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

IF 0.9 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI:10.2298/ntrp2202159r
M. Razab, N. Nawi, R. Sunaiwi, A. Noor, M. Aziz, F. Hadzuan, Fathirah Ibrahim, A. Khaizul, N. Abdullah
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Abstract

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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市售去污剂与氧化石墨烯对核医学科99mTc、131I泄漏的治理效果
由于放射性物质泄漏造成的污染可能经常发生,因此处理核医学中放射性物质的开放来源是一项日常任务。适当和安全的去污管理是一个至关重要的程序。然而,定期购买去污剂的成本很高,而且由于其化学性质,可能有毒。本研究的目的是比较氧化石墨烯作为一种环保的碳基材料和市场上销售的去污剂对放射性泄漏的去污效果。实验室的纯99mTc和131I样本洒在培养皿上。泄漏物立即用市售的去污剂棉签和不同浓度的氧化石墨烯棉签进行净化。每个含有99mTc和131I的拭子的初始放射性使用剂量校准器测量。用紫外-可见分光光度计分析各样品的吸光度光谱。在场发射扫描电镜下观察氧化石墨烯的形貌。使用市售去污剂去污时,131I的放射性略高,而99mTc的放射性略低于高浓度氧化石墨烯。用氧化石墨烯净化后的99mTc和131I在200 ~ 250 nm范围内的吸光度光谱被观察到。*到过渡阶段。
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来源期刊
Nuclear Technology & Radiation Protection
Nuclear Technology & Radiation Protection NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.00
自引率
41.70%
发文量
10
审稿时长
6-12 weeks
期刊介绍: Nuclear Technology & Radiation Protection is an international scientific journal covering the wide range of disciplines involved in nuclear science and technology as well as in the field of radiation protection. The journal is open for scientific papers, short papers, review articles, and technical papers dealing with nuclear power, research reactors, accelerators, nuclear materials, waste management, radiation measurements, and environmental problems. However, basic reactor physics and design, particle and radiation transport theory, and development of numerical methods and codes will also be important aspects of the editorial policy.
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