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Title: REPROCESSING OF POWER REACTOR FUELS. Quarterly Progress Report No. 9 for October 1, 1959 to January 1, 1960

Abstract

Pressure and mechanical vibration are effective in maintaining continuous anodic dissolution in HHO/sub 3/ of stainless steel contained in an electrolytically inert anode basket. Zirconium metal can be electrolytically disintegrated in HNO/sub 2/ by the same technique: in this case 85% of the zirconium precipitates as ZrO/sub 2/ and only 15% remains in solution. When Zr- 10% U alloy is electrolytically disintegrated in HNO/sub 3/, 60 to 80% of the zirconium precipitates as ZrO/sub 2/, carrying 10% or more of the uranium. The constituents of a charge of PRDC elements, zirconium and U- Mo alloy. were dissolved in a two-step process with HNO/sub 3/ and HF. The rate of dissolution of irradiated PRDC fuel is one to two times that of unirradiated fuel. (For preceding period see DP-439.) (auth)

Authors:
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
OSTI Identifier:
4134985
Report Number(s):
DP-479
NSA Number:
NSA-14-025538
DOE Contract Number:  
AT(07-2)-1
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ANODES; DECOMPOSITION; EFFBR; ELECTROLYSIS; FUELS; HYDROFLUORIC ACID; METALS; MOLYBDENUM ALLOYS; NITRIC ACID; PRECIPITATION; REPROCESSING; STAINLESS STEELS; URANIUM ALLOYS; ZIRCONIUM; ZIRCONIUM ALLOYS; ZIRCONIUM OXIDES

Citation Formats

Meyer, L.H. comp. REPROCESSING OF POWER REACTOR FUELS. Quarterly Progress Report No. 9 for October 1, 1959 to January 1, 1960. United States: N. p., 1960. Web. doi:10.2172/4134985.
Meyer, L.H. comp. REPROCESSING OF POWER REACTOR FUELS. Quarterly Progress Report No. 9 for October 1, 1959 to January 1, 1960. United States. doi:10.2172/4134985.
Meyer, L.H. comp. Tue . "REPROCESSING OF POWER REACTOR FUELS. Quarterly Progress Report No. 9 for October 1, 1959 to January 1, 1960". United States. doi:10.2172/4134985. https://www.osti.gov/servlets/purl/4134985.
@article{osti_4134985,
title = {REPROCESSING OF POWER REACTOR FUELS. Quarterly Progress Report No. 9 for October 1, 1959 to January 1, 1960},
author = {Meyer, L.H. comp.},
abstractNote = {Pressure and mechanical vibration are effective in maintaining continuous anodic dissolution in HHO/sub 3/ of stainless steel contained in an electrolytically inert anode basket. Zirconium metal can be electrolytically disintegrated in HNO/sub 2/ by the same technique: in this case 85% of the zirconium precipitates as ZrO/sub 2/ and only 15% remains in solution. When Zr- 10% U alloy is electrolytically disintegrated in HNO/sub 3/, 60 to 80% of the zirconium precipitates as ZrO/sub 2/, carrying 10% or more of the uranium. The constituents of a charge of PRDC elements, zirconium and U- Mo alloy. were dissolved in a two-step process with HNO/sub 3/ and HF. The rate of dissolution of irradiated PRDC fuel is one to two times that of unirradiated fuel. (For preceding period see DP-439.) (auth)},
doi = {10.2172/4134985},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {3}
}

Technical Report:

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