EAST托卡马克上截面效应对电荷交换复合光谱测量结果的影响

离子温度和旋转速度是聚变等离子体中的重要物理参数,在先进实验超导托卡马克EAST(Experimental Advanced Superconducting Tokamak)上电荷交换复合光谱(Charge e Xchange Recombination Spectroscopy,CXRS)诊断是测量这些物理参数的标配诊断之一。由于截面效应的存在,CXRS诊断测量的谱线线型会受到影响,导致得到的离子温度和旋转速度偏离实际值,为了得到真实值,需要对离子温度和旋转速度进行修正。在EAST上,分别采用常用的动力学理论和数值计算方法对测量到的实验数据进行修正,同时对比两种方法对截面效应的修正结果,可以看出两种方法得到的结果趋势基本一致。对2015年EAST上电荷交换复合光谱测量到的典型的实验数据进行修正,结果表明在目前的放电条件下截面效应对离子温度的影响比较小,而对旋转速度的影响低于10%。     

托卡马克等离子体杂质密度的光谱法测量研究

本文介绍了基于托卡马克等离子体被动光谱诊断获得杂质密度的方法。通过被动光谱诊断测量获得杂质线辐射的空间多道弦积分强度分布,利用强度标定系数转换为绝对光亮度分布;通过测量弦与等离子体位形,将弦积分的强度分布反演变换为径向体发射率。根据线辐射强度激发截面求出对应电离态的离子密度,最后采用杂质输运程序模拟计算得出总密度分布。以东方超环(Experimental Advanced Superconducting Tokamak,EAST)托卡马克装置上软X射线-极紫外光谱(Soft X-ray and Extreme Ultraviolet Spectrometers,XEUV)诊断测量到的Mo XXIX-Mo XXXII为例,描叙了获得Mo杂质密度分布的过程,获得的总误差小于10%。     

贝叶斯反卷积在EAST电荷交换复合光谱分析中的应用

电荷交换复合光谱(Charge e Xchange Recombination Spectroscopy,CXRS)诊断是核聚变装置上测量等离子体离子温度和旋转速度的常规诊断之一。然而在实验中,诊断光通过光谱仪后,由于仪器函数的卷积效应,会使测量到的光谱出现明显展宽,影响数据处理的精度,所以需要对实验测量到的光谱进行反卷积处理。本文采用的反卷积方法是基于贝叶斯条件概率公式推导得出,并结合标准灯获取的仪器函数来进行反卷积,分别从仿真和实验两个方面验证了该方法的可靠性。结果表明将贝叶斯反卷积运用到先进实验超导托卡马克(Experimental Advanced Superconducting Tokamak,EAST)电荷交换复合光谱分析中,能有效提高实验测量精度。结合快速极紫外谱仪(Extreme ultraviolet,EUV),对EAST实验中经过贝叶斯反卷积后测量到的光谱进行了杂质谱线识别工作,进一步提高了精度。     

低杂波电流驱动下HT-7超导托卡马克等离子体硬X射线辐射研究

用７个ＮａＩ（Ｔｌ）闪烁探测器组成的阵列观测能量范围在２０－５００ｋｅＶ,来自ＨＴ－７托卡马克等离子体的硬Ｘ射线轫致辐射。实验结果显示,硬Ｘ射线的径向辐射强度分布与低杂波的功率谱和等离子体的密度及磁志强度等放电参数密切相关。通过测量不同放电参数下硬Ｘ射线的径向强度分布,研究低杂波在等离子体中传播和吸收机制。     

CdTe探测器对EAST托卡马克中20–200keV硬X射线测量

介绍了EAST托卡马克装置硬X射线诊断系统。该系统由探测器阵列和电子线路组成,探测器采用水平七道的碲化镉(CdTe)探测器阵列。在EAST托卡马克装置上建立了一套较完善的硬X射线能谱诊断系统,用来测量等离子体在硬X射线辐射能段(20–200 keV)的能谱。实验结果表明,该系统能满足测量相应能量范围的等离子体硬X射线轫致辐射要求。文中给出了碲化镉探测器的标定结果及典型的放电结果。     

超导ECR源SECRAL轫致辐射谱的测量

热电子在ECR（Electron Cyclotron Resonance）源中有着非常重要的作用,为了研究ECR源的工作参数（微波功率、磁场等）对热电子的影响,我们对SECRAL（Superconducting ECR ion source with Advanced design in Lanzhou）等离子体在轴向发出的轫致辐射谱进行了系统的测量。从测得的轫致辐射谱中我们得到用来衡量热电子能量的参考量——光谱温度Tspe,并且对ECR源的几个工作参数与Tspe的关系进行了讨论。     

金属膜电阻型辐射热探测器在EAST上的应用

介绍了托卡马克实验装置(EAST)上用于绝对测量辐射功率的金属膜电阻探测器测量系统。金属膜电阻型探测器采用经典的惠斯通电桥电路结构,结合正弦波激励的载频信号放大技术,该系统实现了对强电磁干扰环境下微弱信号的测量。EAST上的辐射功率测量系统为48路测量阵列,用于测量等离子体放电过程中辐射功率的时空演化。文中给出了对探测器进行绝对标定的结果和典型的测量结果。     

基于中子多重性方法的~(252)Cf中子强度测量算法及实验研究

252 Cf中子发射强度的获取在核技术应用中具有重要意义,为测量其绝对发射强度,分析了一种可能的替代测量算法,该算法基于252 Cf自发裂变的中子多重性分布,并结合中子在测量系统内的衰减时间行为,在不依赖测量系统探测效率和被测样品任何信息的条件下,可给出其中子强度测量值。利用5个252 Cf镀膜中子源在中子多重性测量装置上进行了实验测量,通过测量算法获取的中子强度值与账面记录值最大相对偏差为1.41%,其结果初步验证了该算法的正确性。     

滤波差分法测量软X光谱

研究了一种测量激光等离子体发射软 X 光谱强度的新方法——滤波差分法。文中介绍了滤波差分法基本原理,给出了滤波差分对的理论计算结果及实验测量结果,并用此方法获得软 X 光谱的绝对强度,最后对测量光谱强度的误差进行分析和估算。滤波差分法建立在以往滤波法测量软 X 光能谱的基础上,利用软 X 光能谱仪(Dante 谱仪) 的十个探测道,采取滤波差分法构成两两配对的五个差分对。设计匹配差分对,使其上下 K 边或 L 边之外的能响互相抵消,从而使差分对切割能谱,能基本消除高能尾部对所测能区的贡献,提高能谱测试系统的单色性,提高能谱的反演精度,从而建立滤波差分法测量软 X光谱的系统。     

AXUV探测器标定及受辐照响应衰减研究

在EAST和HT-7装置上,具有宽能谱响应的AXUV光电二极管探测器主要用于辐射功率的绝对测量。探测器在经历多轮等离子体放电中的累积辐照效应后,观察到其表面发生变化。为了解探测器响应衰减程度,设计了相对标定实验,分别采用标准可见光光源和软X射线管作为标定光源,对EAST和HT-7实验中经历过不同放电次数的5个探测器进行了标定。标定结果表明,AXUV探测器在经历了EAST上约25 000次的等离子体放电累积辐照后,其在软X射线能段的响应下降约15%。而探测器在可见光能段的辐照损伤效应主要表现为同一个探测器不同通道之间对可见光响应的不一致性加剧。结合探测器在等离子体放电辐射场中的几何参数,对探测器受到的累积辐照剂量进行了估算。     

Preparation of Zn/TiO2 powder and its photocatalytic performance for oxidation of P-nitrophenol

Zn-doped TiO2 catalysts were prepared using a sol-gel method and characterized by XPS,UV-Vis, BET, XRD in this study. Under the irradiation of simulant sunlight, the photocatalytic activity for the degradation of p-nitrophenol was studied too. After irradiation for 2.5 h, the degradation percentage of p-nitrophenol could rise to more than 80 %. The results showed that the spectrum absorption band edge of Zn/TiO2 powder does not broaden obviously comparing with pure TiO2 powder. Zinc exists as Zn （11）. When calcined at 973 K, there is a new phase as ZnTiO3 in Zn/TiO2 catalyst. The order of photocatalytic activity of Zn/TiO2 catalysts calcined at different temperatures for p-nitrophenol is 773 K 〉 673 K 〉 873 K 〉 573 K 〉 973 K and the photocatalytic activity of Zn/TiO2 catalyst calcined at 773 K is better than TiO2 catalysts heated at the same temperature, and outclasses that of commercial TiO2 catalyst. It also showed that the photocatalytic degradation of p-nitrophenol follows first-order kinetics under the irradiation of simulant sunlight.     

Current status of radiation therapy for prostate cancer

Radiotherapy for the treatment of prostate cancer has been extensively explored in the past. Along with the comprehensive understanding of the biology of prostate cancer and rapid advances in terms of technology, the out- come of treatment for the patients with prostate cancer has improved. The authors review radiotherapy as the primary treatment for the disease, with particular emphasis on the technological advances from both the radiobiological and radiophysics aspects. Nonconventional fractionated irradiation like hyper- or hypo-fractionation has been imple- mented in the clinic, the final results still need to be confirmed in the future. Technological advances like IMRT, IGRT, in the last two decades have significantly improved the delivery of external radiotherapy to the prostate. This has re- sulted in an overall increase in the total dose that can be safely delivered to the prostate, which has led to modest im- provements in the biochemical outcome. However, establishing the standard therapy for prostate cancer remains con- troversial. It is hoped that the next decades will bring continued advances in the development of biologicals that will further improve current clinical outcomes.     

The control system for SSRF injection and extraction

This paper introduces the injection and extraction control system design for SSRF,which is a distributed control system aimed at stability and reliability of the pulse power supplies,PPS(Personnel Protection System)and MPS(Machine Protection System).The hardware environment is mainly based on PLC(Programmable Logic Con- troller),and ARM(Advanced RISC Machine)is also applied for studying stability of the power supplies.WinCC and EPICS(Experimental Physics and Industrial Control System)have been selected as the platforms of SCADA(Super- visory Control and Data Acquisition).For unifying the interfacing to the control computer,all front-end equipments are connected via Industrial Ethemet.     

水平管内含空气蒸汽强制对流冷凝换热模型研究

为研究含空气蒸汽在水平管内强制对流冷凝换热特性,基于对传热传质过程的分析,建立了管内为环状流与波状流条件下的流动冷凝换热模型。从潜热、显热和液膜3个环节对整个换热过程进行建模,最终得到计算局部冷凝换热系数的理论关系式。模型预测结果与实验数据的对比表明,二者相对偏差在±20%以内,验证了该换热模型的准确性与适用性。通过进一步的研究发现：从换热管入口至出口,随着冷凝的进行,管内换热主要热阻由液膜热阻向气液界面的凝结热阻转变;主流气体对流换热过程基本可忽略。     

Investigations on landmine detection by BF3 detector

Experiments were carried out to investigate the possible use of neutron backscattering for the detection of polyethylene (PE) sample buried in the soil. In detection of landmine by neutrons, the neutron detector and its shield play an important role. In this paper, the effects of graphite, heavy water, polyethylene and boric acid moderators on the flux of back scattered neutrons were investigated. We have also experimentally verified the effect of BF3 detector shield and obtained good agreement with theory.     

Web Services interface of SSRF archive data analysis system

Accelerator database stores various static parameters and real-time data of accelerator. SSRF (Shanghai Synchrotron Radiation Facility) adopts relational database to save the data. We developed a data retrieval system based on XML Web Services for accessing the archive data. It includes a bottom layer interface and an interface applicable for accelerator physics. Client samples exemplifying how to consume the interface are given. The users can browse, retrieve and plot data by the client samples. Also, we give a method to test its stability. The test result and performance are described.     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

Assessment of radioactivity levels in some oil samples from the western desert, Egypt

Distributions of natural gamma-emitting radionuclides were determined in 93 oil samples collected from some petroleum fields in the western desert of Egypt. The radioisotope activities in the area under investigation lay in the range of (21 ± 4) to (38 ± 13) Bq?L-1 for 226Ra, (9 ± 2) to (15 ± 5) Bq?L-1 for 232Th, and (154 ± 28) to (303 ± 54) Bq?L-1 for 40K. The mean values were 27, 12, and 201 Bq?L-1, respectively. Among oils, variations in radionuclide ac- tivities could be on account of differences in TDS, HCO3, and Ba, with high or low pH. In this environment, oil prop- erties differently affected the mobilization of natural radionuclides. The range of 226Ra variation had been compared with available data from other countries. The calculated absorbed dose rate ranged from 22.33 to 32.66 nGy?h-1 in lo- cation (B) and (E) respectively, which was less than the accepted value.     

Preparation and properties of 117m Sn(IV)-TTHMP in in-vitro and in small animals

In this work,TTHMP was synthesized and labelled with 117m Sn.The preparation conditions,stability and lipophilicity of 117m Sn(IV)-TTHMP were investigated.Biodistribution of the complex in rabbits and mice was studied.It was found that the quantity of TTHMP and pH value of the prepararion solution had vital effects on the labeling yield of 117m Sn(IV)-TTHMP.It was also found that 117m Sn(IV)-TTHMP was hydrophilic and stable at room temperature and 37℃ in open air 117m Sn(IV)-TTHMP showed unexpectedly high bone uptake and bone-to-blood ratio in the animals.This made it potentially useful as an reagent for skeletal scintigraphy and radiotherapy of bone tumors.     

Gamma radiation levels in the ambient environment of the QNPP Base

Monitoring results of gamma dose rate level in 1992～2004 in the ambient environment of the Qinshan Nuclear Power Plants(QNPP)Base,the northeast of Zhejiang Province,are reported in this paper.It is shown that the gamma dose rate of five monitoring sites of 2.5 km to QNPP Base is 84～113 nGy/h,with an average of 96 nGy/h in the 13 years.The average value is close to the background level of 93 nGy/h prior to operation of the QNPP Base,and is lower than the monitoring result of 101 nGy/h at the reference site in Hangzhou City.Within 50 km from the QNPP Base,the cumulative dose rate of the thermoluminescent dosimeter(TLD)is 90 nGy/h,which is lower than the back- ground level of 111 nGy/h.