Transactions of the Korean Society of Mechanical Engineers A (대한기계학회논문집A)
- Volume 21 Issue 11
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- Pages.1786-1795
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- 1997
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- 1226-4873(pISSN)
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- 2288-5226(eISSN)
DOI QR Code
Prediction of Fracture Resistance Curves for Nuclear Piping Materials(II)
원자력 배관재료의 파괴저항곡선 예측
- Chang, Yoon-Suk (Power Technology Development Research Center, Korea Power Engineering Corporation) ;
- Seok, Chang-Sung (Dept.of Mechanical Engineering, Sungkyunkwan University) ;
- Kim, Young-Jin (Dept.of Mechanical Engineering, Sungkyunkwan University)
- Published : 1997.11.01
Abstract
In order to perform leak-before-break design of nuclear piping systems and integrity evaluation of reactor vessels, full stress-strain curves and fracture resistance (J-R) curves are required. However it is time-consuming and expensive to obtain J-R curves experimentally. The objective of this paper is to modify two J-R curve prediction methods previously proposed by the authors and to propose an additional J-R curve prediction method for nuclear piping materials. In the first method which is based on the elastic-plastic finite element analysis, a blunting region handling procedure is added to the existing method. In the second method which is based on the empirical equation, a revised general equation is proposed to apply to both carbon steel and stainless steel. Finally, in the third method, both full stress-strain curve and finite element analysis results are used for J-R curve prediction. A good agreement between the predicted results based on the proposed methods and the experimental ones is obtained.
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