journal article·2015-09

Effects of specimen size on the flexural strength and Weibull modulus of nuclear graphite IG-110, NBG-18, and PCEA

Se-Hwan Chi

Publisher page

Abstract

Abstract Changes in flexural strength and Weibull modulus due to specimen size were investigated for three nuclear graphite grades, IG-110, NBG-18, and PCEA, using four-point-1/3 point (4-1/3) loading with specimens of three different sizes: 3.18 (Thickness) × 6.35 (Width) × 50.8 (Length), 6.50 (T) × 12.0 (W) × 52.0 (L), 18.0 (T) × 16.0 (W) × 64 (L) (mm) (total: 210 specimens). Results showed some specimen size effects were grade dependent: While NBG-18 (a) showed rather significant specimen size effects (37% difference between the 3 T and 18 T), the differences in IG-110 and PCEA were 7.6–15%. The maximum differences in flexural strength due to specimen size were larger in the PCEA and NBG-18 having larger sized coke particles (medium grain size: >300 μm) than the IG-110 with super fine coke particle size (25 μm). The Weibull modulus showed a data population dependency, in that it decreased with increasing numbers of data used for modulus determination. A good correlation between the fracture surface roughness and the flexural strength was confirmed.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

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

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

References (16)

Show source-provided references
1. http://www.gen-4.org/PDFs/GIF_introduction.pdf.
2. T. Shibata, Japanese design approach and code, in: Presented at The ASME SG-Graphite Core Components meeting, Oarai R & D Center, Japan, June 2–4, 2008.
3. Y. Katoh, C.P. Shih, M. Fechter, L.L. Snead, D. Burchell, Small specimen test technologies for fine-grained nuclear graphite, in: ASTM Symposium on Graphite Testing for Nuclear Application, Seatle, WA, USA, September 19–20, 2013.
4. M.P. Metcalfe, N. Tzelepi, D. Wilde, The effects of test specimen size on graphite strength, in: ASTM Symposium on Graphite Testing for Nuclear Application, Seatle, WA, USA, September 19–20, 2013.10.1520/STP157820130123 ↗
5. M.P. Metcalfe, N. Tzelepi, Review of historical studies on the effects of sample size on graphite strength, in: 13th International Nuclear Graphite Specialist Meeting, Meitingen, Germany, 24–26 September, 2012.
6. Flexural strength of porous graphite in management of ageing in graphite reactor cores
7. Chi · J. Nucl. Mater. · 2013 · 436 · 18510.1016/j.jnucmat.2012.09.023 ↗
8. Yoon · J. Nucl. Mater. · 2011 · 412 · 31510.1016/j.jnucmat.2011.03.019 ↗
9. J.P. Strizak, The Effects of Volume on the Tensile Strength of Several Nuclear-Grade Graphites, CONF-91092666-4, ORNL, USA, 1991.
10. ASTM D 7775-11, Standard Guide for Measurements on Small Graphite Specimens, ASTM International, West Conshohocken, PA 19428-2959, USA, 2011.
11. ASTM C 651-91, Standard Test Method for Flexural Strength of Manufactured Carbon and Graphite Articles Using Four-Point Loading at Room Temperature, ASTM International, West Conshohocken, PA 19428-2959, USA, 2011.
12. ASTM C 1161-13, Standard Test Method for Flexural Strength of Advanced Ceramics at Ambient Temperature, ASTM International, West Conshohocken, PA 19428-2959, USA, 2011.
13. Danzer · J. Eur. Ceram. Soc. · 2006 · 26 · 304310.1016/j.jeurceramsoc.2005.08.021 ↗
14. ASTM D 7219-05, Standard Specification for Isotropic and Near-isotropic Nuclear Graphites, ASTM International, West Conshohocken, PA 19428-2959, USA, 2005.
15. ASTM D 7301-08, Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose, ASTM International, West Conshohocken, PA 19428-2959, USA, 2008.
16. W.W. Dorner, Using Excel for Weibull Analysis, .