核恐怖袭击受照人员血液活化中子生物剂量方法的建立
|
摘要
目的核与辐射突发事件发生后,快速确定人员的受照剂量,为后续的分类、诊断、治疗提供剂量学数据,是核医学救援的首要任务。在常见射线剂量测量中,中子剂量难于测量,是核与辐射医学应急救援研究的热点和难点。本文旨在建立一套能够快速准确测量人体受照中子剂量的技术方法,并开发相应的标准测量装置。
方法测量人体血液中的元素23Na被热中子活化生成的放射性同位素24Na衰变时的γ光子数,使用比活度——中子剂量的转换系数估算人体受照剂量,提出多个影响剂量估算的因素,对直接使用剂量转换系数获得的剂量进行校正。
结果在模拟实验中,使用NaI探测器对血液样品进行测量,获得了24Na的含有本底的特征峰和去本底的特征峰。通过解谱降低本底中40K能量为1.461MeV的γ峰的干扰,得出采集的3mL血样的绝对活度为14.8Bq。在使用ORNL提供的比活度——剂量转换系数进行计算后,得出其剂量为1.94~2.82Gy。
结论本课题围绕人体受中子照射后,采用测量活化血液的方法来估算人体中子剂量,具体研究内容如下:
1.分析了中子照射后人体剂量估算的技术环节,总结出一套完整的人体剂量估算方法。
2.总结归纳出适用于核医学应急救援条件下的中子剂量标准测量流程。
3.通过对比活度——中子剂量转换系数和影响因素进行分析,总结出主要的影响因素,提出修正的技术方法和思路,对其中的5个影响因素给出了修正值或表格数据。
4.进行了便携式血液中子辐照剂量检测仪研发的模拟实验,检验该测量方法从设计思路到测量技术的可行性。
5.研制出了一套便携式血液中子辐照剂量检测仪。对研发配套的血钠测量仪提出改良意见。一是仪器的屏蔽室对便携性影响太大,二是剂量转换系数的积累还不够,需要针对研发的仪器进行实验,积累与该仪器完全匹配、多条件下的剂量转换数据。
本文规范了中子剂量的测量流程,利用该测量流程可在现场实现快速标准化测量;开发了一套便携式中子剂量测量仪,并对仪器进行了调试实验。
Objective The chief task of medical rescue against nuclear accidents is to determine the exposure radiation dose so as to collect dosimetry data efficiently for the following classification, diagnosis and medical treatment. During the common process of determining the radiation dose, it is difficult to measure the neutron dose, which becomes the hotspot and difficult point of nuclear and radiation medical emergency rescue research. This paper aims to build a set of technical methods which can measure the exposure neutron dose of human body precisely and quickly, as well as to develop a set of measuring device.
Method The isotope of 23Na contained in the human blood will becomes the radioactive isotope 24Na through capturing thermo neutrons. The quantity of gamma photons emitted by the decay of 24Na is measured,then is converted to the activity. A rough estimation of the exposure radiation dose can be estimated by using the specific activity-neutron dose coefficient. A multiple of factors that affect the dose estimation are analysed , and are used to correct the neutron dose.
Results In simulating experiments, by measuring the blood samples with the NaI detector, both the characteristic peak with and without background of 24Na are found. After reducing the interference of theγpeak of 1.461MeV 40K from the background, it is found that the absolute activity of the collected 3mL blood samples is 14.8Bq. After using the effective activity, the dose transfer coefficient, provided by ORNL in the calculation, it founds that the dose is 1.94~2.82Gy.
Conclusion This paper focuses on the method of estimating the neutron dose of human body after exposing to neutron radiation by measuring the activatory blood. The following are the details:
1. It analyzes the technical process of human neutron radiation dose estimation after exposure, summarizing a whole method for human dose estimation.
2. It concludes a standard neutron dose measuring flow for nuclear medical emergency rescue.
3. By analyzing the effective activity-neutron dose transfer coefficient and the influencing factors, the chief effecting factors are found, and the regulating technical method and theory are suggested. Five factors are provided with correcting value or data.
4. Simulating experiments on developing the portable blood neutron radiation dose inspection device is made. And the feasibility of its design principle and measuring technology are verified.
5. A set of portable blood neutron radiation dose measuring device is developed. Two improving advices for the development of blood-contained Na measuring device are pointed out. One is that the shielding room has great influence on the portability of the device, and the other is that the available dose transfer coefficient data is not enough, and more experiments should be done on the development of devices and more related dose transfer data in different situations should be cumulated.
This paper aims to regulate the neutron dose measuring flow, with which a quick standard measurement can be achieved in the site scene of an accident; meanwhile, a set of portable neutron dose measuring devices are developed and related adjustment experiments are made.
方法测量人体血液中的元素23Na被热中子活化生成的放射性同位素24Na衰变时的γ光子数,使用比活度——中子剂量的转换系数估算人体受照剂量,提出多个影响剂量估算的因素,对直接使用剂量转换系数获得的剂量进行校正。
结果在模拟实验中,使用NaI探测器对血液样品进行测量,获得了24Na的含有本底的特征峰和去本底的特征峰。通过解谱降低本底中40K能量为1.461MeV的γ峰的干扰,得出采集的3mL血样的绝对活度为14.8Bq。在使用ORNL提供的比活度——剂量转换系数进行计算后,得出其剂量为1.94~2.82Gy。
结论本课题围绕人体受中子照射后,采用测量活化血液的方法来估算人体中子剂量,具体研究内容如下:
1.分析了中子照射后人体剂量估算的技术环节,总结出一套完整的人体剂量估算方法。
2.总结归纳出适用于核医学应急救援条件下的中子剂量标准测量流程。
3.通过对比活度——中子剂量转换系数和影响因素进行分析,总结出主要的影响因素,提出修正的技术方法和思路,对其中的5个影响因素给出了修正值或表格数据。
4.进行了便携式血液中子辐照剂量检测仪研发的模拟实验,检验该测量方法从设计思路到测量技术的可行性。
5.研制出了一套便携式血液中子辐照剂量检测仪。对研发配套的血钠测量仪提出改良意见。一是仪器的屏蔽室对便携性影响太大,二是剂量转换系数的积累还不够,需要针对研发的仪器进行实验,积累与该仪器完全匹配、多条件下的剂量转换数据。
本文规范了中子剂量的测量流程,利用该测量流程可在现场实现快速标准化测量;开发了一套便携式中子剂量测量仪,并对仪器进行了调试实验。
Objective The chief task of medical rescue against nuclear accidents is to determine the exposure radiation dose so as to collect dosimetry data efficiently for the following classification, diagnosis and medical treatment. During the common process of determining the radiation dose, it is difficult to measure the neutron dose, which becomes the hotspot and difficult point of nuclear and radiation medical emergency rescue research. This paper aims to build a set of technical methods which can measure the exposure neutron dose of human body precisely and quickly, as well as to develop a set of measuring device.
Method The isotope of 23Na contained in the human blood will becomes the radioactive isotope 24Na through capturing thermo neutrons. The quantity of gamma photons emitted by the decay of 24Na is measured,then is converted to the activity. A rough estimation of the exposure radiation dose can be estimated by using the specific activity-neutron dose coefficient. A multiple of factors that affect the dose estimation are analysed , and are used to correct the neutron dose.
Results In simulating experiments, by measuring the blood samples with the NaI detector, both the characteristic peak with and without background of 24Na are found. After reducing the interference of theγpeak of 1.461MeV 40K from the background, it is found that the absolute activity of the collected 3mL blood samples is 14.8Bq. After using the effective activity, the dose transfer coefficient, provided by ORNL in the calculation, it founds that the dose is 1.94~2.82Gy.
Conclusion This paper focuses on the method of estimating the neutron dose of human body after exposing to neutron radiation by measuring the activatory blood. The following are the details:
1. It analyzes the technical process of human neutron radiation dose estimation after exposure, summarizing a whole method for human dose estimation.
2. It concludes a standard neutron dose measuring flow for nuclear medical emergency rescue.
3. By analyzing the effective activity-neutron dose transfer coefficient and the influencing factors, the chief effecting factors are found, and the regulating technical method and theory are suggested. Five factors are provided with correcting value or data.
4. Simulating experiments on developing the portable blood neutron radiation dose inspection device is made. And the feasibility of its design principle and measuring technology are verified.
5. A set of portable blood neutron radiation dose measuring device is developed. Two improving advices for the development of blood-contained Na measuring device are pointed out. One is that the shielding room has great influence on the portability of the device, and the other is that the available dose transfer coefficient data is not enough, and more experiments should be done on the development of devices and more related dose transfer data in different situations should be cumulated.
This paper aims to regulate the neutron dose measuring flow, with which a quick standard measurement can be achieved in the site scene of an accident; meanwhile, a set of portable neutron dose measuring devices are developed and related adjustment experiments are made.
引文
[1]罗素明.测量人体血液中24Na估算中子事故剂量.中华放射医学与防护杂志,1997,117(5):338-340.
[2]吴德昌主编,放射医学,军事医学科学院出版社,2001年9月,北京,124-135页.
[3] P. A. FUQUA, M. D., NORWOOD,M. D., etc. Biologic Effects of Human Radiation Exposure, Journal of Occupational Medicine March 1965, Vol.7, No.3: 93.
[4]石会路.便携式血液中子辐照剂量检测仪的研制[D].四川:成都理工大学,2009.
[5]李焕铁,朱天成,谢云瑞,等.从人体钠活化测量估算中子剂量.中国原子能出版社. [J].1975(01):60-73.
[6] Y.Feng, K.S.Brown, W.H.Casson, etc. Determination of Neutron Dose from Criticality Accidents with Bioassays for Sodium-24 in Blood and Phosphorus-32 in Hair. ORNL TM-12028,1993.
[7]核或放射应急医学响应通用程序-IAEA和WHO共同倡议,106~111.
[8]张术,雷呈祥,储智勇,马丽等,辐射剂量的快速生物学估算,中国辐射卫生,2009年3月:18(1):87.
[9]张文仲.电离辐射粒子在人体组织中能量沉积的微剂量学研究[D].北京:中国人民解放军军事医学科学院,2003.
[10]吴治华.原子核物理实验方法[M].北京:原子能出版社,1997.
[11] DALE.E.Hankins. Dosimetry of criticality accidents using activations of the blood and hair, Health Phys. 1980 (38): 529-541.
[12] IWAI SATOSHI Ph.D, Dose Estimation of Radiological Accident,台日工程技术研讨会,2007年11月:64-67.
[13] R. H. Mole. Sodium in man and the assessment of radiation dose after criticality accidents Phys. Med. Biol., 1984, Vol. 29, No.11: 1307-1327.
[14] W. G. Cross, H. Ing. Sodium Activation in the Human body, Radiation Protection Dosimetry. 1985, 10(1-4):265-276.
[15] Edwards R. Risk of radioactive“dirty bomb”growing, New Scientist online, June 2004.
[16] ABS. American Behavioral Scientist, Vol. 46, No.6, February 2003,822-844.
[17] IAEA. Illicit Trafficking Database (ITDB).
[18]袁汉镕、俞安孙、王连璧等,中子源及其应用,科学出版社,1978年,北京,12-69.
[19]丁厚本、王乃彦,中子源物理,科学出版社,1984年,北京,50-379页.
[20]瞿金辉.数字化中子谱仪有关技术研究[D].四川:成都理工大学,2008.
[21]外照射放射防护中使用的换算系数,国际放射防护委员会第74号出版物.原子能出版社. 1998:67-96,242-275.
[22] F. Takahashi, A. Endo, and Y. Yamaguchi, etc. Dose assessment from activated sodium within a body in criticality accidents, Radiation Protection Dosimetry, 2003; 106: 197- 206.
[23] Wang Jixian, Chen Rusong, Zhu Hongda, etc.Data of Anatomical Physiological and Metabolic Characteristics for Chinese Reference Man. The First Edition. Beijing: Atomic Energy Press,1998:1-6,177-195.
[24]王东平,吴娜,隋丽华,等.成年比格犬血液生理生化指标的测定.实验动物科学与管理,2005,22(2):12-15.
[25]成毅.手持式多道γ能谱仪的研制[D].四川:成都理工大学,2007.
[1]丸山隆司,饭沼武.事故時における被爆線量の推定.日本医学放射学会杂志.第26卷.第11号:139-146.
[2]李焕铁,朱天成,谢云瑞,等.从人体钠活化测量估算中子剂量.中国原子能出版社. [J].1975(01):60-73.
[3] R. H. Mole. Sodium in man and the assessment of radiation dose after criticality accidents Phys. Med. Biol., 1984, Vol. 29, No.11: 1307-1327.
[4] W.G.Cross,H. Ing. SODIUM ACTIVATION IN THE HUMAN BODY, Radiation Protection Dosimetry. 1985, 10(1-4):265-276.
[5] F.Takahashi, A. Endo, and Y. Yamaguchi, etc. Dose assessment from activated sodium within a body in criticality accidents, Radiation Protection Dosimetry, 2003; 106: 197- 206.
[6] T. Ishikawa, Measurement of the radio nuclide 24Na produced by neutron exposure to the body, Journal of Japan Radiological Society of Medicine, 2004, 26 (11):175-178.
[7] Y.Feng, K.S.Brown, W.H.Casson, etc. Determination of Neutron Dose from Criticality Accidents with Bioassays for Sodium-24 in Blood and Phosphorus-32 in Hair. ORNL TM-12028,1993.
[8] Wang Jixian, Chen Rusong, Zhu Hongda, etc.Data of Anatomical Physiological and Metabolic Characteristics for Chinee Reference Man. The First Edition.Beijing:Atomic Energy Press,1998:1-6,177-195.
[9] O’connor B H. Level temperal trends of trace element concentrations in vertebral bone. Achieves of Environmental Health, 1980,35(1):21.
[10] ICRP. Report of the task group on Reference Man. ICRP Publication 23. Oxford: Pergamon Presss, 1975.
[11]罗素明.测量人体血液中估算中子事故剂量.中华放射医学与防护杂志,1997,117(5):338-340.
[12] E. S. da Fonseca , C. L. P. Mauricio. Estimate of the Absorbed Dose Received by Individuals Irradiated with Neutrons, Radiation Protection Dosimetry, 1996, 67(2): 147-149.
[13] DALE.E.Hankins. Dosimetry of criticality accidents using activations of the blood and hair, Health Phys. 1980 (38): 529-541.
[14]外照射放射防护中使用的换算系数,国际放射防护委员会第74号出版物.原子能出版社. 1998:67-96,242-275.
[2]吴德昌主编,放射医学,军事医学科学院出版社,2001年9月,北京,124-135页.
[3] P. A. FUQUA, M. D., NORWOOD,M. D., etc. Biologic Effects of Human Radiation Exposure, Journal of Occupational Medicine March 1965, Vol.7, No.3: 93.
[4]石会路.便携式血液中子辐照剂量检测仪的研制[D].四川:成都理工大学,2009.
[5]李焕铁,朱天成,谢云瑞,等.从人体钠活化测量估算中子剂量.中国原子能出版社. [J].1975(01):60-73.
[6] Y.Feng, K.S.Brown, W.H.Casson, etc. Determination of Neutron Dose from Criticality Accidents with Bioassays for Sodium-24 in Blood and Phosphorus-32 in Hair. ORNL TM-12028,1993.
[7]核或放射应急医学响应通用程序-IAEA和WHO共同倡议,106~111.
[8]张术,雷呈祥,储智勇,马丽等,辐射剂量的快速生物学估算,中国辐射卫生,2009年3月:18(1):87.
[9]张文仲.电离辐射粒子在人体组织中能量沉积的微剂量学研究[D].北京:中国人民解放军军事医学科学院,2003.
[10]吴治华.原子核物理实验方法[M].北京:原子能出版社,1997.
[11] DALE.E.Hankins. Dosimetry of criticality accidents using activations of the blood and hair, Health Phys. 1980 (38): 529-541.
[12] IWAI SATOSHI Ph.D, Dose Estimation of Radiological Accident,台日工程技术研讨会,2007年11月:64-67.
[13] R. H. Mole. Sodium in man and the assessment of radiation dose after criticality accidents Phys. Med. Biol., 1984, Vol. 29, No.11: 1307-1327.
[14] W. G. Cross, H. Ing. Sodium Activation in the Human body, Radiation Protection Dosimetry. 1985, 10(1-4):265-276.
[15] Edwards R. Risk of radioactive“dirty bomb”growing, New Scientist online, June 2004.
[16] ABS. American Behavioral Scientist, Vol. 46, No.6, February 2003,822-844.
[17] IAEA. Illicit Trafficking Database (ITDB).
[18]袁汉镕、俞安孙、王连璧等,中子源及其应用,科学出版社,1978年,北京,12-69.
[19]丁厚本、王乃彦,中子源物理,科学出版社,1984年,北京,50-379页.
[20]瞿金辉.数字化中子谱仪有关技术研究[D].四川:成都理工大学,2008.
[21]外照射放射防护中使用的换算系数,国际放射防护委员会第74号出版物.原子能出版社. 1998:67-96,242-275.
[22] F. Takahashi, A. Endo, and Y. Yamaguchi, etc. Dose assessment from activated sodium within a body in criticality accidents, Radiation Protection Dosimetry, 2003; 106: 197- 206.
[23] Wang Jixian, Chen Rusong, Zhu Hongda, etc.Data of Anatomical Physiological and Metabolic Characteristics for Chinese Reference Man. The First Edition. Beijing: Atomic Energy Press,1998:1-6,177-195.
[24]王东平,吴娜,隋丽华,等.成年比格犬血液生理生化指标的测定.实验动物科学与管理,2005,22(2):12-15.
[25]成毅.手持式多道γ能谱仪的研制[D].四川:成都理工大学,2007.
[1]丸山隆司,饭沼武.事故時における被爆線量の推定.日本医学放射学会杂志.第26卷.第11号:139-146.
[2]李焕铁,朱天成,谢云瑞,等.从人体钠活化测量估算中子剂量.中国原子能出版社. [J].1975(01):60-73.
[3] R. H. Mole. Sodium in man and the assessment of radiation dose after criticality accidents Phys. Med. Biol., 1984, Vol. 29, No.11: 1307-1327.
[4] W.G.Cross,H. Ing. SODIUM ACTIVATION IN THE HUMAN BODY, Radiation Protection Dosimetry. 1985, 10(1-4):265-276.
[5] F.Takahashi, A. Endo, and Y. Yamaguchi, etc. Dose assessment from activated sodium within a body in criticality accidents, Radiation Protection Dosimetry, 2003; 106: 197- 206.
[6] T. Ishikawa, Measurement of the radio nuclide 24Na produced by neutron exposure to the body, Journal of Japan Radiological Society of Medicine, 2004, 26 (11):175-178.
[7] Y.Feng, K.S.Brown, W.H.Casson, etc. Determination of Neutron Dose from Criticality Accidents with Bioassays for Sodium-24 in Blood and Phosphorus-32 in Hair. ORNL TM-12028,1993.
[8] Wang Jixian, Chen Rusong, Zhu Hongda, etc.Data of Anatomical Physiological and Metabolic Characteristics for Chinee Reference Man. The First Edition.Beijing:Atomic Energy Press,1998:1-6,177-195.
[9] O’connor B H. Level temperal trends of trace element concentrations in vertebral bone. Achieves of Environmental Health, 1980,35(1):21.
[10] ICRP. Report of the task group on Reference Man. ICRP Publication 23. Oxford: Pergamon Presss, 1975.
[11]罗素明.测量人体血液中估算中子事故剂量.中华放射医学与防护杂志,1997,117(5):338-340.
[12] E. S. da Fonseca , C. L. P. Mauricio. Estimate of the Absorbed Dose Received by Individuals Irradiated with Neutrons, Radiation Protection Dosimetry, 1996, 67(2): 147-149.
[13] DALE.E.Hankins. Dosimetry of criticality accidents using activations of the blood and hair, Health Phys. 1980 (38): 529-541.
[14]外照射放射防护中使用的换算系数,国际放射防护委员会第74号出版物.原子能出版社. 1998:67-96,242-275.