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     

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.     

《核科学与工程》征稿简则

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Geant4 simulation of 238U(n,f) reaction induced by D-T neutron source

Knowledge of actinides(n,f) fission process induced by neutron is of importance in the field of nuclear power and nuclear engineering,especially for reactor applications.In this work,fission characteristics of~(238)U(n,f) reaction induced by D-T neutron source were simulated with Geant4 code from multiple perspectives,including the fission production yields,total nubar,kinetic energy distribution,fission neutron spectrum and cumulative γ-ray spectrum of the fission products.The simulation results agree well with the experimental nuclear reaction data(EXFOR) and evaluated nuclear data(ENDF).Mainly,this work was to examine the rationality of the parametric nuclear fission model in Geant4 and to direct our future experimental measurements for the cumulative fission yields of ~(238)U(n,f) reaction.     

Prompt fission neutron multiplicity and spectrum evaluations for n+238U reaction

The prompt fission neutron multiplicity and spectra for n+²³⁸U reaction are calculated using an improved Los Alamos model which includes the linear relation between the average prompt gamma ray energy and the prompt neutron multiplicity and also the average fission fragment kinetic energy dependence on the incident neutron energy. The coefficients describing the quadratic variation of the fission fragment kinetic energy versus the incident energy are obtained by extrapolation of the data and procedure used for n+²³⁵U reaction. The inverse process compound nucleus cross-section of the fissioning nucleus is calculated using the coupled channel method. In the incident energy range where only the first fission chance is involved the comparison of present spectrum evaluation with spectrum calculation using multi-modal model is made too. The calculated prompt neutron multiplicity and spectra of ²³⁸U neutron induced fission are in good agreement with the experimental data for the entire incident energy range required in evaluations, proving the validity of the used procedure.     

14.8 MeV中子诱发~(238)U裂变产物产额测量

裂变产物产额作为裂变过程的一个重要参数,其准确测量对有关裂变的很多方面都有重要意义。为了准确测量中子诱发~(238)U裂变产物产额,利用中国工程物理研究院PD-300加速器上的T(d,n)4He反应,产生14.8MeV的中子,诱发~(238)U裂变。辐照过程中,通过金硅面垒半导体探测器监测中子通量的变化。使用Al片作为监测片计算整个照射过程中样品的平均中子通量。辐照结束后,利用高纯锗(High-Purity Germanium,HPGe)探测器测得裂变产物特征γ射线计数,计算得到裂变产物的产额,使用MCNPX软件对中子的多次散射和自屏蔽效应进行修正,并通过计算得到样品和监测片的自吸收修正、中子通量波动因子。得到了95Zr、127Sb、140Ba、147Nd、131I、103Ru等长半衰期产物的累积产额值,并将结果与以前的文献值做了比对,研究结果有助于~(238)U裂变产物产额的分析和评价。     

Neutron energy dependence of delayed neutron yields and its assessments

Incident neutron energy dependence of delayed neutron yields of uranium and plutonium isotopes is investigated. A summation calculation of decay and fission yield data is employed, and the energy dependence of the latter part is considered in a phenomenological way. Our calculation systematically reproduces the energy dependence of delayed neutron yields by introducing an energy dependence of the most probable charge and the odd–even e?ect. The calculated fission yields are assessed by comparison with JENDL/FPY-2011, delayed neutron activities, and decay heats. Although the fission yields in this work are optimized to delayed neutron yields, the calculated decay heats are in good agreement with the experimental data. Comparison of the fission yields calculated in this work and JENDL/FPY-2011 gave an important insight for the evaluation of the next Japanese evaluated nuclear data library (JENDL) .     

Energy Dependence of Plutonium Fission-Product Yields

A method is developed for interpolating between and/or extrapolating from two pre-neutron-emission first-chance mass-asymmetric fission-product yield curves. Measured ²⁴⁰Pu spontaneous fission and thermal-neutron-induced fission of ²³⁹Pu fission-product yields (FPY) are extrapolated to give predictions for the energy dependence of the n + ²³⁹Pu FPY for incident neutron energies from 0 to 16 MeV. After the inclusion of corrections associated with mass-symmetric fission, prompt-neutron emission, and multi-chance fission, model calculated FPY are compared to data and the ENDF/B-VII.1 evaluation. The ability of the model to reproduce the energy dependence of the ENDF/B-VII.1 evaluation suggests that plutonium fission mass distributions are not locked in near the fission barrier region, but are instead determined by the temperature and nuclear potential-energy surface at larger deformation.     

基于贝叶斯机器学习对中子诱发235U裂变的产额-能量关系的研究

核裂变碎片产额是核能发展和核技术应用领域的重要基础数据,但在实验和理论上获得精确且完整的能量依赖的裂变产额到目前为止都非常困难。本文提出采用贝叶斯机器学习方法对所有收集到的中子诱发235U裂变产额实验数据进行了数据融合学习和评价。基于该评价方法对关键裂变碎片的产额 能量关系进行推断,并得到了二维的碎片累积产额分布随入射中子能量的变化关系。所得的二维产额分布能合理地反映裂变模式随能量增加的演化,但目前结果的不确定度较大,有待进一步改进。     

Prompt fission neutron spectrum calculations for n+238U reaction using the multi-modal model

The prompt fission neutron spectra for the neutron induced fission of ²³⁸U are calculated in the incident energy range where only the first fission chance is involved using the multi-modal fission theory. The partial spectra of each fission mode are calculated on the basis of Los Alamos model and the total spectrum is calculated by superposition of partial spectra weighted with the respective probability of occurrence. The total fission spectra obtained in this manner are in good agreement with the experimental data.     

Fission Product Data Measured at Los Alamos for Fission Spectrum and Thermal Neutrons on Pu, U, U

We describe measurements of fission product data at Los Alamos that are important for determining the number of fissions that have occurred when neutrons are incident on plutonium and uranium isotopes. The fission-spectrum measurements were made using a fission chamber designed by the National Institute for Standards and Technology (NIST) in the BIG TEN critical assembly, as part of the Inter-laboratory Liquid Metal Fast Breeder Reactor (LMFBR) Reaction Rate (ILRR) collaboration. The thermal measurements were made at Los Alamos' Omega West Reactor. A related set of measurements were made of fission-product ratios (so-called R-values) in neutron environments provided by a number of Los Alamos critical assemblies that range from having average energies causing fission of 400-600 keV (BIG TEN and the outer regions of the Flattop-25 assembly) to higher energies (1.4-1.9 MeV) in the Jezebel, and in the central regions of the Flattop-25 and Flattop-Pu, critical assemblies. From these data we determine ratios of fission product yields in different fuel and neutron environments (Q-values) and fission product yields in fission spectrum neutron environments for ⁹⁹Mo, ⁹⁵Zr, ¹³⁷Cs, ¹⁴⁰Ba, ^141,143Ce, and ¹⁴⁷Nd. Modest incident-energy dependence exists for the ¹⁴⁷Nd fission product yield; this is discussed in the context of models for fission that include thermal and dynamical effects. The fission product data agree with measurements by Maeck and other authors using mass-spectrometry methods, and with the ILRR collaboration results that used gamma spectroscopy for quantifying fission products. We note that the measurements also contradict earlier 1950s historical Los Alamos estimates by ∼5-7%, most likely owing to self-shielding corrections not made in the early thermal measurements. Our experimental results provide a confirmation of the England-Rider ENDF/B-VI evaluated fission-spectrum fission product yields that were carried over to the ENDF/B-VII.0 library, except for ⁹⁹Mo where the present results are about 4%-relative higher for neutrons incident on ²³⁹Pu and ²³⁵U. Additionally, our results illustrate the importance of representing the incident energy dependence of fission product yields over the fast neutron energy range for high-accuracy work, for example the ¹⁴⁷Nd from neutron reactions on plutonium. An upgrade to the ENDF library, for ENDF/B-VII.1, based on these and other data, is described in a companion paper to this work.     

裂变产额的Zp模型评价方法及燃耗不确定度分析

裂变产额在核科学技术和核工程中有着重要的应用,发展可靠、高效的产额评价方法和相应燃耗计算不确定度分析方法,对于建立高质量的产额数据库具有重要的意义。本文根据裂变产物核衰变模式和衰变分支比,建立独立产额与累积产额的转换矩阵,用于Zp模型的扩展,使之适用于独立产额和累积产额的统一描述,并以此建立了用于产额统一评价的拟合程序ZpFit。把ZpFit程序应用于中子诱发235U裂变产物产额评价,获得了自洽的独立产额、累积产额和相应的协方差数据,并建立ENDF格式的中子诱发235U裂变的产额数据库。在此基础上,计算了UAM燃耗基准题的TMI 1栅元的kinf、重要核素原子核密度的不确定度,比对了本工作评价的产额数据和ENDF/B Ⅷ0评价库中产额数据传递给响应量的相对不确定度,结果基本一致,差异不大。     

Estimation of 239Pu independent and cumulative fission product yields from the chain yield data using a Bayesian technique

The independent and cumulative fission product yields (FPYs) are obtained by using the Bayesian technique based on the evaluated mass chain yield, where required constraints such as the normalization can be straightforwardly included. We apply this technique to the ²³⁹Pu FPY data at neutron incident energies of 0.5, 2.0, and 14 MeV, where the most updated mass chain yield ENDF/B-VII.1 data are available. The obtained yield data are compared with the evaluated values by England and Rider in ENDF/B-VI, and differences from their values are investigated. We show that the modern decay data used, such as branching ratios to ground and metastable states, cause differences in the evaluated individual and cumulative fission yields.