skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Chemistry of zirconium related to the behavior of nuclear fuel cladding. Final report

Abstract

Studies of the chemistry of the zirconium-iodine and zirconium-oxygen systems were undertaken to elucidate their thermodynamics and kinetics. It is anticipated that the results obtained will lead to an improved understanding of the chemical processes involved in chemically assisted fuel rod failures. This project not only has classified the thermodynamics of both the gas phase and the solids in the zirconium-iodine system, it has also provided valuable information on the chemisorption of iodine and of oxygen on zirconium surfaces at high temperatures. In addition, the kinetics of reactions on zirconium surfaces were studied. These results have already been helpful in understanding the stress corrosion cracking of Zircaloy.

Authors:
Publication Date:
Research Org.:
SRI International, Menlo Park, CA (USA)
OSTI Identifier:
6075339
Report Number(s):
DOE/ET/11439-T2
ON: DE81029381; TRN: 82-000666
DOE Contract Number:  
AC03-77ET11439
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 22 GENERAL STUDIES OF NUCLEAR REACTORS; FUEL CANS; STRESS CORROSION; ZIRCALOY; ZIRCONIUM; OXIDATION; CHEMICAL REACTION KINETICS; CHEMISTRY; CRACKS; IODINE; OXYGEN; THERMODYNAMICS; ZIRCONIUM IODIDES; ALLOYS; CHEMICAL REACTIONS; CORROSION; ELEMENTS; HALIDES; HALOGEN COMPOUNDS; HALOGENS; IODIDES; IODINE COMPOUNDS; KINETICS; METALS; NONMETALS; REACTION KINETICS; TIN ALLOYS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS; 360105* - Metals & Alloys- Corrosion & Erosion; 220300 - Nuclear Reactor Technology- Fuel Elements

Citation Formats

Cubicciotti, D. Chemistry of zirconium related to the behavior of nuclear fuel cladding. Final report. United States: N. p., 1980. Web. doi:10.2172/6075339.
Cubicciotti, D. Chemistry of zirconium related to the behavior of nuclear fuel cladding. Final report. United States. https://doi.org/10.2172/6075339
Cubicciotti, D. Wed . "Chemistry of zirconium related to the behavior of nuclear fuel cladding. Final report". United States. https://doi.org/10.2172/6075339. https://www.osti.gov/servlets/purl/6075339.
@article{osti_6075339,
title = {Chemistry of zirconium related to the behavior of nuclear fuel cladding. Final report},
author = {Cubicciotti, D.},
abstractNote = {Studies of the chemistry of the zirconium-iodine and zirconium-oxygen systems were undertaken to elucidate their thermodynamics and kinetics. It is anticipated that the results obtained will lead to an improved understanding of the chemical processes involved in chemically assisted fuel rod failures. This project not only has classified the thermodynamics of both the gas phase and the solids in the zirconium-iodine system, it has also provided valuable information on the chemisorption of iodine and of oxygen on zirconium surfaces at high temperatures. In addition, the kinetics of reactions on zirconium surfaces were studied. These results have already been helpful in understanding the stress corrosion cracking of Zircaloy.},
doi = {10.2172/6075339},
url = {https://www.osti.gov/biblio/6075339}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1980},
month = {3}
}