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Title: ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID

Abstract

The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several types of power reactors. (auth)

Authors:
; ; ;
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
Sponsoring Org.:
USDOE
OSTI Identifier:
4833919
Report Number(s):
DP-647
NSA Number:
NSA-16-017759
DOE Contract Number:  
AT(07-2)-1
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ALUMINUM; CORROSION; ELECTROLYSIS; FUEL ELEMENTS; FUELS; MEASURED VALUES; MOLYBDENUM ALLOYS; NITRIC ACID; OXIDATION; POWER PLANTS; RADIOCHEMISTRY; REACTORS; REPROCESSING; SEPARATION PROCESSES; SOLUTIONS; STAINLESS STEELS; TESTING; URANIUM ALLOYS; URANIUM DIOXIDE; VELOCITY; ZIRCALOY; ZIRCONIUM; ZIRCONIUM ALLOYS

Citation Formats

Clark, A.T. Jr., Meyer, L.H., Owen, J.H., and Rust, F.G. ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID. United States: N. p., 1961. Web. doi:10.2172/4833919.
Clark, A.T. Jr., Meyer, L.H., Owen, J.H., & Rust, F.G. ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID. United States. doi:10.2172/4833919.
Clark, A.T. Jr., Meyer, L.H., Owen, J.H., and Rust, F.G. Sun . "ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID". United States. doi:10.2172/4833919. https://www.osti.gov/servlets/purl/4833919.
@article{osti_4833919,
title = {ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID},
author = {Clark, A.T. Jr. and Meyer, L.H. and Owen, J.H. and Rust, F.G.},
abstractNote = {The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several types of power reactors. (auth)},
doi = {10.2172/4833919},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {10}
}