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Title: Phase transformations in neutron-irradiated Zircaloys

Abstract

Microstructural evolution in Zircaloy-2 and -4 spent-fuel cladding specimens after approx.3 years of irradiation in commercial power reactors has been investigated by TEM and HVEM. Two kinds of precipitates induced by the fast-neutron irradiation in the reactors have been identified, i.e., Zr/sub 3/O and cubic-ZrO/sub 2/ particles approximately 2 to 10 nm in size. By means of a weak-beam dark-field ''2-1/2D-microscopy'' technique, the bulk nature of the precipitates and the surficial nature of artifact oxide and hydride phases could be discerned. The Zr(Fe/sub x/,Cr/sub 1-x/)/sub 2/ and Zr/sub 2/(Fe/sub x/,Ni/sub 1-x/) intermetallic precipitates normally present in the as-fabricated material virtually dissolved in the spent-fuel cladding specimens after a fast-neutron fluence of approx.4 x 10/sup 21/ ncm/sup -2/ in the power reactors. The observed radiation-induced phase transformations are compared with predictions based on the currently available understanding of the alloy characteristics. 29 refs.

Authors:
Publication Date:
Research Org.:
Argonne National Lab., IL (USA). Materials Science and Technology Div.
OSTI Identifier:
5462312
Report Number(s):
CONF-860605-20
ON: TI86014487
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: 13. international symposium on the effects of radiation on materials, Seattle, WA, USA, 23 Jun 1986
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; FUEL CANS; PWR TYPE REACTORS; ZIRCALOY; IRRADIATION; PHASE TRANSFORMATIONS; MICROSTRUCTURE; NEUTRONS; PHYSICAL RADIATION EFFECTS; ALLOYS; BARYONS; CRYSTAL STRUCTURE; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NUCLEONS; RADIATION EFFECTS; REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; 360106* - Metals & Alloys- Radiation Effects; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Chung, H M. Phase transformations in neutron-irradiated Zircaloys. United States: N. p., 1986. Web.
Chung, H M. Phase transformations in neutron-irradiated Zircaloys. United States.
Chung, H M. 1986. "Phase transformations in neutron-irradiated Zircaloys". United States. https://www.osti.gov/servlets/purl/5462312.
@article{osti_5462312,
title = {Phase transformations in neutron-irradiated Zircaloys},
author = {Chung, H M},
abstractNote = {Microstructural evolution in Zircaloy-2 and -4 spent-fuel cladding specimens after approx.3 years of irradiation in commercial power reactors has been investigated by TEM and HVEM. Two kinds of precipitates induced by the fast-neutron irradiation in the reactors have been identified, i.e., Zr/sub 3/O and cubic-ZrO/sub 2/ particles approximately 2 to 10 nm in size. By means of a weak-beam dark-field ''2-1/2D-microscopy'' technique, the bulk nature of the precipitates and the surficial nature of artifact oxide and hydride phases could be discerned. The Zr(Fe/sub x/,Cr/sub 1-x/)/sub 2/ and Zr/sub 2/(Fe/sub x/,Ni/sub 1-x/) intermetallic precipitates normally present in the as-fabricated material virtually dissolved in the spent-fuel cladding specimens after a fast-neutron fluence of approx.4 x 10/sup 21/ ncm/sup -2/ in the power reactors. The observed radiation-induced phase transformations are compared with predictions based on the currently available understanding of the alloy characteristics. 29 refs.},
doi = {},
url = {https://www.osti.gov/biblio/5462312}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Apr 01 00:00:00 EST 1986},
month = {Tue Apr 01 00:00:00 EST 1986}
}

Conference:
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