低空气比释动能率系列过滤X射线辐射质的测量与研究

以ISO 4037中推荐的低空气比释动能率系列过滤X射线参考辐射为研究对象,设计合理的半值层测量实验,测量获取第一半值层的值;对建立的辐射质,利用碲锌镉能谱仪测量其过滤X射线能谱,将测量得到的脉冲高度谱经过数据处理和转换,计算出平均能量;根据X射线在材料铝和铜中的衰减规律,拟合单能X射线衰减曲线,计算出该系列过滤X射线的有效能量。测量和计算结果与推荐值进行了比较,两者符合较好。与ISO的半值层数值进行对比,偏差均小于5.0%。     

高剂量率^(192)Irγ射线参考辐射场的搭建北大核心CSCD

为完成高剂量率^(192)Ir放射源参考空气比释动能率的绝对测量工作,设计了专用的辐照器及定位装置,利用医用高剂量率近距离治疗机搭建了准直的参考辐射场。参考ISO 4037等相关标准,对参考辐射场的散射、辐射野、半值层、有效能量等相关参数进行了测量和研究。结果显示,在辐射场多个位置,环境散射份额小于主射束的0.003%;在距离放射源1.4 m的位置,辐射野直径为98 mm,尺寸大于基准石墨空腔电离室;半值层测量结果为8.224 mm(Cu),有效能量为402.8 keV,利用HPGe探测器测量的^(192)Ir能谱与模拟谱契合度良好。各项参数均满足了^(192)Ir近距离治疗源参考空气比释动能率的量值复现要求,为其绝对测量与国际比对工作打下基础。     

10~70 kV低空气比释动能率X射线参考辐射质的建立与能谱的模拟北大核心CSCD

为解决环境水平剂量仪表在低能X射线段量值溯源工作,参考国际规范文件ISO4037-1建立了六个低空气比释动能率X射线辐射质,实验获得辐射质的半值层、能谱、平均能量、有效能量。将实验结果与ISO4037和德国联邦物理技术研究院的数据进行比较,建立的参考辐射场满足标准规范要求。研究工作为环境水平X射线的国际比对和环境监测仪表的量传递奠定了基础。     

重过滤窄谱X射线辐射质的研究与建立

为推进X射线空气比释动能量值传递的工作,实验室建立中能X射线参考辐射装置。通过实验测量和插值计算,建立符合ISO4037-1标准的X射线辐射质,建立的辐射质与ISO4037国际标准的相对偏差在5%以内,满足ISO4037-1的要求。     

X射线散射光子对剂量当量电离室影响

为了测量X射线辐射散射光子对剂量当量电离室的影响,根据ISO-4037建立X射线防护水平参考辐射场.采用PTW-32002 1L和PTW-32003 10L两个不同体积的球形空腔电离室在不同辐射质条件下通过影锥屏蔽法测量散射光子对不同电离室的影响程度.实验结果表明:散射光子对不同体积电离室影响程度不同,对于10 L球形电离室散射份额在2％左右,而对于1L球形电离室散射份额在4％左右.能量越高,散射光子的散射份额也会相对增大.     

低本底环境低能X射线参考辐射场的研究

在平均γ射线剂量率为9.9 nSv/h的环境下进行10 ～50 keV低能X射线参考辐射场研究.利用电离室RC6M测量辐射野的均匀性,使用9种材料的K荧光刻度碲化镉探测器,测量了微型X光机能谱,并计算了空气比释动能率.结果显示:在距X射线出口55 cm处水平方向均匀性好于95％辐射野尺寸约为14 cm,竖直方向辐射野尺寸为16 cm,按窄谱系列附加过滤后能谱与ISO4037中标准模拟谱基本吻合.     

防护水平X射线电离室的校准及不确定度分析

防护水平电离室剂量计是辐射防护的主要计量器具,需要在窄谱参考辐射质下进行检定和校准。利用EGSnrc软件模拟了参考辐射质X射线能谱,分析得到的能谱分辨率和平均能量与ISO 4037-1推荐值的最大偏差分别为7.1％和1.04％,均满足规范要求。依托60~250kV X射线空气比释动能国家基准装置,在窄谱系列参考辐射质下完成了距离X光机1m处参考点的空气比释动能量值复现;然后通过替代法对两个传递电离室进行校准并完成量值传递;最后利用传递电离室复现的2.25m处的空气比释动能率对PTW-32002球形电离室进行校准,获得相应的校准因子,校准因子相对扩展不确定度为2.2%(k=2)。     

钨靶光管钼过滤X射线空气比释动能的量值复现北大核心CSCD

基于低能钨靶X射线光机,配置钼过滤材料参考建立了管电压为23kV、25kV、28kV、30kV、35kV的辐射质,其附加过滤均为0.06mm的钼片。测量了5个辐射质的半值层,结果显示,半值层值在0.346mmAl到0.405mmAl之间。有效能量在15.4~16.4keV之间,明显高于相同管电压激发钼靶光管产生的X射线辐射质。对乳腺X射线自由空气电离室进行了各个修正因子的测量,完成了空气比释动能的测量工作。     

激光损伤的光散射法判别研究

在激光损伤测量系统中,利用光散射法判别激光薄膜损伤,需要寻求光源和探测器之间的最佳位置。为此,在不同损伤激光脉冲能量、不同测量入射角度(0°,30°,45°,60°)和不同探测器距离(200,250 mm)条件下,研究了损伤点散射光能量的角分布。获得结果如下:在相同的探测角度上,散射光能量随着损伤面积和测试光入射角度增加而增加。在探测角度小于反射角度时,随着探测角度增加散射光能量逐渐变强;当探测角度大于反射角度后,随着散射角度增加散射光能量逐渐变弱。散射光相对能量在反射光方向附近出现极大值;在60°入射时,散射光相对能量具有最大值;探测距离在200 mm时,最大散射光相对能量大于探测距离在250 mm时。根据以上结论,可以确定在利用光散射判别损伤的测量系统中,探测器应放置在反射光方向的两侧,并且尽量增加测试光入射角度和缩小探测器与样片间距离。     

X射线铅当量测量辐射质的建立和能谱模拟

医用诊断X射线防护器具的防护性能通常用铅当量表示,根据IEC 61331-1,防护材料衰减性能的测定主要是在40～150kV X射线范围内,研究纯铅、含铅和无铅材料在窄束、宽束以及逆向宽束条件下铅当量的大小。为进一步研究不同测量方法下防护材料的屏蔽性能,需要建立符合标准要求的X射线参考辐射质,并对其能谱进行模拟或测量。依托工业X射线光机,通过添加铝附加过滤和不同厚度铝吸收片,建立了40～150kV范围内8个X射线参考辐射质,测量半值层最大相对偏差为2.8%。利用EGSnrc蒙卡模拟程序,模拟了不同辐射质的X射线能谱,其平均能量与IEC推荐值的最大相对偏差不超过0.4%,满足防护材料X射线铅当量辐射质的要求。     

窄X射线束屏蔽材料铅当量测量研究

辐射防护材料屏蔽性能常用铅当量表示,为了准确衡量不同防护材料的屏蔽能力,根据IEC 61331标准,研究建立了用于铅当量测量的X射线辐射质.利用EGSnrc软件对辐射质能谱进行了模拟,研究了不同厚度的铅对辐射质能谱的影响以及窄射线束X射线铅当量测量方法,并在窄射线束条件下对16种不同防护材料进行了铅当量测量.结果表明建...     

Determination of conversion factors from air kerma to operational dose equivalent quantities for low-energy X-ray spectra

The conversion coefficients from air kerma to ICRU operational dose equivalent quantities for STUK's realisation of the X-radiation qualities N-15 to N-60 of the ISO narrow (N) spectrum series were determined by utilising X-ray spectrum measurements. The pulse-height spectra were measured using a planar high-purity germanium spectrometer and unfolded to fluence spectra using Monte Carlo generated data of the spectrometer response. To verify the measuring and unfolding method, the first and second half-value layers and the air kerma rate were calculated from the fluence spectra and compared with the values measured using an ionisation chamber. For each radiation quality, the spectrum was characterised by the parameters given in ISO 4037-1. The conversion coefficients from the air kerma to the ICRU operational quantities H(p)(10), H(p)(0.07), H'(0.07) and H(*)(10) were calculated using monoenergetic conversion coefficients at zero angle of incidence. The results are discussed with respect to ISO 4037-4, and compared with published results for low-energy X-ray spectra.     

Consideration on calibration and correction factors of an Hp10 chamber for different radiation qualities and angles of incidence

This paper presents the characterisation performed at IRSN (France) of an H(p)(10) chamber in terms of calibration coefficient and correction factors for the radiation qualities of ISO narrow spectrum series. The chamber response, expressed in H(p)(10) using conversion coefficients h(p)(K)(10; N, alpha) listed in ISO 4037-3 in the energy range from 30 to 1250 keV and for angles of incidence between 0 and 70 degrees, was found to be within approximately 10%. However, for photon energies <30 keV, an overresponse of the chamber that could reach 100% was observed. Nevertheless, this overresponse was reduced to 25% using the conversion coefficients estimated at Physikalisch-Technische Bundesanstalt (PTB). This implies that the X-ray spectra produced by the IRSN X-ray units are very similar to those produced by PTB, both containing a little bit more high-energy photons than the spectra used in ISO 4037-3. The dose rate dependence of the chamber tested by gamma radiation from (60)Co sources was found to be within 2% in the range of 0.3 mSv h(-1) to 1 Sv h(-1). The H(p)(10) chamber can measure directly the conventional true value of H(p)(10) after calibration by a reference laboratory, and can be used for transferring H(p)(10) reference quantities from a reference laboratory.     

甲醛氨测定仪校准方法研究

摘要：甲醛氨测定仪可以用于空气或水中的甲醛含量和氨含量测定,所以对甲醛氨测定仪校准方法就显得格外重要,文章着重介绍了甲醛氨测定仪的测校准方法的研究。     

Energy response of different types of RADOS personal dosemeters with MTS-N (LiF:Mg,Ti) and MCP-N (LiF:Mg,Cu,P) TL detectors

The photon energy response of different RADOS (Mirion Technologies) personal dosemeters with MTS-N (LiF:Mg,Ti) and MCP-N (LiF:Mg,Cu,P) thermoluminescence (TL) detectors was investigated. Three types of badges were applied. The irradiation with reference photon radiation qualities N (the narrow spectrum series), and S-Cs and S-Co nuclide radiation qualities, specified in ISO 4037 [International Organization for Standardization (ISO). X and gamma reference radiations for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy. ISO 4037. Part 1-4 (1999)], in the energy range of 16-1250 keV, were performed at the Dosimetry Laboratory Seibersdorf. The results demonstrated that a readout of a single MTS-N or MCP-N detector under the Al filter can be used to determine Hp(10) according to requirements of IEC 61066 [International Electrotechnical Commission (IEC). Thermoluminescence dosimetry systems for personal and environmental monitoring. International Standard IEC 61066 (2006)] for TL systems for personal dosimetry. The new RADOS badge with the experimental type of a holder (i.e. Cu/Al filters) is a very good tool for identifying the radiation quality (photon energy).