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Title: Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979

Abstract

In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing of refractory metals and alloys, graphite, and SiC in PDPM environments was done. A tungsten-metallized Al/sub 2/O/sub 3/-3% Y/sub 2/O/sub 3/ crucible was successfully fabricated. Tungsten microstructure of a plasma-sprayed tungsten crucible was stabilized by nickel infiltration and heat treatment. Solubility measurements of Th in Cd and Cd-Mg alloys were continued, as were experiments to study the reduction of high-fired ThO/sub 2/. Work on the fused salt electrolysis of CaO also was continued. The method of coprocessing of U and Pu by a salt transport process was modified. Tungsten-coated molybdenum crucibles were fabricated. The proliferation resistance of chloride volatility processing of thorium-based fuels is being evaluated by studying the behavior of fission product elements during chlorination of U and Th. Thermodynamic analysis of the phase relationships in the U-Pu-Zn system was initiated. The Pyro-Civex reprocessing method is being reviewed. Reactivity of UO/sub 2/ and PuO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ is being studied along with the behavior of selected fission product elements. Work was continued on the reprocessing of actinide oxides by extracting the actinides from a bismuth solution. Rate of dissolution ofmore » UO/sub 2/ microspheres in LiCl/AlCl/sub 3/ was measured. Nitriding rates of Th and U dissolved in molten tin were measured. In work on the encapsulation of radioactive waste in metal, leach rates of a simulated waste glass were studied. Rates of dissolution of metals (potential barrier materials) in aqueous media are being studied. In work on the transport properties of nuclear waste in geologic media, the adsorption of iodate by hematite as a function of pH and iodate concentration was measured. The migration behavior of cesium in limestone was studied in relation to the cesium concentration and pH of simulated groundwater solutions.« less

Authors:
; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
5034027
Report Number(s):
ANL-79-45
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CADMIUM; SOLUBILITY; CALCIUM OXIDES; ELECTROLYSIS; FUEL CYCLE; CHEMICAL REACTIONS; RESEARCH PROGRAMS; PLUTONIUM; PHASE STUDIES; PLUTONIUM DIOXIDE; POTASSIUM NITRATES; SODIUM NITRATES; THORIUM; TUNGSTEN; MICROSTRUCTURE; URANIUM; URANIUM DIOXIDE; DISSOLUTION; ZINC; CHLORIDE VOLATILITY PROCESS; MICROSPHERES; PYROCHEMICAL REPROCESSING; SPENT FUELS; THORIUM OXIDES; ACTINIDE COMPOUNDS; ACTINIDES; ALKALI METAL COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; CALCIUM COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; ELEMENTS; ENERGY SOURCES; EXTRACTIVE METALLURGY; FUELS; LYSIS; MATERIALS; METALLURGY; METALS; NITRATES; NITROGEN COMPOUNDS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; POTASSIUM COMPOUNDS; PYROMETALLURGY; REACTOR MATERIALS; REFRACTORY METALS; REPROCESSING; SEPARATION PROCESSES; SODIUM COMPOUNDS; THORIUM COMPOUNDS; TRANSITION ELEMENTS; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES; 050800* - Nuclear Fuels- Spent Fuels Reprocessing

Citation Formats

Steindler, M J, Ader, M, and Barletta, R E. Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979. United States: N. p., 1980. Web. doi:10.2172/5034027.
Steindler, M J, Ader, M, & Barletta, R E. Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979. United States. https://doi.org/10.2172/5034027
Steindler, M J, Ader, M, and Barletta, R E. 1980. "Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979". United States. https://doi.org/10.2172/5034027. https://www.osti.gov/servlets/purl/5034027.
@article{osti_5034027,
title = {Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979},
author = {Steindler, M J and Ader, M and Barletta, R E},
abstractNote = {In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing of refractory metals and alloys, graphite, and SiC in PDPM environments was done. A tungsten-metallized Al/sub 2/O/sub 3/-3% Y/sub 2/O/sub 3/ crucible was successfully fabricated. Tungsten microstructure of a plasma-sprayed tungsten crucible was stabilized by nickel infiltration and heat treatment. Solubility measurements of Th in Cd and Cd-Mg alloys were continued, as were experiments to study the reduction of high-fired ThO/sub 2/. Work on the fused salt electrolysis of CaO also was continued. The method of coprocessing of U and Pu by a salt transport process was modified. Tungsten-coated molybdenum crucibles were fabricated. The proliferation resistance of chloride volatility processing of thorium-based fuels is being evaluated by studying the behavior of fission product elements during chlorination of U and Th. Thermodynamic analysis of the phase relationships in the U-Pu-Zn system was initiated. The Pyro-Civex reprocessing method is being reviewed. Reactivity of UO/sub 2/ and PuO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ is being studied along with the behavior of selected fission product elements. Work was continued on the reprocessing of actinide oxides by extracting the actinides from a bismuth solution. Rate of dissolution of UO/sub 2/ microspheres in LiCl/AlCl/sub 3/ was measured. Nitriding rates of Th and U dissolved in molten tin were measured. In work on the encapsulation of radioactive waste in metal, leach rates of a simulated waste glass were studied. Rates of dissolution of metals (potential barrier materials) in aqueous media are being studied. In work on the transport properties of nuclear waste in geologic media, the adsorption of iodate by hematite as a function of pH and iodate concentration was measured. The migration behavior of cesium in limestone was studied in relation to the cesium concentration and pH of simulated groundwater solutions.},
doi = {10.2172/5034027},
url = {https://www.osti.gov/biblio/5034027}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 01 00:00:00 EST 1980},
month = {Tue Jan 01 00:00:00 EST 1980}
}