C-ring, which is one of the main sealing elements of Reactor Pressure Vessels, is composed of a close-wound helical spring surrounded by two metal linings. C-ring has better resilience and sealing characteristics. Just because of the complex structure of C-ring, it was studied by experiments almost. There were also some numerical simulations on C-ring. With these methods, the compression-decompression process of C-ring under ideal condition can be simulated. But them cannot be used to study the sealing behavior of laterally one side restrained C-ring under internal pressure, which is fit for practical condition. This paper will establish a 3D numerical simulation method to study the C-ring which is mentioned as above. In this paper, it can be obtained that with internal pressure forcing and sealing groove squeezing, sealing performance of C-ring will reduce; when p>20MPa, the ratio of reducing becomes bigger; when p>140MPa, it will generate leakage; inner lining and outer lining will generate biggish plastic deformation, while the stress distribution in spring changes much.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5780-9
PROCEEDINGS PAPER
A Study on the Sealing Behaviors of the Laterally One Side Restrained C-Ring Under Internal Pressure by Numerical Simulation
Dong Yuanyuan,
Dong Yuanyuan
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Luo Ying
Luo Ying
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Dong Yuanyuan
Nuclear Power Institute of China, Chengdu, China
Luo Ying
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE25-66288, V002T03A029; 4 pages
Published Online:
October 17, 2017
Citation
Yuanyuan, D, & Ying, L. "A Study on the Sealing Behaviors of the Laterally One Side Restrained C-Ring Under Internal Pressure by Numerical Simulation." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 2: Plant Systems, Structures, Components and Materials. Shanghai, China. July 2–6, 2017. V002T03A029. ASME. https://doi.org/10.1115/ICONE25-66288
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