Abstract
Detailed analysis of the particle distribution in Transformational Challenge Reactor fuel elements indicates that particle packing is not random; instead, it follows a relatively ordered structure near fuel element surfaces. Discrete particle neutronic simulations indicate that the core reactivity is not impacted when assuming homogenization of particles with the silicon carbide matrix. However, the neutronic power distribution resulting from the ordered packing structure indicates that the highest-power particles reside at the top and bottom of the fuel elements and nearest the YH1.85 moderator rods. The power distribution results were applied to thermomechanical simulations using mesh-based power distributions. Previous results indicated high stress at the bottom of the fuel element, where packing is most ordered. To reduce this stress concentration, additively manufactured protrusions were added to the bottom of a test fuel element to disrupt dense particle packing. These protrusions reduced the overall power peaking, but the thermomechanical simulations did not indicate a significant change in the fuel element’s maximum stress or failure probability.
Original language | English |
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Pages (from-to) | 1517-1538 |
Number of pages | 22 |
Journal | Nuclear Science and Engineering |
Volume | 196 |
Issue number | 12 |
DOIs | |
State | Published - 2022 |
Funding
This work was supported by the Office of Nuclear Energy. This work was supported by the DOE-NE TCR program. Special thanks to ORNL Manufacturing Demonstration Facility staff for the initial design iteration of the TCR fuel element, as well Justin Weinmeister and Prashant Jain for additional fuel element design and optimization. This paper has been authored by UT-Battelle, LLC, under contract number DE-AC05-00OR22725 with the DOE. This work was supported by the DOE-NE TCR program. Special thanks to ORNL Manufacturing Demonstration Facility staff for the initial design iteration of the TCR fuel element, as well Justin Weinmeister and Prashant Jain for additional fuel element design and optimization. This paper has been authored by UT-Battelle, LLC, under contract number DE-AC05-00OR22725 with the DOE.
Funders | Funder number |
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DOE-NE | |
U.S. Department of Energy | |
Office of Nuclear Energy | DE-AC05-00OR22725 |
Keywords
- 3-D printing
- TCR
- TRISO
- microreactor
- yttrium hydride