DQ—2型气载放射性碘采样的研制

本文主要介绍了DQ－2型气载放射性碘采样器的结构特点和技术性能的测试结果。粒子碘单元采用直径60mm的高效过滤膜，气态碘单元采用2级以粒径60－80目，厚度为2cm的浸渍椰 壳活性炭为吸附剂的活性炭盒采样。结果表明：1）气密性好，气态碘单元未见可检出的泄漏，粒子碘单元的泄漏率小于0．1％；2）阻力较小，在8.0m^3/h的流量下，采样器的总阻力为30kPa;3）效率高，对粒子碘的采样效率可达99．9％，甲基碘的吸附效率随采样流量和相对湿度的增加而下降，当流量为3.0m^3/h，相对湿度低于40％，炭层厚度为2cm时，对甲基碘的吸附效率达到99．997％，可用于碘吸附器的除碘效率试验；4）采样器在80℃下仍可使用；在高相对湿度（95％）时，推荐的采样流量为不超过3m^3/h。     

活性炭捕集放射性碘的实验研究

采用日立公司制造的TA-1专门设备,研究了5种不同粒度AC活性炭(颗粒活性炭)和两种不同结构的ACF活性炭(纤维活性炭)对甲基碘的吸附效率及它们的阻力,探讨了相对湿度、面速度、浸渍量对活性炭吸附甲基碘效率的影响。     

预吸附甲基碘的TEDA浸渍活性炭解吸规律初探

对于预吸附甲基碘的TEDA浸渍活性炭(碘炭)滞留碘能力进行了研究。探讨了气体流速、水浸时间、温度以及K+加入量等参数对预吸附甲基碘的TEDA浸渍活性炭的滞留碘能力的影响。结果表明:当氮气流速从0.1 m3/h增加至1.5 m3/h时,碘炭解吸的甲基碘增加了3.15倍;当水浸时间仅为0.5 h时,就发现了甲基碘的解吸;在此后测量的几个时间点(1.5 h、2 h、3 h、4 h),甲基碘的解吸量未发生明显变化;温度对甲基碘的影响不明显,在80℃以内的温度范围内,未发现甲基碘的解吸;钾离子的加入可降低碘的解吸,40 g碘炭中,当KCl的加入量为0.06 g时,解吸的甲基碘量仅为未加入KCl时所解吸的甲基碘量的56%。     

聚合物疏水改性多孔材料在高湿环境下吸附放射性气态碘

在高湿环境下去除放射性气态碘时,较高的湿度会对活性炭吸附碘效率产生严重影响。以聚二乙烯基苯（PDVB）为疏水改性剂,采用简单的液相浸渍法对不同种类的活性炭进行疏水改性。通过表征活性炭孔隙结构、表面疏水性能和碘吸附法探究了其在高湿环境下对气态碘的吸附性能和改性机理。结果表明：PDVB本身具有多孔结构且疏水性优异,浸渍改性后,PDVB多孔纳米粒子可以进入材料孔隙结构中改善活性炭的多孔结构性能,增强比表面积和微孔容积,进而有效提升材料对碘的吸附容量。此外,在相对湿度（RH）为96%的高湿度环境进行碘吸附性能测试,由于PDVB疏水改性后疏水性增强,减弱了对水分子的亲和力,降低了水分子竞争吸附的影响,使得其在高湿环境下也具有较好的适用性。还发现该改性方法对其他无机多孔材料的疏水改性也有应用潜力。     

区分气载放射性碘的选择性吸附剂吸附性能的研究

本文研究了用于区分三种气载放射性碘的选择性吸附剂的吸附性能。由3层高效玻璃纤维滤纸、3cm 厚5%CdI_2浸渍的6201型惰性担体和两段3cm 厚5%TEDA 浸渍的椰壳活性炭组成的取样器,可以选择性区分气溶胶态、气态单质和甲基碘态的放射性碘。     

PMS-500 可吸入颗粒物采样器的研制和性能测试

研制了用于环境中可吸入颗粒物(PM10)采样的 PMS-500 采样器.采样器运行流量为560 m3/h,采用变频技术控制流量稳定,用聚丙烯纤维滤材作为PM10的收集介质.设计了一种矩形喷嘴撞击器作为PM10切割器,撞击器的收集介质为容尘量较大的聚氨酯泡沫.对采样器的性能测试结果为切割器的切割粒径为9.9 μm,捕集效率曲线的几何标准偏差为1.4;采样期间流量波动在±2%之内;双层滤材对0.2 μm气溶胶的收集效率不小于99%.采样器可方便地拆分为三部分,机动性较好.本采样器与市售大流量PM10采样器的采样效率相当,其性能可以满足环保行业对PM10采样的要求.     

环己烷在碘吸附器活性炭床上的解吸行为研究

对环己烷气体在碘吸附器用浸渍活性炭上的动态解吸行为进行了实验研究。考察了不同的载气温度、相对湿度、流速、炭床厚度以及进气中环己烷浓度对环己烷在活性炭床上解吸行为的影响,为环己烷试验方法在碘吸附器现场泄漏率试验的研究及推广提供了一定的理论支撑。试验结果表明:(1)在40 ℃,30%相对湿度条件下环己烷在活性炭床上可滞留约500 min,增大气流温度、湿度、浓度和载气流速可以减少滞留时间,其中温度对滞留时间的影响最为显著。(2)在气流相对湿度为80%时,浓度为100 ppm(10^-6)的环己烷在活性炭床上的滞留时间仍达到90 min,这有利于高湿度条件下进行碘吸附器泄漏率试验。     

DQ—01型碘取样器的性能试验

本文报道了一种用于核设施周围环境和工作场所气载放射性碘监测的 DQ—01型碘取样器的性能试验结果。试验测定了采样流量、相对湿度及温度等因素对该取样器捕集放射性碘的效率的影响。试验结果表明,在环境温度和相对湿度小于95%下,即使取样流速高达1061 cm/s,床深6 cm 的取样器对甲基碘的捕集效率也大于95%。     

载银丝光沸石和载银氧化铝对气态碘的吸附研究

针对核设施产生的高湿度、高氮氧化物含碘气体设计一套动态吸附装置，制备了用于吸附气态碘的载银丝光沸石和载银氧化铝，通过改变吸附剂载银量及碘蒸汽的浓度，研究载银丝光沸石和载银氧化铝对气态碘的吸附性能。实验结果表明:实验温度为30℃，相对湿度为100%，NO₂体积含量为0.1%条件下，载银量15.2%的丝光沸石对碘的饱和吸附容量为178.4 mg/g，载银丝光沸石对气态碘的吸附效果优于载银氧化铝；载银丝光沸石和载银氧化铝对气态碘的吸附是一个以化学吸附为主又包括物理吸附的复杂过程。关键词:载银丝光沸石；载银氧化铝；气态碘；动态吸附      

碘吸附器泄漏率检测的方法与影响因素探讨

探讨了用于检验碘吸附器机械泄漏率的几种示踪气体的可行性,包括三氯氟甲烷(R-11)、十氟戊烷(Vertrel-XF)、全氟甲基环戊烷(PMCP)、全氟甲基环己烷(PMCH)及全氟二甲基环己烷(PDCH);在检验碘吸附器泄漏率现场试验期间,分析了示踪剂的分子量和沸点、温度、气流比速、湿度及活性炭含水量等影响因素对示踪气体发生解吸的影响;以R-11为示踪剂分别进行不同湿度环境下碘吸附器机械泄漏率的验证试验和不同含水量活性炭的吸附效率实验;结果表明:Vertrel-XF、PMCP、PMCH和PDCH均满足美国机械工程师协会核空气与气体处理规范(ASME AG-1)中关于替代物的六项标准;气流相对湿度小于20%,活性炭含水量小于15%时,R-11在活性炭上的解吸量很少,因此检测结果更加接近真实值;目前,国内核电厂以R-11测得碘吸附器的机械泄漏率偏结果保守。     

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.