1) core inlet
堆芯进口
2) core inlet flow rate
堆芯进口流速
3) core inlet specific-enthalpy
堆芯进口比焓
4) core inlet temperature
堆芯进口温度
5) core outlet
堆芯出口
1.
Based on the 3D thermal-hydraulics numerical simulation to the core outlet region of China Experimental Fast Reactor(CEFR) with the STAR-CD code,the rationality of the temperature monitoring-spot arrangement and the validity of the monitoring to blockage of assemblies were studied.
借助通用计算流体力学软件STAR-CD,对中国实验快堆堆芯出口区域进行稳态热工数值模拟。
2.
The flow pattern and temperature distribution are very complex in the core outlet region of CEFR (China Experimental Fast Reactor) for the complication of the specific structure and the core arrangement.
特殊的结构和堆芯布置，使得中国实验快堆(简称CEFR)堆芯出口区域的流动和温度分布十分复杂。
6) core melt progression
堆芯熔化进程
1.
The calculated results show that core melt progression is fast and most of the core material melt and relocated to the lower plenum.
结果表明,压水堆发生大破口失水事故时,堆芯熔化进程较快,大量堆芯材料熔化并坍塌至下腔室,反应堆压力容器下封头失效较早,且主回路冷段破口比热段破口更为严重。
2.
In order to predict the in-vessel core melt progression accurately and provide probabilistic safety assessment(PSA) level 2 with the reliable initialization conditions,the creep rupture failure of primary loops pressure boundary was taken into account in code calculation.
为准确预测压力容器内堆芯熔化的进程,为二级概率安全评价提供可信的初始条件,计算中考虑了一回路压力边界的蠕变破裂失效,并评价了人为干预对堆芯熔化进程及事故后果的影响。
3.
In order to predict the in-vessel core melt progression accurately and provide PSA-2 with the reliable initialization conditions,the creep rupture failure of primary loops pressure boundary is taken into account in code calculation.
为准确预测压力容器内堆芯熔化的进程,给二级PSA提供可信的初始条件,计算中考虑了一回路压力边界的蠕变破裂失效,并评价了人为干预对堆芯熔化进程及事故后果的影响。
补充资料：堆芯活性区
分子式：
CAS号：
性质：反应堆的堆芯。是反应堆的核心部分。核燃料在这里发生自持链式裂变反应，并且不断地释放出能量。热中子反应堆活性区由核燃料、慢化剂、冷却剂、结构材料及保证反应堆启动、停闭、正常运行的控制棒等。天然铀石墨慢化水冷反应堆的堆芯就像一个石墨堆砌成的大型蜂窝煤，孔洞中装入燃料元件和通过冷却剂。
CAS号：
性质：反应堆的堆芯。是反应堆的核心部分。核燃料在这里发生自持链式裂变反应，并且不断地释放出能量。热中子反应堆活性区由核燃料、慢化剂、冷却剂、结构材料及保证反应堆启动、停闭、正常运行的控制棒等。天然铀石墨慢化水冷反应堆的堆芯就像一个石墨堆砌成的大型蜂窝煤，孔洞中装入燃料元件和通过冷却剂。
说明：补充资料仅用于学习参考，请勿用于其它任何用途。
参考词条