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Microstructure of RERTR DU-alloys irradiated with krypton ions up to 100 dpa
The radiation stability of the interaction product formed at the fuel–matrix interface of research reactor dispersion fuels, under fission-product bombardment, has a strong impact on fuel performance. Three depleted uranium alloys were cast that consisted of the following five phases to be investiga...
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Published in: | Journal of nuclear materials 2011-04, Vol.411 (1), p.174-180 |
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Main Authors: | , , , , , , |
Format: | Article |
Language: | English |
Subjects: | |
Online Access: | Get full text |
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Summary: | The radiation stability of the interaction product formed at the fuel–matrix interface of research reactor dispersion fuels, under fission-product bombardment, has a strong impact on fuel performance. Three depleted uranium alloys were cast that consisted of the following five phases to be investigated: U(Si, Al)
3, (U, Mo)(Si, Al)
3, UMo
2Al
20, U
6Mo
4Al
43, and UAl
4. Irradiation of transmission electron microscopy (TEM) disc samples with 500-keV Kr ions at 200
°C to doses up to ∼100 displacements per atom (dpa) were conducted using a 300-keV electron microscope equipped with an ion accelerator. TEM results show that the U(Si, Al)
3 and UAl
4 phases remain crystalline at 100
dpa without forming voids. The (U, Mo)(Si, Al)
3 and UMo
2Al
20 phases become amorphous at 1 and ∼2
dpa, respectively, and show no evidence of voids at 100
dpa. The U
6Mo
4Al
43 phase goes to amorphous at less than 1
dpa and reveals high density voids at 100
dpa. |
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ISSN: | 0022-3115 1873-4820 |
DOI: | 10.1016/j.jnucmat.2011.01.121 |