自制CsI(T1)晶体的能量测量性能

本文介绍了近代物理研究所自行生长的CsI(T1)晶体用于γ射线及重离子能量测量的结果.测量662 keV γ射线时得到好于10%的能量分辨(采用光电倍增管读出),同时光输出可达到同类型晶体的130%;测量能量为30MeV/u左右的重离子时得到好于2%的能量分辨(采用光二极管读出).     

CSR外靶实验终端中CsI(T1)晶体的测试

为测量重离子加速器冷却储存环(HIRFL-CSR)的外靶实验终端上不同能量的γ射线,一种用于探测γ射线的高能量分辨的探测装置正在中国科学院近代物理研究所建设,该探测器由中国科学院近代物理研究所自行生长的铊激活的碘化铯CsI(T1)晶体组成.与日本Hamamatsu公司生产的S8664-1010型雪崩光二极管(APD)耦合,测试其光输出的非均匀性和能量分辨,从测试结果给出了所需CsI(T1)晶体合格的标准.目前已完成该γ探测球计划的六分之一,所提供的晶体合格率达94%以上.     

CSR外靶实验终端中CsI（Tl）晶体的测试

为测量重离子加速器冷却储存环（HIRFL-CSR）的外靶实验终端上不同能量的γ射线,一种用于探测γ射线的高能量分辨的探测装置正在中国科学院近代物理研究所建设,该探测器由中国科学院近代物理研究所自行生长的铊激活的碘化铯CsI（Tl）晶体组成。与日本Hamamatsu公司生产的S8664-1010型雪崩光二极管（APD）耦合,测试其光输出的非均匀性和能量分辨,从测试结果给出了所需CsI（Tl）晶体合格的标准。目前已完成该γ探测球计划的六分之一,所提供的晶体合格率达94%以上。     

硅PIN光敏二极管探测X、γ射线的性能及应用

介绍了硅PIN光敏二极管和电荷灵敏前放组成的X射线探测器和配合CsI(Tl)晶体构成的γ射线探测器的性能和测量结果,同时研究了光敏二极管探测器能量分辨率的温度特性。测量X射线时,在-10℃下对241Am的59.5keV射线的能量分辨率为4.8%;用PIN光敏二极管配合10mm×10mm×10mm的CsI(Tl)晶体测量γ射线时,在20℃下对137Cs0.662MeVγ射线的能量分辨率为9.9%,60Co的1.332MeVγ射线的能量分辨率为6.4%,-10℃下的能量分辨率分别为8.7%和6.3%。     

BaF2性能测试及其应用

文章介绍了ＢａＦ２晶体性能的测试方法，对国产ＢａＦ２晶体的能量分辨率、时间分辨率、衰光长度以及杂质含量进行了细致测量。实验发现，用不同原材料或不同生长方法生产的ＢａＦ２晶体，它们的物理性能略有不同；测得的晶体最好能量分辨率为１０．７％，对６６２ｋｅＶγ射线时间分辨为２０２ｐｓ（与Ｐｌａｓｔｉｃ耦合）。另外还将ＢａＦ２晶体应用于重离子熔合反应中测量γ多重性和作为零信号拾取器。     

新型雪崩光电二极管和CsI（Tl）晶体组成的闪烁探测器

本文介绍Ｓ５３４５型雪崩光电二极管用于ＣｓＩ（Ｔｌ）晶体光信号的读出，测量了γ射线的能谱，对应于＾２２Ｎａ的１．２７ＭｅＶ的入射能量，得到６．８％的能量分辨率。并对能量分辨率与光耦合面积及晶体尺寸、成形时间、偏压的关系等进行了测量。将雪崩光电二极管和ＣｓＩ（Ｔｌ）晶体组成一种新型的闪烁探测器的实验研究这在国内尚属首次。     

BaF2探测器测量α粒子的时间分辨随温度变化实验研究

本工作对用于测量α粒子的BaF₂探测器的时间分辨随温度变化情况进行了实验研究。实验选用退激γ射线能量较高的²³⁷Npα源,利用α粒子与退激γ射线的时间关联性得到时间谱,在不改变任何条件的情况下对BaF₂晶体加热,加热到设定温度后保持恒温,在BaF₂晶体达到热平衡后开始测量时间谱,由该时间谱上读出的半高宽与标准偏差的线性关系得出α粒子的时间分辨随温度变化的情况。测量结果显示,时间分辨随温度变化在目前实验条件下较为明显,这为未来快时间分辨α粒子探测器的选择和优化使用提供了依据。     

掺钇BaF2闪烁探测器性能研究

利用22Na放射源释放的β+湮没产生的0.511 MeVγ射线,研究了掺钇BaF_2(钇掺杂为1 at%,原子百分数)闪烁探测器的能量分辨和时间分辨性能。与BaF_2探测器对比实验结果表明:掺钇BaF_2晶体的快慢成分比(1:1.1)远高于BaF_2晶体的快慢成分比(1:5),掺钇BaF_2探测器的能量分辨率(38%)低于BaF_2探测器的能量分辨率(19%);在高强度γ射线环境下,掺钇BaF_2探测器的符合时间分辨率优于BaF_2探测器的时间分辨。分析发现:掺钇BaF_2晶体中慢成分信号的减少,缩短了探测器输出信号的时间宽度,有利于在探测高强度γ射线时减缓或消除探测器中高计数率时间信号的堆积现象,提高探测器的时间分辨能力。     

γ-γ符合测量系统的新型前端读出电路研制

研制了一种新型前端读出电路,用于重离子治癌装置中符合测量原型系统的研究和测试。电路主要包括能量链、时间链和数据处理单元。能量链由截止频率7 MHz的抗混叠滤波器和模数转换器(ADC)组成,形成波形采样电路;时间链由高速比较器构成的定时甄别电路和时间数字转换器(TDC)组成;数据处理单元基于现场可编程门阵列(FPGA)设计实现。电路的线性度优于0.8%,噪声小于0.8 mV(RMS)。配合LaBr_3单晶体条测试,能量分辨为4.5%(FWHM),在与LYSO晶体阵列配合测试时,位置映射散点图清晰。该前端读出电路性能优于CAMAC系统,具有较好的实际应用前景。     

LaBr_3:Ce(5%)闪烁探测器的MC研究

近年来一种采用LaBr3:Ce晶体的闪烁探测器被研发出来,这种新型探测器比NaI(Tl)探测器具有更高的能量分辨率,在662 keV大约为3%。利用蒙特卡罗通用程序MCNP4C分别模拟计算了LaBr3:Ce晶体和NaI(Tl)晶体的γ能谱,模拟能谱与相应的实验测量能谱符合很好。研究还发现晶体尺寸大小对能量分辨率没有影响,能量分辨率不随晶体体积的增加而提高。同样晶体尺寸下通过模拟探测不同入射能量γ射线的峰总比R(E)计算值与NaI(Tl)晶体的模拟值和实验值比较发现,LaBr3:Ce晶体对中高能量γ射线的探测效率较高,而在较低能量时探测效率低于NaI(Tl)晶体。     

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.