Thermal evaluation of uranium suicide miniplates irradiated at high heat flux
Guillen, DP
| HERO ID | 1438516 |
|---|---|
| In Press | No |
| Year | 2012 |
| Title | Thermal evaluation of uranium suicide miniplates irradiated at high heat flux |
| Authors | Guillen, DP |
| Journal | Nuclear Engineering and Design |
| Volume | 250 |
| Page Numbers | 237-246 |
| Abstract | The Gas Test Loop (GTL)-1 irradiation experiment was conducted in the Advanced Test Reactor (ATR) to assess corrosion performance of proposed booster fuel at heat flux levels similar to 30% above the design operating condition. Sixteen miniplates fabricated from 25% enriched, high-density (4.8 g U/cm(3)) U3Si2/Al dispersion fuel with 6061 aluminum cladding were subjected to peak beginning of cycle (BOC) heat fluxes ranging from 411 to 593 W/cm(2). No adverse impacts to the miniplates were observed at these high heat flux levels. A detailed finite element model was constructed to calculate temperatures and heat flux for an as- run cycle average effective ATR south lobe power of 25.4 MW(t). Miniplate heat flux levels and fuel, cladding, hydroxide, and coolant-hydroxide interface temperatures were calculated using the average hydroxide thickness on each miniplate measured during post-irradiation examination. The purpose of this study was to obtain a best estimate of the as-run experiment temperatures to aid in establishing acceptable heat flux levels and designing fuel qualification experiments for this fuel type. (C) 2012 Elsevier B.V. All rights reserved. |
| Doi | 10.1016/j.nucengdes.2012.06.010 |
| Wosid | WOS:000308266500026 |
| Is Certified Translation | No |
| Dupe Override | No |
| Comments | Source: Web of Science WOS:000308266500026Scopus URL: https://www.scopus.com/inward/record.uri?eid=2-s2.0-84864474012&doi=10.1016%2fj.nucengdes.2012.06.010&partnerID=40&md5=1148d507e1d6e8c70e8d3d9687c17568 |
| Is Public | Yes |
| Language Text | English |