Abstract
Uranium-free nonfertile Pu-based alloys, including Pu–40Zr and Pu-12Am–40Zr, represent two candidate fuel alloys for Generation IV (GEN-IV) and transuranic (TRU) type burner reactors. Before their acceptance in these applications, the chemical compatibility and interaction layer growth between these alloys and suggested HT-9 cladding must be reported in detail to facilitate their acceptance in advanced reactor concepts. In this study, each alloy was studied at 700 °C (973 K) for a variable period of time between 100 and 200 h in a diffusion couple geometry with Cr and V. Comparing the 100–200 h tests between Pu-12Am–40Zr fuel and Cr with V suggests a weakening in the interfacial growth rate as a function of annealing time. A quantitative study on the solid-state behavior and evolution of Pu-Am-Zr interacting with both Cr and V barriers at 700 °C (973 K) is reported.
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