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Title: Gallium interactions with zircaloy cladding

Abstract

The effects of Ga from weapons-grade plutonium MOX fuel on zircaloy-IV cladding during power reactor operation have been simulated by implantations of 100 keV Ga-69 ions into a polished zircaloy-IV sample while the sample was maintained at a typical cladding temperature of 375{degrees}C. Analyses were based on scanning electron microscopy, Rutherford backscattering of 280 keV He-3 ions, and secondary ion mass spectroscopy. Subgrains at the zircaloy-IV surface formed at a Ga fluence equivalent to total release of approximately 12 ppm by weight of Ga from the fuel. The subgrains may be an intermetallic compound of Zr{sub 2}Ga. Enhanced diffusion of Ga was observed, but Ga concentrations decreased 3 orders of magnitude over a depth of 3000 {angstrom}.

Authors:
; ; ;  [1]
  1. Texas A&M Univ., College Station, TX (United States)
Publication Date:
Research Org.:
Amarillo National Resource Center for Plutonium, TX (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States); USDOE Office of Fissile Materials Disposition, Washington, DC (United States)
OSTI Identifier:
615633
Report Number(s):
ANRCP-1998-5
ON: DE98005698; TRN: 98:006330
DOE Contract Number:  
FC04-95AL85832
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: May 1998
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FUEL CANS; ZIRCALOY 4; GALLIUM; CHEMICAL REACTIONS; GRAIN GROWTH; DIFFUSION; MIXED OXIDE FUELS; WATER COOLED REACTORS; PLUTONIUM

Citation Formats

Hart, R.R., Rennie, J., Aucoin, K., and West, M. Gallium interactions with zircaloy cladding. United States: N. p., 1998. Web. doi:10.2172/615633.
Hart, R.R., Rennie, J., Aucoin, K., & West, M. Gallium interactions with zircaloy cladding. United States. doi:10.2172/615633.
Hart, R.R., Rennie, J., Aucoin, K., and West, M. Fri . "Gallium interactions with zircaloy cladding". United States. doi:10.2172/615633. https://www.osti.gov/servlets/purl/615633.
@article{osti_615633,
title = {Gallium interactions with zircaloy cladding},
author = {Hart, R.R. and Rennie, J. and Aucoin, K. and West, M.},
abstractNote = {The effects of Ga from weapons-grade plutonium MOX fuel on zircaloy-IV cladding during power reactor operation have been simulated by implantations of 100 keV Ga-69 ions into a polished zircaloy-IV sample while the sample was maintained at a typical cladding temperature of 375{degrees}C. Analyses were based on scanning electron microscopy, Rutherford backscattering of 280 keV He-3 ions, and secondary ion mass spectroscopy. Subgrains at the zircaloy-IV surface formed at a Ga fluence equivalent to total release of approximately 12 ppm by weight of Ga from the fuel. The subgrains may be an intermetallic compound of Zr{sub 2}Ga. Enhanced diffusion of Ga was observed, but Ga concentrations decreased 3 orders of magnitude over a depth of 3000 {angstrom}.},
doi = {10.2172/615633},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri May 01 00:00:00 EDT 1998},
month = {Fri May 01 00:00:00 EDT 1998}
}

Technical Report:

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