Department of Mechanical and Materials Engineering Korea Institute of Nuclear Safety 62 Gwahak-ro Yuseong-gu Daejeon 305-338 Republic of Korea email: shsong@kins.re.kr;
Department of Mechanical and Materials Engineering Korea Institute of Nuclear Safety 62 Gwahak-ro Yuseong-gu Daejeon 305-338 Republic of Korea email: ybkim@kins.re.kr;
Department of Mechanical and Materials Engineering Korea Institute of Nuclear Safety 62 Gwahak-ro Yuseong-gu Daejeon 305-338 Republic of Korea email: k655kjs@kins.re.kr;
Department of Mechanical and Materials Engineering Korea Institute of Nuclear Safety 62 Gwahak-ro Yuseong-gu Daejeon 305-338 Republic of Korea email: wjroh@kins.re.kr;
机译:韩国核电站数字化模拟基础核心中子磁通监测系统研究
机译:压水堆核电站一次冷却剂管道包含内周表面裂纹的概率和非概率失效评估曲线
机译:压水堆(PWR)中的中子伽玛通量和剂量计算
机译:通过加工EX-CORE中子磁通信号反应器内部振动监测加压水反应堆电厂
机译:基于中子功率信号研究的沸水反应堆稳定性分析方法。
机译:秦山第三核电站重水堆工作人员of内部暴露剂量监测
机译:第三秦山核电站重型反应堆工氚内曝光剂量监测
机译:利用Ex-Core中子探测器检测压水堆内核振动和沸腾的灵敏度。