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Title: Microstructural anomalies in hot-isostatic pressed U–10wt.% Mo fuel plates with Zr diffusion barrier

Microstructural anomalies in the co-rolled-and-HIP'ed U–10 wt.% Mo (U10Mo) metallic fuel plate with Zr diffusion barrier assembly were examined as a function of HIP temperature (from 520 to 580 °C) and duration (45, 60, 90, 180 and 345 min) by scanning and transmission electron microscopy. The anomalies observed in this study are carbide/oxide inclusions within the U10Mo fuel alloy, and regions of limited interaction between the U10Mo alloy and Zr barrier, frequently associated with carbide/oxide inclusions. In the U10Mo alloy, the cF8, Fm3m (225) UC phase (a=4.955 Å) and cF12, Fm3m (225) UO2 phase (a=5.467 Å) were observed throughout the U10Mo alloy with an approximate volume percent of 0.5 to 1.8. The volume percent of the UC–UO2 inclusions within the U10Mo alloy did not change as functions of HIP temperature and time. These inclusion phases, located near the surface of the U10Mo alloy, were frequently observed to impede the development of interdiffusion and reaction between the U10Mo alloy and Zr diffusion barrier. The regions of limited interaction between the U10Mo and Zr barrier decreased with an increase in HIP temperature, however no noticeable trend was observed with an increase in HIP duration at constant temperature of 560 °C.
Authors:
 [1] ;  [1] ;  [2] ;  [2] ;  [2] ;  [2] ;  [1]
  1. Univ. of Central Florida, Orlando, FL (United States). Advanced Materials Processing and Analysis Center (AMPAC)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1188616
Report Number(s):
INL/JOU--15-35647
Journal ID: ISSN 1044-5803; TRN: US1500207
DOE Contract Number:
AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Materials Characterization; Journal Volume: 103; Journal Issue: C
Publisher:
Elsevier
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; URANIUM DIOXIDE; FCC LATTICES; URANIUM CARBIDES; FUEL PLATES; MOLYBDENUM ALLOYS; URANIUM BASE ALLOYS; BINARY ALLOY SYSTEMS; INCLUSIONS; MICROSTRUCTURE; URANIUM CARBIDES; PRESSING; NUCLEAR FUELS; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE DEPENDENCE; ZIRCONIUM; TIME DEPENDENCE; SCANNING ELECTRON MICROSCOPY; TRANSMISSION ELECTRON MICROSCOPY; COATINGS URANIUM ALLOY