Research and Development

<正>In 2017,the CIAE won 16 prizes at the province level and above,including 5 prizes for National Defense Science and Technology,10 prizes from the CNNC,one prize from the China Nuclear Energy Association,while the China Experimental     

Research and Development

正The year 2018 witnessed exciting achievements in research and development of nuclear science and technology in CIAE,covering areas including advanced nuclear energy,spent fuel reprocessing,nuclear physics,accelerators,and application of nuclear technologies.     

Research and Development

<正>1 Nuclear physics Basic research in nuclear physics In 2019,CIAE scientists made new achievements in research of key nuclear reactions in astrophysics.The 7Li(6Li,d)11B transfer reaction was used for the first time to measure ground state spectrum amplitude of 11B.The research result provided further improvement for the (11B,7Li) system.     

Revamping Fusion Research

A fundamental revamping of magnetic plasma fusion research is needed, because the current focus of world fusion research—the ITER-tokamak concept—is virtually certain to be a commercial failure. Towards that end, a number of technological considerations are described, believed important to successful fusion research. Beyond critical attention to plasma physics challenges, there must be a much sharper focus on electric utility acceptance criteria, which strongly reflect the public interest. While the ITER-tokamak experience has provided important understanding of a variety of technology issues, it is expensive and time-consuming. Engineers with commercial-world experience must become involved in future fusion research and must have a major influence on program decision-making and evaluation. Fusion engineers will have to be imaginative while being rooted in an understanding of fission reactor development, nuclear regulation, and electric utility realities, the proper consideration of which will impact fusion program success. Properly developed, fusion power holds great promise as an attractive electric power source for the long-term future.     

中国先进研究堆中子散射工程中子导管模拟研究

为使依托中国先进研究堆（CARR）进行的冷中子散射实验拥有更高质量的中子束流,本工作对中子散射工程中的中子导管系统各参数进行分析研究,并首次在国内应用等效中子导管理论,结合解析计算确定出优化的导管方案。同时,应用VITESS程序对各导管方案得到的中子束流进行了模拟,在综合考虑导管系统几何布局及中子束流的发散度影响后,探讨出若干符合实际的设计方案。尔后,利用导管位置计算程序NGPS,计算出各导管方案中每个导管单元的位置坐标。最终,根据各项指标对模拟的各导管方案进行对比,优选出CNGA、CNGB、CNGD3套中子导管系统的最佳参数,为即将进行的中子导管系统的设计和安装提供理论参考。     

池式研究堆衰变热计算与实验研究

采用量热法测量反应堆额定功率运行75.0 h停堆后45 h内的衰变热功率,拟合出归一化衰变热功率的经验关系式.与反应堆衰变热几种半经验公式和标准对比结果表明,实验结果在经验公式计算值范围内,并与EJ/T 745标准预测值符合较好.     

A Review of Research Activities at the Research Reactor Institute of Kyoto University in View of Research Publication Information

A database of research publication was constructed for the purpose of grasping all of the research activities at the Research Reactor Institute, Kyoto University. The database named KURRIP collects all of the research publications of the Institute by not only its own staff but also visiting scientists. The publications are in the form of original papers, review papers, papers in proceedings, short notes and letters, synopses over 3 pages presented orally at scientific meeting, books and doctoral theses. At present, the KURRIP database contains the information on 6,210 items which have been published for 30 years since the Institute was established as an inter- university research institute for joint use of a research reactor and other related large facilities in 1963. By utilizing the KURRIP database, the analyses have been done: (1) affiliation of the authors, (2) kind of publications, (3) classification of publishers, (4) research fields, and (5) experimental facilities. The KURRIP database is now stored in the Data Processing Center of Kyoto University and can be utilized through a computer center at one of the main national universities in Japan.     

研究堆辐照孔道内热中子注量率测量方法研究

采用经典的活化箔法测量研究堆辐照孔道内热中子注量率的相对分布,并选择孔道内有代表性的点进行中子温度和热中子绝对注量率的测量;最后利用镉比修正法对实验结果进行校核。分析表明,2种方法得到的数据符合较好,可以相互校核用于其他孔道内的绝对热中子注量率测量。     

Collaborative Research Design System

正Collaborative research design system(CRDS)is one of the basic conditions for the successful completion of CFR600 design.It will build a solid base for the realization of fast reactor RD design to the direction of"batch design capability and brand formation".The platform integrates the software(method),standard,specification and experience related to fast reactor design by technical means of     

Research reactor RBT-6

Conclusions Reactor RBT-6 is simple in construction and is easily accessible for conducting experiments. The values of neutron flux in it are high for small thermal power; this together with the large duration of continuous operation ensures the possibility of conducting a wide range of experimental investigationa. Such a reactor may be recommended as a research reactor for irradiation of samples of materials up to moderate flux values (10¹⁹–10²¹ neutrons/cm²) and for conducting experiments for studying the change in the properties of materials during irradiation, which are becoming increasingly more important. Estimates show that the number of used fuel assemblies of the SM-2 reactor are sufficient for the operation of several such reactors.If necessary, the number of experimental channels in the active zone of such a reactor can be increased by increasing the number of fuel assemblies and the thermal power. Beryllium can be used as the lateral reflector. This results in a decrease of the volume of the active zone and the thermal power of the reactor, but increases its cost.Translated from Atomnaya Énergiya, Vol. 43, No. 1, pp. 3–7, July, 1977.     

Detector Research Condition Project

<正>The objective of the detector laboratory researching conditions development project is to build part of the experimental conditions of the semiconductor process,which belongs to the construction project of the nuclear base.The construction contents include about 450 m~2 clean laboratory(including 1 000level clean workshop     

Frontiers in Fusion Research

Presentations that were made at a Fusion Power Associates symposium, Frontiers in Fusion Research, are summarized. Discussions include the science frontiers of burning plasma physics, magnetic fusion concepts, inertial fusion concepts, and fusion technology.     

基于β辐生伏特效应的同位素微能源研究

介绍了基于辐生伏特效应的放射性同位素微电池的理论研究,建立了p n型和n p型微电池能量转化结构的理论模型,分析了影响微电池性能的主要参数,并对两种能量转化结构的主要设计参数进行了优化.比较了p n型和n P型两种能量转化结构的性能.     

中国先进研究堆严重事故辐射后果研究

针对高功率研究堆建在大城市远郊区的特殊情况，提出了中国先进研究堆（CARR）严重事故辐射后果的验收准则。为进行CARR严重事故排放方案的设计，研究了不同事故排放方案下，CARR发生严重事故时的环境辐射后果。最终推荐提高反应堆大厅密封性并优化事故后密闭与排风组合排放方案，实现了CARR工程无场外应急的安全设计目标。     

氡气测量研究

讨论了氡的运移规律,结果发现,氡及其子体在理想条件下的空气中,其扩散作用小于１０％,地球引力导致的下沉作用小于４５％,上浮的贡献大于４５％。介绍了氡的探测方法和电离室α杯测氡的应用概况。     

研究堆燃料组件碰撞过程结构响应特性研究

对典型的研究堆燃料组件碰撞过程结构响应特性进行了数值模拟研究,分析了在碰撞过程中燃料组件应力响应特性、燃料元件定位结构的承载特征以及填充缓冲材料对燃料组件碰撞的保护效果。研究发现:在碰撞过程中燃料元件端部附近有明显的应力集中现象,增加燃料元件端部包壳长度可避免应力集中对芯体产生影响;燃料元件端部定位结构承受的载荷显著大于中部,加强端部定位结构的强度可提升燃料组件承载能力;缓冲材料在碰撞过程中对燃料组件具有良好的吸能保护功能,同时能平缓碰撞中的动能变化以及碰撞后的结构振动。