中子剂量估算方法的研究
|
摘要
本课题研究了中子照射的监测方法、中子辐射的防护方法以及辐射防护和各种实用场合的外照射中子剂量估算方法及核突发事件中应急情况的中子剂量的估算方法,并根据中子剂量的剂量学方法,采用MS Visual Basic 6.0编程语言,开发一个用于辐射防护及实用的外照射中子剂量估算的计算机系统,并建立一个基于VB+MS ACCESS的数据库系统,用于存放和管理中子注量到中子剂量的转换系数。
该中子剂量估算的计算机系统能够对辐射防护不同情况以及实用场合的外照射中子剂量进行估算。它的主要功能有:第一,估算中子器官当量剂量和中子有效剂量等辐射防护量,并能对多种(最多3种)中子同时作用产生的中子器官当量剂量或中子有效剂量作简单算术相加。在五种几何条件下的中子照射:前向(AP)照射、背向(PA)照射、侧向(LAT)照射、旋转(ROT)照射和各向同性(ISO)照射,都能根据中子注量快速给出中子器官当量剂量和中子有效剂量。第二,估算中子个人剂量当量和中子周围剂量当量等外辐射实用量,并能对多种(最多6种)中子同时作用产生的中子个人剂量当量或中于周围剂量当量作简单算术相加。第三,估算中子器官吸收剂量和全身平均吸收剂量,并能对多种(最多3种)中子同时作用产生的中子器官吸收剂量或全身平均吸收剂量作简单算术相加。在五种几何条件下的中子照射:前向(AP)照射、背向(PA)照射、侧向(LAT)照射、旋转(ROT)照射和各向同性(ISO)照射,都能根据中子注量快速给出中子器官吸收剂量和全身平均吸收剂量。第四,管理存放中子注量到中子剂量转换系数的数据库,并能查看、添加、修改、删除其中的数据。
本文首先就中子剂量进行了一定研究,总结了当前中子辐射防护常用的中子剂量,并对这几种常用的中子剂量的估算和测量方法进行了详细讨论。然后根据国际辐射防护委员会(ICRP)和国际辐射单位与测量委员会(ICRU)一些出版物中对中子剂量的定义和公式,介绍了几种常用中子剂量的估算算法,并对中子剂量估算系统的设计以及数据库构建的过程进行论述。最后讨论了中子剂量在实践中的几个典型应用,并对中子剂量将来的发展作出了展望。
The method for neutron dose monitoring, neutron dose estimation and neutron radiation protection were studied in this paper. The neutron dose estimation contains that in radiation accident, medical exposure and occupational exposure. Based on the method of neutron dosimetry and by means of the programming language of MS Visual Basic 6.0, a computer program of neutron dose estimation in external radiation was developed for radiation protection and operation. Meanwhile, a database based on MS Visual Basic 6.0 and MS ACCESS is established and the fluence to dose conversion coefficients are stored in the database.
The computer program of neutron dose estimation can be used for external radiation protection and operation. It has four main functions. First, it can be used for neutron organ equivalent dose and neutron effective dose estimation. When neutron irradiates in AP mode or PA mode or LAT mode or ROT mode or ISO mode, the computer program can be used for neutron organ equivalent dose and neutron effective dose estimation. Meanwhile it can do simple add operation of neutron dose for three types of neutrons. Second, it can be used for neutron personal dose equivalent and neutron ambient dose equivalent estimation. Meanwhile it can do simple add operation of neutron dose for six types of neutrons. Third, it can be used for neutron organic absorbed dose and whole body average absorbed dose. When neutron irradiates in AP mode or PA mode or LAT mode or ROT mode or ISO mode, neutron organic absorbed dose and whole body average absorbed dose can be estimated. It can also perform simple addition of neutron dose for three types of neutrons. Fourth, the fluence to dose conversion coefficients in the database can be inquired and perfected.
First of all, investigation of neutron dose was introduced in this paper. Then some routine used neutron dose estimation methods will be presented. The main mode and parameters of neutron dose estimation are based on the reports of ICRP and ICRU. Lastly, some typical applied examples about neutron dose estimation were explained in this paper.
该中子剂量估算的计算机系统能够对辐射防护不同情况以及实用场合的外照射中子剂量进行估算。它的主要功能有:第一,估算中子器官当量剂量和中子有效剂量等辐射防护量,并能对多种(最多3种)中子同时作用产生的中子器官当量剂量或中子有效剂量作简单算术相加。在五种几何条件下的中子照射:前向(AP)照射、背向(PA)照射、侧向(LAT)照射、旋转(ROT)照射和各向同性(ISO)照射,都能根据中子注量快速给出中子器官当量剂量和中子有效剂量。第二,估算中子个人剂量当量和中子周围剂量当量等外辐射实用量,并能对多种(最多6种)中子同时作用产生的中子个人剂量当量或中于周围剂量当量作简单算术相加。第三,估算中子器官吸收剂量和全身平均吸收剂量,并能对多种(最多3种)中子同时作用产生的中子器官吸收剂量或全身平均吸收剂量作简单算术相加。在五种几何条件下的中子照射:前向(AP)照射、背向(PA)照射、侧向(LAT)照射、旋转(ROT)照射和各向同性(ISO)照射,都能根据中子注量快速给出中子器官吸收剂量和全身平均吸收剂量。第四,管理存放中子注量到中子剂量转换系数的数据库,并能查看、添加、修改、删除其中的数据。
本文首先就中子剂量进行了一定研究,总结了当前中子辐射防护常用的中子剂量,并对这几种常用的中子剂量的估算和测量方法进行了详细讨论。然后根据国际辐射防护委员会(ICRP)和国际辐射单位与测量委员会(ICRU)一些出版物中对中子剂量的定义和公式,介绍了几种常用中子剂量的估算算法,并对中子剂量估算系统的设计以及数据库构建的过程进行论述。最后讨论了中子剂量在实践中的几个典型应用,并对中子剂量将来的发展作出了展望。
The method for neutron dose monitoring, neutron dose estimation and neutron radiation protection were studied in this paper. The neutron dose estimation contains that in radiation accident, medical exposure and occupational exposure. Based on the method of neutron dosimetry and by means of the programming language of MS Visual Basic 6.0, a computer program of neutron dose estimation in external radiation was developed for radiation protection and operation. Meanwhile, a database based on MS Visual Basic 6.0 and MS ACCESS is established and the fluence to dose conversion coefficients are stored in the database.
The computer program of neutron dose estimation can be used for external radiation protection and operation. It has four main functions. First, it can be used for neutron organ equivalent dose and neutron effective dose estimation. When neutron irradiates in AP mode or PA mode or LAT mode or ROT mode or ISO mode, the computer program can be used for neutron organ equivalent dose and neutron effective dose estimation. Meanwhile it can do simple add operation of neutron dose for three types of neutrons. Second, it can be used for neutron personal dose equivalent and neutron ambient dose equivalent estimation. Meanwhile it can do simple add operation of neutron dose for six types of neutrons. Third, it can be used for neutron organic absorbed dose and whole body average absorbed dose. When neutron irradiates in AP mode or PA mode or LAT mode or ROT mode or ISO mode, neutron organic absorbed dose and whole body average absorbed dose can be estimated. It can also perform simple addition of neutron dose for three types of neutrons. Fourth, the fluence to dose conversion coefficients in the database can be inquired and perfected.
First of all, investigation of neutron dose was introduced in this paper. Then some routine used neutron dose estimation methods will be presented. The main mode and parameters of neutron dose estimation are based on the reports of ICRP and ICRU. Lastly, some typical applied examples about neutron dose estimation were explained in this paper.
引文
[1]张良安.医用辐射新技术应用中的辐射防护问题[J].辐射防护通讯,2005,25(5),1-5.
[2]张良安,王丹,徐志勇.放射外照射事故剂量重建中的蒙特卡罗模拟方法[J].中华放射医学与防护杂志,2004,24(6),565-568.
[3]Food And Agriculture Organization Of The United Nations,international Atomic Energy Agency,International Labour organisation,OECD Nuclear Energy Agency,Pan American health Organization,World Health Organization,International basic Safety Standards For Protection Against Ionizing Radiation And For The Safety Of radiation Sources,Safety Series No.115,IAEA,Vienna(1996).
[4]International Atomic Energy Agency,International Labour office,Occupational Radiation Protection,Safety Standards Series No.Rs-g-1.1,IAEA,Vienna(1999).
[5]International Atomic Energy Agency,International Labour office,Assessment Of Occupational Exposure Due To External Sources Of Radiation,safety Standards Series No.Rs-g-1.3,IAEA,Vienna(1999).
[6]International Atomic Energy Agency,Calibration Of Radiation Protection Monitoring Instruments,Safety Reports Series No.16,IAEA,Vienna(2000).
[7]International Atomic Energy Agency,Neutron Monitoring For Radiation Protection Purposes(proc.Symp.Vienna,1972),2 Vols,IAEA,Vienna(1973).
[8]International Atomic Energy Agency,Neutron Monitoring(proc.Symp.Vienna,1966),IAEA,Vienna(1967).
[9]International Atomic Energy Agency,Compendium Of Neutron Spectra in Criticality Accident Dosimetry,Technical Reports Series No.180,IAEA,Vienna(1978).
[10]International Atomic Energy Agency,Neutron Monitoring For Radiological Protection,Technical Reports Series No.252,IAEA,Vienna(1985).
[11]International Atomic Energy Agency,Guidelines On Calibration Of Neutron Measuring Devices,Technical Reports Series No.285,IAEA,Vienna(1988).
[12]International Atomic Energy Agency,Compendium Of Neutron Spectra and Detector Responses For Radiation Protection Purposes,Technical Reports Series no.318,IAEA,Vienna(1990).
[13]张文艺,张良安.核应急和临床核医学内照射剂量估算计算机培训班简介[J].中华放射医学与防护杂志,2005,25(1),1.
[14]丁大钊,叶春堂,赵志祥.中子物理学[M].北京:原子能出版社,2001,47-106.
[15]GBZ/T16139-1995.用于中子辐射防护的剂量转换系数[S].北京:中国标准出版社,1995:
[16]GBZ/T1 151-2002。放射事故个人外照射剂量估算原则[S].北京:中国标准出版社,2002:
[17]F Wrobel.M Benabdesselam,P Iacconi.Neutron absorbed dose determination by calculations of recoil energy[J].Radiation Protection Dosimetry,2004,110(14),807-811.
[18]International Commission On Radiation Units And Measurements,Determination of Dose Equivalents from External Radiation Sources.Part 2,Rep.43,ICRU,Bethesda,MD(1988).
[19]张贵英,倪邦发,李丽等.个人中子剂量气泡探测器研制[J].原子核物理评论,2005,22(1),100-102.
[20]梁石强,于涛,乔海涛等.BD-PND中子气泡探测器性能的检验[J].辐射防护,2006,26(5),299-304.
[21]李俊雯.固体核径迹探测器在中子辐射监测中的应用[J].核电子学与探测技术,2004,24(1),108-110.
[22]李桃生,赵修良,方栋.单球多位置灵敏计数器的中子能量响应合理性初步探索[J].核电子学与探测技术,2006,26(5),553-556.
[23]李桃生,杨连珍,马吉增.一种新型中子周围剂量当量(率)测量装置的性能实验[J].辐射防护,2005,25(5),283-290.
[24]International Commission On Radiological Protection,International Commission On Radiation Units And Measurements,Conversion Coefficients for Use in Radiological Protection Against External Radiation,Report of the Joint Task Group,ICRP Rep.74,Pergamon Press,Oxford and New York(1996),and ICRU Rep.57,ICRU,Bethesda,MD(1998).
[25]ICRP.Conversion Coeficients for Use in Radidogical Protection against External Radiation.ICRP Publication 74.1996.
[26]美国国家标准局手册75,中子以及中子和γ混合射线的吸收剂量测量[M],华盛顿特区,1961.
[27]王月兴,鲁永杰,杨翊方.单位中子注量照射中国参考人产生的全身平均吸收剂量[J].中国辐射卫生,2006,15(1),3-5.
[28]International Commission On Radiation Units And Measurements,Determination of Dose Equivalents Resulting from External Radiation Sources,Rep.39,ICRU,Bethesda,MD(1985).
[29]王月兴,鲁永杰,杨翊方.用体表24Na γ计数率评价事故中子照射注量与剂 量的实验研究[J].中华航海医学与高气压医学杂志,2004,11(3),141-145.
[30]王月兴,贾福星,马晓琳.核潜艇核事故艇内放射性应急防护和中子剂量快速评价研究[J].中华航海医学与高气压医学杂志,2005,12(4),193-196.
[31]Masuchika Kohno*,Yoshinobu Koizumi.Neutron dose estimates from5-yen coins[J].NATURE,2000,406(17),693.
[32]张文仲,毛用泽.中子弹核爆炸早期核辐射剂量的研究[J].中华放射医学和防护杂志,2001,21(4),247-249.
[33]罗全勇,朱瑞森.硼中子俘获治疗[J].同位素(A),2004,17(3),174-178.
[34]肖刚,王仲奇,张本爱,朱建士.BNCT治疗计划系统综述[J].中国医学物理学杂志,2006,23(1),5-11.
[35]张晓敏,张文仲,骆亿生.硼中子俘获治疗技术的研究现状[J].国外医学·放射医学核医学分册,2004,28(4),188-191.
[36]王鹏,章翔.硼中子俘获治疗中硼的转运方法研究进展[J].国际神经病学神经外科学杂志,2005,32(6),569-572.
[37]于涛,凌球,邱小平等.基于Synder修正模型的硼中子俘获治疗剂量深度分布计算[J].原子能科学技术,2007,41(3),378-381.
[38]邹华伟,贾明轩,吴荣.调强适形放射治疗计划剂量学的验证[J].中华放射医学和防护杂志,2004,24(3),256-258.
[39]陈超敏,唐木涛,周凌宏等.调强放射治疗中剂量计算与射野参数优化研究[J].中华放射医学和防护杂志,2006,26(3),248-250.
[40]周振山,于广辉,乔艳萍.调强放射治疗计划的剂量验证[J].中华放射医学和防护杂志,2005,25(1),69-70.
[41]Howell RM,Ferenci MS,Hertel NE,Fullerton GD.Investigation of secondary neutron dose for 18 MV dynamic MLC IMRT delivery[J].Medical Physics,2005,32(3),786-793.
[42]江启安,周毅德,申文江.质子射线放射治疗研究现状[J].国际肿瘤学杂志,2006,33(7),510-513.
[43]X.Yan,U.Titt,A.M.Koehler.Measurement of neutron dose equivalent to proton therapy patients outside ofthe proton radiation field[J].Nuclear Instruments and Methods in Physics Research,2002,476(A),429-434.
[44]李俊雯.CR-39中子个人剂量计在石油企业中应用的概况与进展[J].中国预防医学杂志,2002,3(3),228-229.
[45]GBZ/T148-2002.用于中子测井的CR39中子剂量计的个人剂量监测方法(S).北京:中国标准出版社,2002:
[46]卢峰,邓大平,朱建国.影响加速器机房内中子剂量的因素分析[J].中国辐射卫生,2005,14(1),40-41.
[47]纪刚,郭勇,骆亿生.核反应堆中子、γ混合辐射场中小鼠受照剂量的研究[J].中华放射医学和防护杂志,2002,22(5),374-376.
[48]赵海歌,郭诚湛.微型中子源核反应堆绝对中子通量密度计算[J].深圳大学学报理工版,2004,21(2),147-150.
[49]ICRP.Conversion Coeficients for Use in Radidogical Protection against External Radiation.ICRP Publication 74.1996.
[50]徐榭,赵自强,石成玉.基于美国可视人项目图像的成年男子解剖模型及其在医学虚拟仿真上的应用[J].中国基础科学杂志,2002,(6),25-20.
[51]王月兴,鲁永杰,杨翊方.单位中子注量照射中国参考人产生的全身平均吸收剂量[J].中国辐射卫生,2006,15(1),3-5.
[52]王继先,陈如松,诸洪达,等.中国参考人解剖生理和代谢数据[M].北京:原子能出版社,1998.14-35.
[2]张良安,王丹,徐志勇.放射外照射事故剂量重建中的蒙特卡罗模拟方法[J].中华放射医学与防护杂志,2004,24(6),565-568.
[3]Food And Agriculture Organization Of The United Nations,international Atomic Energy Agency,International Labour organisation,OECD Nuclear Energy Agency,Pan American health Organization,World Health Organization,International basic Safety Standards For Protection Against Ionizing Radiation And For The Safety Of radiation Sources,Safety Series No.115,IAEA,Vienna(1996).
[4]International Atomic Energy Agency,International Labour office,Occupational Radiation Protection,Safety Standards Series No.Rs-g-1.1,IAEA,Vienna(1999).
[5]International Atomic Energy Agency,International Labour office,Assessment Of Occupational Exposure Due To External Sources Of Radiation,safety Standards Series No.Rs-g-1.3,IAEA,Vienna(1999).
[6]International Atomic Energy Agency,Calibration Of Radiation Protection Monitoring Instruments,Safety Reports Series No.16,IAEA,Vienna(2000).
[7]International Atomic Energy Agency,Neutron Monitoring For Radiation Protection Purposes(proc.Symp.Vienna,1972),2 Vols,IAEA,Vienna(1973).
[8]International Atomic Energy Agency,Neutron Monitoring(proc.Symp.Vienna,1966),IAEA,Vienna(1967).
[9]International Atomic Energy Agency,Compendium Of Neutron Spectra in Criticality Accident Dosimetry,Technical Reports Series No.180,IAEA,Vienna(1978).
[10]International Atomic Energy Agency,Neutron Monitoring For Radiological Protection,Technical Reports Series No.252,IAEA,Vienna(1985).
[11]International Atomic Energy Agency,Guidelines On Calibration Of Neutron Measuring Devices,Technical Reports Series No.285,IAEA,Vienna(1988).
[12]International Atomic Energy Agency,Compendium Of Neutron Spectra and Detector Responses For Radiation Protection Purposes,Technical Reports Series no.318,IAEA,Vienna(1990).
[13]张文艺,张良安.核应急和临床核医学内照射剂量估算计算机培训班简介[J].中华放射医学与防护杂志,2005,25(1),1.
[14]丁大钊,叶春堂,赵志祥.中子物理学[M].北京:原子能出版社,2001,47-106.
[15]GBZ/T16139-1995.用于中子辐射防护的剂量转换系数[S].北京:中国标准出版社,1995:
[16]GBZ/T1 151-2002。放射事故个人外照射剂量估算原则[S].北京:中国标准出版社,2002:
[17]F Wrobel.M Benabdesselam,P Iacconi.Neutron absorbed dose determination by calculations of recoil energy[J].Radiation Protection Dosimetry,2004,110(14),807-811.
[18]International Commission On Radiation Units And Measurements,Determination of Dose Equivalents from External Radiation Sources.Part 2,Rep.43,ICRU,Bethesda,MD(1988).
[19]张贵英,倪邦发,李丽等.个人中子剂量气泡探测器研制[J].原子核物理评论,2005,22(1),100-102.
[20]梁石强,于涛,乔海涛等.BD-PND中子气泡探测器性能的检验[J].辐射防护,2006,26(5),299-304.
[21]李俊雯.固体核径迹探测器在中子辐射监测中的应用[J].核电子学与探测技术,2004,24(1),108-110.
[22]李桃生,赵修良,方栋.单球多位置灵敏计数器的中子能量响应合理性初步探索[J].核电子学与探测技术,2006,26(5),553-556.
[23]李桃生,杨连珍,马吉增.一种新型中子周围剂量当量(率)测量装置的性能实验[J].辐射防护,2005,25(5),283-290.
[24]International Commission On Radiological Protection,International Commission On Radiation Units And Measurements,Conversion Coefficients for Use in Radiological Protection Against External Radiation,Report of the Joint Task Group,ICRP Rep.74,Pergamon Press,Oxford and New York(1996),and ICRU Rep.57,ICRU,Bethesda,MD(1998).
[25]ICRP.Conversion Coeficients for Use in Radidogical Protection against External Radiation.ICRP Publication 74.1996.
[26]美国国家标准局手册75,中子以及中子和γ混合射线的吸收剂量测量[M],华盛顿特区,1961.
[27]王月兴,鲁永杰,杨翊方.单位中子注量照射中国参考人产生的全身平均吸收剂量[J].中国辐射卫生,2006,15(1),3-5.
[28]International Commission On Radiation Units And Measurements,Determination of Dose Equivalents Resulting from External Radiation Sources,Rep.39,ICRU,Bethesda,MD(1985).
[29]王月兴,鲁永杰,杨翊方.用体表24Na γ计数率评价事故中子照射注量与剂 量的实验研究[J].中华航海医学与高气压医学杂志,2004,11(3),141-145.
[30]王月兴,贾福星,马晓琳.核潜艇核事故艇内放射性应急防护和中子剂量快速评价研究[J].中华航海医学与高气压医学杂志,2005,12(4),193-196.
[31]Masuchika Kohno*,Yoshinobu Koizumi.Neutron dose estimates from5-yen coins[J].NATURE,2000,406(17),693.
[32]张文仲,毛用泽.中子弹核爆炸早期核辐射剂量的研究[J].中华放射医学和防护杂志,2001,21(4),247-249.
[33]罗全勇,朱瑞森.硼中子俘获治疗[J].同位素(A),2004,17(3),174-178.
[34]肖刚,王仲奇,张本爱,朱建士.BNCT治疗计划系统综述[J].中国医学物理学杂志,2006,23(1),5-11.
[35]张晓敏,张文仲,骆亿生.硼中子俘获治疗技术的研究现状[J].国外医学·放射医学核医学分册,2004,28(4),188-191.
[36]王鹏,章翔.硼中子俘获治疗中硼的转运方法研究进展[J].国际神经病学神经外科学杂志,2005,32(6),569-572.
[37]于涛,凌球,邱小平等.基于Synder修正模型的硼中子俘获治疗剂量深度分布计算[J].原子能科学技术,2007,41(3),378-381.
[38]邹华伟,贾明轩,吴荣.调强适形放射治疗计划剂量学的验证[J].中华放射医学和防护杂志,2004,24(3),256-258.
[39]陈超敏,唐木涛,周凌宏等.调强放射治疗中剂量计算与射野参数优化研究[J].中华放射医学和防护杂志,2006,26(3),248-250.
[40]周振山,于广辉,乔艳萍.调强放射治疗计划的剂量验证[J].中华放射医学和防护杂志,2005,25(1),69-70.
[41]Howell RM,Ferenci MS,Hertel NE,Fullerton GD.Investigation of secondary neutron dose for 18 MV dynamic MLC IMRT delivery[J].Medical Physics,2005,32(3),786-793.
[42]江启安,周毅德,申文江.质子射线放射治疗研究现状[J].国际肿瘤学杂志,2006,33(7),510-513.
[43]X.Yan,U.Titt,A.M.Koehler.Measurement of neutron dose equivalent to proton therapy patients outside ofthe proton radiation field[J].Nuclear Instruments and Methods in Physics Research,2002,476(A),429-434.
[44]李俊雯.CR-39中子个人剂量计在石油企业中应用的概况与进展[J].中国预防医学杂志,2002,3(3),228-229.
[45]GBZ/T148-2002.用于中子测井的CR39中子剂量计的个人剂量监测方法(S).北京:中国标准出版社,2002:
[46]卢峰,邓大平,朱建国.影响加速器机房内中子剂量的因素分析[J].中国辐射卫生,2005,14(1),40-41.
[47]纪刚,郭勇,骆亿生.核反应堆中子、γ混合辐射场中小鼠受照剂量的研究[J].中华放射医学和防护杂志,2002,22(5),374-376.
[48]赵海歌,郭诚湛.微型中子源核反应堆绝对中子通量密度计算[J].深圳大学学报理工版,2004,21(2),147-150.
[49]ICRP.Conversion Coeficients for Use in Radidogical Protection against External Radiation.ICRP Publication 74.1996.
[50]徐榭,赵自强,石成玉.基于美国可视人项目图像的成年男子解剖模型及其在医学虚拟仿真上的应用[J].中国基础科学杂志,2002,(6),25-20.
[51]王月兴,鲁永杰,杨翊方.单位中子注量照射中国参考人产生的全身平均吸收剂量[J].中国辐射卫生,2006,15(1),3-5.
[52]王继先,陈如松,诸洪达,等.中国参考人解剖生理和代谢数据[M].北京:原子能出版社,1998.14-35.