Non-volatile immobilization of iodine by the cold-sintering of iodosodalite

Highly radioiodine gas capture by 2-mercaptobenzimidazole-functionalized Bi/Mg oxide and effective iodine waste immobilization by etidronic-Bi2O3 complex

The present work prepared a novel BiMgO-2MBD (X = 0.42) material for iodine vapor capture in temperature conditions related to spent nuclear fuel reprocessing and nuclear accidents. BiMgO-2MBD (X = 0.42) was synthesized by a solvothermal process and exhibited an exceptional ultrafast and high iodine uptake with a capacity of 4352.12 mg/g and 5147.08 mg/g after 5 h at 75 °C and 150 °C, respectively. The TGA analysis shows that Bi/Mg oxide substrate highly contributed to improving the thermal stability of the functionalized BiMgO-2MB (X = 0.42) as indicated by the weight losses of the material components of 3.77 wt%, 29.32 wt%, and 97.72 wt%, respectively for Bi/Mg oxide, BiMgO-2MBD, and 2-MBD. The material characterization and DFT calculations indicate that 2-MBD played a significant role towards improving iodine capture capacity. For long-term and safe waste disposal, a chemically durable waste form was made from etidronic acid and Bi2O3, and successfully immobilized the iodine-loaded wastes (I2 @BiMgO-2MBD) which exhibited a low normalized leaching rate of 1.098 × 10-6 g.m2/day for 7 days under the PCT-A method. In addition, BiMgO-2MBD (X = 0.42) showed an ability to be reused after several regeneration cycles. The comparison with previously reported materials shows that the current BiMgO-2MBD (X = 0.42) is the first functionalized metal oxide comparable to metal-organic and covalent organic frameworks for iodine uptake. BiMgO-2MBD (X = 0.42) shows promising results for practical applications in the gas phase capture of radioactive iodine.

Investigation of bismuth-based metal-organic frameworks for effective capture and immobilization of radioiodine gas

In this study, we investigated the use of Bi-mna, a specific type of bismuth metal organic framework (MOF) for the capture and disposal of iodine, a key nuclide of concern in nuclear fuel reprocessing plants and nuclear power plants. To find the suitable form of Bi-mna for the purpose, experiments were performed by synthesizing four different Bi-mna with varying reagent ratios and connecting iodine adsorption and conversion for immobilization. After iodine adsorption and characterization to investigate their adsorption mechanisms, the Bi-mna samples went through conversion for immobilization to fix captured iodine into the adsorbents. The converted materials are characterized to examine their thermal stability. The Bi-2mna, showing the best performance of adsorption and thermal stability after the conversion, was selected to explore its chemical stability. According to the test results, the converted compound showed relatively low leaching rate (3.06 ×10-5 g/m2∙day) compared with other iodine containing waste forms for disposal. Based on the results, we proposed the Bi-2mna as a candidate material as iodine adsorbent as well as waste form precursor. ENVIRONMENTAL IMPLICATION: Radioiodine a key nuclide of concern in nuclear fuel reprocessing plants and nuclear power plants. Once ingested, it is accumulated in thyroid grand, causing negative health effects. Currently, a typical radioiodine adsorbent is silver-based zeolites. Despite a strong affinity to iodine of silver, it has a chemical toxicity that causes a potential issue in disposal. Therefore, it is substantially required to develop new type of adsorbents which are both good for capture and disposal of radioiodine. In this respect, we suggested a bismuth-based metal-organic framework as an alternative adsorbent to manage the life cycle of radioiodine.

Apatite/Chitosan Composites Formed by Cold Sintering for Drug Delivery and Bone Tissue Engineering Applications

In the biomedical field, nanocrystalline hydroxyapatite is still one of the most attractive candidates as a bone substitute material due to its analogies with native bone mineral features regarding chemical composition, bioactivity and osteoconductivity. Ion substitution and low crystallinity are also fundamental characteristics of bone apatite, making it metastable, bioresorbable and reactive. In the present work, biomimetic apatite and apatite/chitosan composites were produced by dissolution-precipitation synthesis, using mussel shells as a calcium biogenic source. With an eye on possible bone reconstruction and drug delivery applications, apatite/chitosan composites were loaded with strontium ranelate, an antiosteoporotic drug. Due to the metastability and temperature sensitivity of the produced composites, sintering could be carried out by conventional methods, and therefore, cold sintering was selected for the densification of the materials. The composites were consolidated up to ~90% relative density by applying a uniaxial pressure up to 1.5 GPa at room temperature for 10 min. Both the synthesised powders and cold-sintered samples were characterised from a physical and chemical point of view to demonstrate the effective production of biomimetic apatite/chitosan composites from mussel shells and exclude possible structural changes after sintering. Preliminary in vitro tests were also performed, which revealed a sustained release of strontium ranelate for about 19 days and no cytotoxicity towards human osteoblastic-like cells (MG63) exposed up to 72 h to the drug-containing composite extract.

Bi0-Reduced Graphene Oxide Composites for the Enhanced Capture and Cold Immobilization of Off-Gas Radioactive Iodine

Radioactive waste management is critical for maintaining the sustainability of nuclear fuel cycles. In this study, we propose a novel bismuth-based reduced graphene oxide (Bi0-rGO) composite for the immobilization of off-gas radioactive iodine. This material synthesized via a solvothermal route exhibited a low surface area (2.96 m2/g) combined with a maximum iodine sorption capacity of 1228 ± 25 mg/g at 200 °C. The iodine sorbent was mixed with Bi2O3 powder and distilled water to fabricate waste matrices, which were cold-sintered at 300 °C under a uniaxial pressure of 500 MPa for 20 min to achieve a relative density of ∼98% and Vickers hardness of 1.3 ± 0.1 GPa. The utilized methodology reduced the iodine leaching rate by approximately 3 orders of magnitude through the formation of a chemically durable iodine-bearing waste form (BiOI). This study demonstrates the high potential of Bi0-rGO as an innovative solution for the immobilization of radioactive waste at relatively low temperatures.

Analysis of Radioactive Iodine Trapping Mechanism by Zinc-Based Metal-Organic Frameworks with Various N-Containing Carboxylate Ligands

This study aimed to develop effective adsorbents for capturing radioactive iodine in nuclear power waste gas. Two zinc metal-organic frameworks (Zn-MOFs) were synthesized and found to have favorable properties such as a large surface area, thermal stability, surface rich in π-electron-containing nitrogen, and redox potential. Adsorption experiments revealed maximum capacities of 1.25 and 1.96 g g^-1 for the MOFs at 75 °C, with the pseudo-second-order kinetic model fitting the data well. The Langmuir equation provided a better fit in cyclohexane, with maximum adsorption amounts of 249 and 358 mg g^-1 for Zn-MOF-1 and Zn-MOF-2, respectively. The MOFs were also stable during six cycles of adsorption and desorption. Furthermore, electron transfer occurred due to the synergistic adsorption of Zn, N, and O atoms, resulting in the conversion of some iodine to polyiodide. Zn-MOF-2 exhibited better chemisorption than Zn-MOF-1 due to a smaller highest occupied molecular orbital (HOMO)-lowest unoccupied molecular orbital (LUMO) gap. Notably, it was discovered that N-containing radicals had stronger interactions with iodine compared to radicals without N. These findings provide valuable insights into MOF synthesis and environmental protection.

Effects of Cold Sintering on the Performance of Zeolite 13X as a Consolidated Adsorbent for Cesium

Cold sintering, a novel low-temperature consolidation technique, has shown promising results in various inorganic materials. However, the application of this technique to nanoporous materials for energy and environmental fields is not yet fully understood. This study investigates the effects of cold sintering on the relative densities, compressive strengths, chemical durabilities, crystal structures, specific surface areas, and adsorption capacities of zeolites. Cold sintering at 200 °C achieved 10 to 20% greater densification than conventional high temperature (700 °C) sintering; however, the original nanoporous structure of dry cold sintered zeolite was not maintained. Introducing liquid agents during the cold sintering process resulted in reduced degradation of the SSA and increased densification. Using NaOH as the liquid agent increased the solubility of elements in zeolite, which promoted chemical mobility and achieved the highest relative density (96.7 ± 2.8%). However, soluble layers between the particles led to fragmentation, making it unsuitable for aqueous applications. Using H₂O as the liquid agent resulted in a relative density of 90.4 ± 4.1% while maintaining the nanoporous properties and structural integrity of zeolite under water. The cesium adsorption capacity (19.0 ± 0.1 mg·g^-1) was similar to that of conventional zeolite ion exchangers, indicating that cold sintering with H₂O was an efficient, economical, and safer alternative to conventional high-temperature consolidation method. Our findings suggest that this cold sintering can be applied to other nanoporous materials, such as metal-organic frameworks and covalent organic frameworks, in separation, catalysis, and adsorption applications.

Review of recent developments in iodine wasteform production

Radioiodine capture and immobilization is not only important to consider during the operation of reactors (i.e., I-131), during nuclear accidents (i.e., I-131 and I-129) or nuclear fuel reprocessing (i.e., I-131 and I-129), but also during disposal of nuclear wastes (i.e., I-129). Most disposal plans for I-129-containing waste forms (including spent nuclear fuel) propose to store them in underground repositories. Here, iodine can be highly mobile and, given its radiotoxicity, needs to be carefully managed to minimize long-term environmental impacts arising from disposal. Typically, any process that has been used to capture iodine from reprocessing or in a reactor is not suitable for direct disposal, rather conversion into a wasteform for disposal is required. The objectives of these materials are to use either chemical immobilization or physical encapsulation to reduce the leaching of iodine by groundwaters. Some of the more recent ideas have been to design capture materials that better align with disposal concepts, making the industrial processing requirements easier. Research on iodine capture materials and wasteforms has been extensive. This review will act as both an update on the state of the research since the last time it was comprehensively summarized, and an evaluation of the industrial techniques required to create the proposed iodine wasteforms in terms of resulting material chemistry and applicability.

Barbituric and thiobarbituric acid-based UiO-66-NH2 adsorbents for iodine gas capture: Characterization, efficiency and mechanisms

Efficient iodine gas capture is necessitated in many industries like spent nuclear fuel off-gas treatment in view of environmental protection and resource recycling. However, the adsorption efficiency and stability of the current adsorbents are limited. In the present work, efficient and stable barbituric and thiobarbituric acid-based UiO-66-NH₂ adsorbents (i.e., UiO-66-NH-B.D and UiO-66-NH-T.D, respectively) have been synthesized by post-synthetic covalent modification. Characterization approaches, including SEM-EDS, TEM, XRD, FTIR, XPS, ¹H NMR, TGA and BET, are used to obtain information on the properties and adsorption mechanisms of these metal-organic framework (MOF) adsorbents. The kinetics and mechanisms involved are studied in detail. The treatment efficiency and recyclability of the adsorbents are checked and compared with the adsorbents reported in previous works. The results show that the current adsorbents are potentially suitable for efficient iodine gas capture. High maximum iodine adsorption amount by UiO-66-NH-B.D and UiO-66-NH-T.D (1.17 and 1.33 g/g) was achieved under 75 °C. These new adsorbents are thermally stable for iodine adsorption and regenerated and reused with good performance. The adsorption mechanisms were revealed based on experimental results, indicating that iodine is adsorbed by both physisorption and chemisorption.