| dc.contributor | Oak Ridge National Laboratory, 37831, Oak Ridge, Tennessee | |
| dc.contributor.author | R. E. Pawel | en_US |
| dc.contributor.author | G. L. Yoder | |
| dc.contributor.author | D. K. Felde | |
| dc.contributor.author | B. H. Montgomery | |
| dc.contributor.author | M. T. McFee | |
| dc.date.accessioned | 2013-12-04T01:17:32Z | |
| dc.date.accessioned | 2015-09-12T02:49:30Z | |
| dc.date.available | 2013-12-04T01:17:32Z | |
| dc.date.available | 2015-09-12T02:49:30Z | |
| dc.date.issued | 2013-12-03 | |
| dc.identifier.citation | Oxidation of Metals (1991) Vol 36 p 175-194 | en_US |
| dc.identifier.uri | http://hdl.handle.net/11115/216 | |
| dc.description.abstract | The corrosion of aluminum alloy fuel cladding in ultrahigh flux research reactors such as the Advanced Neutron Source may pose special temperature and structural problems associated with the buildup of reaction products during the lifetime of the core. In order to ensure that both the fuel and cladding integrity are maintained for the special conditions to be imposed on the ANS fuel plates, an experimental facility was constructed that permits the examination of material behavior for a wide range of thermal-hydraulic conditions, particularly high heat flux (to 20 MW/m ) and coolant velocity (to 35m/sec). 25 occurrences ov 6061. | en_US |
| dc.relation.uri | http://dx.doi.org/10.1007/BF00938461 | |
| dc.title | The corrosion of 6061 aluminum under heat transfer conditions in the ANS corrosion test loop, | en_US |
