An investigation of fracture behaviors of NBG-18 nuclear graphite using in situ mechanical testing coupled with micro-CT

被引:6
作者
Liu, Gongyuan [1 ]
Tang, Yichun [1 ]
Hattar, Khalid [2 ,3 ]
Wang, Yuzhou [4 ]
Windes, William [4 ]
Haque, Aman [1 ]
Du, Jing [1 ]
机构
[1] Penn State Univ, Dept Mech Engn, 316B Leonhard Bldg, University Pk, PA 16802 USA
[2] Sandia Natl Labs, POB 5800, Albuquerque, NM 87185 USA
[3] Univ Tennessee, Dept Nucl Engn, Knoxville, TN 37996 USA
[4] Idaho Natl Lab, Idaho Falls, ID 83415 USA
关键词
Fracture; X-ray tomography; Defects; In situ; TRANSMISSION ELECTRON-MICROSCOPY; NEUTRON-IRRADIATION; CRACK-PROPAGATION; MICROSTRUCTURE; TOUGHNESS; DAMAGE; DEFORMATION; TOMOGRAPHY; CHALLENGES; STRENGTH;
D O I
10.1557/s43578-023-00929-7
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Nuclear graphite contains defects spanning from nanoscale basal cracks to sub-mm scale voids. This study aims to establish an experimental method to investigate pre-existing defects and 3-D crack growth inside nuclear graphite, NBG-18. Three-point bending tests were performed on single-edge notched beam specimens with and without coupling with micro-CT. The fracture toughness was measured to be 1.17 +/- 0.06 MPa root m . Cracks were observed to initiate from the pores and thermal cracks on the edge of the notch and then deflect or twist to grow along the pre-existing defects. Crack bridging, deflection, and twisting were the primary toughening mechanisms. The crack resistance curve exhibited a trend of rising-plateau-rising that can be related to the interaction of crack front and the pre-existing defects. The results highlight the capability of laboratory micro-CT-based experimental method for the visualization of multi-scale defect interactions, which remains to be a challenge in the characterization of nuclear graphite.
引用
收藏
页码:1984 / 1993
页数:10
相关论文
共 34 条
[1]   Materials challenges for Generation IV nuclear energy systems [J].
Allen, T. R. ;
Sridharan, K. ;
Tan, L. ;
Windes, W. E. ;
Cole, J. I. ;
Crawford, D. C. ;
Was, Gary S. .
NUCLEAR TECHNOLOGY, 2008, 162 (03) :342-357
[2]  
[Anonymous], 2007, ORNLTM2007153 NGNP
[3]  
[Anonymous], STANDARD TEST METHOD, DOI [10.1520/D7779-20, DOI 10.1520/D7779-20]
[4]   Multiscale characterization and comparison of historical and modern nuclear graphite grades [J].
Arregui-Mena, Jose David ;
Worth, Robert N. ;
Bodel, William ;
Maerz, Benjamin ;
Li, Wenjing ;
Campbell, Anne A. ;
Cakmak, Ercan ;
Gallego, Nidia ;
Contescu, Cristian ;
Edmondson, Philip D. .
MATERIALS CHARACTERIZATION, 2022, 190
[5]   Characterisation of the spatial variability of material properties of Gilsocarbon and NBG-18 using random fields [J].
Arregui-Mena, Jose David ;
Edmondson, Philip D. ;
Margetts, Lee ;
Griffiths, D., V ;
Windes, William E. ;
Carroll, Mark ;
Mummery, Paul M. .
JOURNAL OF NUCLEAR MATERIALS, 2018, 511 :91-108
[6]   Site specific, high-resolution characterisation of porosity in graphite using FIB-SEM tomography [J].
Arregui-Mena, Jose David ;
Edmondson, Philip D. ;
Campbell, Anne A. ;
Katoh, Yutai .
JOURNAL OF NUCLEAR MATERIALS, 2018, 511 :164-173
[7]   Damage, crack growth and fracture characteristics of nuclear grade graphite using the Double Torsion technique [J].
Becker, T. H. ;
Marrow, T. J. ;
Tait, R. B. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 414 (01) :32-43
[8]   A comparison of multi-scale 3D X-ray tomographic inspection techniques for assessing carbon fibre composite impact damage [J].
Bull, D. J. ;
Helfen, L. ;
Sinclair, I. ;
Spearing, S. M. ;
Baumbach, T. .
COMPOSITES SCIENCE AND TECHNOLOGY, 2013, 75 :55-61
[9]  
Burchell TD, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 2: MATERIAL PROPERTIES/OXIDE FUELS FOR LIGHT WATER REACTORS AND FAST NEUTRON REACTORS, P285
[10]   The effect of neutron irradiation damage on the properties of grade NBG-10 graphite [J].
Burchell, Timothy D. ;
Snead, Lance L. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) :18-27