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Published: 2018-03-30
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DOI: https://doi.org/10.53747/jnst.v8i1.77
Issue
Vol. 8 No. 1 (2018)
Section
Articles
How to Cite
Kuen, T., Nguyen, A. T., Chen, K. T., Wang, L. H., Li, Y. C., & Kuo, T. L. (2018). Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock. Nuclear Science and Technology, 8(1), 1-9. https://doi.org/10.53747/jnst.v8i1.77

Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock

Kuen Ting1, Anh Tuan Nguyen2, Kuen Tsann Chen2, Li Hwa Wang3, Yuan Chih Li3, Tai Liang Kuo3
1 Lunghwa Univesity of Sci. and Tech., Graduate School of Engineering Technology, No.300, Sec.1, Wanshou Rd., Guishan Shiang, Taoyuan County 33306,Taiwan, R.O.C.
2 National Chung Hsing University, Department of Applied Mathematics, No. 250 Kuo Kuang Rd., Taichung 402, Taiwan, R.O.C.
3 Industrial Technology Research Institute, Material and Chemical Research Laboratories, RM 824, Bldg.52, No.195, Sec.4, Chung Hsing Rd., Chutung, Hsinchu, 31040, Taiwan, R.O.C.

Main Article Content

Abstract

The beltline region is the most important part of the reactor pressure vessel, become embrittlement due to neutron irradiation at high temperature after long-term operation. Pressurized thermal shock is one of the potential threats to the integrity of beltline region also the reactor pressure vessel structural integrity. Hence, to maintain the integrity of RPV, this paper describes the benchmark study for deterministic and probabilistic fracture mechanics analyzing the beltline region under PTS by using FAVOR code developed by Oak Ridge National Laboratory. The Monte Carlo method was employed in FAVOR code to calculate the conditional probability of crack initiation. Three problems from Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel (PROSIR) round-robin analysis were selected to analyze, the present results showed a good agreement with the Korean participants’ results on the conditional probability of crack initiation.

Article Details

Keywords

Probabilistic Fracture Mechanics, Beltline Region, Reactor Pressure Vessel, Pressurized Thermal Shock

References

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