Effects of fast neutron irradiation on zirconium carbide
Source abstract
Abstract
Abstract High-purity zone refined zirconium carbide has been fast neutron irradiated in the dose and temperature range of 1–10 × 1025 N/m2 (E > 0.1 MeV) and 635–1480 °C, respectively. Non-irradiated and as-irradiated properties were measured including the lattice parameter, hardness and elastic modulus as determined through nano-indentation, thermal conductivity, and indentation fracture toughness. The effects of neutron irradiation on the microstructure were also determined though using transmission electron microscopy. The general finding of this paper, limited to this particular zone refined ZrC of nominal C/Zr ratio of 0.93, is that this ceramic is quite stable under neutron irradiation in the temperature and dose range studied. Measurement of lattice parameter before and after irradiation indicated a lack of significant crystalline strain due to irradiation. Only modest changes were observed in the mechanical properties of hardness, elastic modulus, and indentation fracture toughness. The thermal conductivity underwent a slight reduction near 1000 °C irradiation, though was essentially unchanged for 1300–1480 °C irradiation. Transmission electron microscopy revealed black-spot-type defects (likely Frank or other small loops) for irradiation at 670 °C, maturing to faulted Frank loops at 1280 °C. As the irradiation temperature increased from 1280 °C to the highest irradiation temperature, of 1496 °C, a transition to prismatic loops occurs.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Advanced materials and composites · Nuclear Materials and Properties · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (29)
Show source-provided references
1. Reynolds · J. Nucl. Mater. · 1976 · 62 · 910.1016/0022-3115(76)90279-8 ↗
2. Ueta · J. Nucl. Mater. · 2008 · 376 · 14610.1016/j.jnucmat.2008.02.068 ↗
3. Versluis · HTR2008 · 2008 · 85325
4. Research and development of ZrC-coated UO2 particle fuel at JAERI
5. Ogawa · J. Am. Ceram. Soc. · 1992 · 75 · 298510.1111/j.1151-2916.1992.tb04375.x ↗
6. Ogawa · J. Nucl. Mater. · 1982 · 99 · 8510.1016/0022-3115(81)90141-0 ↗
7. Ogawa · J. Nucl. Mater. · 1986 · 22 · 179
8. T. Ogawa, K. Fukuda, ZrC Coated Particle Fuel Development, JAERI-M 92-207 (1992), pp. 554.
9. Gan · J. Nucl. Mater. · 2009 · 389 · 31710.1016/j.jnucmat.2009.02.021 ↗
10. Yang · J. Nucl. Mater. · 2008 · 378 · 34110.1016/j.jnucmat.2008.06.042 ↗
11. Gan · J. ASTM Int., JAI12376 · 2006 · 3 · 110.1520/JAI12376 ↗
12. Keilholtz · Fuels Mater. Develop. Quart. Prog. Rept., ORNL-4390 · 1968 · 113
13. Andrievskii · Neorg. Mater. · 1978 · 14 · 526
14. Dyslin · ORNL-4480 · 1969 · 245
15. Gosset · J. Nucl. Mater. · 2008 · 373 · 12310.1016/j.jnucmat.2007.05.034 ↗
16. Keilholtz · Nucl. Appl. · 1968 · 4 · 33010.13182/NT68-A26398 ↗
17. Kovalchenko · Neorg. Mater. · 1973 · 9 · 321
18. Storms · High Temp. Sci. · 1973 · 5 · 454
19. Ogawa · J. Nucl. Mater. · 1981 · 97 · 10410.1016/0022-3115(81)90423-2 ↗
20. K. Minato, T. Ogawa, K. Fukuda, Review of Experimental Studies of Zirconium Carbide Coated Fuel Particles for High Temperature Gas Cooled Reactors, JAERI-Review 95-004, 1995.
21. Fukuda · J. Nucl. Mater. · 1979 · 87 · 36710.1016/0022-3115(79)90574-9 ↗
22. Auskern · J. Nucl. Mater. · 1967 · 22 · 25710.1016/0022-3115(67)90043-8 ↗
23. Massalski · 1996
24. L.L. Snead, A.M. Williams, A.L. Qualls, Revisiting the use of SiC as a post irradiation temperature monitor, in: The Effects of Radiation on Materials: 21st International Symposium, 2003.10.1520/STP11262S ↗
25. Kovalchenko · Neorganicheskie Materlaly · 1973 · 9 · 321
26. Hannink · Proc. Roy. Soc., Lond. · 1972 · A32 · 40910.1098/rspa.1972.0017 ↗
27. Ponton · Mater. Sci. Technol. · 1989 · 5 · 86510.1179/mst.1989.5.9.865 ↗
28. Taubin · At. Energy. · 1991 · 70 · 5510.1007/BF01129994 ↗
29. Zinkle · J. Nucl. Mater. · 1997 · 251 · 20010.1016/S0022-3115(97)00224-9 ↗