机译:核电站蓄电池压力边界管道和蒸汽发生器管概率故障指标估计现有研究的审查与分类
Univ Illinois Dept Nucl Plasma & Radiol Engn Urbana IL USA;
Univ Illinois Dept Nucl Plasma & Radiol Engn Urbana IL USA;
Univ Illinois Dept Nucl Plasma & Radiol Engn Urbana IL USA;
Univ Illinois Dept Nucl Plasma & Radiol Engn Urbana IL USA;
Univ Illinois Dept Nucl Plasma & Radiol Engn Urbana IL USA;
Univ Illinois Dept Nucl Plasma & Radiol Engn Urbana IL USA;
Univ Illinois Dept Nucl Plasma & Radiol Engn Urbana IL USA;
Gesell Anlagen & Reaktorsicherheit GRS Safety Res Div Containment Dept Cologne Germany;
Gesell Anlagen & Reaktorsicherheit GRS Safety Res Div Containment Dept Cologne Germany;
SIGMA PHASE INC Vail AZ USA;
Tunisian Elect & Gas Co Alternat Energies Project Tunis Tunisia;
Ryerson Univ Dept Civil Engn Toronto ON Canada;
Candu Energy Inc Mississauga ON Canada;
Lithuanian Energy Inst Lab Nucl Installat Safety Kaunas Lithuania;
KAERI Daejeon South Korea;
Agensi Nuklear Malaysia Reactor Technol Ctr Kajang Malaysia;
IAEA Vienna Austria;
IAEA Vienna Austria;
Reactor Coolant Pressure Boundary; Piping; Steam generator tubes; Loss of coolant accident; Probabilistic safety assessment; Probabilistic risk assessment;
机译:高温严重事故条件下温度感应堆冷却剂系统和蒸汽发生器管蠕变破裂概率的估算
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:将更新过程模型与故障概率物理相集成:在核电站冷却剂事故损失(LOCA)频率估计中的应用
机译:核电厂蒸汽发生器和反应器冷却泵高强锚固螺栓的结构完整性评价。
机译:有机酸在核工业蒸汽发生器中的核管腐蚀中有机酸的作用研究
机译:高压严重事故条件下温度诱导的反应器冷却剂系统和蒸汽发生器管蠕变破裂概率的估计
机译:Barsebaeck-1反应堆冷却剂压力边界管道的故障率。管道故障数据库的应用