Damage tolerance of nuclear graphite at elevated temperatures

Author:

Liu Dong,Gludovatz BerndORCID,Barnard Harold S.,Kuball Martin,Ritchie Robert O.

Publisher

Springer Science and Business Media LLC

Subject

General Physics and Astronomy,General Biochemistry, Genetics and Molecular Biology,General Chemistry

Reference41 articles.

1. Kelly, B. T. Graphite-the most fascinating nuclear material. Carbon 20, 3–11 (1982).

2. Taylor, R. et al. The mechanical properties of reactor graphite. Carbon 5, 519–531 (1967).

3. Tucker, M. O., Rose, A. P. G. & Burchell, T. D. The fracture of polygranular graphites. Carbon 24, 581–602 (1986).

4. Burchell, T. D. A microstructurally based fracture model for polygranular graphites. Carbon 34, 297–316 (1996).

5. Idaho National Laboratory, Oak Ridge National Laboratory & Argonne National Laboratory. Next Generation Nuclear Plant Research and Development Program Plan. INEEL/EXT-05-02581. Available at https://digital.library.unt.edu/ark:/67531/metadc779528/m2/1/high_res_d/859112.pdf (INEEL, 2005).

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