| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
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Accelerated Materials Evaluation for Nuclear Applications Utilizing Irradiation and Integrated Modeling
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| Presentation Title |
In-situ Neutron Characterization of Advanced Nuclear Fuels - The Road to a New Neutron Irradiation Testing Capability |
| Author(s) |
Edward G. Obbard, Claudia Gasparrini, Patrick Burr, Kyle Johnson, Denise A. Lopes, Clara Anghel, Simon Middleburgh, Daniel J. Gregg, Klaus Dieter Liss, Grant Griffiths, Nicholas Scales, Gordon Thorogood, Greg Lumpkin |
| On-Site Speaker (Planned) |
Edward G. Obbard |
| Abstract Scope |
Neutron diffraction offers a method to characterise encapsulated nuclear materials, reducing the need to handle contaminating samples. Precise thermal expansion measurements and phase characterisation were performed from room temperature to 1873K, for U3Si2 and UN/U3Si2 accident tolerant fuel composites. U3Si2 shows a negative, linear temperature dependence of the instantaneous thermal expansion described by α(T) = 2.10E-05 – 7.25E-09 x T (1/K). Precise thermal expansion for UN was obtained over this temperature range. Post annealing characterisation highlighted the reaction between vanadium canning material and UN-U2.8Si2 composite, accompanied by vanadium grain boundary transport and formation of V5Si3 and V3Si. Results are interpreted in their direct context, and also regarding wider aims to enable testing of advanced fuels in research reactors that may not have extensive fuel PIE facilities but nonetheless do have world-leading small angle, wide angle and neutron tomography capability for this type of non-contact experimentation. |
| Proceedings Inclusion? |
Undecided |