Assessing the solid-state kinetics and behavior for uranium-free Pu-12Am-40Zr alloys at 973 K

JOURNAL OF ALLOYS AND COMPOUNDS

卷:817

Article

Aguiar, Jeffery A.¹  Miller, Brandon D.¹  Tsuboi, Yasushi²  Johnson, Thomas¹  Arie, Kazuo²  Mariani, Robert D.¹ 

[1] Idaho Natl Lab, 2525 Fremont Ave, Idaho Falls, ID 83402 USA

[2] Toshiba Energy Syst & Solut Corp, Kawasaki, Kanagawa, Japan

关键词: Uranium-free Pu-based fuels;    Solid state kinetics;    Solid state chemistry;    Transmission electron microscopy;    Gen IV nuclear reactors;   

DOI  :  10.1016/j.jallcom.2019.152735

来源: Elsevier

【 摘 要 】

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 degrees 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 degrees C (973 K) is reported. (C) 2019 Elsevier B.V. All rights reserved.

【 授权许可】

Free