Article Sidebar

PDF
Published: 2018-03-30
Abstract Views: 93
Views PDF: 41
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

[1] Myung JJ, Young HC, Yoon SC, Jong MK, Jong WK., “PFM Round-robin Analysis on RPV Integrity during PTS by Korean Participants”, The 8th International Workshop on the Integrity of Nuclear Components, Japan, 2009.
[2] Elisabeth K, Cornelia S, Albert S, Roland H. “Life management of reactor pressure vessels under pressurized thermal shock loading: deterministic procedure and application to Western and Eastern type of reactors”, International Journal of Pressure Vessels and Piping, 78, p.85-98, 2001.
[3] Myung JJ, Chang HJ, Seok HK, Young HC, Hho JK, Sung GJ, Jong MK, Gap HS, Tae EJ, Taek SC, Ji HK, Jong WK, Keun BP. “Round-robin Analysis for Probabilistic Structural Integrity Reactor Pressure Vessel under Pressurized Thermal Shock”, Journal of Mechanical Science and Technology, 19, p.634-648, 2005.
[4] IAEA TECDOC 1627, “Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment”, International Atomic Energy Agency, Austria, 2010.
[5] Guian Q, Markus N. “Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks”, Nuclear Engineering and Design, p. 35-50, 2013.
[6] Oya OG, Uner C. “Comparision of pressure vessel integrity analyses and approaches for VVER 1000 and PWR vessels for PTS conditions”, Nuclear Engineering and Design, p. 231-241, 2003.
[7] Vladislav P, Miroslav P, Dana L. “Probabilistic assessment of pressurized thermal shocks”, Nuclear Engineering and Design, 269, p. 165-170, 2014.
[8] William PT, Dickson TL, Yin S, Fracture Analysis of Vessels-Oak Ridge FAVOR, v12.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations, Oak Ridge National Laboratory, United States, 2012.
[9] Claude F, PROSIR Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel, Electricite De France, France, 2003.
[10] Nuclear Regulatory Commision Regulatory Guide 1.99 Rev. 2, Radiation Embrittlement of Reactor Pressure Vessel, United States, 1988.
[11] OECD, Probabilistic Structural Integrity of a Pressurised Water Reactor Pressure Vessel, Final Report, Nuclear Safety, NEA/CSNI, 2016.