Investigating the effects of confining pressure on graphite material failure modes and strength criteria

Yi Yanan; Liu Guangyan; Xing Tongzhen; Lin Guang; Sun Libin; Shi Li; Ma Shaopeng

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자료유형: 학술저널

저자정보: Yi Yanan Liu Guangyan Xing Tongzhen Lin Guang Sun Libin Shi Li Ma Shaopeng

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제7호

발행연도: 2020.1

수록면: 1,571 - 1,578 (8page)

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As a critical material in very/high-temperature gas-cooled reactors, graphite material directly affects the safety of the reactor core structures. Owing to the complex structures of graphite material in reactors, the material typically undergoes complex stress states. It is, therefore, necessary to study its mechanical properties, failure modes, and strength criteria under complex stress states so as to provide guidance for the core structure design. In this study, compressive failure tests were performed for graphite material under the condition of different confining pressures, and the effects of confining pressure on the triaxial compressive strength and Young's modulus of graphite material were studied. More specifically, graphite material based on the fracture surfaces and fracture angles, the graphite specimens were found to exhibit four types of failure modes, i.e., tension failure, shear-tension failure, tension-shear failure and shear failure, with increasing confining pressure. In addition, the Mohr strength envelope of the graphite material was obtained, and different strength criteria were compared. It showed that the parabolic MohrCoulomb criterion is more suitable for the strength evaluation for the graphite material.

참고문헌 (32)

참고문헌 신청

S. P. Jing / 2016 / 3D microstructures of nuclear graphite: IG-110, NBG-18 and NG-CT-10, / Nucl. Sci. Tech 27:1~8

G. Singh / 2017 / Failure predictions for graphite reflector bricks in the very high temperature reactor with the prismatic core design / Nucl. Eng. Des 317:190~198

X. W. Zhou / 2017 / Nuclear graphite for high temperature gas-cooled reactors / N. Carbon Mater 32:193~204

Z. X. Wu / 2002 / The design features of the HTR-10 / Nucl. Eng. Des 218:25~32

Z. X. Wu / 2007 / The module HTGR development in China / Eng. Sci 4:59~67

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