机译:SFR中燃料针失效情况下钠池中铯的保留因子估算
Computational Simulation Section, Safety Engineering Division, Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India;
Computational Simulation Section, Safety Engineering Division, Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India;
Computational Simulation Section, Safety Engineering Division, Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India;
Computational Simulation Section, Safety Engineering Division, Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India;
b: constant; C: concentration (g/m~3); C_p: Specific heat capacity (J/(kgK)); d: diameter (m); D: diffusion coefficient (m~2/s); et al;
机译:估算从热钠池到典型SFR惰性覆盖气体的铯的蒸发速率
机译:使用改良艺术MOD 2的反应器压力容器和燃料池同时发生铯复合行为评估:Fukushima Daiichi事故模拟
机译:SFR细胞中钠池火灾事件的地板表面液体钠溢出的分析
机译:具有两相钠行为的SAS-SFR代码的CABRI-1单燃料销LOF实验BI1的分析
机译:铯和钠-钾蒸气的脉冲和连续激光实验:铯蒸气中5DJ + 6PJ'进入DJ'+ 6S1 / 2能量池碰撞的速度依赖性以及钠钾3(1)pi的绝对跃迁偶极矩到X(1)sigma +和3(1)pi使用Autler-Townes光谱法进行A(1)sigma +过渡
机译:估计早产儿RDS的早期生命内源性表面活性剂池和CPAP衰竭
机译:基于铯与Technetium的比例的单通熔池保留