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Title: Evaluation of Corrosion of Aluminum Based Reactor Fuel Cladding Materials During Dry Storage

Abstract

This report provides an evaluation of the corrosion behavior of aluminum cladding alloys and aluminum-uranium alloys at conditions relevant to dry storage. The details of the corrosion program are described and the results to date are discussed.

Authors:
Publication Date:
Research Org.:
Savannah River Site (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
14489
Report Number(s):
WSRC-TR-95-0345
TRN: US0111053
DOE Contract Number:  
AC09-89SR18035
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 21 Oct 1999
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; ALUMINIUM ALLOYS; CORROSION; DRY STORAGE; FUEL CANS; EVALUATION; SPENT FUELS; URANIUM ALLOYS

Citation Formats

Peacock, H.B. Jr. Evaluation of Corrosion of Aluminum Based Reactor Fuel Cladding Materials During Dry Storage. United States: N. p., 1999. Web. doi:10.2172/14489.
Peacock, H.B. Jr. Evaluation of Corrosion of Aluminum Based Reactor Fuel Cladding Materials During Dry Storage. United States. doi:10.2172/14489.
Peacock, H.B. Jr. Thu . "Evaluation of Corrosion of Aluminum Based Reactor Fuel Cladding Materials During Dry Storage". United States. doi:10.2172/14489. https://www.osti.gov/servlets/purl/14489.
@article{osti_14489,
title = {Evaluation of Corrosion of Aluminum Based Reactor Fuel Cladding Materials During Dry Storage},
author = {Peacock, H.B. Jr.},
abstractNote = {This report provides an evaluation of the corrosion behavior of aluminum cladding alloys and aluminum-uranium alloys at conditions relevant to dry storage. The details of the corrosion program are described and the results to date are discussed.},
doi = {10.2172/14489},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {10}
}