基于BIXS方法的气体中高浓度氚在线测量技术

工艺气体中高浓度氚的在线测量要求探测器具有体积小、密封性好、稳定性高等特点。针对该需求,本工作基于氚β射线诱发X射线谱测量方法(BIXS)建立了高浓度氚在线测量实验系统,采用PENELOPE程序建立了理论计算模型,对系统中5个关键参数进行了设计优化,搭建了1.77 mL小体积BIXS实验系统,使用含氚的氢氩混合气体对实验系统进行了响应能谱测量,并对获得的BIXS能谱谱形进行了初步分析。实验结果表明,对于含氚的氢氩混合气体,BIXS系统重复测量结果显示全谱计数率偏差<0.8%,Ar的Kα峰计数率偏差<1.3%,Au的Mα峰偏差<3.8%,整体稳定性较好;不同压强下BIXS实验系统测量结果显示,BIXS能谱总计数率、Ar的Kα峰强度以及轫致辐射谱强度随压强增加呈线性上升趋势,但Au的Mα峰强度在该气氛下几乎不随氚的分压改变。     

加速器氚靶膜厚误差对BIXS方法反演的影响

BIXS(β-ray induced X-ray spectrometry)方法是一种氚β衰变诱发X射线谱的氚无损分析技术,在反演过程中会受到诸多因素的影响,氚靶膜厚误差的影响不可忽略。本文基于蒙特卡罗方法程序PENELOPE模拟和实验验证研究,表明加速器氚靶膜厚误差会对BIXS方法反演有一定的影响,其中对递增分布的影响最大,对递减分布的影响最小;氚在靶膜中的深度分布的斜率越大,膜厚误差对BIXS方法反演的影响也越大。     

利用伴随α粒子能谱分析固体氚靶中氚浓度深度分布

在目前的氘氚中子发生器源中子分析过程中,固体氚靶中氚浓度深度分布信息的缺失是普遍遇到的问题。为解决此问题,本文建立了利用伴随粒子能谱反演氚浓度深度分布的模型,采用来自氚钛靶的α实验能谱作为模型测试对象,通过该模型获得了氚钛靶中氚浓度深度分布的数据。结果表明,氚浓度随氚钛靶深度的增加呈双峰趋势,两峰之间的氚浓度波谷位于靶中0.94 μm处,该深度正是入射氘粒子的射程极限。所得的氚浓度深度分布趋势与其他实验方法测量结果相符,表明该模型能为氘氚中子发生器的源中子分析提供即时的氚浓度深度分布信息。     

氧化层厚度对氘氚中子产额影响研究

对氚化钛膜表面氧化层厚度对氘氚中子产额的影响进行了理论与实验研究.理论计算表明,能量为120keV的氘核入射氚化钛膜的深度为833 nm,入射钛氧化层的深度为527-577 nm.实验结果表明,氧化层降低了氘氚反应的中子产额,且中子产额随氧化层厚度的增加而减小,氧化层厚度低于220nm,中子产额与氧化层厚度的线性关系为Y=(7.524-0.01326X)×106.     

氚深度分布对β射线诱发X射线光谱法测量能谱中Ar(Kα)强度的影响

BIXS(β射线诱发X射线光谱法)是一种针对材料中氚的无损测量方法,该方法通过探测氚在材料与工作气体(氩气)中诱发的特征X射线与轫致辐射X射线谱计算材料表层(β射线射程范围内)与基体中的氚含量与分布。通常认为氩的Kα特征峰强度与材料表层氚含量呈正比,然而该结论的前提是氚在材料表层均匀分布,而未考虑非均匀分布的情形。本文详细评估了氚在材料表层的深度分布对BIXS能谱中Ar(Kα)强度的影响,结果表明,在均匀分布的情况下,β射线最大射程的1/10范围内的氚对Ar(Kα)强度的贡献约为50%;在非均匀分布的情况下,Ar(Kα)的强度与均匀分布有数倍的差异。因此在实际测量中需根据氚在材料表层的具体分布对结果进行修正。     

基于BIXS方法的高浓度气态氚探测器设计

近年来,氚的监测在确保反应堆的安全运行、工作人员的健康安全有着重要作用,特别是对以氚为核燃料的聚变反应堆。基于β射线诱发的韧致辐射X射线谱仪(BIXS)由于记忆性效应低、探测器尺寸小已逐渐成为国内外研究的热点。利用蒙特卡洛方法(MCNP)对BIXS探测器的尺寸以及材料进行了优化设计。结果表明,在0.5 MPa的工作压力下,铍窗厚度为0.1 mm、铍窗镀金层厚度为125 nm的小型BIXS测量系统可实现氚气的在线测量和探测器的小型化,其中100 s探测限为1.79×10⁸ Bq。     

含氚气体中氚分压BIX在线测量方法研究

建立了一种聚变堆氘氚燃料循环系统燃料气及工艺气等含氚混合气体中氚分压在线快速测量方法,该方法通过测量氚衰变产生的β射线与材料相互作用发射的轫致X射线（BIX）,利用轫致X射线的计数率与含氚气体氚分压的标定关系曲线,实现含氚气体中氚分压（活度浓度）的实时测量。该方法中的轫致X射线是通过β射线与表面喷金的铍窗材料作用而产生的,X射线的测量采用NaI(Tl)探测器。研究过程中建立了轫致X射线计数率与氚分压的标定关系曲线,对于纯氚气体,氚压测量范围为1 Pa~10 kPa（氚活度浓度为10¹²~10¹⁵ Bq/m³）时,计数率（C）与氚压（p）的标定曲线为C=5.01×10⁴（1-e^-4.55×10-5p）,其指数拟合相关系数为1.000 00。对于氚体积分数为1%的氚-氦混合气体,氚分压测量范围为1~100 Pa（氚活度浓度为10¹¹~10¹⁴ Bq/m³）时,计数率与氚分压的标定曲线为C=5.24×10²(1-e^-4.69×10-3p),其指数拟合相关系数为0.998 60。对于氚体积分数为1%的氚 氢混合气体,氚分压测量范围为1~100 Pa（10¹¹~10¹⁴ Bq/m³）时,计数率与氚分压的标定曲线为C=5.18×10²(1-e^-4.61×10-3p),其指数拟合相关系数为0.999 53。利用以上标定曲线,对任意氚分压的含氚混合气体进行验证测量,结果表明,该方法测量精度较高、响应速度快、测量稳定性好,在氚测量技术中是一种很有前景的方法。     

离子注入法制备超薄氚源

叙述了一种用于中微子静止质量测量的大面积高活度氚源的离子注入制备过程。氚注入在微晶玻璃基板上的碳膜中，由此获得窄条形（０．２ｍｍ宽）、大面积（４０×３０ｍｍ２）、高活度（约２０ＭＢｑ／ｃｍ２）、氚分布均匀（９５％）、氖注入厚度为２μｇ／ｃｍ２、氚的逃逸速度≤４×１０２Ｂｑ／ｈ的氚源。     

氚衰变对氚化钛结构影响的XRD分析

氚自然衰变生成3He,3He的聚集会引起贮氚材料物理和化学性质的明显变化。本文以氚化钛为研究对象,运用XRD研究其晶体结构在贮存初期的演化规律,对氦在氚化钛贮存初期的时效行为进行了研究。结果表明:氚化钛特征峰的宽化是由氚衰变生成的3He累积所引起,氚化钛晶体结构保持fcc结构不变。     

氚钛片辐照硅基半导体器件电学输出性能

制备了多个不同厚度金属钛膜吸附不同量^3H的氚钛片,利用这些源片辐照硅基半导体器件,测试并分析了它们的电学输出性能。结果表明,这些氚钛片辐照硅基半导体器件可以输出电流,但由于金属钛对氚源β射线的阻挡,器件输出电流和最大输出功率与钛膜中贮氚量不呈正比增长关系,小的钛膜厚度有利于提高β射线能量利用率。     

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.