Laser scribe silver-reduced graphene oxide as novel bactericidal filter

Noor, An’amt Mohamed; Zin, Farah Amanina Mohd; Wei, Lee Seong; Huang, Nay Ming; Bakar, M. H. Abu; Sajab, Mohd Shaiful; Abdullah, Nor Hakimin; Zulhisyam, A. K.

doi:10.1063/1.5089325

Cited by 4 publications

(3 citation statements)

References 12 publications

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“…Synthesis of Graphene Oxide. Graphene oxide (GO) was prepared using the simplified Hummers method [12][13][14]. 3 g of graphite was mixed into solution of H2SO4 and H3PO4 (4:1) respectively, followed by KMnO4.…”

Section: Methodsmentioning

confidence: 99%

Characterization of GO:I-131 for Radioactive Clinical Waste Water Management in Nuclear Medicine

Mansor

Noor

Latif

et al. 2020

MSF

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Iodine-131 (I-131) mostly used in nuclear medicine for radioiodine ablation (RAI) therapy and hyperthyroid treatment. Patient was orally ingested I-131 and warded within 3 to 4 days for RAI therapy, whereas outpatient for hyperthyroid treatment. Radioactive waste from patient’s body such as urine and feces were eliminated from the ward into delay tank. Delay tank is an underground system to reduce radioactivity of contaminated I-131 clinical waste water at certain level before will be discharged into ordinary sewage system. Delay tank indirectly restricted the number of patient admission due to its periodical clearance and small volume size. Thus, a new technique to extract I-131 radionuclide with contaminated mixtures in solid form from the delay tank has been proposed as an alternative for clinical waste water management in nuclear medicine. Radioactive clinical waste water samples from delay tank were mixed with Graphene Oxide (GO) with varies in concentrations before filtered using micro pore filter paper. After 15 – 30 minutes, the radioactivity of the water residue left beneath the filter paper were counted using well counter. The measurements were repeated on fourth, eighth, twelfth and sixteenth days, which is significant to the natural decay of I-131 radionuclide. The water residue radioactivity decreases over the concentration of GO throughout the experiment. The mixtures of GO:I-131 (sediment formed on the filter paper) were analyzed using Field Emission Scanning Electron Microscopy (FESEM) and Energy Dispersive X-rays (EDX) for morphology and elemental analysis. FESEM image revealed the maximum GO concentration produced high agglomeration morphology. EDX shows I-131 and other elements were attracted to GO layered sheets. The results showed that the GO had high sorption capacities in the removal of radionuclides, which was attributed to the large number of oxygen-containing functional groups on the surface or edge sites.

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Section: Methodsmentioning

confidence: 99%

Characterization of GO:I-131 for Radioactive Clinical Waste Water Management in Nuclear Medicine

Mansor

Noor

Latif

et al. 2020

MSF

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“…The Graphene oxide was synthesised by the widely used Hummer's method [29][30][31]. About 3 g of graphite and 18 g of KMnO 4 were added to the 320 mL of H 2 SO 4 and 80 mL of H 3 PO 4 in a ratio of 4:1, respectively.…”

Section: Synthesis Of Graphene Oxidementioning

confidence: 99%

Fluorine-18 Fluorodeoxyglucose Isolation Using Graphene Oxide for Alternative Radiopharmaceutical Spillage Decontamination in PET Scan

et al. 2022

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Radiopharmaceuticals (RPC) used for diagnostic and therapeutic purposes in nuclear medicine may contaminate surface areas due to spillage during its preparation or accident during RPC transfer from laboratory to the treatment room. Fluorine-18 Fluorodeoxyglucose (18F-FDG) is the most common RPC for positron emission tomography (PET) scan in nuclear medicine due to its ideal annihilation converted energy at 511 keV and short half-life at 109.8 min. Ineffective medical waste management of 18F-FDG may pose a risk to the environment or cause unnecessary radiation doses to the personnel and public. Depending on the incident rate of these events, simple decontamination methods such as the use of chemicals and swabs might not be cost-effective and sustainable in the environment. This study aims to propose an alternative method to decontaminate 18F-FDG by using graphene oxide (GO). GO was synthesised using the Hummers method while the physical morphology was analysed using a field emission scanning electron microscope (FESEM). 18F-FDG adsorption efficiency rate using GO nanolayers was analysed based on the kinetic study of the GO:18F-FDG mixtures. The chemical adsorbability of the material was analysed via UV–vis spectrophotometer to interlink the microstructures of GO with the sorption affinity interaction. Resultantly, the adsorption rate was effective at a slow decay rate and the optical adsorption of GO with 18F-FDG was dominated by the π → π* plasmon peak, which was near 230 nm. By elucidating the underlining GO special features, an alternative technique to isolate 18F-FDG for the decontamination process was successfully proven.

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“…GO was pre pared ac cord ing to sim pli fied Hummer's method [10][11][12]. Ini tially, 3 g of graph ite pow der was mixed with 320 ml of H 2 SO 4 so lu tion and 80 ml of H 3 PO 4 so lu tion with a ra tio of 4:1.…”

Section: Syn the Sis Of Gomentioning

confidence: 99%

Efficiency of marketable decontamination agent and graphene oxide on 99mTc and 131I spillages in nuclear medicine department

Nawi

Sunaiwi²,

Noor

et al. 2022

NUCL TECH RAD PROT

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Dealing with open sources of radioactive substances in nuclear medicine is a daily task since contamination due to radioactive spills may happen frequently. Proper and safe decontamination management is a vital procedure. However, regular purchase of decontamination agents incurs high costs and might be toxic due to their chemical properties. The purpose of this study is to compare graphene oxide, which is an environmentally friendly carbon-based material and marketable decontamination agent, in decontaminating radioactive spillage. Samples of pure 99mTc and 131I from the laboratory were spilled on a petri dish. The spill was immediately decontaminated with a marketable decontamination agent swab and varying concentrations of graphene oxide swab. The initial radioactivity of each swab containing 99mTc and 131I was measured using a dose calibrator. The absorbance spectra of each sample were analysed using an ultraviolet-visible spectrophotometer. The morphology image of graphene oxide was observed under field emission scanning electron microscope. For decontamination using a marketable decontamination agent, the radioactivity of 131I was slightly higher, whereas that of 99mTc was slightly lower than the high concentration of graphene oxide. The absorbance spectra of 99mTc and 131I that had been decontaminated using graphene oxide were observed at a range of 200 nm to 250 nm due ???* to the transition.

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Laser scribe silver-reduced graphene oxide as novel bactericidal filter

Cited by 4 publications

References 12 publications

Characterization of GO:I-131 for Radioactive Clinical Waste Water Management in Nuclear Medicine

Characterization of GO:I-131 for Radioactive Clinical Waste Water Management in Nuclear Medicine

Fluorine-18 Fluorodeoxyglucose Isolation Using Graphene Oxide for Alternative Radiopharmaceutical Spillage Decontamination in PET Scan

Efficiency of marketable decontamination agent and graphene oxide on 99mTc and 131I spillages in nuclear medicine department

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