机译:超快反应堆给水控制器的改进
Department of Nuclear Engineering and Management, The University of Tokyo,Hongo, Bunkyo-ku, Tokyo 113-8685, Japan;
Nuclear Professional School, The University of Tokyo, Shirane, Shirakata,Tokai-mura, Naka-gun, Ibaraki 319-1188, Japan ,China Nuclear Power Technology Research Institute, Shenzhen 518026, China;
Nuclear Professional School, The University of Tokyo, Shirane, Shirakata,Tokai-mura, Naka-gun, Ibaraki 319-1188, Japan;
Nuclear Professional School, The University of Tokyo, Shirane, Shirakata,Tokai-mura, Naka-gun, Ibaraki 319-1188, Japan;
generation IV; supercritical water-cooled reactor; fast reactor; once-through coolant cycle; main steam temperature; power-to-flow ratio; plant control system; feedwater controller; plant system analysis;
机译:基于M_s约束的积分增益优化方法的Advanced Power Reactor 1400给水控制系统的控制器整定常数
机译:中国实验快堆失水事故下冷热钠池耦合的三维热力水力瞬态计算
机译:钠冷快堆中具有多个直流蒸汽发生器的给水控制系统的建模与仿真(Ⅰ):动态模型开发
机译:压水堆给水调节的模糊逻辑控制器
机译:高温气冷反应堆的反应堆腔冷却系统中的结垢方法和热工水力分析,以及钠快速反应堆中的热喷射混合。
机译:光伏系统性能分析的改进:脉宽调制充电控制器中的阵列功率监控
机译:超临界CO 2冷却快堆的反应堆物理设计