~(60)Co和~(137)Csγ辐射场的照射量率的比对

用NPL防护水平次级标准NE2550剂量率仪对国防计量系统和有关厂矿的防护水平~(60)Co和~(187)Cs γ辐射场进行了照射量率的测量和反平方律的检验,并作了照射量率的比对。~(137)Cs γ辐射场照射量率最大相差+3.6％(2.58×10~(-6)-2.58×10~(-4)Ckg~(-1)h~(-1)),而~(60)Co γ辐射场最大相差分别为+1.4％(2.58×10~(-4)-2.58×10~(-3)Ckg~(-1)h~(-1))、+9.9％(2.58×10~(-6)-2.58×10~(-4)Ckg~(-1)h~(-1))和+24.5％(2.58×10~(-7)-2.58×10~(-6)Ckg~(-1)h~(-1))。~(60)Co和~(137)Cs γ辐射场的照射量率,在一定的距离范围内反平方律在±5％以内符合。     

防护级~(60)COγ 射线照射量标准测量装置的研究

本文介绍低于7.2×10~-_7A·kg~(-1)(10R·h~(-1))的~(60)Coγ射线照射量率的标准测量装置和测量方法。给出了电离室各种修正因子的实验测定值或理论计算值,并计算了照射量率测量的不确定度。     

强源倒装中的安全防护与辐射监测

本文介绍上海辐射技术推广应用中心1986—1988年进行的三次强源(3.7—7.9×10~(15)Bq)倒装的操作程序、安全措施和倒源过程中的辐射监测。监测结果表明:运输铅容器表面的照射量率最大为17mR·h~(-1);工作人员在一次倒源操作中接受的剂量当量最大为9.1×10~(-2)mSv;钴元件污染或泄漏的放射性活度的检测值最大为42Bq/支,低于 ISO 规定的限值(185Bq/支);装源后辐照室周围环境的照射量率最大为17μ·h~(-1)。     

15MeV D-T中子场比释动能测定

本文叙述了用自己研制的组织等效电离室和组装的G-M计数管γ剂量计测定快中子比释动能的方法和测量结果,测量结果总的估计不确定度为±5.2％。并与用美国FWT IC-17A组织等效电离室和FWT GM-2计数管所测的结果进行了比对,两者符合得很好。     

用CaSO4：Dy剂量计测定湖南省环境贯穿辐射水平

本文报告了用CaSO_4:Dy热释光剂量计测量湖南省环境贯穿辐射水平的结果:室内为(9.97±1.61)×10~(-8)y·h~(-1),室外为(7.59±1.27)×10~(-8)Gy·h~(-1);并估算了湖南省居民受照剂量,人均年有效剂量当量约为680μS_v,集体年有效剂量当量约为3.68×10~4man·S_v。     

4πβ G-M计数器的探测效率

本文研究了双圆筒型4πβG-M计数管的一些性能及其探测效率。从计数管的坪曲线、稳定性等一些性能来看,所研究的4π计数管可以用做一般精确度的β放射性强度的绝对测量。做了计数管结构的几何条件、样品(放射性物质及其承托物)的位置等因素对探测效率的影响的实验。估计了由于“假计数”、“死时间”漏计数校正引入的误差。最后给出计数管对于射出样品的β粒子的探测效率接近100%,误差小于±1%。     

钴—60远距离治疗源的活度

本文简述了钴-60远距离治疗源的照射量率测量、活度计算及其误差分析。结果的合成不确定度分别小于±4%和±10%。同时,它适用于其它高活度钴-60密封源.     

可携式中子剂量当量率仪

本文介绍NH1型可携式中子剂量当量率仪的结构和性能。该剂量仪由包有聚乙烯慢化体和硼塑料层的球形~3He计数管和电子学系统组成,适于热能—15MeV能区的中子剂量当量率的测量。剂量当量率测量范围在0.1—10~4μSv/h之间;在热能附近能区和0.3—5MeV能区,剂量当量率响应随能量的变化在±30％以内,对于能量为1.15MeV的中子,响应值约为0.56cps/μSv·h~(-1)。该剂量仪具有模拟和数字显示,重量为7kg。在改换量的名称并对能响作适当修正的条件下,NH1型中子剂量当量率仪可用于中子周围剂量当量率的测量。     

切尔诺贝利核事故前后下部大气层中进行的本底辐射测量

使用轻便γ闪烁探测器和具有电离室的卡蒂派测量仪对切尔诺贝利核事故前后(1986年4月26日)北希腊塞萨洛尼基地区温带纬度区(40°)不同海拔高度(达1100m)和地面上下部大气层的本底辐射进行了测量。切尔诺贝利核事故前,地面总本底辐射的平均值为87nGy·h~(-1)(10.0μR·h~(-1),25计数·s~(-1))。即60％来自地面辐射,55nGy·h~(-1)(6.3μR·h~(-1),15计数·s~(-1))和40％来自宇宙辐射,32nGy·h~(-1)(3.7μR·h~(-1),10计数·s~(-1)),然而,切尔诺贝利核事故后,由于悬浮在大气中和或沉积在地面的长寿命放射性沉降物的影响,总本底辐射增加了1倍。     

用 NaI(TI)γ 谱仪测量环境 γ 照射量率的总谱能量法

本文介绍用 NaI(Tl)γ谱仪测量环境γ照射量率的总谱能量法。谱仪用标准镭源刻度,刻度系数 K_r 为17.82(GeV/20min)/(μR/h),环境γ照射量率测量值的总不确定度约为±9.5%,在玉泉路高能所内外20多个测量点上的测量结果表明,γ谱仪与高气压电离室的测量值较好符合。文中还讨论了用总谱能量法测量环境γ照射量率时的几个有关问题。     

Identification of radiation treatment of wheat （Triticum aestivum. L）and rice （Oryza sativa. L） samples using thermoluminescence of contaminating minerals

Food irradiation is gaining popularity worldwide and this technology is important to improve quality and reduce the post harvest losses of food. Because of the rapid commercialization of irradiated foods throughout the world, compliance of different regulations relating to use of technology in different countries and demand of consumers for clear labelling of irradiated foods, there is need for the development of analytical methods to detect radiation treatment of food. Among several methods studied so far, thermoluminescence （TL） is an important method that can be used to find out the irradiation history of food that contain even a very minute amount of dust particles. In this study, the irradiated and unirradiated wheat and rice samples were analyzed using the TL method. The samples were purchased from the local market of Peshawar and irradiated to radiation doses of 0.5 and 1.0 kGy using Co-60 gamma irradiator at the Nuclear Institute for Food and Agriculture （NIFA）, Peshawar. The mineral contaminants were isolated by jet water, ultrasonic treatment, and density gradient. TL glow curves of the isolated minerals from irradiated and unirradiated samples were recorded between the temperature ranges of 50-500℃ using a TL reader. Generally, the glow curves for irradiated samples showed much higher TL intensities （TL1） than the unirradiated samples. The results were normalized by rerradiation of mineral samples to gamma-ray dose of 1.0 kGy followed by determination of the second glow curves （TL2）. The ratio of the area of first glow curve to that of second glow curve （TL1/TL2） was calculated for selected temperature intervals and compared with the recommended values for unirradiated and irradiated samples. Finally, the shapes of the glow curves for irradiated and unirradiated samples were also analyzed. On the basis of these results （comparison of TL-intensities, TL1/TL2 ratios and shapes of the glow curves）, all the irradiated and unirradiated samples of wheat and rice were unequivocally identified.     

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。     

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.     

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.     

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.     

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.     

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.