A machine learning approach to thermal conductivity modeling: A case study on irradiated uranium-molybdenum nuclear fuels

Author:

Kautz Elizabeth J.,Hagen Alexander R.,Johns Jesse M.,Burkes Douglas E.

Publisher

Elsevier BV

Subject

Computational Mathematics,General Physics and Astronomy,Mechanics of Materials,General Materials Science,General Chemistry,General Computer Science

Reference73 articles.

1. Fuel thermo-physical characterization project: Fiscal year 2013 final report;Burkes,2013

2. Fuel thermo-physical characterization project: Fiscal year 2014 final report;Burkes,2015

3. Thermal properties of U-Mo alloys irradiated to moderate burnup and power;Burkes;J. Nucl. Mater.,2015

4. Review of 15 years of high-density low-enriched UMo dispersion fuel development for research reactors in europe;Van Den Berghe;Nucl. Eng. Technol.,2014

5. Microstructural evolution of the interdiffusion zone between U-9 wt% Mo fuel alloy and Zr-1 wt% Nb cladding alloy upon annealing;Neogy;Metall. Mater. Trans. A,2017

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