Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Journal Article · Thu Sep 09 00:00:00 EDT 2021 · JOM. Journal of the Minerals, Metals & Materials Society

DOI:https://doi.org/10.1007/s11837-021-04844-2· OSTI ID:1819484

Parker, S. S.; Newman, S.; Fallgren, A. J.; White, J. T.

Abstract

The miscibility, lattice parameter, and thermophysical properties of (Th _0.2 U _0.8 )N and (Th _0.5 U _0.5 )N have been investigated. It is shown that additions of thorium nitride (ThN) to uranium nitride (UN) increases the thermophysical performance of the mixed nitride fuel form in comparison to reference UN. In the more dilute limit, additions of ThN serve as a burnable neutronic poison and reduces the change in k _eff over the lifecycle of the fuel. At higher concentrations, additions of ThN serve as a significant fertile source of ²³³ U. Where appropriate, comparisons to previous work on UN + PuN mixtures are made, as this is a comparable fuel form for potential fast reactor concepts, and a suitable point of contrast in the possible design space afforded by mixed (Th _x U _1 − x )N fuel forms. The data from this work are the input parameters for finite element modeling of the temperature distribution in a compact reactor. The results of modeling and simulation of this core design are shown for the case of steady-state operation and during double, adjacent heat pipe failure.

• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA)
• OSTI ID: 1819484
• Journal Information: JOM. Journal of the Minerals, Metals & Materials Society, Journal Name: JOM. Journal of the Minerals, Metals & Materials Society Journal Issue: 11 Vol. 73; ISSN 1047-4838
• Publisher: Springer Science + Business Media
• Country of Publication: United States
• Language: English