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Title: Microstructural Analysis of As-Processed U-10 wt% Mo Monolithic Fuel Plate in AA6061 Matrix with Zr Diffusion Barrier

Abstract

For higher U-loading in low-enriched U-10wt.%Mo fuels, monolithic fuel plate clad in AA6061 is being developed as a part of Reduced Enrichment for Research and Test Reactor (RERTR) program. This paper reports the first characterization results from a monolithic U- 10wt.%Mo fuel plate with a Zr diffusion barrier that was fabricated as part of a plate fabrication campaign for irradiation testing in the Advanced Test Reactor (ATR). Both scanning and transmission electron microscopy (SEM and TEM) were employed for analysis. At the interface between the Zr barrier and U-10wt.%Mo, going from Zr-to-U(Mo), UZr2, ?-UZr, Zr solidsolution and Mo2Zr phases were observed. The interface between AA6061 cladding and Zr barrier plate consisted of four layers, going from Al-to-Zr, (Al,Si)2Zr, (Al,Si)Zr3 (Al,Si)3Zr, and AlSi4Zr5. Irradiation behavior of these intermetallic phases is discussed based on their constituents. Characterization of as-fabricated phase constituents and microstructure would help understand the irradiation behavior of these fuel plates, interpret post-irradiation examination, and optimize the processing parameters of monolithic fuel system.

Authors:
; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NA
OSTI Identifier:
990829
Report Number(s):
INL/JOU-10-18803
Journal ID: ISSN 0022-3115; TRN: US1007396
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 402; Journal Issue: 1
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ALUMINIUM BASE ALLOYS; DIFFUSION BARRIERS; FABRICATION; FUEL PLATES; FUEL SYSTEMS; IRRADIATION; MICROSTRUCTURE; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; PROCESSING; RESEARCH AND TEST REACTORS; TEST REACTORS; TESTING; TRANSMISSION ELECTRON MICROSCOPY; URANIUM-MOLYBDENUM FUELS; nuclear fuels; transmission electron microscopy; uranium alloy

Citation Formats

E. Perez, B. Yao, D. D. Keiser, Jr., and Y. H. Sohn. Microstructural Analysis of As-Processed U-10 wt% Mo Monolithic Fuel Plate in AA6061 Matrix with Zr Diffusion Barrier. United States: N. p., 2010. Web. doi:10.1016/j.jnucmat.2010.04.016.
E. Perez, B. Yao, D. D. Keiser, Jr., & Y. H. Sohn. Microstructural Analysis of As-Processed U-10 wt% Mo Monolithic Fuel Plate in AA6061 Matrix with Zr Diffusion Barrier. United States. doi:10.1016/j.jnucmat.2010.04.016.
E. Perez, B. Yao, D. D. Keiser, Jr., and Y. H. Sohn. Thu . "Microstructural Analysis of As-Processed U-10 wt% Mo Monolithic Fuel Plate in AA6061 Matrix with Zr Diffusion Barrier". United States. doi:10.1016/j.jnucmat.2010.04.016.
@article{osti_990829,
title = {Microstructural Analysis of As-Processed U-10 wt% Mo Monolithic Fuel Plate in AA6061 Matrix with Zr Diffusion Barrier},
author = {E. Perez and B. Yao and D. D. Keiser, Jr. and Y. H. Sohn},
abstractNote = {For higher U-loading in low-enriched U-10wt.%Mo fuels, monolithic fuel plate clad in AA6061 is being developed as a part of Reduced Enrichment for Research and Test Reactor (RERTR) program. This paper reports the first characterization results from a monolithic U- 10wt.%Mo fuel plate with a Zr diffusion barrier that was fabricated as part of a plate fabrication campaign for irradiation testing in the Advanced Test Reactor (ATR). Both scanning and transmission electron microscopy (SEM and TEM) were employed for analysis. At the interface between the Zr barrier and U-10wt.%Mo, going from Zr-to-U(Mo), UZr2, ?-UZr, Zr solidsolution and Mo2Zr phases were observed. The interface between AA6061 cladding and Zr barrier plate consisted of four layers, going from Al-to-Zr, (Al,Si)2Zr, (Al,Si)Zr3 (Al,Si)3Zr, and AlSi4Zr5. Irradiation behavior of these intermetallic phases is discussed based on their constituents. Characterization of as-fabricated phase constituents and microstructure would help understand the irradiation behavior of these fuel plates, interpret post-irradiation examination, and optimize the processing parameters of monolithic fuel system.},
doi = {10.1016/j.jnucmat.2010.04.016},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 402,
place = {United States},
year = {Thu Jul 01 00:00:00 EDT 2010},
month = {Thu Jul 01 00:00:00 EDT 2010}
}