钯合金膜分离器级联氢同位素分离研究

提出了一种基于钯合金膜分离器串联(PMSCS)的氢同位素分离系统的初步设计,建立了评估该分离方法分离效果的数学模型,根据此模型和前期关于分离器分离系数的测定结果,估算了多级氢同位素分离系统分离级数与分离产品气、尾气中氘和氕之间的关系.结果表明,分离系统所串联的分离级数量越大分离效果越好.对于一个5级串联分离系统(单级分离器分离系数q=1.8),当以50%H-50%D混合气体为原料气时,若产品气的提取比例为40%,产品气中的D含量将达到约92%,产品气得到了充分富集;若尾气的提取比例为40%,尾气中的氢含量将达到约99.95%,尾气中的氘得到了充分的贫化.与低温蒸馏、热循环吸附分离和钯合金膜分离器级联分离比较,钯合金膜分离器串联系统具有结构简单、氚的贮留量小等优点,适用于氢同位素混合气体的分批次操作分离.     

吸附温度低于273 K的Pd/k柱TCAP全回流实验研究

为满足实验室规模的氢同位素分离需求,对少量氚（小于3.7×10¹³ Bq）的高效氢同位素分离方法进行了研究。采用TCAP全回流工艺,将钯/硅藻土（Pd/k）填充色谱柱（长2 m,外径6 mm）吸附H-D混合气体（D丰度为50%）的温度控制在273 K以下,经多次加热 冷却循环后,从分离柱前、后两端加热各提取15%样品气,利用低温色谱法对样品气进行氢同位素丰度分析,对色谱柱的分离性能进行评价。研究结果发现,原料气进入填充柱后（全回流之前）尾端提取气的氘丰度约为98.5%,经5个全回流循环（循环总时间为1.25 h）后,尾端提取气的氘丰度达99.9%。经15个全回流循环后,前端提取气的氘丰度由50%（原料气氘丰度）降至13.6%。通过实验数据对柱中氘分布进行了理论模拟,发现进样速率过快可能是导致前端提取气氘丰度过高的主要原因,柱中氘丰度最低点可能出现在色谱柱的中部。     

基于氢同位素研究商用钯银合金膜的渗氚性能

钯银合金膜可用于熔盐堆尾气中气态氚（HT和T₂）的分离与纯化。本文研究了厚度为80 μm的钯银合金膜在纯H₂气氛中及Ar气存在下对H₂的分离效果。结果表明,渗氢过程中氢原子在膜内部的体相扩散是控制速率的关键。Ar气存在时,在钯银合金膜工作温度为480 ℃、混合气体进气流速为100 mL/min、氢分压差为20～100 kPa的条件下,钯银合金膜对H₂气的渗透通量随氢分压差的增大而增加,随Ar气浓度的升高而减小。在氢分压差相同的条件下,纯氢的渗透通量明显高于Ar-H₂混合气的渗透通量,说明钯银合金膜受Ar气的影响分离效果变差。渗氢后的钯银合金膜表面变得光滑,有晶界形成。     

蜜胺树脂柱色谱法从模拟高放废液中回收钯的研究

研究了在１ｍｏｌ／ｌＨＮＯ３介质中用蜜胺树脂柱色谱法从模拟高放废液中回收钯。结果表明，蜜胺树脂柱色谱法能有效地分离钯，涓附容量可达５０－７０ｍｇ／ｇ；吸附的钯可用３％硫脲溶液解吸，蜜胺树脂有抗辐照性能。本方法在高放废液及贵金属提取工艺中分离回收钯等方面有应用前景。     

氦中痕量杂质气体气相色谱检测分析方法研究

为实现聚变堆氘氚燃料工艺气中痕量杂质气体组分的快速检测分析,需建立特殊的高精度在线气相色谱检测分析方法。以高纯氦作为载气,在不同的色谱柱温度和载气流速控制下,通过分子筛毛细管柱和PLOT-Q柱进行分离,采用放电氦离子化检测器（DID）进行检测,对氦中含量为1、10以及100 ppm的杂质标准气体进行检测分析。结果表明：在柱温为40 ℃、流速为15～20 mL/min实验条件下,分子筛柱在160 s内能够实现H₂、O₂、N₂、CH₄和CO全部分离,且柱效较高,响应值的重复性较好,H₂和O₂之间的分离度高于1.5,实现了完全分离;在柱温为40 ℃、流速为20 mL/min时,PLOT-Q柱分离CO₂组分效果最佳。     

热循环吸附法分离氕、氘的研究

对热循环吸附法(TCAP)全回流模式和生产模式下的氕 氘分离实验进行了研究。全回流模式下,主要考核了初始进料比、冷/热循环温度、进料位置对分离效果的影响。结果表明,原料气体从分离柱中部进料时,初始进料比相对越大,冷/热循环温差越大,分离效果越好;而从回流柱进料时,分离效果相对更好。在几组实验中,回流柱初始进料为90%、冷/热循环温度分别为56 ℃/290 ℃的一组效果最好。生产模式下,由于分离柱中气阻较大,有可能影响氕、氘的分离效果,这部分实验还有待继续进行。     

氘氚燃料气体氕纯化系统设计及工艺初探

在惯性约束聚变氘氚冷冻靶制备中,对氘氚原料气中氕含量有严格限制。为控制少量燃料中氕含量,有必要开展相关氢同位素分离研究及工程研制。根据热循环吸附(Thermal Cycling Absorption Process,TCAP)原理及前期冷实验数据,研制了一套小型纯化热实验系统。系统内配置了一根长2 m、外径6.4 mm的钯/硅藻土填充柱用于对氕的过滤。按照纯化工艺设计,占总吸附量10%的原料气从填充柱一端输入,经过一次加热冷却循环后从柱另一端输出,氕在色谱柱内累积,进而实现原料气的纯化。经过纯化工艺初步探索,连续输入33次原料气后,柱内氕含量由12%累积到了52%,产品气中氕含量由12%降至3%,氘氚燃料回收率为82.5%,实现了柱内氕的有效富集,以及氘氚气体中氕的有效过滤。     

钯-氢体系中氢氘的排代研究

研究了一维排代条件下,Pd-H体系中气-固相间氢-氚的相互排代性能。实验结果表明：对于较细的钯颗粒（≈0.15mm),室温（≈22℃）下气体线流速在2.0～8.5cm/s范围内具有较理想的排代效果,表现反应速率主要取决于气-固界面的化学速率;在22～75℃范围内,温度对排代效果的影响较小,当温度降至10℃时,氢氚在固相内的扩散速率较小,排代效果显著变差。     

氘气中氢同位素的低温气相色谱法测定

针对高纯氘气中H₂、HD与D₂等氢同位素气体间不易分离分析的特点,以5A分子筛微填充石英毛细管色谱柱,在－95℃下对氢同位素进行分离,以气相色谱-脉冲放电氦离子化检测器对氢同位素进行分析。研究建立的H₂、HD与D₂等同位素气体测定方法精密度小于15%,最小检出摩尔分数为1×10^－6。     

用于氢同位素分离的置换色谱分离材料的研究进展

置换色谱法是一种较有优势的氢同位素分离方法,而分离材料的性能是决定置换色谱法分离效果的一个关键因素。目前研究的置换色谱分离材料包括钯材料和很多非钯材料。钯虽然价格昂贵,但由于其出色的分离性能而难以用廉价金属或合金来替代。本文简要介绍了置换色谱法分离氢同位素的原理,重点介绍了几种置换色谱含钯分离材料(纯钯、载钯硅藻土、载钯氧化铝、钯铂合金等)的性能,初步分析了置换色谱分离材料的发展方向。     

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.