journal article·2011-08

Microstructural characterization and pore structure analysis of nuclear graphite

J. Kane, C. Karthik, D.P. Butt, W.E. Windes, R. Ubic

Journal of Nuclear Materials· Volume 415· Issue 2
Publisher page

Abstract

Abstract Graphite will be used as a structural and moderator material in next-generation nuclear reactors. While the overall nature of the production of nuclear graphite is well understood, the historic nuclear grades of graphite are no longer available. This paper reports the virgin microstructural characteristics of filler particles and macro-scale porosity in virgin nuclear graphite grades of interest to the Next Generation Nuclear Plant program. Optical microscopy was used to characterize filler particle size and shape as well as the arrangement of shrinkage cracks. Computer aided image analysis was applied to optical images to quantitatively determine the variation of pore structure, area, eccentricity, and orientation within and between grades. The overall porosity ranged between ∼14% and 21%. A few large pores constitute the majority of the overall porosity. The distribution of pore area in all grades was roughly logarithmic in nature. The average pore was best fit by an ellipse with aspect ratio of ∼2. An estimated 0.6–0.9% of observed porosity was attributed to shrinkage cracks in the filler particles. Finally, a preferred orientation of the porosity was observed in all grades.
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Research context

OpenAlex topics: Graphite, nuclear technology, radiation studies · Radiation Shielding Materials Analysis · Nuclear and radioactivity studies

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (21)

Show source-provided references
1. B.J. Marsden, Li H. Fok, Irradiation behavior and structural analysis of HTR/VHTR graphite core components, in: 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18), China, Beijing, August 7–12, 2005. SMiRT18-A01-7.
2. R. Bratton, W. Windes, NGNP graphite selection and acquisition strategy, ORNL/TM-2007/153-10-07 (INL/MIS-10-19427), Oak Ridge National Laboratory, July 28, 2010.
3. W. Windes, T. Burchell, R. Bratton, Graphite technology development plan, INL/EXT-07-13165, Idaho National Laboratory, September 2007.10.2172/968671 ↗
4. Kelly · 1962
5. Kelly · 2000
6. ASTM Standard D7219, 2008, Standard specification for isotropic and near-isotropic nuclear graphites, ASTM International, West Conshohocken, PA, 2003, doi:10.1520/D7219-08.10.1520/D7219-08 ↗
7. Manufacturing
8. Structure
9. Blackstone · J. Nucl. Mater. · 1977 · 65 · 7210.1016/0022-3115(77)90043-5 ↗
10. Kelly · Carbon · 1974 · 12 · 15110.1016/0008-6223(74)90021-9 ↗
11. Kelly · Carbon · 1992 · 30 · 37910.1016/0008-6223(92)90034-T ↗
12. Kelly · Carbon · 1994 · 32 · 11910.1016/0008-6223(94)90017-5 ↗
13. Telling · Philos. Mag. · 2007 · 87 · 479710.1080/14786430701210023 ↗
14. Gonzalez · 2008
15. Burchell · Carbon · 1996 · 34 · 29710.1016/0008-6223(95)00171-9 ↗
16. C.I. Contescu, T.D. Burchell, Characterization of porosity development in oxidized graphite using automated image analysis techniques, ORNL/TM-2009/192, 2009.10.2172/970899 ↗
17. Babout · Carbon · 2005 · 43 · 76510.1016/j.carbon.2004.11.002 ↗
18. Babout · Scr. Mater. · 2006 · 54 · 82910.1016/j.scriptamat.2005.11.028 ↗
19. Hodgkins · Mater. Sci. Technol. · 2006 · 22 · 104510.1179/174328406X114126 ↗
20. Wen · J. Nucl. Mater. · 2008 · 381 · 19910.1016/j.jnucmat.2008.07.012 ↗
21. Otsu · IEEE Syst. Man Cybern. · 1979 · 9 · 6210.1109/TSMC.1979.4310076 ↗