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Title: REPROCESSING OF POWER REACTOR FUELS. Tenth Quarterly Progress Report for JANUARY 1, 1960 to April 1, 1960

Abstract

Electrolytic dissolution of unirradiated Fcrmi core elements and of Zircaloy-2 was successfully demonstrated on a laboratory scale. Tantalum and niobium are adequate as materials of construction for the inert anode basket of as electrolytic dissolver in a field of 10/sup 7/ rep/hr. The corrosion of 304L and 3O9SCb in boiling HNO/sub 3/ is increased by the presence of dissolved stainless steel, which promotes intergranular attack of these metals. Corrosion tests of both welded and wrought 309SCb indicated that a solution of 0.075M HF and 0.05 to 1M HNO/sub 3/ offers advantages over either the 0.075M HF or the 0.075M HF --3.0M HNO/sub 3/ solutions previously proposed for the chemical dissolution of Fermi core elements, Urirradiated Zr--low U alloy was dissolved in 1M HNO/sub 3/ by intermittent addition of HF at such a rate as to obtain an average penetration rate of 4.5 mils per hour. The average composition of the off-gas was 8% H/sub 2/, 18% N/sub 2/. 50% NO. 23% N/sub 2/O. and 1% miscellaneous trace gases. (For preceding period see DP-479.) (auth)

Authors:
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
OSTI Identifier:
4142701
Report Number(s):
DP-491
NSA Number:
NSA-15-001458
DOE Contract Number:  
AT(07-2)-1
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; CORROSION; ELECTROLYSIS; FUEL ELEMENTS; HYDROFLUORIC ACID; LEACHING; NIOBIUM; NITRIC ACID; TANTALUM; URANIUM ALLOYS; WASTE PROCESSING; ZIRCALOY; ZIRCONIUM ALLOYS

Citation Formats

Oscchipinti, E.S. comp. REPROCESSING OF POWER REACTOR FUELS. Tenth Quarterly Progress Report for JANUARY 1, 1960 to April 1, 1960. United States: N. p., 1960. Web. doi:10.2172/4142701.
Oscchipinti, E.S. comp. REPROCESSING OF POWER REACTOR FUELS. Tenth Quarterly Progress Report for JANUARY 1, 1960 to April 1, 1960. United States. doi:10.2172/4142701.
Oscchipinti, E.S. comp. Sat . "REPROCESSING OF POWER REACTOR FUELS. Tenth Quarterly Progress Report for JANUARY 1, 1960 to April 1, 1960". United States. doi:10.2172/4142701. https://www.osti.gov/servlets/purl/4142701.
@article{osti_4142701,
title = {REPROCESSING OF POWER REACTOR FUELS. Tenth Quarterly Progress Report for JANUARY 1, 1960 to April 1, 1960},
author = {Oscchipinti, E.S. comp.},
abstractNote = {Electrolytic dissolution of unirradiated Fcrmi core elements and of Zircaloy-2 was successfully demonstrated on a laboratory scale. Tantalum and niobium are adequate as materials of construction for the inert anode basket of as electrolytic dissolver in a field of 10/sup 7/ rep/hr. The corrosion of 304L and 3O9SCb in boiling HNO/sub 3/ is increased by the presence of dissolved stainless steel, which promotes intergranular attack of these metals. Corrosion tests of both welded and wrought 309SCb indicated that a solution of 0.075M HF and 0.05 to 1M HNO/sub 3/ offers advantages over either the 0.075M HF or the 0.075M HF --3.0M HNO/sub 3/ solutions previously proposed for the chemical dissolution of Fermi core elements, Urirradiated Zr--low U alloy was dissolved in 1M HNO/sub 3/ by intermittent addition of HF at such a rate as to obtain an average penetration rate of 4.5 mils per hour. The average composition of the off-gas was 8% H/sub 2/, 18% N/sub 2/. 50% NO. 23% N/sub 2/O. and 1% miscellaneous trace gases. (For preceding period see DP-479.) (auth)},
doi = {10.2172/4142701},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {10}
}

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