with 3He detectors interspersed throughout. When used for passive measurements, the sample is placed in the cylindrical cavity, whereas in active interrogation mode, the 252Cf neutron source and the sample are placed in close proximity to each other in the cylindrical cavity. Measurements that actively interrogated samples, notably containing (among other isotopes) either 235U or 239Pu whose mass was on the order of fractions of a gram, carried out using the 252Cf neutron source found that the average delayed neutron count rate was on the same order of magnitude as those obtained from passive measurements using several kilograms of natural uranium. The Monte Carlo N-Particle 6 version 2.0 radiation transport code was used to simulate the aforementioned active interrogations and to inform the experimental results. Results showed that, due to the close proximity of the polyethylene moderator to the 252Cf source, the neutron energy spectrum traversing the fissile sample has a significant thermal component that maximizes the fission reaction rate in the interrogated fissile samples, thereby allowing for successful measurements.

Deep anoxic aquifers could act as sinks for uranium through microbial-assisted mineral trapping

Uptake of uranium (U) by secondary minerals, such as carbonates and iron (Fe)-sulfides, that occur ubiquitously on Earth, may be substantial in deep anoxic environments compared to surficial settings due to different environment-specific conditions. Yet, knowledge of U reductive removal pathways and related fractionation between 238U and 235U isotopes in deep anoxic groundwater systems remain elusive. Here we show bacteria-driven degradation of organic constituents that influences formation of sulfidic species facilitating reduction of geochemically mobile U(VI) with subsequent trapping of U(IV) by calcite and Fe-sulfides. The isotopic signatures recorded for U and Ca in fracture water and calcite samples provide additional insights on U(VI) reduction behaviour and calcite growth rate. The removal efficiency of U from groundwater reaching 75% in borehole sections in fractured granite, and selective U accumulation in secondary minerals in exceedingly U-deficient groundwater shows the potential of these widespread mineralogical sinks for U in deep anoxic environments.

NANO-MECHANISMS OF CONNECTION IN THE SOLID PHASE OF TUNGSTEN AND TANTALUM IN THE MANUFACTURE OF A NEUTRON SOURCE TARGET

Nano-mechanisms of solid-phase bonding of tungsten and tantalum, which are implemented in the manufacture of a neutron source target for the research nuclear facility (RNF) of NSC KIPT, are considered. This facility is a new type of nuclear reactor, in the core of which the intensity of the nuclear fission reaction of the uranium isotope 235U is controlled by an electron accelerator. An installation for joining metals in the solid phase is described, its parameters are given, as well as the parameters of the joined metals. An electron-probe X-ray spectral analysis of the interface between the samples was carried out. The physical foundations of the nano-mechanism of bonding in the solid phase of tungsten and tantalum at the dynamic and isostatic stages at hot vacuum pressing are formulated. Experimental data on the relative temperature convergence of rolls at the dynamic and isostatic stages of hot vacuum pressing have been obtained.

Hydrochemistry and weathering at Pardo River basin, São Paulo State, Brazil.

This work was conducted at the Pardo River hydrographic basin, which is a federal watershed belonging to the Paranapanema River hydrographic basin (PRHB) in Brazil (São Paulo State and Paraná State). The aim was to realize an integrated hydrochemical and radiometric (U-isotopes and 210Po) approach, highlighting the water/soil-rock and surface water/groundwater interactions, with implications to the weathering processes occurring there. The study area has been often considered one of the best preserved/unpolluted river in São Paulo State, contributing to the water supply of several cities distributed along its banks. However, the results reported here suggest possible lead diffuse pollution caused by the use of phosphate fertilizers in agricultural activities taking place in the basin. The analyzed groundwaters and surface waters tend to be neutral to slightly alkaline (pH of 6.8-7.7), possessing low mineral concentration (total dissolved solids up to 500mg/L). SiO2 is the major dissolved constituent in the waters, while bicarbonate is the dominant anion, and calcium is the preponderant cation. The effects of the weathering of silicates to control the dissolution of constituents in the liquid phase have been identified from some diagrams often utilized in hydrogeochemical studies. Chemical weathering rates have been estimated from hydrochemical data associated to analytical results of the natural uranium isotopes 238U and 234U concerning to samples of rainwater and Pardo River waters. The fluxes in this watershed are permitted to obtain the following rates: 11.43 t/km2 year (sodium), 2.76 t/km2 year (calcium), 3.17 t/km2 year (magnesium), 0.77 t/km2 year (iron), and 8.64 t/km2 year (uranium). This new dataset constitutes valuable information for people engaged on the management of the Pardo River watershed, as well as to researchers interested on comparative studies considering the available data from other basins worldwide.

Elevated uranium concentration and low activity ratio (234U/238U) in the Œuf river as the result of groundwater–surface water interaction (Essonne river valley, South of Paris Basin, France)

Uranium (U) is a naturally occurring radioactive heavy metal widely distributed on Earth. Noticeable elevated U concentration and low activity ratio (AR) were occasionally detected in headwater stream of the Essonne river (Seine Basin, France), the namely Œuf river. This paper aims at providing new insight on geogenic U features in headwater streams and examines the role of river-groundwater interaction. The Œuf river was sampled four times in 2020 to investigate the influence of heterogeneous geology and hydrological seasonality. The dissolved fraction of water samples was analyzed for a variety of chemical parameters (anion, major, minor and trace element concentrations, isotopes 234U and 238U). The Œuf river was shown to exhibit elevated U concentration up to 19.3 μg L−1 (exceeding by 100-fold the value of 0.19 μg L−1 known for riverine average) and low AR down to 0.41 (almost the third of the value expected in surface water, i.e., 1.17). The Œuf river got enriched in U when receiving groundwater from Beauce Limestone Aquifer System. High U concentration (above 15 μg L−1) was found in association with low AR (below 0.5) in the stream water when flowing in the outcrop zone of one BLAS unit. Taking advantage of changes in the stream flow conditions and the geochemical contrast between surface and ground waters, mixing volumes were calculated. This study first examined the potential of using U isotopes in combination with selenium as hydrogeochemical tracers of the river-groundwater continuum. In HWS, the aquifer discharge was shown to supply 12 to 59 % of the river water. This study demonstrates the key role played by the river-groundwater interaction on river water chemistry in small streams draining catchment with various geology setting. It also supports the use of combining redox sensitive trace elements to track the river-groundwater continuum.

Evaluation of Uranium Concentration and Calculated Doses of Radiation Resulting From the Tap and Bottled Drinking Water in Babylon - middle Iraq

In this study, uranium concentrations were evaluated and the annual effective dose was calculated from the consumption of bottled water and tap water used for drinking in Babylon, middle Iraq. Uranium isotopes (238U, 234U, 235U) were determined for all samples collected using the phosphorylation analyzer technique represented device (KPA). Forty-four samples were collected to cover almost all districts and regions of Babylon. Thirty tap water samples were collected from residential neighborhoods, with 14 samples from local brand bottled water. The results show that the uranium concentrations in the tap water samples ranged from 1.66 μg.L-1 to 2.64 μg.L-1, with an average of 2.12 μg.L-1, and the bottled water samples varied from 1.06 μg.L-1 to 1.82 μg.L-1, with an average 1.47 μg.L-1. This means that the uranium contents in tap and bottled water samples are less than 15 μg.L-1 and 30 μg.L-1, which are safe values of the WHO, and the EPA respectively. The annual effective dose values of 238U, 234U, and 235U for adult consumption of tap water range between 0.67, 0.0.33, 0.74 μSv.y-1 to 1.07, 0.052, 1.18 μSv.y-1 with averages of 0.86, 0.042, 0.95 μSv.y-1, respectively. Their values in bottled water ranged from 0.43, 0.020, 0.47 μSv.y-1 to 0.73, 0.035, 0.81 μSv.y-1, with an average of 0.59, 0.029, 0.65 μSv.y-1, respectively. The value of the annual effective dose of total uranium isotopes in tap water samples ranged between 1.45 μSv.y-1 to 2.30 μSv.y-1 with an average of 0.85 μSv.y-1, whereas in bottled water varied from 0.92 to 1.58 μSv.y-1 with an average of 1.28 μSv.y-1.

Green extraction of uranium (238U) from natural radioactive resources

Numerous strategies have been devised to effectively extract uranium (U[VI] or 238U) from raw materials because it is a significant energy source. This study focused on the highly selective extraction of 238U isotopes from altered granite rock (AGR) utilizing bio-absorbents/extracts from Three-dimensional mesoporous silica monoliths (MSMs), which have been successfully created from affordable and sustainable resources like rice husk (RH). The MSMs exhibited micrometric particle sizes, mesoscopic hexagonal geometry, and irregular nano/microspace voids and grooves along their surfaces. To establish specific binding sites for the extremely selective adsorption/trapping/capturing of ultratrace levels of 238U isotope at pH 3, the MSMs were modified with (2-diethylphosphatoethyl) triethoxy silane chelating agent. Considering that the spent adsorbent/extractor could be recycled/regenerated by using H2SO4 as a stripping agent, the recycled bio-adsorbents could be reused several times with high retention efficiency. The isotherm, kinetic models, and thermodynamic parameters of U(VI) extraction were investigated to describe the nature of adsorption between the bio-adsorbents/extractors and adsorbate species. Results indicated that the MSM and MMSM biosorbents were promising effective extractors for 238U isotopes due to (i) their natural sources; (ii) their contribution to the management of RH waste; (iii) their low cost and eco-friendliness; (iv) their high efficiency, sensitivity, selectivity, and capacity for the target ions; (v) their minimization of waste volume by enabling multiple reuse/cycles; (vi) and their retention of structural performance for several reuse/cycles that resulted in a cost-effective extraction/capture process. Our proposed natural, sustainable porous material and efficient approach might enable the efficient extraction of uranium species from different resources and the appropriate exploitation of natural/agro-waste for clean energy production.

Thorium as an abundant source of nuclear energy and challenges in separation science

Abstract Today about 440 nuclear power plants, with total installed capacity of 390 GW(e) are in operation worldwide generating around 10% of global electricity which are largely fuelled by enriched uranium oxide [Nuclear Power in the World Today. https://world-nuclear.org/information-library/current-and-future-generation/nuclear-power-in-the-world-today.aspx]. Thorium is 3–4 times more abundant than uranium and needs to be exploited by countries with limited stock of uranium. Historically, there have been several attempts to develop Th based reactors, but none has reached commercial scale. In recent years, High Temperature Reactor based on thorium has gained prominence for production of hydrogen with long term goal of complete carbon neutrality. However, unlike natural uranium, which contains ∼0.7% fissile 235U isotope, natural thorium does not contain any ‘fissile’ material and is made up exclusively of the ‘fertile’ 232Th which can be converted to ‘fissile’ 233U, thereby enlarging the fissile material resources. However, there is a need to develop robust closed fuel cycle to address to the challenges of high gamma dose due to the presence of decay products of 232U. It is necessary to gain more experience with promising THOREX process to achieve the desired recovery and D.F. of 233U from the irradiated 232Th. There is also scope to have a close look at some of the alternative extractants and emerging separation techniques for the reprocessing of spent Th based fuels. In view of the distinct advantages of non aqueous reprocessing over aqueous reprocessing, there is need to intensify the efforts to develop the former on a commercial scale. Molten Salt Breeder Reactor (MSBR) is particularly promising in this context. There is a need to investigate Th as energy amplifier under Accelerator Driven Sub-critical System (ADSS) which has potential to burn long lived radio nuclides, considered as a threat to environment over million of years.