Nuclear Waste Management Research Articles

Constructing high-performance radiation-resistant ternary YSZ-MgO-CNT nanocomposites via tailored nanostructures

Developing long-lifetime bulk-form ceramic-based materials with high irradiation resistance is crucial for advanced nuclear systems. Here, we incorporated carbon nanotubes (CNTs) into yttria-stabilized zirconia (YSZ) and magnesia (MgO) nanocrystals to fabricate bulk YSZ-MgO-CNT nanocomposites with abundant ternary nanostructures by spark plasma sintering. To understand the role of tailored ternary nanostructure on irradiation, we investigated the microstructure and mechanical properties evolutions of the YSZ-MgO-CNT nanocomposites irradiated by multi-energy He+ ions at high temperature to different fluences. Compared with the single-phase YSZ and ultrafine-grained YSZ-MgO composites, the YSZ-MgO-CNT nanocomposites possessed higher ability to manage irradiation-induced He bubbles/defects via the defect-interface interactions of proposed “loading-unloading” and “loading-transporting-unloading” mechanisms for controlling the dynamical behaviors of He atoms/defects in the CNT-doped ternary nanostructures, thereby presenting more stable microstructure and better performance in resisting irradiation hardening. This work provides insight into the design of advanced inert matrix nuclear fuel and new nuclear waste management materials.

Complexation of Lanthanides and Heavy Actinides with Aqueous Sulfur-Donating Ligands

The separation of trivalent lanthanides and actinides is challenging because of their similar sizes and charge densities. S-donating extractants have shown significant selectivity for trivalent actinides over lanthanides, with single-stage americium/lanthanide separation efficiencies for some thiol-based extractants reported at >99.999%. While such separations could transform the nuclear waste management landscape, these systems are often limited by the hydrolytic and radiolytic stability of the extractant. Progress away from thiol-based systems is limited by the poorly understood and complex interactions of these extractants in organic phases, where molecular aggregation and micelle formation obfuscates assessment of the metal-extractant coordination environment. Because S-donating thioethers are generally more resistant to hydrolysis and oxidation and the aqueous phase coordination chemistry is anticipated to lack complications brought on by micelle formation, we have considered three thioethers, 2,2'-thiodiacetic acid (TDA), (2R,5S)-tetrahydrothiophene-2,5-dicarboxylic acid, and 2,5-thiophenedicarboxylic acid (TPA), as possible trivalent actinide selective reagents. Formation constants, extended X-ray absorption fine structure spectroscopy, and computational studies were completed for thioether complexes with a variety of trivalent lanthanides and actinides including Nd, Eu, Tb, Am, Cm, Bk, and Cf. TPA was found to have moderately higher selectivity for the actinides because of its ability to bind actinides in a different manner than lanthanides, but the utility of TPA is limited by poor water solubility and high rigidity. While significant competition with water for the metal center limits the efficacy of aqueous-based thioethers for separations, the characterization of these solution-phase, S-containing lanthanide and actinide complexes is the most comprehensively available in the literature to date. This is due to the breadth of lanthanides and actinides considered as well as the techniques deployed and serves as a platform for the further development of S-containing reagents for actinide separations. Additionally, this paper reports on the first bond lengths for Cf and Bk with a neutral S donor.

An investigation into gamma radiation shielding parameters of the (Al:Si) and (Al+Na):Si-doped international simple glasses (ISG) used in nuclear waste management, deploying Phy-X/PSD and SRIM software

Nuclear power plants that produce sustainable energy are the most striking examples of generating carbon-free energy. However, nuclear power plants demand the safe management of nuclear waste. The radiation tests of the materials, which are used in successful waste management in nuclear power plants, must be carried out. In this study, the radiation interaction parameters were examined of International simple glasses (ISG) with superior properties, used in nuclear waste management. The gamma radiation shielding properties of the (Al:Si) and (Al + Na):Si-dopped ISG glasses were investigated using Photon Shielding and Dosimetry (Phy-X / PSD) software for the selected energy range. LAC, MAC, MFP, HVL, TVL, Zeff, Neff, Ceff Zeq, EBF, EABF and FNRCS calculations were applied to assess the radiation protection parameters by Phy-X/PSD software. In addition, MSP and PR (H1, He+2) values were calculated by SRIM software. Also, each obtained parameter provided us with so important information on radiation protection, and these methods have been used frequently in the literature. Substituting an atomic fraction of (Al:Si) with (Al + Na):Si resulted in a reduction of the total atomic cross-section of the glass, which lowered the MAC. The obtained results showed that the highest MAC value belong to ISG-A00N glass. The MAC value gradually decreased as the Al, Na and Si contents increased. Likewise, the HVL, TVL and MFP values changed coherent with this. Moreover, Zeff and Neff values were seen in the ISG-A00N sample to take the maximum values to each other inversely. The most effective glass sample turned out to be ISG-A00N glass at the mean free path penetration power of MSP and PR values. Computations were made for glasses with SiO2, Al2O3, B2O3, Na2O, CaO and ZrO2 content given with ISG-C, ISG-A00, ISG-A12, ISG-A22, ISG-A00N, ISG-A11N, ISG-A18N and ISG-A23N codes. When all the results were evaluated, ISG-A00N glass which has the highest Si and Ca contents and density was found to be the glass with the best radiation shielding feature. It is also noteworthy that this glass does not contain any Al component. As the results of the investigation, it was found out that such a small doped of the Si increases the radiation shielding feature of the glass. The obtained results have revealed that the ISG-A00N > ISG-A00 > ISG-C > ISG-A12 > ISG-A11N > ISG-A22 > ISG-A18N > ISG-A23N samples, in ascending order that attenuators for low energy radiations.

Women in Science Portrait – Dr. Margit Fábián

Dr. Margit Fabian is one of the leading figures among the new breed of talents working at the Budapest Neutron Centre. As a senior research fellow, she is the nuclear waste management team lead at ...

Using socio-technical analogues as an additional experience horizon for nuclear waste management A comparison of wind farms, fracking, carbon capture and storage (CCS) with a deep-geological nuclear waste disposal (DGD)

Energy technologies can be described as socio-technical ensembles, in which social, political, economic and technical dimensions are embedded. Based on this concept as well as other theoretical approaches dealing with the deployment and development of technologies (e.g. the multi-level perspective of Geels (2002)) this contribution investigates the dynamics and interactions that can occur within the socio-technical ensemble of a deep geological disposal (DGD) for high-level radioactive waste (HLRW). We compare socio-technical analogues and relate findings of three energy technologies with large-scale infrastructures to a DGD. The analysis is based on a systematic literature review and aims to gain indirect knowledge for nuclear waste management (NWM) deduced from the dynamics within the socio-technical ensembles of wind farms, fracking and carbon dioxide capture and storage (CCS). The analysis is based on a systematic literature review along four central dimensions with eight respective criteria e.g. public participation, conflicts, role of science, etc.

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Studies on sophisticated coordination geometries of actinides in solid‐state compounds provide useful hints on improving nuclear waste management. We report here in this work two distinct uranium compounds that simultaneously contain all three typical coordination geometries of the uranyl ion. Additionally, compound 1 displays an atypical temperature‐induced single‐crystal‐to‐single‐crystal phase transformation and luminescence evolution. More details are discussed in the article by Wang et al. on page 597—604.image

Prospects of functionalized porous materials towards extraction of spent nuclear fuel radionuclides

Radioactive waste levels have continued to increase due to the growth and development of nuclear energy, industrial or medical radioactive use. In this regard, conventional radioactive waste generated by nuclear power plants cannot be ignored. Effective management of nuclear radioactive waste plays a vital role in alleviating negative impacts on the society and environment. Despite the progress that has been made concerning separation and recycling of spent nuclear fuel through the PUREX process, several gaps in knowledge still exist especially towards the development of a robust separation system based on solid-phase extraction using porous materials. Solid phase extraction is being viewed as one of the most convenient and effective approaches in the removal of cations in radionuclide solutions. This is due to its ability to increase the selectivity and sensitivity of the method as it permits discriminatory binding of analyte to a solid support where the analyte can be collected and thereafter eluted using small quantity of a different solvent. The review covers the current methods used in aqueous nuclear reprocessing, highlights their deficiencies and introduces the potential of applying solid-phase extraction in management of nuclear waste. This study gives the prospects of functionalized porous sorbent materials as solid support in solid-phase extraction of spent nuclear fuel elements.

Safer-than: Making Nuclear Waste Disposal More Familiar

ABSTRACT Geological disposal has been proposed as the solution for managing the most radioactive nuclear wastes. These wastes stay hazardous for periods better measured in geological rather than human time. This challenges the capacity of science to accurately predict the future evolution and safety of geological disposal facilities. Thus nuclear waste management organisations, such as the Finnish Posiva, utilise a broad range of historical and cultural evidence and discursive tactics to support their scientific argumentation for the long-term safety of geological disposal. Posiva, for instance, makes its safety case by anchoring its disposal project in broader international scientific settings and engineering practices; by giving the abstract disposal concept form and tangible through mundane objects and spaces and in so doing presenting geological disposal as an extension of the everyday; and finally by juxtaposing the underground and the aboveground to depict the underground as more predictable and knowable, essentially as ‘safer than.’ By invoking and imagining geological disposal through the familiar, Posiva negotiates the limits of scientific knowledge, and undermines the nuclearity of geological disposal to make its case for the implementability, manageability and safety of geological disposal and, crucially, to present geological disposal as the only available option for long-term nuclear waste management.

Drum breach: Operational temporalities, error politics and WIPP's kitty litter nuclear waste accident.

In February 2014 at the WIPP transuranic waste repository in New Mexico, a drum erupted in fire. It exposed 22 people to radiation, shut down the underground facility for 35 months and cost the United States over a billion dollars. Heat and pressure had built up in the drum due to chemical reactions with an organic kitty litter, Swheat Scoop, which had been mistakenly added to it at Los Alamos National Laboratory, the birthplace of the atomic bomb. This article disrupts two prominent narratives: (a) that the accident was induced by a typographical error made after a waste packaging operations supervisor misheard 'inorganic kitty litter' as 'an organic kitty litter' during a meeting, and (b) that it was induced primarily by 'mismanagement' at WIPP, Los Alamos and the DOE's New Mexico field offices. It does so by exploring how a series of overambitious political initiatives, fraught labor relationships, financialized subcontracting arrangements and US Department of Energy (DOE) performance incentives set the stage for Los Alamos's notorious error by accelerating US waste packaging, shipping and repository emplacement rates beyond systemic capacity. Attention to operational temporalities shows how an often-overlooked nexus of schedule pressures, political-economic imperatives and regulatory breakdowns converged to modulate nuclear waste management workflows and, ultimately, trigger a radiological accident.

Dynamic cost analysis for disposal of low and intermediate level nuclear waste in China

The management and financial problems of nuclear waste have raised the concern worldwide due to lack of experience in decommissioning and disposal. In this paper, a primary cost estimation model is proposed based on Activity-based Life Cycle Costing (AB-LCC) approach in order to influence the strategy of Low and Intermediate Level Waste (LILW) disposal in China. AB-LCC model provides a dynamic cost estimation of LILW disposal and its application is not restricted by the region and time. A dynamic analysis of resources due to time and regional differences of LILW management during its life cycle time has been performed on the basis of Activity-based Costing (ABC) matrix. The static and dynamic costs of the primary and secondary activities at each stage of the disposal repositories are obtained. The model is verified by comparison with statistics from the cases of Aube repositories and difference is approximately less than 5%. Therefore AB-LCC model is used to estimate the LILW disposal costs in China with different disposal modes. Finally, LILW management strategy was suggested to the Chinese policy-makers that the Northwest Centralized Disposal Mode (NCDM) is more cost-saving than the Coastal Independent Disposal Mode (CIDM) and Gansu province is the most recommended disposal site for economic considerations.

The role of scientific research on nuclear radiation waste management and preserving environment

On the level of this article, we deal with nuclear radiation (and their residues), which is defined as a physical phenomenon and strong atomic activity that occurs in unstable atoms of elements. We are interested in studying radiation as the emission or diffusion of energy into space in the form of electromagnetic waves or particles. The scientist Fermi (1934 AD) is among the first to present scientific research in this field. Radioisotopes are considered one of the most prominent discoveries of modern science and based on the importance of the topic, scientists and researchers searched for methods and techniques to facilitate the implementation of practical applications for radiation measurement, and among those methods a specialized program was used to simulate radiation dose (digital simulation in a computer through the use of an imaginary model of the radiometric process with technology Monte Carlo using code (Geant 4). We have also highlighted the views of researchers and specialists in the area of disposal of radioactive waste, relying on a field study and a comparison of some of the currently adopted techniques to get rid of the negative consequences that each unreasonable (reckless) management and measure of this radioactive waste may have Among the most prominent results we have reached is highlighting the weakness of dealing with this topic and not giving it the right to research and scientific achievements carried out by researchers, which increases the complexity of the situation and from which it is difficult to control the problem in the future.

Attempts to share information between public sector organisations over time: A case-based exploration of value conflicts

Despite the importance of inter-organisational information sharing (IOIS) in the public sector, such endeavours often fail. Existing research has shown that the values held by collaborating organisations are one important factor affecting these kinds of initiatives. However, research has sought only to a limited extent to address how value conflicts come into play over time. Therefore, this paper aims to explore how conflicting values shape an inter-organisational information-sharing practice in the public sector over time. Using the local/global network framework, we analyse four years’ worth of information sharing in an inter-organisational advisory group in the context of Swedish nuclear waste management. We conclude that different value conflicts are emphasised to different extents at different points in time. That is, values do not uniformly affect IOIS activities, and such conflicts over time reduce the set of potential IOIS activities. We also conclude that when IOIS activities are driven by an individual organisation’s values, individual value rational activities may co-exist with a dysfunctional long-term IOIS practice.

Effect of temperature on the complexation of triscarbonatouranyl(VI) with calcium and magnesium in NaCl aqueous solution.

The complex formation of triscarbonatouranyl(VI) UO2(CO3)34- with the alkaline earth metal ions Mg2+ and Ca2+ in 0.10 mol kgw-1 NaCl was studied at variable temperatures: 5-30 °C for Mg2+ and 10-50 °C for Ca2+. Under appropriate conditions, the ternary complexes (MnUO2(CO3)3(4-2n)- with n = 1 for Mg, n = {1; 2} for Ca) were identified by time-resolved laser-induced luminescence spectrometry. Their pure spectral components at 50 °C for CanUO2(CO3)3(4-2n)- and 30 °C for MgUO2(CO3)32- were recovered by multivariate curve resolution alternating least-squares analysis. Approximation models were tested to fit the experimental data-the equilibrium constants of complexation measured at different temperatures-and deduce the thermodynamic functions, i.e., enthalpy, entropy, and heat capacity. The weak influence of temperature on complexation constants induces large uncertainties in terms of thermodynamic functions. Assuming the enthalpy is constant with temperature using the Van't Hoff equation, the first stepwise complexation of UO2(CO3)34- by Ca2+ is estimated to be slightly endothermic, with , while the second stepwise complexation of CaUO2(CO3)32- by Ca2+ with is slightly exothermic, . In contrast to Ca2+, the complexation of UO2(CO3)34- by Mg2+ is slightly exothermic, with . These values are not significantly different from zero inasmuch as the uncertainties are important due to a weak dependence of log10 K° values. The entropic character of the complexation is verified as for the first stepwise complexation of UO2(CO3)34- by Ca2+, for the second stepwise complexation of CaUO2(CO3)32- by Ca2+, and for the complexation of UO2(CO3)34- by Mg2+. The energetics of complexation and sensitivity analysis of the model estimates with temperature are discussed. The uranium speciation in the case of the safety of nuclear waste management, using the present thermodynamic functions, provides support to the assessment of underground nuclear waste repositories.

Changing the System Culture: Mobilizing the Social Sciences in the Swedish Nuclear Waste System

The purpose of this paper is to analyze how competence in the humanities and social sciences has been introduced into the system culture of the Swedish nuclear waste system (SNWS) traditionally dominated by scientists and engineers. In the spring of 1980, fierce local protests were directed against drilling teams sent out to investigate the geology of potential locations for a repository of spent nuclear fuel. This demonstrated the political and ethical dimensions of the waste issue and the limitations of the technocratic approach that had hitherto dominated the system culture of the SNWS. In order to counter this tendency, the government established an advisory board, Samrådsnämnden för kärnavfall (abbreviated KASAM), in 1985 with the task to widen the perspectives on the nuclear waste issue. KASAM engaged social scientists and humanists and started organizing annual workshops inviting engineers and scientists working with the waste issue to discuss its ethical and political dimensions. In the early 1990s, SKB, the Swedish implementer organization responsible for the management of nuclear waste, changed its strategy for finding suitable locations for a repository of spent nuclear fuel. Approval from the local population became a key condition. In the early 2000s, only two municipalities remained, both of them already housing nuclear power plants. After careful investigations and many deliberations, one of them was eventually chosen. The combination of KASAM’s activities to broaden the discussion and the local protests in many communities initiated a gradual change of the system culture within the SNWS. The initial technocratic approach was broadened to encompass ethical, social, and political aspects, and the main organizations now acknowledge that not only technical and scientific skills but also competence from social science and the humanities were of essence.

MODELING AND SIMULATION OF THE VERTICAL AXIS WIND TURBINE BY QBLADE SOFTWARE

The use of wind energy has no harmful effects on the environment. This makes it a clean energy that is a real alternative to the problem of nuclear waste management and greenhouse gas emissions. Vertical axis wind turbines have prospective advantages in the field of domestic applications, because they have proven effectual in urban areas where wind flow conditions are intermittent, omnidirectional, unsteady and turbulent. The wind cannot ensure a regular energy supply without optimising the aerodynamics of the blades. This article presents a reminder about wind energy and wind turbines, especially the VAWT type wind turbines and also gives a presentation on the aerodynamic side of VAWT by studying the geometry and aerodynamic characteristics of the blade profiles with the acting forces and also the explanation of the DMS multiple flow tube model. This work also gives the different simulation methods to optimize the behaviour of the blades from the selected NACA profiles; the analysis first goes through the design of the blades by the design and simulation software Qblade which is used to calculate also the forces on the blade and the coefficients of lift, drag and fineness. At the end of this article we have the DMS simulation of the VAWT turbines, by determining the power coefficient and the power collected by the turbine to select the wind turbine adapted to a well characterized site.

Experimental determination of solubilities of tri-calcium di-citrate tetrahydrate [Ca3[C3H5O(COO)3]2•4H2O], earlandite, in NaCl and MgCl2 solutions to high ionic strengths

In this study, solubility measurements on tri-calcium di-citrate tetrahydrate [Ca3[C3H5O(COO)3]2•4H2O, abbreviated as Ca3[Citrate]2•4H2O, earlandite] as a function of ionic strength are conducted in NaCl solutions up to I = 5.0 mol kg−1 and in MgCl2 solutions up to I = 7.5 mol kg−1, at room temperature (22.5 ± 0.5 °C). The solubility constant (logKsp0) for Ca3[Citrate]2•4H2O and formation constant (logβ10) for Ca[C3H5O(COO)3]–,(1)Ca3[C3H5O(COO)3]2•4H2O (earlandite) = 3Ca2+ + 2[C3H5O(COO)3]3– + 4H2O(2)Ca2+ + [C3H5O(COO)3]3– = Ca[C3H5O(COO)3]–are determined as −18.11 ± 0.15 and 4.97 ± 0.15, respectively, with a set of Pitzer parameters describing the specific interactions in NaCl-bearing and MgCl2-bearing media.The solubility measurements and thermodynamic modeling indicate that earlandite could become a solubility-controlling phase for citrate in the near field of geological repositories for nuclear waste when the inventories of citrate reach the saturation concentrations for Ca3[Citrate]2•4H2O, and it is a solubility-limiting phase for calcium/citrate in other low temperature environments such as agro-food industrial waste-waters. The Pitzer model presented in this work will enable researchers to assess the role of citrate in low temperature environments over a wide range of ionic strengths, and is expected to find applications in many fields such as food and pharmaceutical sciences, cement and concrete industries as well as nuclear waste management.

Decisive Role of 5f-Orbital Covalence in the Structure and Stability of Pentavalent Transuranic Oxo [M6O8] Clusters.

Actinide metal oxo clusters are of vital importance in actinide chemistry, as well as in environmental and materials sciences. They are ubiquitous in both aqueous and nonaqueous phases and play key roles in nuclear materials (e.g., nuclear fuel) and nuclear waste management. Despite their importance, our structural understanding of the actinide metal oxo clusters, particularly the transuranic ones, is very limited because of experimental challenges such as high radioactivity. Herein we report a systematic theoretical study on the structures and stabilities of seven actinide metal oxo-hydroxo clusters [AnIV6O4(OH)4L12] (1-An; An = Th-Cm; L = O2CH-) along with their group 4 (Ti, Zr, Hf, Rf) and lanthanide (Ce) counterparts [MIV6O4(OH)4L12] (1-M). The work shows the Td-symmetric structures of all of the 1-An/M clusters and suggests the positions of the -OH functional groups, which are experimentally challenging to determine. Furthermore, by removing six electrons from 1-An, we found that oxidation could happen on the AnIV metal ions, producing [AnV6O4(OH)4L12]6+ (2-An; An = Pa, U, Np), or on the O2- and OH- ligands, producing [AnIV6(O•-)4(OH•)2(OH)2L12]6+ (3-An; An = Pu, Am, Cm). On the basis of 2-An, we constructed a series of tetravalent and pentavalent actinide metal oxo clusters [AnIV6O14]4- (4-An) and [AnV6O14]2+ (5-An), which proves the feasibility of the highly important pentavalent actinyl clusters, demonstrates the f orbital's structure-directing role in the formation of linear [O≡AnV═O]+ actinyl ions, and expands the concept of actinyl-actinyl interaction into pentavalent transuranic actinyl clusters.

Towards best possible safety – current regulatory research for the German site selection process for high-level radioactive waste disposal

Abstract. The Federal Office for the Safety of Nuclear Waste Management (BASE – Bundesamt für die Sicherheit der nuklearen Entsorgung) is the German federal regulatory authority for radioactive waste disposal. It supervises the German site selection process and is responsible for the accompanying public participation. Task related research is an integral part of BASE's activities. The projects MessEr and übErStand compiled the state-of-the-art science and technology regarding surface based exploration methods suitable for addressing the criteria and requirements specified in the German Site Selection Act. The results support BASE to review and define the surface-based exploration programs to be executed by the national implementer BGE (Bundesgesellschaft für Endlagerung mbH). To support BASE in reviewing the application of the exclusion criteria “active fault zones” according to the Site Selection Act, the project KaStör reviewed the current knowledge on active faults and fault zones in Germany and recommends methodological approaches to date and identify the activity of faulting. For the time being, the Site Selection Act defines 100 ∘C as a draft limit on the temperature at the outer surface of a repository container for all host rocks. The project Grenztemperatur studied the temperature dependency of the different thermal-hydraulic-mechanical-chemical/biological (THMC/B) processes according to available features-events-processes (FEP) catalogues for rock salt, clay stone, and crystalline rock and describes ways to defining host rock specific maximum temperatures based on specific disposal and safety concepts. Safety oriented weighting of different criteria and comparison of different potential regions and sites are key challenges during the siting process. The project MABeSt studied and reviewed methodological approaches to this weighting and comparison problem with special emphasis on multi criteria analysis (MCA) and multi criteria decision analysis (MCDA). A key requirement for safe geological disposal of nuclear waste is barrier integrity. The project PeTroS performed the first triaxial flow-through experiments on natural rock salt samples at disposal relevant p−T conditions and studied potential percolation mechanisms of fluids within rock salt. The data substantiate that the minimum stress criterion and/or the dilatancy criterion are the prime “percolation thresholds” in rock salt. The research results support BASE in fulfilling its tasks as national regulator according to state-of-the-art science and technology and are also relevant to other stakeholders of the siting process.

Preliminary Study of the Potential Graphene Oxide as Radioactive Clinical Wastewater Adsorbability in Nuclear Medicine

This paper reports the ability of graphene oxide (GO) as a radionuclide adsorbent material for an alternative approach in nuclear medicine radioactive waste management. Notable physicochemical properties of GO mainly consist of oxygen-containing functional groups on its basal plane and edges site in the form of epoxy, hydroxyl, and carboxyl groups, making it a promising candidate for radionuclide extraction material from aqueous solution. Herein, GO was synthesised via a simplified Hummers method. The radioactive clinical waste, which is urine, was collected right after the scanning procedure and mixed with GO in various concentrations: 1 mg/ml, 1.5 mg/ml, 2 mg/ml, 2.5 mg/ml, and 3 mg/ml. The mixture was then filtered using micropore filter paper, leaving sediments on the filter paper and wastewater residues. The radioactivity of sediment and water residue was determined by using a well counter after 3, 6, 9, and 12 hours of filtration process. The activities of the sediment and water residues were found to be decreased with increasing GO concentrations. The FESEM image revealed high agglomeration structure when the sample was treated with GO of 3 mg/ml concentration. Further analysis via EDX showed the presence of other elements in the urine, which led to its attraction to the GO-layered sheets. This analysis also confirmed the presence of oxygen-functioning group in GO that facilitated the agglomeration process and solidified the radionuclide waste.