Thomas J. Downar, Sean M. McDeavitt
Cermet nuclear fuel has been demonstrated to have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle produces intriguing options for advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. This paper will first describe the fuel thermal performance model developed for the analysis of dispersion metal matrix fuels. The model is then applied to the design and analysis of thorium/uranium/zirconium metal-matrix fuel pins for light-water reactors using neutronic simulation methods.
@article{7c25d612-45a4-4cb7-bc5e-3ad7fc7d834b,
title={Thoria Based Cermet Nuclear Fuel Neutron},
author={Thomas J. Downar and Sean M. McDeavitt},
year={2026},
language={en}
}TY - JOUR TI - Thoria Based Cermet Nuclear Fuel Neutron AU - Thomas J. Downar AU - Sean M. McDeavitt PY - 2026 LA - en ER -
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