| [1] |
BURCHELL T D, TUCKER M, MCENANEY B. Qualitative and quantitative studies of fracture in nuclear graphites[C]∥Materials for Nuclear Reactor Core Application. London: [s. n.], 1987: 95-103.
|
| [2] |
BECKER T H, MARROW T J, TAIT R B. Damage, crack growth and fracture characteristics of nuclear grade graphite using the Double Torsion technique[J]. Journal of Nuclear Materials, 2011, 414: 32-43.
|
| [3] |
NEMETH N N, BRATTON R L. Overview of statistical models of fracture for non-irradiated nuclear-graphite components[J]. Nuclear Engineering and Design, 2010, 240: 1-29.
|
| [4] |
NEMETH N N, POWERS L M, JANOSIK L A, et al. CARES/LIFE ceramics analysis and reliability evaluation of structures life prediction program[R]. US: NASA/TM, 2003.
|
| [5] |
WEIBULL W. A statistical theory of the strength of materials[M]. Switzerland: The Royal Swedish Institute for Engineering Research, 1939.
|
| [6] |
PEIRCE F T. Tensile tests for cotton yarns: The weakest link-theorems on the strength of long and of composite specimens[J]. J Text Inst Trans, 1926, 17: 355-368.
|
| [7] |
BATDORF S B, CROSE J G. A statistical theory for the fracture of brittle structures subjected to nonuniform polyaxial stresses[J]. Journal of Applied Mechanics, 1974, 41(2): 459-464.
|
| [8] |
BATDORF S B. New light on Weibull theory[J]. Nuclear Engineering and Design, 1978, 47: 267-272.
|
| [9] |
BURCHELL T D, YAHR T, BATTISTE R. Modeling the multiaxial strength of H-451 nuclear grade graphite[J]. Carbon, 2007, 45: 2570-2583.
|
| [10] |
SCHMIDT A. Reliability analysis of graphite structures, Part Ⅰ: Theory[R]. US: Westinghouse, 2000.
|
| [11] |
HINDLEY M P, MITCHELL M N, ERASMUS C, et al. A numerical stress based approach for predicting failure in NBG-18 nuclear graphite components with verification problems[J]. Journal of Nuclear Materials, 2013, 436: 175-184.
|
| [12] |
HINDLEY M P, BLAINE D C, GROENWOLD A A, et al. Failure prediction of full-size reactor components from tensile specimen data on NBG-18 nuclear graphite[J]. Nuclear Engineering and Design, 2015, 284: 1-9.
|
| [13] |
ASME. ASME boiler and pressure vessel code ASME Ⅲ division 5: High temperature reactors[S]. US: ASME, 2015.
|
| [14] |
HINDLEY M P, GROENWOLD A A, BLAINE D C, et al. Optimization of the link volume for weakest link failure prediction in NBG-18 nuclear graphite[J]. Nuclear Engineering and Design, 2014, 274: 10-19.
|
| [15] |
HU Yuqin, SUN Libin, WANG Hongtao, et al. Domestic graphite strength test for HTR engineering verfication[J]. Science & Technology Review, 2012.
|
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