Synthesis and sintering of UN-UO2 fuel composites
Source abstract
Abstract
Abstract The design and development of an economical, accident tolerant fuel (ATF) for use in the current light water reactor (LWR) fleet is highly desirable for the future of nuclear power. Uranium mononitride has been identified as an alternative fuel with higher uranium density and thermal conductivity when compared to the benchmark, UO2, which could also provide significant economic benefits. However, UN by itself reacts with water at reactor operating temperatures. In order to reduce its reactivity, the addition of UO2 to UN has been suggested. In order to avoid carbon impurities, UN was synthesized from elemental uranium using a hydride-dehydride-nitride thermal synthesis route prior to mixing with up to 10 wt% UO2 in a planetary ball mill. UN and UN – UO2 composite pellets were sintered in Ar – (0–1 at%) N2 to study the effects of nitrogen concentration on the evolved phases and microstructure. UN and UN-UO2 composite pellets were also sintered in Ar – 100 ppm N2 to assess the effects of temperature (1700–2000 °C) on the final grain morphology and phase concentration.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (38)
Show source-provided references
1. Ott · J. Nucl. Mater. · 2014 · 448 · 52010.1016/j.jnucmat.2013.09.052 ↗
2. Development strategy for advanced LWR fuels with enhanced accident tolerance
3. Youinou · Nucl. Technol. · 2014 · 188 · 12310.13182/NT14-22 ↗
4. Zinkle · J. Nucl. Mater. · 2014 · 448 · 37410.1016/j.jnucmat.2013.12.005 ↗
5. Wachs · Trans. Am. Nucl. Soc. · 2014 · 110 · 42
6. Koo · Nucl. Technol. · 2014 · 186 · 29510.13182/NT13-89 ↗
7. Brown · Nucl. Eng. Des. · 2014 · 275 · 39310.1016/j.nucengdes.2014.04.040 ↗
8. Bragg-Sitton · 2013
9. Lessing · 2012
10. Zakova · Ann. Nucl. Energy · 2012 · 47 · 18210.1016/j.anucene.2012.03.033 ↗
11. Hayes · J. Nucl. Mater. · 1990 · 171 · 28910.1016/0022-3115(90)90376-X ↗
12. Hayes · J. Nucl. Mater. · 1990 · 171 · 30010.1016/0022-3115(90)90377-Y ↗
13. Zhao · Prog. Nucl. Energy · 2014 · 71 · 15210.1016/j.pnucene.2013.11.008 ↗
14. Sugihara · J. Nucl. Sci. Technol-T · 1969 · 6 · 23710.1080/18811248.1969.9732878 ↗
15. Sunder · J. Alloys Compd. · 1998 · 271 · 56810.1016/S0925-8388(98)00157-1 ↗
16. Rao · J. Nucl. Mater. · 1991 · 185 · 23110.1016/0022-3115(91)90340-D ↗
17. Chaudri · Prog. Nucl. Energy · 2013 · 63 · 5710.1016/j.pnucene.2012.11.001 ↗
18. Inorganic Crystal Structure Database. FIZ Karlsruhe Karlsruh, Germany.
19. Bauer · React. Technol. · 1972 · 15 · 87
20. Cleveland · Nucl. Technol. · 1975 · 25 · 54110.13182/NT75-A24391 ↗
21. Matzke · 1986
22. Olschewski · J. Nucl. Mater. · 1992 · 188 · 24410.1016/0022-3115(92)90479-5 ↗
23. Oi · J. Nucl. Sci. Technol. · 1972 · 9 · 52110.1080/18811248.1972.9734891 ↗
24. Paljevic · J. Nucl. Mater. · 1975 · 57 · 25310.1016/0022-3115(75)90208-1 ↗
25. Wilkinson · 1962
26. Malkki · J. Nucl. Mater. · 2014 · 452 · 54810.1016/j.jnucmat.2014.06.012 ↗
27. Kim · Thermochim. Acta · 2006 · 441 · 12710.1016/j.tca.2005.12.009 ↗
28. Muromura · J. Nucl. Mater. · 1977 · 71 · 6510.1016/0022-3115(77)90187-8 ↗
29. Matthews · J. Nucl. Mater. · 1988 · 151 · 33410.1016/0022-3115(88)90029-3 ↗
30. Bugl · 1964
31. Jaques · J. Nucl. Mater. · 2008 · 381 · 30910.1016/j.jnucmat.2008.07.043 ↗
32. Tennery · Trans. Am. Nucl. Soc. · 1974 · 19 · 101
33. Tennery · J. Am. Ceram. Soc. · 1971 · 54 · 32710.1111/j.1151-2916.1971.tb12306.x ↗
34. Matzke · J. Chem. Soc. Faraday Trans. · 1990 · 86 · 124310.1039/ft9908601243 ↗
35. Inouye · J. Am. Ceram. Soc. · 1968 · 51 · 610.1111/j.1151-2916.1968.tb11818.x ↗
36. Javed · J. Less-Common Metals · 1972 · 29 · 15510.1016/0022-5088(72)90186-5 ↗
37. Jain · J. Nucl. Mater. · 1993 · 202 · 24510.1016/0022-3115(93)90394-E ↗
38. Arai · J. Nucl. Mater. · 1993 · 202 · 7010.1016/0022-3115(93)90030-3 ↗