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Title: In-Situ TEM Self Ion Irradiation and Thermal Aging of Zirconium Alloys.

Abstract

Abstract not provided.

Authors:
; ; ;
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1373253
Report Number(s):
SAND2016-7076C
646142
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the Microscopy and Microanlysis held July 24-28, 2016 in Columbus, Ohio.
Country of Publication:
United States
Language:
English

Citation Formats

Muntifering, Brittany R, Hattar, Khalid Mikhiel, Dingreville, Remi Philippe Michel, and Qu, Jianmin. In-Situ TEM Self Ion Irradiation and Thermal Aging of Zirconium Alloys.. United States: N. p., 2016. Web.
Muntifering, Brittany R, Hattar, Khalid Mikhiel, Dingreville, Remi Philippe Michel, & Qu, Jianmin. In-Situ TEM Self Ion Irradiation and Thermal Aging of Zirconium Alloys.. United States.
Muntifering, Brittany R, Hattar, Khalid Mikhiel, Dingreville, Remi Philippe Michel, and Qu, Jianmin. 2016. "In-Situ TEM Self Ion Irradiation and Thermal Aging of Zirconium Alloys.". United States. doi:. https://www.osti.gov/servlets/purl/1373253.
@article{osti_1373253,
title = {In-Situ TEM Self Ion Irradiation and Thermal Aging of Zirconium Alloys.},
author = {Muntifering, Brittany R and Hattar, Khalid Mikhiel and Dingreville, Remi Philippe Michel and Qu, Jianmin},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2016,
month = 7
}

Conference:
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  • The aging in plutonium is predominantly caused by its internal self-irradiation. The self-irradiation in Pu-239 is by the decay process of transmuting the Pu atom into uranium atom and emitting an {alpha}-particle. Most of the lattice damage comes from the uranium recoil resulting in Frenkel-type defects consisting of vacancies and self-interstitial atoms, helium in-growth and defect clusters and possibly even though it is not yet observed, the generation of voids. As part of the stockpile stewardship, it is important to understand the changes in the structure and microstructures and their correlations to the physical properties. Changes in the physical propertiesmore » have a direct relationship to the quality of the structure, in terms of formation of defects and defect clustering, accumulation of voids, grain boundaries, phase changes and etc. which can adversely affect the stability of the material. These changes are very difficult to monitor because of the high activity of the sample, high atomic number making x-ray and synchrotron probe into the bulk very difficult (neutron probe is not feasible) and the long life time which normally requires decades to measure. In this paper we describe the development of an in-situ in-house transmission x-ray diffraction (XRD) experimental technique used to monitor the structural changes in these materials. This technique calls for a very thin sample of less that 2 mm and to accelerate the aging process due to self-irradiation, spiked alloy of 7.5 weight percent of Pu-238 is used. This is equivalent to roughly 17 times the normal rate of aging. Current results suggest that over a period of 2.8 equivalent years, an increase of 0.5% in unit cell parameter is observed. The increase appears to be an abrupt jump at about 1.1 equivalent years, brought about by the collapsing of the atoms from the interstitials to the lattice sites. Further data analysis is on the way.« less
  • The Fe-Cr-Mn austenitic alloy system is being studied as a replacemnet of the Fe-Cr-Ni system for fusion applications in which reduced long-term radioactivation is an important consideration. This paper describes two aspects of the respone of this alloy system to material and environmental variables. First, the neutron-induced void swelling of simple binary and ternary alloys is investigated as a function of composition, thermal-mechanical treatment, temperature (693 to 873K) and displacement level (9 to 76 dpa). The swelling rate of this alloy system approaches 1%/dpa for those conditions which do not favor formation of large levels of ferrite phases. Second, themore » tendency of the potentially detrimental sigma phase to form during thermal aging is explored at high manganese levels. Variables such as carbon concentration, cold-work level and aging time are shown to influence the distribution and rate of sigma formation. 18 refs., 10 figs., 1 tab.« less
  • The High Voltage Electron Microscope (HVEM)/Tandem facility at Argonne National Laboratory has been used to conduct detailed studies of the phase stability and microstructural evolution in zirconium alloys and compounds under ion and electron irradiation. Detailed kinetic studies of the crystalline-to-amorphous transformation of the intermetallic compounds Zr{sub 3}(Fe{sub 1{minus}x},Ni{sub x}), Zr(Fe{sub 1{minus}x},Cr{sub x}){sub 2}, Zr{sub 3}Fe, and Zr{sub 1.5}Nb{sub 1.5}Fe, both as second phase precipitates and in bulk form, have been performed using the in situ capabilities of the Argonne facility under a variety of irradiation conditions (temperature, dose rate). Results include a verification of a dose rate effect onmore » amorphization and the influence of material variables (stoichiometry x, presence of stacking faults, crystal structure) on the critical temperature and on the critical dose for amorphization. Studies were also conducted of the microstructural evolution under irradiation of specially tailored binary and ternary model alloys. The stability of the {omega}-phase precipitation in Zr-2.5Nb under Ar ion irradiation. The ensemble of these results is discussed in terms of theoretical models of amorphization and of irradiation-altered solubility.« less
  • Abstract not provided.