| 李夏,马永忠,王时进.质子加速器放射治疗场所活化核素所致人员受照剂量估算与分析[J].中华放射医学与防护杂志,2016,36(8):630-633.Li Xia,Ma Yongzhong,Wang Shijin.Estimating and analysis of personnel doses from activated nuclides in radiotherapy place of a proton accelerator[J].Chin J Radiol Med Prot,2016,36(8):630-633 |
| 质子加速器放射治疗场所活化核素所致人员受照剂量估算与分析 |
| Estimating and analysis of personnel doses from activated nuclides in radiotherapy place of a proton accelerator |
| 投稿时间：2016-03-15 |
| DOI：10.3760/cma.j.issn.0254-5098.2016.08.015 |
| 中文关键词: 质子加速器 放射治疗 活化核素 放射性活度浓度 剂量估算 |
| 英文关键词:Proton acceterator Radiotherapy Activation nuclides Radioactive activity concentration Doses estimation |
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| 中文摘要: |
| 目的 了解质子加速器放射治疗场所空气活化产物可能致工作人员的受照剂量水平，为治疗场所的防护设计和人员的放射防护提供技术基础。方法 以PROTEUS235型质子治疗系统为例，分析质子加速器运行时场所空气中可能产生的主要活化核素，估算工作场所内活化核素的放射性活度浓度及其所致人员的受照剂量。结果 在质子加速器厅内，活化核素15O的放射性活度浓度最高，为4.1×10-2Bq ·cm-3；13N、41Ar和11C依次为3.3×10-2、6.2×10-3和2.0×10-2Bq ·cm-3。在质子束治疗室内，上述核素放射性活度浓度约为加速器厅内的5%。工作人员在停束后5和30 min进入质子加速器厅内，因外照射可能受到的年有效剂量分别小于1和0.1 mSv；在质子治疗停束后即刻进入治疗室，因空气活化所致年有效剂量为1.3～2.0 mSv，而在停束后5和15 min进入时分别为0.7～1.2和0.3～0.6 mSv。结论 质子加速器治疗场所空气中活化核素所致人员受照剂量不容忽视，应主要考虑活化核素15O、13N、41Ar、11C所致外照射对工作人员造成的剂量贡献，并采取必要的防护措施。 |
| 英文摘要: |
| Objective To ascertain the dose levels to personnel from the activation products in the radiotherapy place of a proton acceterator and to provide technical basis for protection design of the treatment place and the personnel's radiation protection. Methods A PROTEUS 235 proton therapy system was analyzed for the potentials to produce activated nuclides in the air during its operation. The concentrations of the main radionuclides and the resultant personnel doses were estimated. Results The activity concentrations of activated nuclides were 15O 4.1×10-2, 13N 3.3×10-2,41Ar 6.2×10-3 and 11C 2.0×10-2 Bq\5cm-3, respectively, in proton accelerator hall, whereas those in the proton beam radiotherapy room were only about 5% of the corresponding values in the proton accelerator hall. The annual doses to the radiation workers from immersion external exposure due to air activation were less than 1 and 0.1 mSv, respectively, when entering the proton accelerator hall 5 and 30 min after beam stopping; whereas those were 1.3-2.0, 0.7-1.2 and 0.3-0.6 mSv, respectively, when entering the therapy hall 0, 5 and 15 min after beam stopping. Conclusions The personnel doses received from activated nuclides in the air in the radiotherapy place of a proton acceterator are unignorable. The contribution to doses from immersed external exposure of 15O, 13N, 41Ar and 11C should be taken into full considerations, with necessary protection measures needed. |
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