| 曹叶,舒迪昀,肖宇峰,等.硼中子俘获治疗后患者体内放射性核素分析及体外辐射水平调查研究[J].中华放射医学与防护杂志,2025,45(7):668-673.Cao Ye,Shu Diyun,Xiao Yufeng,et al.In vivo measurement of radionuclides and radiation levels around patients after BNCT treatment[J].Chin J Radiol Med Prot,2025,45(7):668-673 |
| 硼中子俘获治疗后患者体内放射性核素分析及体外辐射水平调查研究 |
| In vivo measurement of radionuclides and radiation levels around patients after BNCT treatment |
| 投稿时间：2024-08-19 |
| DOI：10.3760/cma.j.cn112271-20240819-00310 |
| 中文关键词: 硼中子俘获治疗(BNCT) 辐射防护 剂量 中子活化 |
| 英文关键词:Boron neutron capture therapy (BNCT) Radiation protection Dose Neutron activation |
| 基金项目:厦门市医疗卫生指导性项目(3502Z20224ZD1101);国家自然科学基金(12261131621) |
| 作者 | 单位 | E-mail | | 曹叶 | 厦门弘爱医院BNCT中心, 厦门 361006
南京航空航天大学, 南京 210016 | | | 舒迪昀 | 中硼(厦门)医疗器械有限公司, 厦门 361000 | | | 肖宇峰 | 厦门弘爱医院BNCT中心, 厦门 361006 | | | 赖友群 | 厦门弘爱医院BNCT中心, 厦门 361006 | laiyouqun@haxm.com | | 程金生 | 中国疾病预防控制中心辐射防护与核安全医学所 辐射防护与核应急中国疾病预防控制中心重点实验室, 北京 100088 | | | 郑森兴 | 福建省职业病与化学中毒预防控制中心, 福州 350000 | | | 袁继龙 | 中国疾病预防控制中心辐射防护与核安全医学所 辐射防护与核应急中国疾病预防控制中心重点实验室, 北京 100088 | | | 缪晓华 | 福建省职业病与化学中毒预防控制中心, 福州 350000 | | | 潘建基 | 厦门弘爱医院BNCT中心, 厦门 361006 | | | 刘渊豪 | 厦门弘爱医院BNCT中心, 厦门 361006
南京航空航天大学, 南京 210016
中硼(厦门)医疗器械有限公司, 厦门 361000
南京中硼联康医疗科技有限公司, 南京 211112 | |
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| 中文摘要: |
| 目的 探究患者接受硼中子俘获治疗(BNCT)后体外辐射水平与体内中子活化情况。方法 回顾性选取2022年10月至2024年4月于厦门弘爱医院的21例头颈部及脑部肿瘤患者,采用极锋刀NeuPex加速器硼中子俘获治疗(AB-BNCT)系统实施了29次BNCT治疗。用X (γ)剂量率巡检仪测量患者周围环境剂量当量率,分别测量了距离患处照射位置0、0.5、1.0和2.0 m,距照射位置正对侧0、0.5、1.0和2.0 m,肚脐处及患侧膝盖处的γ射线剂量率。同时,用便携式高纯锗γ谱仪测量患者治疗后体内活化核素能谱,分析得到每次BNCT治疗时因中子活化产生的放射性核素种类。结果 经BNCT治疗的患者体内主要产生了放射性核素24Na、38Cl和49Ca;治疗后20 min距离患者照射位置1.0 m处光子周围剂量当量率< 2.5 μSv/h。结论 BNCT后的患者对工作人员及家属所产生剂量较小,所导致辐射安全风险较低。根据可合理达到尽可能低(ALARA)的原则,建议治疗后对患者采取一定管控措施,尽可能减少患者及工作人员的受照剂量。 |
| 英文摘要: |
| Objective To explore the in vitro radiation levels and in vivo neutron activation after patients receiving boron neutron capture therapy (BNCT). Methods Totally 29 BNCT treatments were performed for 21 patients with head and neck and brain cancer using the NeuPex accelerator-based boron neutron capture therapy (AB-BNCT) system in Xiamen Humanity Hospital from October, 2022 to April, 2024. The ambient dose equivalent rate around the patients was measured with an X/gamma dose rate survey meter. The gamma radiation dose rates were measured at 0, 0.5, 1.0, and 2.0 m from the irradiation position, at 0, 0.5, 1.0, and 2.0 m from the opposite side of the irradiation position, and at the navel and the affected knee, respectively. Meanwhile, a portable high-purity germanium gamma spectrometer was used to measure the spectrum of activated nuclides in the bodies of patients who had underwent the treatment, and the types of radionuclides generated by neutron activation during each BNCT treatment were analyzed. Results The radionuclides 24Na, 38Cl, and 49Ca were mainly produced in the bodies of patients treated with BNCT. 20 minutes after BNCT treatment, the ambient dose equivalent rate at a distance of 1.0 m from the irradiation position was lower than 2.5 μSv/h. Conclusions The dose delivered to the staff and family members by the patients undergoing BNCT is relatively low, and the resulting radiation risk is low. According to the ALARA principle, it is recommended that certain control actions be taken for patients having received BNCT treatment to minimize the exposure doses of both patients and staff as much as possible. |
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