C-ring, whose sealing behavior is the key to the sealing structure, is one of the main seal-rings for a reactor pressure vessel (RPV). A finite-element model with less simplification has been established using ANSYS APDL to simulate the sealing behavior of C-ring. The numerical results, including sealing-behavior curve, specific pressure, and springback value, have been compared with test results at 7.67%, 8.42%, and 8.09% compression ratios, respectively. It confirms the validity of this numerical simulation method. With the numerical method, the deformation and stress distribution and sealing-behavior curve of C-ring can be obtained. The behavior curve can be divided into five sections. At 10% compression ratio, the peak contact stress is 501 MPa, the contact width is 3.22 mm, the total springback value is 0.460 mm, the effective springback value is 0.332 mm, and the linear load is . As C-ring is composed of three parts, three models, i.e., spring-only, spring with inner lining, and spring with two linings, have been simulated to study the effect of the contact states among each part on sealing behavior.
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October 2016
Research Papers
Numerical Simulation of Sealing Behavior of C-Ring for Reactor Pressure Vessel
Dong Yuanyuan,
e-mail: sshuimus@163.com
Dong Yuanyuan
Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory
, Changshun Avenue Section 1, No. 328, Chengdu, Sichuan 610213
, China
e-mail: sshuimus@163.com
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Luo Ying,
e-mail: npicluo@sina.com
Luo Ying
Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory
, Changshun Avenue Section 1, No. 328, Chengdu, Sichuan 610213
, China
e-mail: npicluo@sina.com
Search for other works by this author on:
Zhang Liping
Zhang Liping
Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory
, Changshun Avenue Section 1, No. 328, Chengdu, Sichuan 610213
, China
Search for other works by this author on:
Dong Yuanyuan
Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory
, Changshun Avenue Section 1, No. 328, Chengdu, Sichuan 610213
, China
e-mail: sshuimus@163.com
Luo Ying
Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory
, Changshun Avenue Section 1, No. 328, Chengdu, Sichuan 610213
, China
e-mail: npicluo@sina.com
Zhang Liping
Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory
, Changshun Avenue Section 1, No. 328, Chengdu, Sichuan 610213
, China
Manuscript received October 9, 2015; final manuscript received April 13, 2016; published online October 12, 2016. Assoc. Editor: Jovica R. Riznic.
ASME J of Nuclear Rad Sci. Oct 2016, 2(4): 041007 (5 pages)
Published Online: October 12, 2016
Article history
Received:
October 9, 2015
Revision Received:
April 13, 2016
Accepted:
April 29, 2016
Citation
Yuanyuan, D., Ying, L., and Liping, Z. (October 12, 2016). "Numerical Simulation of Sealing Behavior of C-Ring for Reactor Pressure Vessel." ASME. ASME J of Nuclear Rad Sci. October 2016; 2(4): 041007. https://doi.org/10.1115/1.4033551
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