摘要：针对现有加速器驱动核能系统概念设计中存在的安全隐患,采用MCNP程序设计了加装辅助停堆系统的次临界实验装置;通过改变热区栅距、热区厚度和控制棒的下插深度来改变堆芯参数,对反应堆有效增殖系数进行计算和比较分析,实现了不同堆芯参数下keff值可调;对几种不同热区栅距和热区燃料棒根数所对应的停堆深度和控制棒价值进行了计算,结果表明,辅助停堆系统提高了加速器驱动系统(ADS)的安全性。

摘要：在加速器驱动次临界系统 (ADS)靶件模型上进行二维流动可视化研究。示踪粒子为直径 0 5mm的聚苯乙烯球状颗粒 ,采用片激光法对流场进行显示和KappaCCD数码摄像系统对流场进行实时拍摄 。

摘要：【本刊2013年11月综合报道】比利时核能研究中心（SCK-CEN）已将价值2400万欧元（3200万美元）的Myrrha加速器驱动研究堆前端工程设计合同授予了一个由阿海珐集团（Areva）牵头的跨国联合体。除了阿海珐集团之外，这个联合体的成员还包括意大利安萨尔多核公司（AnsaldoNucleare）和西班牙恩普雷萨里奥斯·阿格鲁潘多斯公司（EmpresariosAgrupados）。

摘要：分析加速器驱动系统(ADS)钠冷金属燃料快堆重金属燃料不同核素对堆芯有效增殖系数(keff)的影响,给出了燃料成分的确定方法,详细分析次锕系核素(MA)嬗变特性。运用耦合了MCNP4c3与ORIGEN2的三维燃耗程序COUPLE对堆芯进行稳态与燃耗计算。结果分析表明,调节燃料中239Pu的质量比例并使其在燃耗过程中保持稳定是使keff达到设计值并在燃耗过程中保持稳定的有效手段。散裂中子引起堆芯内区较外区更硬的中子能谱,有利于提高MA的裂变截面与裂变吸收比。全堆MA嬗变支持比为8.3,具有较好的嬗变效果。由于堆芯内区的高通量,堆芯内外区的嬗变率有明显差异,将MA集中布置于内区有利于减少装料量,改善总体嬗变效果。

摘要：Wire position monitor(WPM)is designed to monitor contraction of the cold masses during the cooling-down operation in an accelerator driven *** of material difference,machining error,assembly error,etc.,each WPM has to be *** sensing voltage and wire position are of a nonlinear relationship,which is expressed by high order *** mean square(RMS)of the polynomial fitting error were 3.8μm and 7.4μm at x and y directions,*** alignment test was carried out on the beta *** instruments were used to verify the WPM measuring *** differences between WPM measuring results and optical measurements were 0.044 and 0.05 mm in x and y direction,respectively.A significant asymmetric contraction was detected,and asymmetry of material was taken as the main reason through analysis.

摘要：[澳大利亚铀信息中心网站2002年6月报道]目前一些国家正在开发下两代反应堆.第一个(第三代)先进反应堆自1996年起在日本开始运行.更新的先进反应堆具有减少总投资的更先进和更简单的设计.它们的燃料效率更高、固有安全性更好.

摘要：In the paper presented are results of comparative analysis and choice of liquid metal coolants for fast reactors, current status of studies on physical chemistry and technology of sodium coolant for fast neutron reactors and heavy liquid metal coolants (HLMC), namely: Pb-Bi and Pb for fast reactors and accelerator driven systems. There are descriptions of devices designed for control of the impurities in sodium coolant and their removal and methods of HLMC quality control, removal of impurities from HLMC and steel surface of components of nuclear power plants (NPP) and relevant equipment. Attention is given to the issues of modeling of impurities mass transfer in liquid metal coolants and designing new liquid metal coolants for NPP. Results of analysis of NPP abnormal operating conditions are presented. The adopted design approaches assure reliable protection against accidents. By now, about 200 reactor-years of sodium cooled fast reactors operation and about 80 reactor-years of submarine reactors operation have been gained. The new goals on sodium and HLMC technology have been formulated as applied to the new generation fast reactors.