Fatigue Life Evaluation for Nuclear Power Plant Using Green’s Function and Real Operating Histories

Author(s):  
J.C. Kim ◽  
M.Y. Ahn ◽  
Yoon Suk Chang ◽  
Jae Boong Choi ◽  
Young Jin Kim ◽  
...  
2006 ◽  
Vol 326-328 ◽  
pp. 979-982 ◽  
Author(s):  
J.C. Kim ◽  
M.Y. Ahn ◽  
Yoon Suk Chang ◽  
Jae Boong Choi ◽  
Young Jin Kim ◽  
...  

In general, the fatigue life of major nuclear components has been evaluated based on design codes conservatively. However, sometimes, more exact fatigue life evaluation is required for continued operation beyond the endorsed life. The purpose of this paper is to carry out 3-D stress and fatigue analyses reflecting full geometry as well as actual operating data. The actual operating data acquired through a monitoring system were filtered and assessed. Then, temperature and stress transfer Green’s functions were developed and applied to critical locations of reactor pressure vessel. The finite element analyses results for representative design transients were verified through comparison to reference solution and showed that the conservatism of current 2-D evaluation. Therefore, it is anticipated that the proposed scheme adopting Green’s function and real operating histories can be utilized for remaining life time evaluation of major components.


2007 ◽  
Vol 26-28 ◽  
pp. 1251-1254
Author(s):  
Sang Guk Lee ◽  
Keun Bong Yoo ◽  
Sung Keun Park ◽  
Duck Gun Park

The objective of this study is to estimate the feasibility of advanced nondestructive method(X-ray diffraction, AE(acoustic emission) and BN(barkhausen noise)measurement application for fatigue life evaluation of the high-temperature pipeline steel such as main steam pipe etc. in power plant. In this study, various nondestructive tests using various types of specimen simulated low cycle fatigue damage were performed in order to analyze fatigue properties when fatigue damage conditions become various stages such as 1/4, 1/2 and 3/4 of fatigue life, respectively. As a result of X-ray diffraction tests for specimens simulated fatigue damages, we conformed that the variation of the full width at half maximum intensity decreased in proportion to the increase of fatigue life ratio. And also, AE and BN signal due to fatigue damage has linear relationship with fatigue life ratio algebraically. From this relationship, it was suggested that direct expectation of the life consumption rate was feasible.


2012 ◽  
Vol 19 (5) ◽  
pp. 1768-1773 ◽  
Author(s):  
Akihiko Shimada ◽  
Masaki Sugimoto ◽  
Hisaaki Kudoh ◽  
Kiyotoshi Tamura ◽  
Tadao Seguchi

2007 ◽  
Vol 120 ◽  
pp. 25-30 ◽  
Author(s):  
J.C. Kim ◽  
Jae Boong Choi ◽  
Yoon Suk Chang ◽  
Young Jin Kim ◽  
Youn Won Park ◽  
...  

While the demand on electric power is consistently increasing, public concerns and regulations for the construction of new nuclear power plants are getting restrict, and also operating nuclear power plants are gradually ageing. For this reason, the interest on lifetime extension for operating nuclear power plants by applying lifetime management system is increasing. The 40-year design life concept was originally introduced on the basis of economic and safety considerations. In other words, it was not determined by technological evaluations. Also, the transient design data which were applied for fatigue damage evaluation were overly conservative in comparison with actual transient data. Therefore, the accumulation of fatigue damage may result in a big difference between the actual data and the design data. The lifetime of nuclear power plants is mostly dependent on the fatigue life of a reactor pressure vessel, and thus, the exact evaluation of fatigue life on a reactor pressure vessel is a crucial factor in determining the extension of operating life. The purpose of this paper is to introduce a real-time fatigue monitoring system for an operating reactor pressure vessel which can be used for the lifetime extension. In order to satisfy the objectives, a web-based transient acquisition system was developed, thereby, real-time thermal-hydraulic data were reserved for 18 operating reactor pressure vessels. A series of finite element analyses was carried out to obtain the stress data due to actual transient. The fatigue life evaluation has been performed based on the stress analysis results and, finally, a web-based fatigue life evaluation system was introduced by combining analysis results and on-line monitoring system. Comparison of the stress analysis results between operating transients and design transients showed a considerable amount of benefits in terms of fatigue life. Therefore, it is anticipated that the developed web-based system can be utilized as an efficient tool for fatigue life estimation of reactor pressure vessel.


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