HPLC法测定葛根提取物片中葛根素含量的不确定度评定

目的建立HPLC法测定葛根提取物片中的葛根素的不确定度评定方法。方法采用HPLC法测定葛根素 含量,分析影响其不确定度的因素来源,量化不确定度分量,最终计算合成不确定度,并得出测量结果的扩展不确定度。结果 葛根素的不确定度评估为±6. 66%。结论本方法可用于HPLC法测定药物含量的不确定度分析,使测定结果更加可靠。     

HPLC法测定板蓝根颗粒中（R,S）-告依春含量的不确定度评定

目的建立HPLC法测定板蓝根颗粒中（R,S）-告依春含量的不确定度评定方法。方法采用HPLC法测定板蓝根颗粒中（R,S）-告依春含量,建立数学模型,分析各因素引起的不确定度,评定各分量不确定度,合成不确定度,并计算测定结果的扩展不确定度。结果扩展不确定度为0.21μg·g^-1,最终报告结果为：HPLC法测定板蓝根颗粒中（R,S）-告依春的含量为（50.17±0.21）μg·g-1。结论本法可用于不确定度评定,建立的HPLC测定板蓝根颗粒中（R,S）-告依春的含量测定方法是合理可行的,可用于板蓝根颗粒的质量控制。     

HPLC法测定人血浆中法罗培南浓度的不确定度

目的对人血浆中法罗培南浓度HPLC法测定的不确定度进行评定。方法对HPLC法测定人血浆中法罗培南浓度全过程进行分析。量化各个测量不确定度分量,合成标准测量不确定度,给出扩展测量不确定度。结果置信概率为95%时,血浆低、中、高法罗培南的扩展不确定度分别为0.01607、0.09807、0.02709μg.ml-1。结论该方法适用于HPLC法测定血浆中法罗培南浓度的不确定度评定,为复杂生物基质分析过程中的不确定度评定提供了重要参考依据。     

HPLC法测定头孢克洛胶囊中头孢克洛含量不确定度评定

目的分析HPLC法测定头孢克洛胶囊中头孢克洛含量的不确定度。方法通过建立数学模型,找出影响不确定度的因素、对各个不确定度分量进行评估计算、并计算合成不确定度,最终给出测量结果的扩展不确定度。结果扩展不确定度为1.6%。结论测量不确定度可用于对头孢克洛胶囊含量测定结果的评定,为测定结果的有效性及方法的优化提供科学依据。     

甘麦宁心胶囊中梓醇含量测定的不确定度分析

 目的 对高效液相色谱法测定梓醇含量的测量不确定度进行分析,以找到影响不确定度的因素,为质量标准的制定提供科学依据。方法 采用高效液相色谱法测定甘麦宁心胶囊中梓醇含量,评估不确定度。结果 标准不确定度为2.70%,含量为(1.17±0.063)mg/g。结论 本试验建立的不确定度评估方法适用于HPLC法测定梓醇含量的不确定度评定。     

2017年全国外照射个人剂量监测能力考核不确定度评定分析

目的 规范全国放射卫生技术服务机构的外照射个人剂量监测不确定度评定工作,提高不确定度评定能力和水平,确保评定质量。方法 开展2017年全国外照射个人剂量能力考核工作,对其考核报告中不确定度评定存在的问题进行分析总结。结果 提交完整考核报告及检定/校准证书机构259家,A类不确定度评定正确率为20.8%,校准、能量响应、角度响应、非线性响应B类不确定度评定正确率分别为55.2%、50.6%、25.5%、51.4%。被测量估计值及其不确定度有效位数表述正确率为34.0%。结论 关于不确定度评定方面检测机构的能力还有待提高,建议加大对检测机构不确定度评定的系统化培训力度,规范考核报告表述,从而提高测量结果报告的水平。     

RP-HPLC法测定阿司匹林肠溶片中阿司匹林含量的不确定度分析

目的对反相高效液相色谱法测定阿司匹林肠溶片中阿司匹林含量的不确定度进行评定。方法用反相高效液相色谱法测定阿斯匹林肠溶片中阿斯匹林含量，用回归方程对测定进行分析并计算测定的不确定度。结果阿司匹林肠溶片的阿司匹林含量测定扩展不确定度为5．94％，相对不确定度为3．96％。结论该评定方法较可靠。     

CR39中子个人剂量监测的不确定度评定

目的 通过对CR39中子个人剂量监测的不确定度评定,定量分析中子个人监测结果的可靠性,提高中子个人剂量监测的质量水平。方法 建立适当数学模型,通过对个人剂量计各个环节因素引入不确定度的计算,评定CR39中子个人剂量监测的扩展不确定度。结果 中子个人监测的A类不确定度主要来自测量值和本底,测量值为A类不确定度的最大分量,为11.68%。引入B类不确定度主要为能量响应为7.85%、剂量线性检验为4.0%、距离响应为1.68%和蚀刻条件为3.0%等。相对扩展不确定度约为32%,k=2。结论 放射性同位素场所不确定度评定中,对于某一较小能量范围的中子（即中子的能量分群）,应采用符合其能量响应特性的中子探测器。     

火器性四肢骨折320例创伤弹道特点

讨论了物理实验教学中引入不确定度的必要性及其评定方法，并在一个实例中分析了实验结果的不确定度表示方法。     

生鲜乳中菌落总数的不确定度测量

【目的】为了准确测定生鲜乳中的菌落总数，采用微生物培养法对生鲜乳中菌落总数计数，建立结果不确定度的数学模型。【方法】根据《测量不确定度的评定与表示》相关规定对实验过程中的不确定度来源、分量进行分析计算，评估结果的不确定度。分别对同批次采样的一份生鲜乳和16份生鲜乳进行菌落总数的测定后，分析二者的结果不确定度。【结果】单一样品重复测量10次计算出的扩展不确定度为0.198 6;16个样品分别重复测量2次计算出的扩展不确定度为0.089 0。【结论】实验中生鲜乳菌落总数的检测结果符合不确定度的评估。     

双热释光元件个人剂量计Hp(10)测量不确定度评定

目的 介绍双热释光元件个人剂量计H_p（10）测量不确定度评定方法。方法 采用GUM法建立测量模型,根据个人剂量计的性能,对个人剂量当量H_p（10）测量不确定度进行评定。结果 当测量结果经非线性响应及能量响应等修正时,H_p（10）的相对扩展不确定度U_rel为28%;当测量结果未进行非线性响应及能量响应等修正时,H_p（10）的相对扩展不确定度U_rel为33%。结论 该方法可对常规监测中的个人剂量当量H_p（10）测量不确定度进行有效评定。     

硼中子俘获治疗(BNCT)设备中子束流质量控制检测项分析

目的通过对医院中子照射器(IHNI)的超热中子束流辐射特性参数和剂量学特性参数的检测, 为建立硼中子俘获治疗(BNCT)设备中子束流的质量控制检测方法提供参考。方法通过对比各项检测结果的不确定度与欧洲联合研究中心(EC-JRC)推荐的偏差值, 分析评估相应检测方法的可行性。结果超热中子注量率的不确定度为2.7%;热中子与超热中子注量率比值的不确定度为3.1%;快中子空气比释动能率与超热中子注量率比值的不确定度为9.3%;γ空气比释动能率与超热中子注量率比值的不确定度为8.7%;中子注量率空间分布的不确定度为2.7%;模体内热中子注量率的不确定度为1.8%;模体内中子和γ射线剂量率的不确定度分别为17.1%和4.0%。结论模体内中子剂量率测量结果不确定度高, 需要进一步研究该项检测方法来提高检测结果的准确度;其余检测项测量结果不确定度低, 检测结果准确度预期能满足欧洲联合研究中心的推荐允许偏差值, 检测方法可行。     

Standardization of 89Sr at the National Office of Measures.

Strontium-89 is an important radiotherapy nuclide in bone palliation. The standardization of 59Sr has been performed at the National Office of Measures (OMH) within the frame of the BIPM CCRI(II)-K2.Sr-89 key comparison. The activity concentration of the 89Sr solution was measured by two different methods. The conventional 4pi beta counting technique was used with two proportional counting measurement systems. The 4pi beta-gamma-coincidence efficiency tracing method was used with a 4pi beta-gamma-coincidence measurement system using 24Na as the tracer radionuclide. The beta efficiencies of each of these counting techniques were nearly 100%. The combined uncertainties of the activity concentration determined by these absolute methods are 0.3%. The general agreement of results between the two methods was 0.5%. The measurement equipment, evaluation methods and results of activity concentration measurements with their uncertainty budgets are reported.     

Importance of covariances for uncertainty estimates in measurement of radionuclide mixtures by multichannel counting.

Multichannel counting is often used when samples containing a mixture of known radionuclides are measured. Solutions to this method have been presented but to our knowledge, none of them took into account the covariances for evaluating the uncertainty of measurement. This paper presents new solutions for estimating uncertainties in measurement of radionuclide mixtures by multichannel counting and shows that covariances may contribute significantly to uncertainty of measurement so that they must be evaluated.     

Uncertainty analysis of in-situ gamma spectrometry measurements of air cleaning filter cartridges and 200 L drums by a HPGe detector

This work deals with most significant sources of uncertainty in determination of radionuclides massic activity in 200 L drums with radioactive waste (RAW) from decommissioning of nuclear power plant (NPP) A1 and operational air cleaning filters coming from different parts of NPP's ventilation system. It turned out that the most significant source of uncertainty is determination of photo peak detection efficiency, in particular measurement geometry. The detection efficiency of HPGe detector has been determined by calculation using ISOCS software (In Situ Object Counting System) and detector characteristics delivered by the manufacturer (LABSOCS). The detector efficiency is influenced by various factors like measurement geometry, deviation from standard geometry, environmental characteristics, sample properties (density, material composition), used collimator etc. Mentioned factors and their contributions to the uncertainty of detection efficiency and thus to the total uncertainty of massic activity determination have been individually evaluated in the paper. The main part of the work consists of evaluation of maximum uncertainty factor due to presence of hypothetical point source in measurement volume for both types of measurement geometry.     

Sensitivity and uncertainty analysis of the simulation of 123I and 54Mn gamma and X-ray emissions in a liquid scintillation vial

Radiation transport simulations of the most probable gamma- and X-ray emissions of ¹²³I and ⁵⁴Mn in a three photomultiplier tube liquid scintillation detector have been carried out. A Geant4 simulation was used to acquire energy deposition spectra and interaction probabilities with the scintillant, as required for absolute activity measurement using the triple to double coincidence ratio (TDCR) method. A sensitivity and uncertainty analysis of the simulation model is presented here. The uncertainty in the Monte Carlo simulation results due to the input parameter uncertainties was found to be more significant than the statistical uncertainty component for a typical number of simulated decay events. The model was most sensitive to changes in the volume of the scintillant. Estimates of the relative uncertainty associated with the simulation outputs due to the combined stochastic and input uncertainties are provided. A Monte Carlo uncertainty analysis of an ¹²³I TDCR measurement indicated that accounting for the simulation uncertainties increases the uncertainty of efficiency of the logical sum of double coincidence by 5.1%.