Abstract
An enhanced thermal conductivity UO2-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Elemnet Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. The results showed significant increase in the fuel thermal conductivities and have good agreement with the measured ones. The reactor performance analysis showed that the decrease in centerline temperature was 250-350K for the UO2-BeO composite fuel, and thus we can improve nuclear reactors' performance and safety, and high-level radioactive waste generation.
| Original language | English |
|---|---|
| Title of host publication | LWR Fuel Performance Meeting, Top Fuel 2013 |
| Publisher | American Nuclear Society |
| Pages | 1167-1173 |
| Volume | 2 |
| ISBN (Print) | 9781629937212 |
| Publication status | Published - 2013 |
| Event | LWR Fuel Performance Meeting, Top Fuel 2013 - Charlotte, NC, United States Duration: 15 Sept 2013 → 19 Sept 2013 |
Publication series
| Name | |
|---|---|
| Volume | 2 |
Conference
| Conference | LWR Fuel Performance Meeting, Top Fuel 2013 |
|---|---|
| Place | United States |
| City | Charlotte, NC |
| Period | 15/09/13 → 19/09/13 |
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
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SDG 12 Responsible Consumption and Production
Research Keywords
- ANSYS
- Composite fuel
- FEM
- Temperature difference profiles
- Thermal conductivity
- UO2-BeO
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