Magnetic field enhanced radio frequency ion source and its application for Siincorporation diamond-like carbon film preparation

Various ion sources are key components to prepare functional coatings,such as diamond-like carbon(DLC)films.In this article,we present our trying of surface modification on basis of Si-incorporation diamond-like carbon(Si-DLC)produced by a magnetic field enhanced radio frequency ion source,which is established to get high density plasma with the help of magnetic field.Under proper deposition process,a contact angle of 111°hydrophobic surface was achieved without any surface patterning,where nanostructure SiC grains appeared within the amorphous microstructure.The surface property was influenced by ion flow parameters as well as the resultant surface microstructure.The magnetic field enhanced radio frequency ion source developed in this paper was useful for protective film applications.     

国外最新消息

美国NRG能源公司将建造更多的核电厂美国NRG能源公司执行总裁David Crane表示,公司将拥有更多的核电厂,包括计划在得克萨斯州建造的两座机组。(编译自路透社2007年11月6日报道)     

《原子能科学技术》征稿简则

须包括题目、作者姓名、作者单位、城市名、省名和邮政编码,并应写成叙述性文摘(含有研究目的、方法、结果和结论);关键词3～8个。3)文稿应采用阿拉伯数字进行分级编号。引言不编号,也不写引言字样。4)基金项目名称及项目编号、作者简介(第1作者姓名(出生年—)、性别(民族,汉族略)、籍贯、职称、学位、从事     

国外最新消息

切尔诺贝利核电机组完成最后一次卸料工作2008年4月23日,切尔诺贝利核电厂完成了其3号机组的最后一次卸料工作。此次卸料工作的完成,意味着切尔诺贝利核电厂已完成了所有的机组卸料工作。(编译自世界核新闻网站2008年4月24日报道)     

国际原子能机构成员国

1957年阿富汗、阿尔巴尼亚、阿根廷、澳大利亚、奥地利、白俄罗斯、巴西、保加利亚、加拿大、古巴、丹麦、多米尼加共和国、埃及、萨尔瓦多、埃塞俄比亚、法国、德国、希腊、危地马拉、海地、罗马教廷、匈牙利、冰岛、印度、印度尼西亚、以色列、意大利、日本、大韩民国、摩纳哥、摩洛哥、缅甸、荷兰、新西兰、挪威、巴基斯坦、巴拉圭、秘鲁、波兰、葡萄牙、罗马尼亚、俄罗斯联邦、塞尔维亚和黑山、南非、西班牙、斯里兰卡、瑞典、瑞士、泰国、突尼斯、土耳其、乌克兰、英国、美国、委内瑞拉、越南1958年比利时、厄瓜多尔、芬兰、伊朗伊斯兰共和国、卢森堡、墨西哥、菲律宾、苏丹     

茜素红的辐射降解研究

用60Co γ射线辐照茜素红水溶液,研究该染料的辐射降解特性.通过对辐照前后茜素红的紫外可见光谱、脱色率、总有机碳(Total organic carbon,TOC)去除率的研究.探讨了吸收剂量、初始浓度、溶液pH值、H2O2加入量、在不同气体饱和条件下对茜素红溶液降解和矿化效果的影响.结果表明,辐射技术能有效降解茜素红染料,在空气饱和双氧水浓度为4mmol/L的条件下,吸收剂量为7.5kGy时,茜素红脱色率可达98%,TOC去除率可达70%.     

前言

由中国文物保护技术协会释光与电子自旋共振测定年代专业委员会(挂靠在上海博物馆)和中国国家地震局地质研究所共同主办的全国第十次释光(Luminescence)与电子自旋共振(ESR)测定年代学术讨论会于2006年11月6-10日在杭州的浙江省地震局培训中心召开.来自内地和香港的大学、中国科学院及部委研究所和文博系统32个单位的专家、学者出席了讨论会.这次讨论会共有27篇论文在会上作了交流,内容涉及热释光(TL)、光释光(OSL)和电子自旋共振测定年代的理论、方法和技术;考古和地质样品年代的测定及其应用;陶瓷器古剂量的测定;释光特性与矿藏成因;热释光、光释光测量仪器研制和改进等.本选编辑录了其中13篇论文予以发表.     

一株耐辐射菌的分离与初步鉴定

对新疆古尔班通古特沙漠土样中分离到的一株耐辐射菌RL2进行了多相分类鉴定.结果发现,此菌为革兰氏阳性,球形,菌落为淡红色;菌株的(G C)mol%含量为71.62%;16S rDNA序列分析表明,菌株RL2的16S rDNA基因序列与D.radiodurans DSM20539T同源性最高(97.2%).通过表型及系统进化树分析,确定RL2菌种分类应归于Deinococcus菌属,并可能是该菌属中的-个新种.     

Activated persulfate by DBD plasma and activated carbon for the degradation of acid orange Ⅱ

In this study, the effect of activated peroxydisulfate(PDS) by dielectric barrier discharge(DBD) plasma and activated carbon(HGAC) on the removal of acid orange Ⅱ(AOⅡ) was investigated. The effects of applied voltage, PDS dosage, HGAC dosage, initial pH value, and inorganic anions on the removal rate of AOⅡ were discussed. The main free radicals degrading azo dyes during the experiment were also studied. Experimental results show that the removal rate of AOⅡ in DBD/HGAC/PDS synergistic system is much higher than that in the single system. With the applied voltage of 16 kV, HGAC dosage of 1 g l-1, PDS and AOⅡ molar ratio of 200:1, initial pH value of 5.4 and concentration of AOⅡ solution of 20 mg l-1, the removal rate of AOⅡ reached 97.6% in DBD/HGAC/PDS process after 28 min of reaction.Acidic and neutral conditions are beneficial for AOⅡ removal. Sulfate and hydroxyl radicals play an important role in the removal of AOⅡ. Inorganic anions are not conducive to the removal of AOⅡ.     

反应堆核加热冷启动压力控制及超压问题仿真分析

基于反应堆核加热冷启动过程操纵和控制要求,开展了反应堆核加热冷启动过程压力自动控制方法研究,完成了系统压力自动控制方法设计与控制仿真验证;同时对冷启动水密实状态的超压问题进行了仿真分析,提出了防止超压事故的联锁控制方法。结果表明,当核功率不超过一定功率水平时,压力自动控制方法可实现反应堆核加热冷启动过程系统压力的有效控制。      

基于顺序控制技术的反应堆自动启动系统

在深入分析反应堆启动过程各项技术操作的基础上,提出利用顺序控制技术实现反应堆自动启动的构想.对基于顺序控制技术的反应堆自动启动系统的设计思路、层次结构、系统组成和系统设计的关键技术进行了研究,并初步进行了系统设计.所设计的顺序控制系统能够实现反应堆的自动启动,减轻运行人员工作负担,从而提高了反应堆启动运行的安全性和经济性.     

Experimental simulation study on start-up of the 5 MW nuclear heating reactor

An experimental simulation study on the start-up of a low temperature, natural circulation nuclear heating reactor (5 MW developed by the Institute of Nuclear Energy of Tsinghua University, Beijing) is presented. The experiment was performed on the test loop (HRTL-5), which simulates the geometry and system design of the 5 MW reactor. The manifestation of different kinds of two-phase flow instability, namely geysering, flashing instability and low steam quality density wave instability on the start-up are described. The mechanism of flashing instability, which has never been well studied in this field, is especially interpreted. Based on the study of these instabilities, it is suggested that the start-up process, from initial condition to boiling operation condition, should consist of three steps: increasing of initial pressure by means of a noncondensable gas (N₂), start-up of the reactor at this pressurized condition (single-phase regime operation), and transition to a lower pressure, boiling operation. Three transition methods are discussed. As a result of these studies, the method of transition with low heat flux and low inlet subcooling is proposed. A stable start-up process of the 5MW reactor is achieved by careful selection of the thermohydraulic parameters.     

CPR1000核电厂反应堆功率标定系统设计及验证

简要介绍CPR1000核电厂反应堆功率标定系统的运算原理、系统结构、验证过程及结果。采用IAPWS-IF97水和蒸汽物性模型、焓差-热功率原理计算核电厂核蒸汽供应系统热功率与反应堆核功率。该套系统于岭澳核电站3号机组调试启动中成功完成了反应堆功率测量系统、控制系统的实态标定。实际应用表明功率标定系统能够可靠地完成CPR1000核电厂堆芯功率标定。     

The dynamic simulation of cold start-up based on two-group point reactor model

A two-group point reactor model has been used to simulate the cold start-up of a small pressurized-water reactor. When compared with the results of a three-dimensional computation model, the simulation results obtained with this method show that the method is suitable for the prediction of the power variations, variations of coolant average temperature and fuel temperature when a small pressurized-water reactor starts up in a cold state is of interest. It is also shown that the method is conservative for safety analysis of reactor cold start-up, even though it requires a shorter computing time.     

核供热堆不凝结气体排放份额试验研究

叙述了核供热堆上空腔不凝结气体在发生排放事故工况下排放特性的试验研究。试验模拟了核供热堆排放工况的主要参数，着重研究了在排放过程中的氮气排放份额，及氮气对排放背压的影响。本试验是在５ＭＷ核供热堆热工水力学试验回路（ＨＲＴＬ－５）和排放回路上进行的，系统压力为１．５ＭＰａ，初始氮气分压为０．３４ＭＰａ。采用静态校验法，成功地获得了氮气的排放份额。这些试验数据为核供热堆的安全分析提供了重要的试验数据。     

AP1000机组首次临界试验验证计算

首次临界试验是压水堆核电厂调试启动过程的关键环节,旨在确认核反应堆堆芯能按照设计要求达到预期的临界运行状态。本文利用西安交通大学自主研发的NECP-Bamboo程序系统对AP1000机组堆芯的首次临界试验的设计结果进行了验证计算,并与AP1000堆芯的核设计结果进行了比较。计算结果表明：预估临界状态下的硼浓度的偏差为-15 ppm,控制棒积分价值的最大偏差为-52 pcm,硼微分价值的偏差不超过0.2 pcm/ppm,反应性温度系数的偏差不超过1 pcm/K。本文计算结果的精度与高保真计算程序KENO（概率论方法）和VERA（确定论方法）的计算精度相当,为确保AP1000堆芯调试启动阶段的核安全提供了进一步的数据支撑。     

Analytic method study of point-reactor kinetic equation when cold start-up

The reactor cold start-up is a process of inserting reactivity by lifting control rod discontinuously. Inserting too much reactivity will cause short-period and may cause an overpressure accident in the primary loop. It is therefore very important to understand the rule of neutron density variation and to find out the relationships among the speed of lifting control rod, and the duration and speed of neutron density response. It is also helpful for the operators to grasp the rule in order to avoid a start-up accident. This paper starts with one-group delayed neutron point-reactor kinetics equations and provides their analytic solution when reactivity is introduced by lifting control rods discontinuously. The analytic expression is validated by comparison with practical data. It is shown that the analytic solution agrees well with numerical solution. Using this analytical solution, the relationships among neutron density response with the speed of lifting control rod and its duration are also studied. By comparing the results with those under the condition of step inserted reactivity, useful conclusions are drawn.     

泳池式反应堆自启停控制技术研究

反应堆实现自动启停,可以有效减轻运行人员工作强度,减少误操作,提高反应堆启动运行的安全可靠性。本文基于对典型泳池式反应堆的工艺特点以及启动操作的分析,对泳池式反应堆自启停系统的控制范围、层次结构、断点、典型控制逻辑进行研究,并搭建泳池式反应堆自启停的仿真测试系统。该自启停系统能够实现泳池式反应堆的自动启停,启停过程无人工操作,降低人员误操作可能性。      

反应堆物理启动提棒外推临界修正方法

反应堆物理启动提棒外推临界时,外推临界曲线常出现外凸现象。若按此曲线外推,将导致超临界。本文分析了出现这种现象的原因,引入一种外推临界修正方法,并进行了实例计算。与实际反应堆物理启动参数进行的比较表明：此方法较好地改善了曲线外凸现象,按修正后的曲线进行临界外推,可降低反应堆启动期间出现超临界现象的风险。