高炉中心装焦法

在将矿石和焦炭交互分层装入高炉的高炉装料方法中，先将焦炭插入炉中心以置换矿石层的炉中心部分，或者先在焦炭层的炉中心部分装入优质焦炭，然后在其周围装入矿石或普通焦炭，同时调整装入中心的焦炭的流态化开始气流速度和（或）炉顶平均气流速度，使装入炉中心的焦炭流态化的开始气流速度Ｕｍｆ与炉顶平均气流速Ｕｔ满足下式的关系：０．３０≤Ｕｔ／Ｕｍｆ≤０．５２。     

往铸铁中添加稀土硅化物

一、引言自从Morrogh研究工作表明混合稀土金属在铸铁中具有形成球状石墨的能力以来,稀土在铸铁生产中的作用的研究一直在继续。然而,除了个别情况以外,在球铁的工业生产中,稀土金属的应用和镁相比是属于次要地位的。稀土金属通     

集成SNR估计的LDPC码译码器的设计与实现

基于TMS320C6416高性能通用DSP,实现了对AWGN信道的信噪比(sNR)估计,并以此估计值设计了一种低密度奇偶校验(LDPC)码的译码系统;详尽介绍了集成SNR估计的译码系统的实现方案和流程;仿真结果表明,此估计下的译码器具有较好的性能.     

煤液化固液分离技术

煤液化一般有下面四种方法: 1.直接加氢液化法。 2.干馏加氢液化法。 3.提取加氢液化法。 4.间接法——合成液化法。这些方法的一般工艺流程如图所示,主要有原料调节、膏化、提取液化、固液分离、加氢分解、蒸馏以及废渣气化制氢等工序,并由它们组成各种工艺。虚线部分是用干馏得到的焦油进行加氢分解的干馏加氢液化法。其中直接加氢液化法及提取液化法与固液分离技术密切有关。     

日本冲绳海槽和欧亚板块附加体二维构造应力场的有限元模拟及其构造意义初探

应用有限元方法模拟了日本冲绳海槽和欧亚大陆板块附加体二维构造应力场,并根据库仑-摩尔准则讨论了有限元模型中断裂构造发育与变形,定量化地研究了大陆岩石圈的扩张作用以及菲律宾海板块的俯冲作用对大陆板块边缘构造应力场及其变形作用的影响。数学模拟的结果表明,大陆地壳底部的扩张作用使得冲绳海槽内发育正断层,从而导致冲绳海槽这一弧后盆地的形成。菲律宾海板块的俯冲作用引起欧亚板块附加体中形成逆掩断层。有限单元模拟实验结果与研究区地震震源机制的研究结果是一致的。     

零待机功耗芯片的实现之路

可实现零待机功耗的芯片技术正开始朝实用化方向发展（见图1）。在该领域领先一步的是日本罗姆公司,该公司于2008年成功试制出采用相应技术的微处理器原型,现在正在为多家设备厂商设计定制芯片。罗姆公司表示：“我们将于2009年下半年开始提供定制IC,采用这些芯片的设备将在2009年末上市。”     

放射性廃棄物量を低減するための低放射化材料の開発

When nuclear plants will reach to decommission stage, a huge amount of concrete should be disposed as radioactive waste. So design methodology for reinforced concrete of nuclear power plants to reduce radioactive wastes in decommission phase has been developed. To realize this purpose （1）Development of raw materials database of cements, aggregates and steel bars on concentration of radioactive target elements, （2）trial production of low activation cement and steel bars based on the material database, and （3）development of tools for estimation and prediction of the amount of radioactive elements in reactor shielding walls have been carried out.
Manufactu cements, low-a crete. After th ring tests by etivation addi at, we devel mixing together with low-activation aggregate, low-activation tives, etc, have been performed to develop low-activation conoped various types （1/10, 1/20, 1/30, …, 1/1000, 1/3000, and 1/10000） of low activation concrete composed of low activation raw materials as very useful shielding material in a nuclear facility. The term＂1/10 of low-activation concrete＂ denotes that the activity reduction rate to ordinary concrete is designed to be 1/10. By adopting some suitable types of low-activation concrete, most of the shielding concrete around ABWR and APWR are classified below clearance level on decommissioning.
To reduce the radioactive concrete, the most effective methodology is not to use the materials of high radio-nuclide content such as coal ash and blast furnace slag, and to use limestone as additives or aggregate. However, concrete uses Portland cement for hardening, therefore, it is difficult to reduce the amount of radioactive concrete unless radio-nuclide content in cement is reduced. So in this study, we tried to develop the new type of low-activation cement by reducing of radio-nuclide as europium and cobalt.