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}
}