PMMA、SAN改性PVC/CPE共混体的研究

研究了刚性聚合物(PMMA、SAN)对PVC/CPE共混体力学性能、冲击断面形貌及流变性的影响。结果表明,PMMA对PVC/CPE=100/10、100/15体系,SAN对PVC/CPE=100/10体系都具有显著的增韧作用和一定的增强作用;初步的测定显示,刚性聚合物能改善共混熔体的流变性,促进PVC/CPE共混体系中CPE网络结构的形成和分散性。     

PCE/POM/EVA共混体系高强高韧化的研究

对PCE/POM、PCE/EVA、PCE/POM/EVA三种共混体系的物理机械性能进行了研究和对比。通过分析表明,EVA对PCE/POM共混体系有增容作用,POM对PCE/EVA共混体系有增强作用,从而开发出一种强韧的聚氯醚合金。      

聚乙烯/EVA共混体系相分离行为的动态流变研究

通过动态流变手段研究了HDPE/EVA和LDPE/EVA两种共混体系的相分离行为,比较了聚乙烯分子结构对共混物相容性的影响。结果表明:对于HDPE/EVA体系,当HDPE质量含量为25%时产生相分离;而LDPE/EVA体系所有组成均未呈现明显相分离。     

MWNTs/PVC复合材料的性能与结构

选用聚团状多壁碳纳米管(MWNTs)及氯化聚乙烯(CPE)、乙烯-醋酸乙烯共聚物(EVA)等改性剂对聚氯乙烯(PVC)进行抗静电及增韧研究,测试及分析了PVC共混体系的电性能、耐热性能及聚团状多壁碳纳米管在不同复合体系中的分散。结果表明,添加一定量的MWNTs能明显提高材料的抗静电性能。加入MWNTs后,复合体系的热稳定性有所提高,在不同体系中由于相结构的不同,效果差别很大。MWNTs/CPE/PVC体系具有较高的抗静电效果及综合性能。     

纳米CaCO_3对CPE/ACR共混增韧PVC力学性能的影响

研究了纳米碳酸钙(CaCO_3)对氯化聚乙烯(CPE)/丙烯酸树脂(ACR)/聚氯乙烯(PVC)共混体系力学性能的影响,并通过动态机械热分析(DMA)和扫描电子显微镜(SEM)对共混体系的力学松弛行为、纳米CaCO_3在CPE/ACR/PVC共混体系中的分散状态及共混体系的断面形貌特征进行了表征。结果表明,纳米CaCO_3能够显著提高CPE/ACR/PVC共混体系的冲击性能,而不降低共混体系的强度。加入纳米CaCO_3后,共混体系的低温损耗(tanδ)峰强度显著增大,并且与冲击强度的变化具有很好的对应性。SEM观察发现,8 phr纳米CaCO_3可在CPE/ACR/PVC基体中形成纳米尺度的均匀分散,加入过多纳米CaCO_3则会出现明显的团聚。     

CPE对PVC／PP体系流变性能的影响

利用Instron毛细管流变仪对PVC/PP及PVC/PP/CPE共混体系的流变性能进行了细致的考察。结果发现,增容剂CPE对PVC/PP体系的流变性能起着双重作用。一方面,在PVC/PP共混物为“海-岛”结构时,CPE起着作为橡胶的增粘效应;另一方面,在PVC/PP共混物为“互锁”结构时,CPE的润滑增塑效应使得它起着降低“互锁”共混物熔体粘度、提高成型加工性能的作用。     

原位增容HDPE/PET共混体系结构与性能的研究

采用DSC、WAXD、SEM及TGA研究了HDPE/PET共混体系在增容剂EVA及EAA作用下的结晶性,断口的形态结构及热稳定性.结果表明,EVA及EAA的加入使HDPE/PET体系中HDPE组分的熔融热焓降低,结晶度下降,但熔融峰位置和晶胞结构基本保持不变;从扫描电镜照片可以观察到EVA及EAA对共混体系具有一定的增容作用,且EAA的效果优于EVA;共混体系的热稳定性随EVA及EAA的加入有所下降,而EAA的下降幅度则远远小于EVA.     

反气相色谱法研究聚合物共混体系相分离的探讨-Ⅰ

本工作以两种氯含量十分相近的氯化聚乙烯(CPE)的共混体系为对象,对以反气相色谱法(IGC)研究聚合物共混体系相分离进行了探讨。实验结果表明,在升温过程中CPE/CPE共混体系的保留图上出现两个拐折点;第一个拐折点应为共混体系相分离的开始。同时还注意到,探针的保留峰形及峰高随温度或时间有一系列特殊的变化。这些变化应与共混体系的相分离过程有关,其本质有待进一步研究。可以认为IGC是研究聚合物共混体系相分离过程的灵敏方法之一。     

聚乳酸/EVA共混材料力学性能研究

研究了PLA/EVA及PLA/EVA/PE-PA-GMA共混体系的力学性能,结果表明,EVA14-2对PLA有一定的增韧作用,PE-PA-GMA使PLA/EVA/PE-PA-GMA体系的韧性有较明显提高,对80/20的PLA/EVA体系来说,加入5份PE-PA-GMA效果最好.     

PP/EVA共混体系的动态流变行为研究

采用动态流变方法研究不同配比下PP/EVA共混体系的相分离行为。研究发现,EVA与PP相容性较差,当EVA含量超过20%时,体系发生相分离;当EVA含量超过50%时,就会产生相反转。本研究采用Cole-Cole曲线、Han曲线、Van Gurp曲线以及TTS迭加等方法对PP/EVA共混体系相行为进行表征。     

Effect of gamma radiation on optical and electrical properties of tellurium dioxide thin films

Gamma radiation induced changes in the optical and electrical properties of tellurium dioxide (TeO₂) thin films, prepared by thermal evaporation, have been studied in detail. The optical characterization of the as-deposited thin films and that of the thin films exposed to various levels of gamma radiation dose clearly show that the optical bandgap decreases with increase in the gamma radiation dose up to a certain dose. At gamma radiation doses above this value, however, the optical bandgap has been found to increase. On the other hand, the current vs voltage plots for the as-deposited thin films and those for the thin films exposed to various levels of gamma radiation dose show that the current increases with the gamma radiation dose up to a certain dose and that the value of this particular dose depends upon the thickness of the film. The current has, however, been found to decrease with further increase in gamma radiation dose. The observed changes in both the optical and electrical properties indicate that TeO₂ thin films can be used as the real time gamma radiation dosimeter up to a certain dose, a quantity that depends upon the thickness of the film.     

辐射剂量对环氧树脂电子束固化行为的影响

分析了电子束剂量对环氧树脂体系辐射固化行为的影响规律。研究结果表明，电子束辐射过程中，温度由树脂辐射体系表面向内部逐渐降低，随着辐射剂量提高，树脂体系温度上升，辐射表面与内部的温度梯度加大，高辐射剂量下的温度变化缓慢。树脂辐射固化层厚度以及在相同厚度的固化程度均随辐射剂量增加，但增幅逐渐变小，树脂辐射固化度沿固化深度会加速下降。     

Occupational exposure to staff during endoscopic retrograde cholangiopancreatography in Sudan

Endoscopic retrograde cholangiopancreatography (ERCP) procedure is an invasive technique that requires fluoroscopic and radiographic exposure. The purpose of this study was to determine the occupational dose of ionising radiation at three gastroenterology departments (Fedial, Soba and Ibn seena hospitals) in Khartoum, Sudan. The radiation dose was measured during 55 therapeutic ERCP procedures. Thermoluminescence dosemeters were used. The mean radiation dose for the first operator was 0.27 mGy for the eye lens, 0.21 for the thyroid, 0.32 for the chest, 0.17 for the hand and 0.22 for the leg. The mean radiation dose for the second operator was 0.21 mGy for the hand and 0.20 mGy for the chest, while the mean radiation dose for the nurse was 0.44 mGy for the hand and 0.19 for the chest. The radiation dose received by the staff in these hospitals was found to be higher than most of the values in the literature. The radiation absorbed dose received by the different organs is relatively low. Additional studies need to be conducted for radiation dose optimisation.     

含有不同光敏剂的m-LLDPE薄膜的辐照交联

将加入不同光敏剂硬脂酸铁(FeSt)、硬脂酸钴(CoSt)和二乙基二硫代氨基甲酸铁(FeDEC)的茂金属线性低密度聚乙烯(m-LLDPE)分别吹塑成膜,研究了含有不同光敏剂的m-LLDPE薄膜在60Co-γ射线辐照的条件下,辐照剂量及剂量率等因素对交联度的影响。结果表明,m-LLDPE薄膜的交联度随着辐照剂量的增加而增加。光敏化剂CoSt对m-LLDPE薄膜的凝胶化作用比FeSt和FeDEC效果好,含有CoSt0.3%的m-LLDPE的凝胶含量最高。越靠近辐照源则辐射剂量率越高,交联度随着辐照剂量的增加而较快地增加。     

Analysis of radiation workers' dose records in the Korean National Dose Registry

Data are presented on the externally received personal dose equivalent for radiation workers who used the Korea Radioisotope Association's personal monitoring and dose record keeping service since 1984, and provide initial statistics on Korean workers who have been exposed to ionising radiation in different occupations. The total number of workers registered during the period of 1984 to 1999 was 64,518. The number increased steadily and the accumulated dose also increased. The proportion of radiation workers by occupation was 38.4% for nuclear power plants, 20.3% for industrial organisations and 12.4% for non-destructive industry. The annual collective dose of radiation workers was 31.72 man.Sv in 1999. The mean annual dose by sex was 1.49 mSv for males and 0.56 mSv for females and the mean annual dose for a worker was 1.41 mSv with the highest mean dose being received by non-destructive industry (3.53 mSv). Very few workers (0.8%) received more than 20 mSv (2 rem) and only one more than 50 mSv, the legal limit for an annual dose increase. There has been a steady decline in the mean dose since 1984, showing a significant decrease in dose with time (p<0.001). The data showed that radiation protection in Korea was improving, though annual doses were still higher than other countries.     

Dose quantities in radiation protection and their limitations

For more than 50 years the quantity absorbed dose has been the basic physical quantity in the medical applications of ionising radiation as well as radiological protection against harm from ionising radiation. In radiotherapy relatively high doses are applied (to a part of the human body) within a short period and the absorbed dose is mainly correlated with deterministic effects such as cell killing and tissue damage. In contrast, in radiological protection one is dealing with low doses and low dose rates and long-term stochastic effects in tissue such as cancer induction. The dose quantity (absorbed dose) is considered to be correlated with the probability of cancer incidence and thus risk induced by exposure. ICRP has developed specific dosimetric quantities for radiological protection that allow the extent of exposure to ionising radiation from whole and partial body external radiation as well as from intakes of radionuclides to be taken into account by one quantity. Moreover, radiological protection quantities are designed to provide a correlation with risk of radiation induced cancer. In addition, operational dose quantities have been defined for use in measurements of external radiation exposure and practical applications. The paper describes the concept and considerations underlying the actual system of dose quantities, and discusses the advantage as well as the limitations of applicability of such a system. For example, absorbed dose is a non-stochastic quantity defined at any point in matter. All dose quantities in use are based on an averaging procedure. Stochastic effects and microscopic biological and energy deposition structures are not considered in the definition. Absorbed dose is correlated to the initial very short phase of the radiation interaction with tissue while the radiation induced biological reactions of the tissue may last for minutes or hours or even longer. There are many parameters other than absorbed dose that influence the process of cancer induction, which may influence the consideration of cells and/or tissues at risk which are most important for radiological protection.     

Biological weighting of absorbed dose in radiation therapy

Absorbed dose is a quantity which is scientifically rigorously defined and used to quantify the exposure of biological objects, including humans, to ionising radiation. There is, however, no unique relationship between absorbed dose and induced biological effects. The effects induced by a given absorbed dose to a given biological object depend also on radiation quality and temporal distribution of the irradiation. In radiation therapy, empirical approaches are still used today to account for these dependencies in practice. In hadron therapy (neutrons, protons, ions), radiation quality is accounted for with a diversity of (almost hospital specific) methods. The necessity to account for temporal aspects is well known in external beam therapy and in high dose rate brachytherapy. The paper reviews the approaches for weighting the absorbed dose in radiation therapy, and focusses on the clinical aspects of these approaches, in particular the accuracy requirements.     

电子束固化环氧树脂的物理过程及固化厚度的分析

对环氧树脂电子束辐射固化的物理过程进行了分析,研究了辐射剂量、引发剂用量、树脂分子量及其分布,以及化学结构对固化厚度的影响。研究结果显示,环氧树脂体系在电子束辐射后形成围绕入射中心均匀扩展的固化区域,随着辐射剂量的提高,树脂辐射固化厚度的增加幅度变小。引发剂用量增加,辐射固化厚度呈现一种先上升后下降的趋势。提高辐射剂量,树脂分子量对固化厚度的影响减小,固化厚度的增加幅度与树脂的分子量分散性成反比。对于分子量相近而结构不同的环氧树脂,酚醛型环氧树脂在低辐射剂量下的固化区域较大,双酚A型环氧树脂的固化厚度随辐射剂量提高有较大幅度增加,脂环族环氧树脂的固化区域相对较小。     

Review of reconstruction of radiation incident air kerma by measurement of absorbed dose in tooth enamel with EPR

Electron paramagnetic resonance dosimetry with tooth enamel has been proved to be a reliable method to determine retrospectively exposures from photon fields with minimal detectable doses of 100 mGy or lower, which is lower than achievable with cytogenetic dose reconstruction methods. For risk assessment or validating dosimetry systems for specific radiation incidents, the relevant dose from the incident has to be calculated from the total absorbed dose in enamel by subtracting additional dose contributions from the radionuclide content in teeth, natural external background radiation and medical exposures. For calculating organ doses or evaluating dosimetry systems the absorbed dose in enamel from a radiation incident has to be converted to air kerma using dose conversion factors depending on the photon energy spectrum and geometry of the exposure scenario. This paper outlines the approach to assess individual dose contributions to absorbed dose in enamel and calculate individual air kerma of a radiation incident from the absorbed dose in tooth enamel.     

Space dosimetry with the application of a 3D silicon detector telescope: response function and inverse algorithm

One of the many risks of long-duration space flights is the excessive exposure to cosmic radiation, which has great importance particularly during solar flares and higher sun activity. Monitoring of the cosmic radiation on board space vehicles is carried out on the basis of wide international co-operation. Since space radiation consists mainly of charged heavy particles (protons, alpha and heavier particles), the equivalent dose differs significantly from the absorbed dose. A radiation weighting factor (w(R)) is used to convert absorbed dose (Gy) to equivalent dose (Sv). w(R) is a function of the linear energy transfer of the radiation. Recently used equipment is suitable for measuring certain radiation field parameters changing in space and over time, so a combination of different measurements and calculations is required to characterise the radiation field in terms of dose equivalent. The objectives of this project are to develop and manufacture a three-axis silicon detector telescope, called Tritel, and to develop software for data evaluation of the measured energy deposition spectra. The device will be able to determine absorbed dose and dose equivalent of the space radiation.