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合成了含8个CArG元件的放射敏感性启动子E8,将其连接于胞嘧啶脱氨酶(Cytosine Deaminase, CD)基因及GFP报告基因上游,构建了重组慢病毒载体pGC-FU-E8-codA-GFP。与慢病毒包装系统共转染293T细胞包装重组慢病毒颗粒E8-codA-GFP LV,研究重组慢病毒感染EJ细胞在不同剂量125I的电离辐射下绿色荧光表达情况及其将5-FC转化为5-FU的能力。结果显示:构建的含有E8启动子及CD基因的重组慢病毒载体,包装的重组慢病毒滴度为2×108TU/mL;经125I照射的重组慢病毒感染EJ细胞均可观察到绿色荧光,其细胞上清液均可检测到5-FC转化成的5-FU紫外峰,其中55.5 kBq及74.0 kBq 125I照射的细胞组绿色荧光明显,148 kBq 125I照射的细胞组,其5-FU紫外峰最为明显。以上结果表明:本工作所构建的放射敏感性启动子调控CD基因/5-FC自杀系统重组慢病毒载体具有电离辐射调控作用,可在125I的电离辐射作用下诱导下游基因表达,为放射性核素125I联合CD基因/5-FC自杀系统对肿瘤细胞的治疗作用研究提供了实验基础。 相似文献
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125I粒子组织间植入近距离治疗恶性肿瘤 总被引:1,自引:0,他引:1
采用125I粒子植入法对20例恶性肿瘤患者的24个病灶进行治疗,以评价125I粒子组织间植入恶性肿瘤的可行性及不良反应。术前制定肿瘤组织间三维立体定向放射治疗计划,在全麻剖腹直视下、全麻腹腔镜下或局麻CT、局麻彩色多普勒导向下经皮穿刺将125I粒子植入恶性肿瘤病灶内。20例患者125I粒子植入均顺利完成,术中及术后1周观察粒子在病灶内的分布基本与计划相符合,未观察到粒子迁移;术中及术后不良反应较为轻微且易于处理;多数患者临床症状得到不同程度的缓解,血清肿瘤标志物水平呈现不同程度的下降; 病情完全缓解(CR)20.00%(4/20例), 部分缓解(PR)35.00%(7/20例), 稳定(SD)30.00%(6/20例),进展(PD)15.00%(3/20例),总有效率(CR+PR)55.00%(11/20例)。以上结果表明,125I粒子组织间植入近距离内放射治疗恶性肿瘤施术方便、安全有效,具有较高的临床价值,值得进一步推广及深入研究。 相似文献
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依据混合裂变产物中碘及其母体碲的同位素的半衰期设计分离132I的流程。该流程的主要步骤为浓HBr蒸发和CCl4萃取。实验研究了浓HBr蒸发对碘的去污效果;在硝酸介质中,用含I2的CCl4作为萃取剂,研究了HNO3浓度、水相中KI含量和有机相CCl4中I2含量对132I萃取率的影响,测定了含SO2水溶液对132I的反萃率。用设计的推荐流程获得了放化纯的132I,其中含有的131I的活度为132I的1.3%,分离流程全程对132I的化学回收率约为60%,流程对主要γ核素的去污因子大于103。 相似文献
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碳酸酐酶Ⅸ(Carbonic anhydrase Ⅸ,CA Ⅸ)是碳酸酐酶家族(Carbonic anhydrases,CAs)的异构体之一,在许多肿瘤中过量表达,是一种与肿瘤相关的跨膜糖蛋白。它催化CO2水解为碳酸氢根和氢离子,维持肿瘤细胞内的pH,酸化细胞外环境,有利于肿瘤的生长和转移。在核医学的靶向诊断和治疗中,CA Ⅸ成为一个抗肿瘤药物的靶向目标,也成为病人病情的一个预后因子。CA Ⅸ抑制剂可以作为一种诊断药物,用于肿瘤的分子影像;也可以作为一种治疗药物,阻断CA Ⅸ所调控的通路。利用89Zr、111In、124I 或125I标记靶向CA Ⅸ的单克隆抗体或其片段进行分子影像,能精确定位CA Ⅸ的分布,灵敏检测CA Ⅸ的表达情况;利用90Y、131I、177Lu或186Re标记靶向CA Ⅸ的单克隆抗体,在放免疫治疗中可有效延迟肿瘤的生长。本文对CA Ⅸ及其在核医学中的研究进展进行了综述。 相似文献
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针对0Cr18Ni10Ti不锈钢放射源源壳钨极氩弧焊(TIG)焊接过程,采用ANSYS有限元软件对焊接温度场进行数值模拟分析,建立了非稳态TIG焊接熔池形态的数值分析模型,分析中引入了热焓和表面分布高斯电弧热源模型,初步计算了焊接电流和焊接速度对焊接温度场分布的影响。通过比较焊缝有效熔深的测量结果和计算结果,验证了所建模型的正确性和可靠性。以计算结果为基础,对焊接工艺参数进行优化,建立了0Cr18Ni10Ti不锈钢放射源源壳的焊接工艺路线。 相似文献
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The kinetic response of a boiling water reactor (BWR) equilibrium core using thorium as a nuclear material, in an integrated blanket–seed assembly, is presented in this work. Additionally an in-house code was developed to evaluate this core under steady state and transient conditions including a stability analysis. The code has two modules: (a) the time domain module for transient analysis and (b) the frequency domain module for stability analysis. The thermal–hydraulic process is modeled by a set of five equations, considering no homogeneous flow with drift-flux approximation and non-equilibrium thermodynamic. The neutronic process is calculated with a point kinetics model. Typical BWR reactivity effects are considered: void fraction, fuel temperature, moderator temperature and control rod density. Collapsed parameters were included in the code to represent the core using an average fuel channel. For the stability analysis, in the frequency domain, the transfer function is determined by applying Laplace-transforming to the calculated pressure drop perturbations in each of the considered regions where a constant total pressure drop was considered. The transfer function was used to study the system response in the frequency domain when an inlet flow perturbation is applied. The results show that the neutronic behavior of the core with thorium uranium fuel is similar to a UO2 core, even during transient conditions. The stability and transient analysis show that the thorium–uranium fuel can be operated safely in current BWRs. 相似文献
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《Fusion Engineering and Design》2014,89(1):40-48
Heat source parameters were usually recommended by experience in welding simulation process, which induced error in simulation results (e.g. temperature distribution and residual stress). In this paper, a new method was developed to accurately estimate heat source parameters in welding simulation. In order to reduce the simulation complexity, a sensitivity analysis of heat source parameters was carried out. The relationships between heat source parameters and welding pool characteristics (fusion width (W), penetration depth (D) and peak temperature (Tp)) were obtained with both the multiple regression analysis (MRA) and the partial least-squares regression analysis (PLSRA). Different regression models were employed in each regression method. Comparisons of both methods were performed. A welding experiment was carried out to verify the method. The results showed that both the MRA and the PLSRA were feasible and accurate for prediction of heat source parameters in welding simulation. However, the PLSRA was recommended for its advantages of requiring less simulation data. 相似文献
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为保证85Kr测厚源的密封质量,通过85Kr测厚源结构设计、焊接工艺参数优化,制备合格的85Kr测厚源。铜管与壳体的连接采用真空钎焊工艺,钎焊温度约900 ℃,时间约30 min;源窗与壳体的连接采用电子束焊工艺,焊接电流7 mA,焊接转速13 mm/s;源后盖与壳体的连接采用激光焊工艺,焊接功率180~185 W,焊接速度2 mm/s。测厚源检验结果表明,所制备的85Kr测厚源,氦质谱检漏结果小于1.0×10-9 Pa·m3·s-1,放射性气体检验不超过4 kBq/24 h,符合GB/T 15849—1995中“其他射气检验方法”要求。金相实验结果表明,采用优化参数试样的焊缝中未发现明显的裂纹、未焊透、未熔合等缺陷,最大焊接熔深约0.73 mm。 相似文献
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Lei Xiu Zhihong Liu Gang Lv Jianguo Ma Feixiang Jin Huaichu Dai Yang Qiao 《Journal of Fusion Energy》2018,37(4):193-199
The China fusion engineering test reactor (CFETR) vacuum vessel is welded by narrow gap TIG (NG-TIG) welding, and the welding residual stress of the CFETR vacuum vessel can be redistributed by trailing welding ultrasonic impact treatment. In order to investigate the feasibility of the residual stress removing scheme, and to obtain the optimal trailing ultrasonic impact treatment technological parameters in the process of removing welding residual stress, a welding model that similar to vacuum vessel welding seam is established by using ABAQUS software, a NG-TIG welding heat source subroutine which is written in FORTRAN language used to simulate NG-TIG welding. According to the welding simulation results, a trailing welding ultrasonic impact treatment model is established, and the effects of the impact pin number, the impact method, the impact pin diameter and the impact frequency on welding residual stress are studied. The results show that the longitudinal residual stress in welding seam and its adjacent area and the lateral residual stress in the whole region have been obviously decreased by different trailing welding ultrasonic impact processes, and have made the tensile stress in the welding seam and its adjacent area has been changed into compressive stress, which can provide theoretical guidance and reference for actual production. 相似文献
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贯穿件J形坡口焊接残余应力分析 总被引:1,自引:1,他引:0
核电站反应堆压力容器(RPV)顶盖控制棒驱动机构(CRDM)管座J形坡口焊缝在一回路高温高压水环境下存在应力腐蚀开裂(SCC)的风险,而焊接残余应力是SCC的主要驱动力。使用二维轴对称模型有限元方法对CRDM中心管座J形坡口进行焊接残余应力分析。为了探索一种简单、高效和保守的方法,研究了热源简化、焊缝形状简化、屈服强度、相变和强化行为对焊接残余应力的影响。结果表明:双椭球热源与均匀热源得到的残余应力结果基本一致;焊缝形状由鱼鳞状简化为方块模型对焊接残余应力结果影响不大,但是与合并焊道的结果相差较大;采用低屈服强度得到的残余应力结果并不保守;在ANSYS软件中,固液相变对残余应力结果影响不大;等向强化模型的结果比随动强化模型的结果保守;在工程上,建议采用均匀热源、方块焊道模型和等向强化模型进行焊接模拟。 相似文献