The possible usage of ex-ADU uranium dioxide fuel pellets with low-temperature sintering
Source abstract
Abstract
Abstract UO2 fuel pellets are prepared conventionally by high- and low-temperature sintering. Both ex-ammonium uranyl carbonate (AUC) and ex-ammonium diuranate (ADU) UO2 are used in these techniques. Larger quantities of chemicals (NH3 and CO2) are required for the AUC process which is a significant complication compared with the ADU process. In this work, it is aimed to search the important parameters such as theoretical density (TD) and grain size of ex-ADU UO2 pellets which are in an oxidative atmosphere at low temperature. A density of ≈95% TD is obtained at 1150°C. The grain structure of the pellets sintered in an oxidative atmosphere is monomodal unlike the duplex grain structure of ex-AUC oxide, but it is in accord with ex-ammonium uranate (AU) oxide. The grain structure, distribution and size are compared with the ex-AUC and ex-AU conversion processes. It is shown that the grain structure development depends on both the powder properties and the sintering atmosphere.
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 (21)
Show source-provided references
1. Assmann · J. Nucl. Mater. · 1986 · 140 · 110.1016/0022-3115(86)90189-3 ↗
2. A.S. Halim, KWU-Report B 22/83/e 17 (1983)10.1080/10714839.1983.11723579 ↗
3. W. Dörr, H. Assmann, in: Proceedings of the Fourth International Meeting on Modern Ceramics Technologies, Saint Vincent, Italy, 1979, Elsevier, Amsterdam, 1980, p. 913
4. Han · J. Korean Nucl. Soc. · 1983 · 15 · 197
5. Harada · J. Nucl. Mater. · 1996 · 238 · 23710.1016/S0022-3115(96)00443-6 ↗
6. Song · J. Nucl. Mater. · 1994 · 209 · 28010.1016/0022-3115(94)90264-X ↗
7. Song · J. Nucl. Mater. · 1993 · 200 · 4110.1016/0022-3115(93)90007-L ↗
8. Yuda · J. Nucl. Mater. · 1991 · 178 · 19510.1016/0022-3115(91)90386-L ↗
9. H.S. Kim, S.H. Kim, B.G. Kim, Y.W. Lee, D.S. Sohn, in: Proceedings of the Workshop on Manufacturing Technology and Process for Reactor Fuels, JAERI-Conference 96-006, Tokai, Japan, 1996, p. 92
10. Haas · Nucl. Technol. · 1988 · 81 · 39310.13182/NT88-A16060 ↗
11. H. Assmann, H. Stehle, in: Proceedings of the Fourth International Meeting on Modern Ceramics Technologies, Saint Vincent, Italy, 1979, Elsevier, Amsterdam, 1980, p. 893
12. Assmann · J. Am. Ceram. Soc. · 1984 · 67 · 63110.1111/j.1151-2916.1984.tb19608.x ↗
13. Ganguly · J. Nucl. Mater. · 1991 · 178 · 17910.1016/0022-3115(91)90384-J ↗
14. Baldewicz · Nucl. Technol. · 1979 · 46 · 26310.13182/NT79-A32326 ↗
15. Turnbull · J. Nucl. Mater. · 1974 · 50 · 4710.1016/0022-3115(74)90059-2 ↗
16. Assmann · J. Nucl. Mater. · 1981 · 98 · 21610.1016/0022-3115(81)90401-3 ↗
17. Fuhrman · J. Am. Ceram. Soc. · 1963 · 46 · 11410.1111/j.1151-2916.1963.tb11692.x ↗
18. Harada · J. Nucl. Mater. · 1997 · 245 · 21710.1016/S0022-3115(96)00755-6 ↗
19. M.T. Aybers, B. Kopuz, A. Yaylı, L. Çolak, A.A. Akşit, Y. Bayram, Resarch Report-260, 1989, Cekmece Nuclear Research and Training Center, Turkish Atomic Energy Association
20. Dörr · J. Nucl. Mater. · 1982 · 106 · 6110.1016/0022-3115(82)90333-6 ↗
21. B. Ayaz, A.N. Bilge, Advances in Dry Processing 2000, Cahners, November 1999, A Supplement to Powder/Bulk Solids, p. 54