The role of nuclear energy in the carbon neutrality goal

Liu, Limin; Hui, Guo; Dai, Lu; Liu, Maolong; Xiao, Yao; Cong, Tenglong

doi:10.1016/j.pnucene.2023.104772

Cited by 41 publications

(7 citation statements)

References 10 publications

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“…Nuclear power is rapidly emerging as the most reliable alternative power source to conventional sources because of its low carbon emission burden on the environment and sustainability due to the in situ production of fissile materials, viz., 239 Pu. − One of the major challenges faced in the nuclear industry is the safe handling of the highly radioactive mass known as fission and the activation products . Recycling of the unspent fissile 235 U by the closed fuel cycle along with the thus generated 239 Pu is one of the most accepted strategies for the sustainable growth of nuclear power. , The widely used technology for spent fuel reprocessing is the PUREX (Plutonium Uranium Redox EXtraction) process, which involves the selective extraction of U and Pu from the fission products as well as the activation products consisting of the minor actinides, viz., Np, Am, and Cm.…”

Section: Introductionmentioning

confidence: 99%

First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am³⁺ and Eu³⁺: Use of BTP-Grafted Silica Decorated on Activated Carbon

Ansari,

Gujar,

Bhattacharyya

et al. 2024

Ind. Eng. Chem. Res.

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A new composite sorbent material was prepared by grafting bistriazinylpyridine (BTP) onto silica and then blending it with activated charcoal (AC− Si−BTP) for the selective separation of Am 3+ over Eu 3+ using a 1-cycle solid-phase extraction for the direct separation of lanthanides from actinides. BTP was attached to silica via a sulfonamide bond between R−BTP and amino silane, and the resulting Si− BTP was covalently bonded to activated carbon (AC) with a favorable orientation of the ligand coordination sites. The material exhibited a significantly large distribution coefficient for Am 3+ over Eu 3+ at lower acidities (<0.5 M HNO 3 ), and the separation factor between the two metal ions was found to be maximum in 0.2 M HNO 3 with a value of 110. The loading capacity of the material was 4.05 ± 0.12 mg of Eu per gram of the composite when investigated at pH 3. The radiation stability of the material was excellent when studied up to an absorbed dose of 1000 kGy. The material was tested for the separation of Am 3+ and Eu 3+ in a column mode, which gave selective loading of Am 3+ over Eu 3+ . The reusability studies indicated slow leaching of the BTP fraction from the solid, with a resultant decrease of the K d values with time. To address this issue, the material was embedded in polysulfone beads for a separate set of studies, but the separation efficiencies were found to be comparable.

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Section: Introductionmentioning

confidence: 99%

First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am³⁺ and Eu³⁺: Use of BTP-Grafted Silica Decorated on Activated Carbon

Ansari,

Gujar,

Bhattacharyya

et al. 2024

Ind. Eng. Chem. Res.

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“…For a sustainable operation of the nuclear power plants, recycling of the spent nuclear fuel to recover the fissile materials, including the unutilized 235 U and the neutron activated 239 Pu, is a requisite step. This is the genesis of the closed nuclear fuel cycle, already adopted by many countries. − For this purpose, the plutonium uranium redox extraction (PUREX) process is being used globally for over six decades . Tri- n -butyl phosphate (TBP) is the organic extractant used in the PUREX process to selectively extract the hexavalent U and tetravalent Pu, leaving behind the fission and activation products, including the minor actinides, in the raffinate.…”

Section: Introductionmentioning

confidence: 99%

Understanding the Interaction of Uranyl Cation with Two C-Pivot Tripodal Amides: Synthesis, Complexation, Microcalorimetry, and DFT Studies

Ansari,

Mohapatra,

et al. 2024

Inorg. Chem.

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Complexation of uranyl ions with two structurally related Cpivotal tripodal amides with varying spacer lengths, synthesized for the first time, was studied by optical spectroscopy. In the tripodal amides, the coordination was through the carbonyl O atoms where the carbonyl groups were away from the central C-atom by three spacer atoms (L I ) and four spacer atoms (L II ), respectively. Increasing the spacer atoms going from L I to L II favors the complexation with the linear uranyl cations and results in stronger complex formation. The complexation heat between the uranyl cations and the two amide ligands was directly measured by microcalorimetric titrations. The complexation with both the ligands was driven by exothermic enthalpy and positive entropy changes. Formation of the complex proceeded by the replacement of water molecules from the primary coordination sphere of the uranyl cation. Both ligands formed bisolvated (ML 2 -type) complexes in which one unit of the ligand binds in a monodentate manner and the other in a bidentate mode. Density functional theory calculations further supported our experimental observations.

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“…Nuclear energy is clean, safe, and highly efficient and thus provides a promising source of energy. Therefore, it plays a key role in the development of energy strategies for carbon neutralization with the lowest hazardous emissions to the environment [ 1 ]. Considering the rapid growth of nuclear energy, it has been expected that about 3200 t of spent nuclear fuel will be produced solely in China by the year 2030 [ 2 ].…”

Section: Introductionmentioning

confidence: 99%

Adsorption and Desorption Behavior and Mechanism of Ruthenium in Nitrite–Nitric Acid System

Li,

Xie,

Jiang

et al. 2024

Toxics

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Ruthenium is required to separate from high-level liquid waste (HLLW) because Ru is a valuable resource and is negatively influential on the vitrification process of HLLW. However, the separation of Ru is very challenging due to its complicated complexation properties. In this study, the adsorption and desorption characteristics of ruthenium on a synthesized SiPyR-N3 (weak-base anion exchange resin with pyridine functional groups) composite were investigated in nitric acid and nitrite–nitric acid systems, respectively, and the adsorption mechanism was explored. The experimental results showed that SiPyR-N3 has a significantly better adsorption effect on Ru in the nitrite–nitric acid system than in the nitric acid system, with an increase in the adsorption capacity of approximately three times. The maximum adsorption capacity of Ru is 45.6 mg/g in the nitrite–nitric acid system. The SiPyR-N3 possesses good adsorption selectivity (SFRu/other metal ions is around 100) in 0.1 M NO2−–0.1 M HNO3 solution. The adsorption processes of Ru in the two different systems are fitted with the pseudo-second-order kinetic model and Langmuir model for uptake kinetics and adsorption isotherms, respectively. The results obtained from the FT-IR, XPS, and UV absorption spectrometry indicate that NO2− was involved in the adsorption process either as a complexing species with the metal ions or as free NO2− from the solution. A 0.1 M HNO3 + 1 M thiourea mixed solution shows effective desorption performance, and the desorption efficiency can reach 92% at 328 K.

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The role of nuclear energy in the carbon neutrality goal

Cited by 41 publications

References 10 publications

First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am³⁺ and Eu³⁺: Use of BTP-Grafted Silica Decorated on Activated Carbon

First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am³⁺ and Eu³⁺: Use of BTP-Grafted Silica Decorated on Activated Carbon

Understanding the Interaction of Uranyl Cation with Two C-Pivot Tripodal Amides: Synthesis, Complexation, Microcalorimetry, and DFT Studies

Adsorption and Desorption Behavior and Mechanism of Ruthenium in Nitrite–Nitric Acid System

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The role of nuclear energy in the carbon neutrality goal

Cited by 41 publications

References 10 publications

First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am3+ and Eu3+: Use of BTP-Grafted Silica Decorated on Activated Carbon

First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am3+ and Eu3+: Use of BTP-Grafted Silica Decorated on Activated Carbon

Understanding the Interaction of Uranyl Cation with Two C-Pivot Tripodal Amides: Synthesis, Complexation, Microcalorimetry, and DFT Studies

Adsorption and Desorption Behavior and Mechanism of Ruthenium in Nitrite–Nitric Acid System

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First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am³⁺ and Eu³⁺: Use of BTP-Grafted Silica Decorated on Activated Carbon

First Report on a 1-Cycle Solid-Phase Extraction Method for Selective Separation of Am³⁺ and Eu³⁺: Use of BTP-Grafted Silica Decorated on Activated Carbon