journal article·2015-03

Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications

Daejong Kim, Hyun-Geun Lee, Ji Yeon Park, Weon-Ju Kim

Publisher page

Abstract

The SiC ceramics are under investigation for the fuel cladding in the light water nuclear reactors because of its excellent high temperature strength and corrosion resistance against hot steam under the severe accident conditions. In this study, the SiC triplex tubes consisting of a SiC inner layer, a SiC/PyC/SiC intermediate layer, and a SiC outer layer were fabricated by the chemical vapor processes. The hoop strength and fracture behaviors of the SiC triplex tube were investigated. The SiC triplex tubes fabricated at the high ratio of H2/MTS had a quite high average strength with a relatively small standard deviation. The hoop strength of the composite tubes tends to increase with the volume fraction of the reinforced fibers. The highest fiber volume fraction was obtained using Tyranno SA3-0.8k with the dense winding patterns such as bamboo-like mosaic pattern, which resulted in the high hoop strength compared to other fibers of Tyranno SA3-1.6k and Hi-Nicalon Type S. Hoop strength also increased slightly as the winding angle increased from 45° to 65°. Fracture behaviors of the SiC triplex tube were investigated via the observation of microstructure of the failed samples.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Advanced ceramic materials synthesis · Aluminum Alloys Composites Properties · Advanced materials and composites

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

References (34)

Show source-provided references
1. Makham · Ceram. Eng. Sci. Proc. · 2013 · 33 · 101
2. K. Barrett, S. Bragg-Sitton, D. Galicki, Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study, INL/EXT-12-27090, 2012.
3. Cheng · J. Nucl. Mater. · 2012 · 427 · 39610.1016/j.jnucmat.2012.05.007 ↗
4. Yueh · Nucl. Eng. Int. · 2010 · 55 · 14
5. Katoh · J. Nucl. Mater. · 2011 · 417 · 40010.1016/j.jnucmat.2010.12.088 ↗
6. Snead · J. Nucl. Mater. · 2007 · 371 · 32910.1016/j.jnucmat.2007.05.016 ↗
7. G. Youinou, R.S. Sen, Enhanced Accident Tolerant Fuels for LWRs – A Preliminary System Analysis, INL/EXT-13-30211, 2013.
8. Feinroth · E-J. Adv. Maint. · 2013 · 5 · 128
9. Y. Katoh, K.A. Terrani, L.L. Snead, Systematic Technology Evaluation Program for SiC/SiC Composite-based Accident-Tolerant LWR Fuel Cladding and Core Structures, ORNL/TM-2014/210, 2014.10.2172/1215606 ↗
10. Kim · J. Mater. Sci. Lett. · 2002 · 21 · 73310.1023/A:1015797324658 ↗
11. Kim · J. Mater. Sci. Lett. · 2003 · 22 · 58110.1023/A:1023390111074 ↗
12. Park · J. Nucl. Mater. · 2013 · 433 · 60310.1016/j.jnucmat.2013.07.058 ↗
13. Katoh · J. Nucl. Mater. · 2014 · 448 · 49710.1016/j.jnucmat.2013.10.002 ↗
14. Hinoki · Mater. Trans. · 2002 · 43 · 61710.2320/matertrans.43.617 ↗
15. Kishimoto · J. Nucl. Mater. · 2002 · 307–311 · 113010.1016/S0022-3115(02)01050-4 ↗
16. Katoh · J. Nucl. Mater. · 2011 · 417 · 41610.1016/j.jnucmat.2011.02.006 ↗
17. Katoh · J. Nucl. Mater. · 2011 · 416 · 40010.1016/j.jnucmat.2010.12.088 ↗
18. Koyanagi · J. Nucl. Mater. · 2014 · 448 · 47810.1016/j.jnucmat.2013.10.005 ↗
19. Katoh · J. Nucl. Mater. · 2001 · 289 · 4210.1016/S0022-3115(00)00681-4 ↗
20. S. Bragg-Sitton, Advanced LWR Nuclear Fuel Cladding System Development Technical Program Plan, INL/MIS-12-25696, 2012.
21. Shaw-Stewart · Mater. Des. · 1985 · 6 · 14010.1016/0261-3069(85)90063-9 ↗
22. Byun · J. Nucl. Mater. · 2007 · 367–370 · 65310.1016/j.jnucmat.2007.03.014 ↗
23. Park · Ceram. Eng. Sci. Proc. · 2003 · 24 · 61310.1002/9780470294826.ch89 ↗
24. Yang · Mater. Trans. · 2003 · 44 · 179710.2320/matertrans.44.1797 ↗
25. Newsome · J. Nucl. Mater. · 2007 · 371 · 7610.1016/j.jnucmat.2007.05.007 ↗
26. Broutman · 1975
27. Agarwal · 1990
28. Morozov · Compos. Struct. · 2006 · 76 · 12310.1016/j.compstruct.2006.06.018 ↗
29. Kim · J. Kor. Ceram. Soc. · 2013 · 50 · 35910.4191/kcers.2013.50.6.359 ↗
30. Soden · Compos. Sci. Technol. · 1993 · 46 · 36310.1016/0266-3538(93)90182-G ↗
31. Xia · Compos. Struct. · 2001 · 51 · 27310.1016/S0263-8223(00)00137-9 ↗
32. Y. Lee, M.S. Kazimi, A structural model for multi-layered ceramic cylinders and its application to silicon carbide cladding of light water reactor fuel, J. Nucl. Mater., 2014, accepted for publication.10.1016/j.jnucmat.2014.12.013 ↗
33. Stempien · Nucl. Technol. · 2013 · 183 · 1310.13182/NT12-86 ↗
34. H. Feinroth, M. Ales, E. Barringer, G. Kohse, D. Carpenter, R. Jaramillo, Mechanical Strength of CTP triplex SiC fuel clad tubes after irradiation in MIT research reactor under PWR coolant conditions, in: Proc. 33rd ISACC, 2013.