机译:考虑维护人员错误的核电站反应堆保护系统反应堆杂散停机率估计模型
Nuclear and Quantum Engineering Department, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon 305-701, Republic of Korea;
rnIntegrated Safety Assessment Team, Korea Atomic Energy Research Institute, 1045, Daedeok - daero, Daejeon, 305-353, Republic of Korea;
rnIntegrated Safety Assessment Team, Korea Atomic Energy Research Institute, 1045, Daedeok - daero, Daejeon, 305-353, Republic of Korea;
rnNuclear and Quantum Engineering Department, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon 305-701, Republic of Korea;
λ: constant random hardware failure rate of a component; p_(cm): probability of first corrective maintenance; q_h: component random hardware failure probability between two refueling shutdowns; γ_r: human error probability in refueling maintenance; γ_t: human error probability in a single periodic test; et al;
机译:测试和维护人员错误的特征,导致核电厂计划外的反应堆跳闸
机译:Forsmark 1 + 2核电站的停机冷却系统更换和反应堆压力容器喷嘴焊缝的维修
机译:从韩国核电厂的人为失误危险角度对意外反应堆跳闸事件进行调查
机译:韩国核电厂与人相关的计划外反应堆跳闸事件涉及的任务类型和错误类型分析
机译:确定反应堆电站保护系统中子传感器原位响应测试方法的实验和数学模拟技术
机译:在福岛第一核电站反应堆厂房内检测源自核燃料的α粒子发射器
机译:基于状态转换图的核电站反应堆保护系统的动态建模
机译:与许可核电厂反应堆安全系统组件相关的人为错误的初步量化