SEPARATION AND PURIFICATION TECHNOLOGY
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2024
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IF 8.1
Yongsheng Niu,Lixin Sun,Haiying Fu,Qiang Dou,Yuan Qian,Qingnuan Li
Molybdenum-99 ( 99 Mo) is one of the most important radionuclides for nuclear medicine. This isotope of molybdenum is mainly produced as a result of fission and decay processes occurring in nuclear reactors. Molten salt reactors (MSRs), a unique reactor with the fuel dissolved in a molten salt , have attracted attention as a source of 99 Mo. In this work, the feasibility of fluoride volatility process as a potential technique for selective extraction of trace amount of 99 Mo from fuel salt in the form of volatile MoF 6 by nitrogen trifluoride (NF 3 ) is illustrated. The results showed that in the case of using LiF-BeF 2 -ZrF 4 -UF 4 -MoF 3 (64.4–29.7–5.0–0.5–0.4 mol.%) molten salt as the simulated fuel salt, MoF 3 reacted with NF 3 to form MoF 6 at or above 570℃, while the conversion of UF 4 to volatile UF 6 required higher temperatures (≥650℃), when both exposed to 20 % NF 3 /Ar mixture. Based on above “cold” experiments, fluoride volatility process in LiF-BeF 2 -ZrF 4 molten salt containing irradiated UF 4 was carried out, and the extraction rate of 99 Mo was determined by detecting the change of its γ activity in the molten salt. The results indicated that 99 Mo could be extracted from the molten salt containing a quantity of uranium with the extraction rate of 98 % under current experimental conditions, and the content of uranium in collected 99 Mo product was only 0.9 wt%.
研究领域:
核医学
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化学工程
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核能工程
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DOI
高影响因子
CERAMICS INTERNATIONAL
·
2025
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IF 5.6
Yue Ji,Tian Tian,Pengju Chen,Yuan Zhao,Hao Wu,Yan Wu,Hiroshi Watabe,Wenlong Li,Yuezhou Wei,Xiangbiao Yin
99m Tc is one of the most widely used radioisotopes in nuclear medicine for diagnostic applications, with its supply critically dependent on the beta (β)-decay of the parent nuclide 99 Mo. To address this dependency, the cold sintering process has been introduced as a novel and facile technique to fabricate high-density MoO 3 ceramic targets for efficient 99 Mo production. It was explored in detail for the effects of transient liquid solutions, sintering temperature, uniaxial pressure, holding time, and additive formulation on the densification of raw MoO 3 powder. The results show that the typical transition solution of (NH 4 ) 6 Mo 7 O 24 ·4H 2 O and H 2 O mixture was most conducive to densifying MoO 3 material. The optimum conditions for cold sintering were under temperature of 200 °C, pressure of 500 MPa, holding time of 10 min, and transient aqueous solution of 10 wt.% (NH 4 ) 6 Mo 7 O 24 ·4H 2 O and 10 wt.% H 2 O. After further annealing cold-sintered MoO 3 at 600 °C, pure MoO 3 ceramic was obtained with the disappearance of the second phase. The pure MoO 3 ceramic target had a relative density of 95.48%, compressive strength of 118.01 MPa, and micro-Vickers hardness of 0.472 GPa. All these results suggested that cold sintering could be an energy-saving economical and efficient technique on the densification of MoO 3 for preparation its ceramic target, which are expected to inspire new insights to establish more practical technologies for 99 Mo and 99m Tc productions.
研究领域:
核医学
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材料科学
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放射性同位素生产
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产品关联
DOI
高影响因子
TALANTA
·
2026
·
IF 6.7
Lijuan Song,Lusheng Wang,Xiaolin Hou,Xiongxin Dai,Diandou Xu
Molybdenum-99 is an important radionuclide used in nuclear medicine, and efficient extraction of high purity 99 Mo from irradiated target is required to meet the medical application demands. A novel method is presented for the separation and purification of 99 Mo from thorium target irradiated by accelerator proton beam. In this method, ThO 2 target was dissolved in mixed HCl and HF acids, and Mo as MoO 2 Cl n− was preliminary separated from the Th matrices and many other radionuclide impurities using anion exchange chromatography. By precipitation of Mo with α-benzoin oxime (ABO) and secondary anion exchange chromatography purification, an overall chemical recovery of consistently over 80% for 99 Mo was achieved. A pure 99 Mo solution matching the requirements for medical purpose (according to European Pharmacopoeias for 99 Mo produced from neutron irradiated 235 U) was obtained with this method, and the produced 99 Mo can be directly used for the preparation of 99 Mo- 99m Tc generator.
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产品关联
DOI
PubMed
高影响因子
SEPARATION AND PURIFICATION TECHNOLOGY
·
2026
·
IF 9.1
Weiquan Liu,Qingru Zeng,Juan Liu,Zihang Yi,Mohammed F. Hamza,Yuezhou Wei,Lifeng Chen,Shunyan Ning
99m Tc, one of the most vital radioisotopes in nuclear medicine, is primarily supplied by molybdenum‑technetium ( 99 Mo/ 99m Tc) generators using alumina as the adsorbent. Nevertheless, this conventional technology poses challenges including the adsorbent's low Mo adsorption capacity, low distribution coefficient, and potential radioactive leakage. To address this challenge, a novel silica-based amine adsorbent (DDA/SiO 2 -P) was developed for the high adsorption capacity of Mo and efficiently separation of Mo and Tc. Given their similar chemical properties, rhenium (Re) was employed as a non-radioactive surrogate for technetium in this study. The adsorbent demonstrates exceptional performance with a Mo adsorption capacity of 119 mg/g, 170 mg/g, and 222 mg/g at 288 K, 308 K, and 318 K at pH = 2 respectively, achieving a remarkable separation factor ( SF Mo/Re ) of 3200. Furthermore, the adsorbent enables efficient elution of Re using 0.9 wt% NaCl solution. In a dynamic column experiment simulating generator operation, the recovery rate of Re reached 85.15% in the first ten collected fractions with the chemical purity of Re 99%, corresponding to a radiochemical purity of 99.9%. Additionally, the synthesis method for this adsorbent is straightforward and cost-effective, positioning it as a promising candidate for next-generation 99 Mo/ 99m Tc generators.
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产品关联
DOI
高影响因子
SEPARATION AND PURIFICATION TECHNOLOGY
·
2025
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IF 9
Ruihua Chen,Hao Deng,Junpeng Jiang,Daoyang Han,Gang Shao,Hailong Wang,Rui Zhang,Chao Ma
To overcome the problem of insufficient molybdenum adsorption capacity of commercially utilized alumina in 99 Mo/ 99m Tc generator, UiO-66(Ce)@MXene composites as potential molybdenum adsorbents were successfully prepared via in-situ growth method in this work. The adsorption performance and adsorption mechanism were investigated. The results indicate that the UM3 possesses superlative adsorption behavior compared to the other two samples. The adsorption kinetics are well described by the quasi-second-order model and the adsorption reaches equilibrium within 30 min. The adsorption isotherm can be well fitted with the Langmuir model, displaying the maximum molybdenum adsorption capacity of 833 mg/g at pH 3, superior to other reported adsorbents. The adsorption capacity manifests that polymolybdates are captured by the hydroxyl groups on MXene through hydrogen bonds. The monomolybdates can diffuse into micropores and are adsorbed on adsorption sites, e.g. missing-linker defects and Ce-OH groups. Consequently, the constructed hierarchical frameworks promote molybdenum adsorption and increase adsorption capacity significantly. The unrivalled adsorption performance of UiO-66(Ce)@MXene composites as molybdenum adsorbents have promising potential for the application in 99 Mo/ 99m Tc generator.
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产品关联
DOI
高影响因子
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