| 赵锡鹏,彭建亮,张震,等.90Y树脂微球内放射治疗轫致辐射剂量水平测定与理论估算研究[J].中华放射医学与防护杂志,2024,44(12):1077-1082.Zhao Xipeng,Peng Jianliang,Zhang Zhen,et al.Measurement and theoretical estimation of bremsstrahlung doses in selective internal radiation therapy using 90Y resin microspheres[J].Chin J Radiol Med Prot,2024,44(12):1077-1082 |
| 90Y树脂微球内放射治疗轫致辐射剂量水平测定与理论估算研究 |
| Measurement and theoretical estimation of bremsstrahlung doses in selective internal radiation therapy using 90Y resin microspheres |
| 投稿时间：2024-04-15 |
| DOI：10.3760/cma.j.cn112271-20240415-00136 |
| 中文关键词: 90Y-SIRT 轫致辐射 剂量测定 理论计算 衰减因子 |
| 英文关键词:90Y-SIRT Bremsstrahlung Dose measurement Theoretical calculation Attenuation factor |
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| 中文摘要: |
| 目的 评估90Y微球选择性内放射治疗(90Y-SIRT)中轫致辐射外照射剂量水平和工作人员受照剂量。方法 使用AT1123型X、γ剂量率仪,分别测量有无铅屏蔽时距90Y药物30、100 cm处的轫致辐射周围剂量当量率,计算铅罐和铅围裙对90Y轫致辐射的衰减因子;同时使用公式法理论估算相应位点的剂量率水平,结合实测结果估算放射工作人员年受照剂量。结果 铅屏蔽体表面1m处的90Y轫致辐射剂量率测量值范围为0.19~0.26 μSv·h-1·GBq-1,无铅屏蔽的西林瓶、有机玻璃转运桶、注射输送箱和患者表面1 m处为1.00~1.60 μSv·h-1·GBq-1;90Y轫致辐射剂量计算值与测量值的偏差大多接近或小于±20%;在年治疗患者200人次,每瓶90Y药物3 GBq,每位患者常用最高2 GBq条件下,核医学科分装技师、介入科注射医师和查房医师个人年有效剂量估计值分别为2.24、1.04和0.22 mSv,手部年当量剂量分别为49.9、25.5和2.06 mSv;6.4 mmPb当量铅罐和0.5 mmPb当量铅围裙对90Y轫致辐射的衰减因子测量值分别介于0.13~0.15和0.45~0.50之间。结论 正常工作情况下,90Y-SIRT中工作人员年有效剂量不会超过5 mSv,在90Y注射阶段穿戴个人防护用品或用铅围裙覆盖患者的注射部位可以降低工作人员约50%的受照剂量。 |
| 英文摘要: |
| Objective To determine the external bremsstrahlung doses and doses to radiation workers in selective internal radiation therapy using 90Y resin microspheres (90Y-SIRT). Methods Using an AT1123 X-ray and gamma radiation dosimeter, the ambient dose equivalent rates of bremsstrahlung at distances of 30 and 100 cm from the 90Y drug with and without lead shielding were measured. The attenuation factors of 90Y bremsstrahlung attributed to lead cans and lead aprons were calculated. Furthermore, the dose rates at corresponding sites were theoretically estimated using formula. Finally, the annual doses to radiation workers were estimated based on estimated and measured bremsstrahlung doses. Results The measured dose rates of 90Y bremsstrahlung ranged from 0.19 to 0.26 μSv·h-1·GBq-1 at a distance of 1 m from the surface of the lead shield and from 1.00 to 1.60 μSv·h-1·GBq-1 at a distance of 1 m from the surface of the unshielded penicillin bottle, plexiglass transport container, injection delivery box, and the patient. The deviations between the calculated and measured bremsstrahlung doses were mostly close to or less than ±20%. Under conditions of 200 patients treated annually, 3 GBq for each bottle of 90Y resin microspheres, and a maximum dose of 2 GBq per patient, the estimated annual effective doses to nuclear medicine technologists, interventional injection physicians, and ward-round physicians were 2.24, 1.04 and 0.22 mSv, respectively, and the annual equivalent doses to their hands were 49.9, 25.5 and 2.06 mSv, respectively. The measured attenuation factors of 90Y bremsstrahlung attributed to the lead can of 6.4 mmPb equivalent and the lead apron of 0.5 mmPb equivalent ranged from 0.13 to 0.15 and from 0.45 to 0.50, respectively. Conclusions Under normal working conditions, the annual effective doses to the radiation workers in 90Y-SIRT will not exceed 5 mSv. Wearing personal protective equipment (PPE) or covering the injection sites of patients using a lead apron during 90Y injection can reduce the doses to the workers by approximately 50%. |
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