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| Content Provider | The American Society of Mechanical Engineers (ASME) Digital Collection |
|---|---|
| Author | Lu, Guangyao Lu, Zhaohui Xiang, Wenyuan Lv, Yonghong Huang, Wenyou Zhou, Jianming |
| Copyright Year | 2013 |
| Abstract | The control rod drive mechanism (CRDM) is installed on the CRDM socket in reactor pressure vessel (RPV). Directed by Rod Control and Rod Position Indicating System (RGL), CRDM can impel the control rods move up and down in the nuclear reactor core, which implements the functions of reactor start-up, power regulation, power maintaining, normal reactor shutdown and abnormal (accident) shutdown. CRDM was developed by China Nuclear Power Research Institute (CNPRI). Several design improvements were conducted to solve the problems appeared in the operation of nuclear power station. Test bench was also set up and cold tests were carried out to investigate the characteristics of CRDM. The cold tests included lifting experiment, inserting experiment, rod drop experiment. And studies were carried out to analyze the signals of lifting coil, moving coil, stationary coil and the vibration signals. The test results show that the design of CRDM is reasonable and the operation is reliable. |
| Sponsorship | Nuclear Engineering Division |
| File Format | |
| ISBN | 9780791855799 |
| DOI | 10.1115/ICONE21-15196 |
| Volume Number | Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors |
| Conference Proceedings | 2013 21st International Conference on Nuclear Engineering |
| Language | English |
| Publisher Date | 2013-07-29 |
| Publisher Place | Chengdu, China |
| Access Restriction | Subscribed |
| Subject Keyword | Control rode drive mechanism (crdm) Cold test Experimental Pressurized water reactor Design Nuclear power Reactor vessels Vibration China Rods Nuclear reactors Signals Nuclear power stations Pressurized water reactors Accidents |
| Content Type | Text |
| Resource Type | Article |
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