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Title: Experiments for evaluation of corrosion to develop storage criteria for interim dry storage of aluminum-alloy clad spent nuclear fuel

Abstract

The technical bases for specification of limits to environmental exposure conditions to avoid excessive degradation are being developed for storage criteria for dry storage of highly-enriched, aluminum-clad spent nuclear fuels owned by the US Department of Energy. Corrosion of the aluminum cladding is a limiting degradation mechanism (occurs at lowest temperature) for aluminum exposed to an environment containing water vapor. Attendant radiation fields of the fuels can lead to production of nitric acid in the presence of air and water vapor and would exacerbate the corrosion of aluminum by lowering the pH of the water solution. Laboratory-scale specimens are being exposed to various conditions inside an autoclave facility to measure the corrosion of the fuel matrix and cladding materials through weight change measurements and metallurgical analysis. In addition, electrochemical corrosion tests are being performed to supplement the autoclave testing by measuring differences in the general corrosion and pitting corrosion behavior of the aluminum cladding alloys and the aluminum-uranium fuel materials in water solutions.

Authors:
; ; ;
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10193892
Report Number(s):
WSRC-MS-94-0564; CONF-941207-12
ON: DE95002691;
DOE Contract Number:
AC09-89SR18035
Resource Type:
Conference
Resource Relation:
Conference: Spent nuclear fuel meeting: challenges and initiatives,Salt Lake City, UT (United States),14-16 Dec 1994; Other Information: PBD: [1994]
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 36 MATERIALS SCIENCE; SAVANNAH RIVER PLANT; RADIOACTIVE WASTE DISPOSAL; SPENT FUELS; PACKAGING; ALUMINIUM; PITTING CORROSION; HIGHLY ENRICHED URANIUM; BENCH-SCALE EXPERIMENTS; 052002; 360105; WASTE DISPOSAL AND STORAGE; CORROSION AND EROSION

Citation Formats

Peacock, H.B., Sindelar, R.L., Lam, P.S., and Murphy, T.H. Experiments for evaluation of corrosion to develop storage criteria for interim dry storage of aluminum-alloy clad spent nuclear fuel. United States: N. p., 1994. Web.
Peacock, H.B., Sindelar, R.L., Lam, P.S., & Murphy, T.H. Experiments for evaluation of corrosion to develop storage criteria for interim dry storage of aluminum-alloy clad spent nuclear fuel. United States.
Peacock, H.B., Sindelar, R.L., Lam, P.S., and Murphy, T.H. Tue . "Experiments for evaluation of corrosion to develop storage criteria for interim dry storage of aluminum-alloy clad spent nuclear fuel". United States. doi:. https://www.osti.gov/servlets/purl/10193892.
@article{osti_10193892,
title = {Experiments for evaluation of corrosion to develop storage criteria for interim dry storage of aluminum-alloy clad spent nuclear fuel},
author = {Peacock, H.B. and Sindelar, R.L. and Lam, P.S. and Murphy, T.H.},
abstractNote = {The technical bases for specification of limits to environmental exposure conditions to avoid excessive degradation are being developed for storage criteria for dry storage of highly-enriched, aluminum-clad spent nuclear fuels owned by the US Department of Energy. Corrosion of the aluminum cladding is a limiting degradation mechanism (occurs at lowest temperature) for aluminum exposed to an environment containing water vapor. Attendant radiation fields of the fuels can lead to production of nitric acid in the presence of air and water vapor and would exacerbate the corrosion of aluminum by lowering the pH of the water solution. Laboratory-scale specimens are being exposed to various conditions inside an autoclave facility to measure the corrosion of the fuel matrix and cladding materials through weight change measurements and metallurgical analysis. In addition, electrochemical corrosion tests are being performed to supplement the autoclave testing by measuring differences in the general corrosion and pitting corrosion behavior of the aluminum cladding alloys and the aluminum-uranium fuel materials in water solutions.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Nov 01 00:00:00 EST 1994},
month = {Tue Nov 01 00:00:00 EST 1994}
}

Conference:
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