基于变压吸附法的大气中氩室温分离方法

放射性惰性气体³⁷Ar是地下核爆炸的特征活化产物,可用于全面禁止核试验条约现场视察,为判断是否进行了可疑核爆炸提供证据。基于变压吸附原理,建立了基于LiX分子筛和4A分子筛两级变压吸附分离、结合制备色谱的空气样品中氩的室温分离纯化方法,氩回收率大于65%,氩纯度满足放射性测量要求,流程操作时间小于2h。     

~(37)Ar活度比对测量

37Ar是地下核爆确定的、明确的指示剂,目前已经被CTBTO确定为现场视察的核查核素.中国工程物理研究院核物理与化学研究所研制了适合现场视察的37Ar探测系统--移动式37Ar快速探测系统(Movable 37Ar Rapid Detection System,MARDS),该系统采用LLC方法(Low Level Decay Counting)测量37Ar的活度.目前国际上尚无37Ar活度测量的标准装置,因此开展37Ar活度比对测量是一项很有必要的工作.本文介绍了我所(中国工程物理研究院核物理与化学研究所,INPC)与瑞士伯尔尼大学大气与环境物理研究所(KUP)开展的37Ar活度比对测量工作.比对测量的结果说明MARDS测量37Ar活度的方法和结果有很高的可信度,为MARDS系统应用于现场视察提供了技术支持.     

放射性气体37Ar监测方法与系统发展现状概述

³⁷Ar属于地下核爆炸特征活化产物，是全面禁止核试验条约组织(CTBTO)规定的核爆试验现场视察的核查核素，因此对采集的³⁷Ar气体活度浓度进行精准的现场或实验室测量尤为关键。对³⁷Ar的特性、取样纯化技术与活度测量方法进行搜集整理，归纳了国内外现场或实验室测量的先进装置与技术现状，为³⁷Ar活度浓度相关监测等应用领域提供技术支撑。     

现场视察Xe的分离测量技术

根据全面禁止核试验条约组织临时技术秘书处(PTS)对放射性核素Xe的现场视察技术要求,开展了现场视察Xe的取样分离测量技术研究,建立了Xe的分离纯化流程。流程的采样量为10m3,Xe的提取产额大于90%。采用高纯锗γ谱仪,测量24h,133Xe的最小探测浓度为0·053Bq/m3。     

低本底内充气正比计数管测量37Ar活度

³⁷Ar是全面禁止核试验条约现场视察重要监测核素之一,高灵敏地探测³⁷Ar活度是地下核试验监测的关键环节。本文研究建立了低本底内充气正比计数管³⁷Ar活度测量装置,在铅屏蔽室上、下各装配1个塑料闪烁体探测器,主动屏蔽宇宙射线在计数管中产生的本底。相对于原始能谱,反宇宙射线能谱中³⁷Ar峰区本底计数率降至原来的7.3%,测量24 h,³⁷Ar的最小可探测活度达2.5 mBq。     

基于常温吸附的放射性氙样品高效纯化制备技术研究

大气放射性氙是全面禁止核试验条约重要的监测目标,为提高氙样品的探测灵敏度,在进行放射性活度测量前,需将样品纯化、除氡并转移至测量容器。本文针对氙样品高效纯化制备过程中的关键技术,研究了氙在三级吸附柱上的吸附脱附行为,并考察了氙样品量及色谱参数对氙色谱峰宽的影响,确定了纯化制备流程参数。利用氙样品对纯化制备流程进行测试,氙的回收率大于90%,氡去污因子大于10⁴,实现了放射性氙样品的高效纯化制备。     

地下核试验的现场调查

为了搜寻地下核试验的证据,必须开展现场调查(on一site Inspection—051),在051工作中,地球化学和地球物理勘查方法得到有效应用。 地球化学勘查方法主要是确定核裂变产生的核素在土壤中存在的情况。Xe和Ar是2个主要核裂变产物,即使核试验在地下很深处进行,裂变产物都会向地表土壤扩散、迁移。应用高灵敏Ge探测器可测量其在土壤中的含量变化。 地球物理勘查方法,如共振地震、磁测、重力、地质雷达和电磁等,用来探测核试验引起的岩石空洞和裂隙等。地下核试验的现场调查@张淼     

^37Ar测量系统的本底降低技术

从放射性本底来源分析了37Ar测量系统的本底组成,采用MCNP程序对改进前及拟改进的屏蔽体的屏蔽效果进行了模拟计算.考虑到本系统的使用场景,重点对屏蔽体结构进行优化设计,并完成了加工,对改进后的测量系统进行了本底测量实验.实验结果表明:改进后,测量系统的本底降低到改进前的75%,并与理论计算结果相一致,进一步提高了37Ar的探测灵敏度.     

用内充气正比计数管准确测量~(131)Xe~m活度浓度

~(131)Xe~m、~(133)Xe~m、~(133)Xe和~(135)Xe是全面禁止核试验条约(Comprehensive Nuclear-Test-Ban Treaty,CTBT)监测地下核试验最重要的核素。氙同位素活度通常采用HPGeγ能谱法和β-γ符合法等相对方法测量,准确刻度测量系统的探测效率是氙同位素活度准确测量的关键。本文介绍了用内充气正比计数管系统通过长度补偿法准确测量~(131)Xe~m活度浓度的方法,~(131)Xe~m活度浓度测量结果为(1.75±0.01)Bq·mL~(–1),为相对测量系统的探测效率刻度提供了活度标准。     

放射性惰性气体分离与分离材料研究进展

放射性惰性气体氙(¹³³Xe)、氪(⁸⁵Kr)与氩(³⁷Ar)是重要的气体裂变产物,主要产生于核电站反应堆、地下核试验、乏燃料后处理等人类核活动中。放射性惰性气体的快速高效分离、分析与检测在核军控核查、核环境监控、核燃料循环等领域中均有重要意义。利用固体多孔吸附材料在室温环境下从复杂环境气氛中选择性地将目标放射性惰性气体高效吸附分离出来是目前最简单与高效的方法。近些年发展的金属有机框架材料、多孔有机框架材料、多孔有机聚合物等新型多孔材料在惰性气体Xe与Kr的分离上已经展现出优异的性能与良好的应用前景。本文系统性地综述了放射性惰性气体(Xe、Kr、Ar)分离与分离材料的研究进展,并对未来研究趋势进行了展望。     

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.