低能离子探测器的设计及测试

自行设计制作并测试了用于电子-离子碰撞电离截面测量实验的低能离子探测器。该探测器由Al_2O_3转换板、加速电极、单通道电子倍增器三部分组成。离子沿70°方向轰击转换板,产生数目与离子能量成正比的二次电子,电子由单通道倍增器测量。采用合适的电子学线路和甄别阈,可以有效地把离子计数与本底分开。对10keV Ar~+在入射束流小于10~4s~(-1)时,探测效率接近100％。本探测器可用于低能重离子的计数测量。     

中子计数器探测效率的校准

设计制作了一个 BF3长硼中子计数器 ,采用伴随粒子法标定了其中子探测效率 ,约为 3.17×10 -4 ( 1± 18% )。利用这个中子探测器测量了中子管脉冲中子产额 ( 10 7/ pulse)     

聚变反应堆壁材料钨和钼的表面离子束效应

利用扫描电子显微镜 (SEM )及氘的定量深度分布测量 ,系统地研究了在氘离子轰击下金属钨和钼的损伤情况 ,特别是钨表面气泡的形成及机制 ,以及氘在表面层的滞留量和气泡形成机制之间的关系。D+离子能量为 10 0eV— 1keV ,轰击剂量为 1× 10 19— 1× 10 2 1D+/cm2 。轰击过程中靶表面温度分别控制在室温、6 0 0℃和 80 0℃。     

用于超灵敏小型迴旋加速器质谱计的微通道板粒子探测器

我们制造并测试了为超灵敏小型通旋加速器质谱计研究设计的单粒子探测系统。探测器由Al_2O_3打拿极、微通道板电子倍增器和阳极三部分组成。入射离子沿80°角方向轰击打拿极,以0.8电子/keV的转换系数产生数目与离子能量成正比的次级电子,每个电子在不同的通道管内单独放大至饱和,阳极收集的电荷数与入射离子能量成正比。用选择甄别阈的方法可以有效地将离子计数与本底分开。从实测数据外推到40keV K或Ar离子时可知:相应于90％计数效率的本底率为10~(-3)/S。探测系统的能量分辨△E=6.5keV,可以用于测量极低能量的重离子谱。     

铍窗正比计数管的制造、性能及其应用

正比计数管是测量核辐射的一种基本探测元件。在测量X射线和低能γ射线时,和闪烁计数器比较,在两者的探测效率大体相同的情况下,正比计数管具有较高的能量分辨本领,并且能够测量较低的能量。因此,在X射线和低能γ射线(<100keV)的测量方面,正比计数管获得广泛的应用。     

~(252)Cf快裂变室研制

采用甲烷、氩气或其混合气体 ,在 2 52 Cf平行板裂变室极间距 1.0 0至 5.0 0 mm、电压 50至70 0 V的条件下 ,测量了 142 B电荷灵敏前置放大器输出脉冲波形和脉冲幅度谱。 2 52 Cf裂变室中子强度为 2 .0 7× 10 4 s-1,上升时间为 7.69( 1± 9.1% ) ns,裂变碎片探测效率为 98.4 % ,能够清晰分辨裂变碎片和 α粒子信号。     

在~(41)Ar存在情况下空气中氚水蒸气浓度的连续监测

本文介绍了一种采用气液混合取样方法和液体闪烁计数技术相结合的氚连续监测装置。它的取样原理是基于~(41)Ar 和氚水蒸气(HTO)在闪烁液中溶解度的差异,使得~(41)Ar 在液相中的存留量不致于对欲测的 HTO 造成严重的干扰。装置本底为14cpm,其刻度系数对应于5×10~(-9)Ci/L 的 HTO 为6.8×10~3pm,响应时间为20分钟,无~(41)Ar 存在下探测下限至少可达到9×10~(-12)Ci/L(空气) (95%置信度)。当反应堆现场的~(41)Ar 平均浓度为3×10~(-8)Ci/L 时,对 HTO 的探测下限低于1×10~(-10)Ci/L。     

氦离子辐照非晶态合金的表面损伤研究

用扫描电子显微镜研究了室温下氦离子辐照Fe77Ni5B18等 10种非晶态合金的表面形貌。氦离子的能量为 4 0keV和 6 0keV ,总注量为 1.0× 10 18— 4 .0× 10 18He/cm2 。对于不同的注量和不同的材料 ,观察到了层离、发泡、剥落、发泡破裂、二代发泡和多孔结构等多种表面损伤类型。测量了泡的直径和剥落泡皮的厚度 ,并讨论了表面损伤类型和初现的临界注量与材料种类和离子能量的关系。     

Ar+离子辐照对锆4合金耐腐蚀性能的影响

为了研究辐照损伤对锆4合金电化学耐腐蚀性能的影响,使用直线加速器产生单电荷载能Ar+,在液氮温度下辐照样品表面,产生缺陷.然后,测量辐照后锆4合金的电化学极化曲线,使用钝化电流密度作为评定腐蚀性能的指标,分析不同注量Ar+离子辐照对锆4合金钝化电流密度的影响.同时使用透射电子显微镜分析不同注量Ar+辐照下锆4合金损伤层的微观结构.实验结果表明在低离子注量范围内(＜3×1014/cm2),随着辐照量的增加钝化电流密度升高,耐腐蚀性能降低;在中等离子注量范围内(3×1014-1×1016/cm2),随着辐照量的增加钝化电流密度急速下降,耐腐蚀性能显著提高;在高离子注量范围内(1×1016-1×1017/cm2),随着辐照量的增加钝化电流密度又开始增加,耐腐蚀性能再次降低.最后,根据原子碰撞理论对实验结果进行了理论分析.     

蒙特卡罗方法计算用于低能光子测量的高纯锗探测器的效率

在内照射活体测量中,为了用蒙特卡罗方法计算探测器对光子尤其是低能光子的探测效率,需要对探测器准确建模。通过使用蒙特卡罗模拟计算和实验测量相结合的方法来准确确定低能光子高纯锗探测器晶体的死层厚度、半径和长度;结果表明使用此方法确定的晶体尺寸来模拟计算探测器效率,在17．5～662keV光子能量范围内,低能光子高纯锗探测器探测效率的模拟计算结果与实验结果比较,相对偏差平均小于1．0％,最大为3．2％。     

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.     

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.     

The role of AGFA high-energy CR in the calibration and quality control of multileaf collimators （MLC）

Linear accelerators equipped with multileaf collimators （MLC） are becoming more common and are widely used in the intensity-modulated radiotherapy （IMRT）. There is an imperative need to ensure the commissioning specification of the linear accelerators for the sake of quality assurance （QA） and quality control （QC）. This paper is aimed to investigate the role of AGFA high-energy CR （Computed Radiography） in calibrating dynamic multileaf collimators and evaluating the accuracy of the leaf position. The result shows that AGFA high-energy CR can easily and conveniently be used to calibrate MLC and verify its position. Hence, the application of AGFA high-energy CR is proved to be an accurate and time-saving method for routine MLC QC, especially when MLC calibration adjustments are required.     

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.