| Autor: |
Nagothi BS; General Electric Research Center, 1 Research Circle, Schenectady, NY 12309, USA.; College of Nanotechnology, Science, and Engineering, University at Albany, Albany, NY 12203, USA., Qu H; General Electric Research Center, 1 Research Circle, Schenectady, NY 12309, USA., Zhang W; General Electric Research Center, 1 Research Circle, Schenectady, NY 12309, USA., Umretiya RV; General Electric Research Center, 1 Research Circle, Schenectady, NY 12309, USA., Dolley E; General Electric Research Center, 1 Research Circle, Schenectady, NY 12309, USA., Rebak RB; General Electric Research Center, 1 Research Circle, Schenectady, NY 12309, USA. |
| Abstrakt: |
After the Fukushima nuclear disaster, the nuclear materials community has been vastly investing in accident tolerant fuel (ATF) concepts to modify/replace Zircaloy cladding material. Iron-chromium-aluminum (FeCrAl) alloys are one of the leading contenders in this race. In this study, we investigated FA-SMT (or APMT-2), PM-C26M, and Fe17Cr5.5Al over a time period of 6 months in simulated BWR environments and compared their performance with standard Zirc-2 and SS316 materials. Our results implied that water chemistry along with alloy chemistry has a profound effect on the corrosion rate of FeCrAl alloys. Apart from SS316 and Zirc-2 tube specimens, all FeCrAl alloys showed a mass loss in hydrogen water chemistry (HWC). FA-SMT displayed minimal mass loss compared to PM-C26M and Fe17Cr5.5Al because of its higher Cr content. The mass gain of FeCrAl alloys in normal water chemistry (NWC) is significantly less when compared to Zirc-2. |
