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口服[131I] 碘酸钠污染的管理与评价。

Management and evaluation of sodium [131I] iodide contamination after oral administration.

机构信息

Departments of Nuclear Medicine.

Pharmacy, CHU de Caen Normandie, Normandie Univ, UNICAEN, Caen, France.

出版信息

Nucl Med Commun. 2020 Nov;41(11):1218-1220. doi: 10.1097/MNM.0000000000001276.

Abstract

Radioiodine therapy using oral administration of Iodine-131 (I) is a widespread employed strategy for the treatment of hyperthyroidism and thyroid cancer. Such a therapy requires well-trained staff, equipment and procedures regarding radiation safety. The aims of this work are to report an incidental experience of radioprotection with a 370 MBq sodium [I] iodide capsule, which arose following vomiting one minute after the oral administration in a nuclear medicine department and assessment of capsule leakage in a stomach like environment by in vitro experiment. Measurements of the radiation dose rate at the different steps of the decontamination procedure were performed and management of the situation described. Dose rate in vomit was 113 µSv/h [directional dose equivalent H'(0.07)] after capsule withdrawal and was decreased by 10 times after the first decontamination attempt. To evaluate the I release following administration to the patient, an in vitro experiment was designed to recap capsules degradation in a stomach like environment including acidic solution (pH 1) and temperature at 35-37°c. A significant release of I (<6%) was observed in the first 2 min of the in vitro experiment. Sodium [I] iodide capsules disruption occurred at 150 s for capsule 1 and 133 s for capsule 2. Incidental contamination with I in the clinics is of important concern in nuclear medicine and precautions that allow optimization and pertinent management of the situation should be known by the nuclear medicine and radioprotection community.

摘要

放射性碘-131(I)口服治疗是治疗甲状腺功能亢进症和甲状腺癌的广泛应用策略。这种治疗需要经过良好培训的工作人员、设备和辐射安全程序。本工作的目的是报告核医学部门在口服后 1 分钟呕吐后,对 370MBq 钠[I]碘化物胶囊进行放射防护的偶然经验,以及在类似于胃的环境中通过体外实验评估胶囊泄漏。对去污程序的不同步骤的辐射剂量率进行了测量,并描述了情况的管理。在取出胶囊后,呕吐物中的剂量率为 113µSv/h[定向剂量当量 H'(0.07)],首次去污尝试后降低了 10 倍。为了评估患者给药后 I 的释放情况,设计了一个体外实验,以模拟类似于胃的环境中的胶囊降解,包括酸性溶液(pH 1)和 35-37°C 的温度。在体外实验的前 2 分钟观察到 I 的显著释放(<6%)。胶囊 1 的胶囊破裂发生在 150 秒,胶囊 2 的胶囊破裂发生在 133 秒。核医学中,临床中偶然的 I 污染是一个重要的关注点,核医学和放射防护界应该了解允许优化和适当管理情况的预防措施。

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