Nuclear reactor pressure vessel (RPV) steels degrade due to neutron irradiation during normal operation. As a result, the ductile-brittle transition curve of the steel shifts to higher temperature which decreases operation margins in both the temperature and pressure. The loss of these margins however can be offset somewhat by appealing to arguments based on constraint of potential/postulated shallow cracks. In this paper, we demonstrate that the fracture toughness values for ASME postulated shallow flaws are higher than those determined from high constraint, standard deep cracked test specimens. The J-A2 three-term solution is used to characterize the crack-tip stress field where J represents the level of loading and A2 quantifies the level of constraint. It is shown that shallow (deep) flaws have lower (higher) constraint and A2. Based on the RKR cleavage model, procedures to quantify the temperature shift between specimens with different constraint levels are developed. The experimental data by Sherry et al. [1] for the A533B RPV steel are used to demonstrate the procedure and it is shown that the ductile-brittle transition curve shifts to lower temperature from high constraint to low constraint specimens.
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ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
July 23–27, 2006
Vancouver, BC, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4757-8
PROCEEDINGS PAPER
Effect of Constraint on the Shift of Ductile-Brittle Transition Curve of Reactor Pressure Vessel Steels
Zhong-An Chen,
Zhong-An Chen
Jiangsu University, Zhenjiang, Jiangsu, China
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Zhen Zeng,
Zhen Zeng
Jiangsu University, Zhenjiang, Jiangsu, China
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Yuh J. Chao
Yuh J. Chao
University of South Carolina, Columbia, SC
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Zhong-An Chen
Jiangsu University, Zhenjiang, Jiangsu, China
Zhen Zeng
Jiangsu University, Zhenjiang, Jiangsu, China
Yuh J. Chao
University of South Carolina, Columbia, SC
Paper No:
PVP2006-ICPVT-11-93412, pp. 57-64; 8 pages
Published Online:
July 23, 2008
Citation
Chen, Z, Zeng, Z, & Chao, YJ. "Effect of Constraint on the Shift of Ductile-Brittle Transition Curve of Reactor Pressure Vessel Steels." Proceedings of the ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference. Volume 6: Materials and Fabrication. Vancouver, BC, Canada. July 23–27, 2006. pp. 57-64. ASME. https://doi.org/10.1115/PVP2006-ICPVT-11-93412
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