首页 | 本学科首页   官方微博 | 高级检索  
     


Simulation Study of AVR-U Nuclear Process Heat Plant
Abstract:A pebble-bed high temperature gas-cooled reactor AVR located at Jülich, West Germany has a modification plan to include a process heat loop. In the plan, half of the primary helium heated up to 950°C by the AVR core is supplied to the process heat loop. The helium flow of the process heat loop influences the flow of the AVR loop and vice versa. Consequently, flow instabilities and reverse flow in the modified plant may possibly happen.

In the paper, a computer simulation is performed to investigate the dynamic behavior of the primary helium flow in the modified plant. At first, dynamic experiments conducted at the AVR plant are simulated in order to grasp the accuracy of the computer code. Then, the modified plant is simulated. As a result, the behavior of the primary flow is rather moderate against the disturbances which are expected under the normal plant operation. Further, the condition when the reverse flow appears is evaluated analytically by using a simplified flow network model.
Keywords:accuracy  AVR reactor  AVR-U  circulator head  comparative evaluations  computerized simulation  DSNP code  dynamics  experimental data  flow rate  fluid flow  pressure drop  process heat  stability  steam reformer
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号