As a key device, the Control Rod Drive Mechanism (CRDM) is of great important for the safety operation of the nuclear reactor, where the pressure shell of CRDM is exposed to the primary loop pressure, and is installed on the head of the reactor pressure vessel by the Ω seal. During the operation cycle of the reactor, cracks may be induced on the Ω seal weld by primary water stress corrosion cracking which is the major factor leading to leakage of coolant and impacting the safety of the reactor. Therefore, the Ω seal is required to be repaired to maintain structural integrity and safety by using the evaluated overlay weld technology. Based on fracture mechanics, this paper investigates the crack growth safety assessment of the overlay weld structure on the Ω seal of control rod drive mechanism, induced by the operation fatigue and stress corrosion, and the evaluation is completed by the standard code. The calculation method and assessment results can be a reference for the overlay weld structure design and safety evaluation of the Ω seal in CRDM.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5782-3
PROCEEDINGS PAPER
Crack Growth Safety Assessment of Overlay Weld on the Ω Seal for Control Rod Drive Mechanism
Jiacheng Luo,
Jiacheng Luo
Nuclear Power Institute of China, Chengdu, China
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Yong Zhang,
Yong Zhang
Nuclear Power Institute of China, Chengdu, China
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Pengzhou Li,
Pengzhou Li
Nuclear Power Institute of China, Chengdu, China
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Juan Luo,
Juan Luo
Nuclear Power Institute of China, Chengdu, China
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Lei Sun
Lei Sun
Nuclear Power Institute of China, Chengdu, China
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Jiacheng Luo
Nuclear Power Institute of China, Chengdu, China
Yong Zhang
Nuclear Power Institute of China, Chengdu, China
Pengzhou Li
Nuclear Power Institute of China, Chengdu, China
Juan Luo
Nuclear Power Institute of China, Chengdu, China
Lei Sun
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE25-67615, V004T06A036; 4 pages
Published Online:
October 17, 2017
Citation
Luo, J, Zhang, Y, Li, P, Luo, J, & Sun, L. "Crack Growth Safety Assessment of Overlay Weld on the Ω Seal for Control Rod Drive Mechanism." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management. Shanghai, China. July 2–6, 2017. V004T06A036. ASME. https://doi.org/10.1115/ICONE25-67615
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