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Lewis, M.A.; Pereira, C.
Dept. of Energy, Washington, DC (United States)1997
Dept. of Energy, Washington, DC (United States)1997
AbstractAbstract
[en] A method is described for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form leach resistant sodalite with occluded radionuclides and hazardous nuclear material. The zeolite and glass are heated to a temperature up to about 1000 K to convert the zeolite to sodalite and thereafter maintained at a pressure and temperature sufficient to form a sodalite product near theoretical density. Pressure is used on the formed sodalite to produce the required density
Primary Subject
Secondary Subject
Source
18 Mar 1997; 19 Jan 1995; [10 p.]; US PATENT DOCUMENT 5,613,240/A/; US PATENT APPLICATION 8-375,141; Available from Patent and Trademark Office, Box 9, Washington, DC 20232 (United States); Application date: 19 Jan 1995
Record Type
Patent
Country of publication
ALKALI METAL COMPOUNDS, ALUMINIUM COMPOUNDS, CHLORINE COMPOUNDS, HALIDES, HALOGEN COMPOUNDS, INORGANIC ION EXCHANGERS, ION EXCHANGE MATERIALS, MANAGEMENT, MATERIALS, MINERALS, OXYGEN COMPOUNDS, SILICATE MINERALS, SILICATES, SILICON COMPOUNDS, SODIUM COMPOUNDS, WASTE DISPOSAL, WASTE MANAGEMENT, WASTE PROCESSING, WASTES
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AbstractAbstract
[en] Preliminary short-term experiments to study the effect of gamma radiation on the waste package materials interactions in the environment of a nuclear waste repository in basalt were completed. Experimental parameters were similar to those expected during the saturated post-closure period of the repository, i.e., a temperature of 2000C and a hydrostatic pressure of ≥ 70 bar. The test components included various combinations of synthetic groundwater (GR4), low carbon steel coupons, CH4, basalt, and basalt/bentonite mixtures (packing). The tests were run in low carbon steel pressure vessels. It was found that gamma radiation at a dose rate of 104 rad/hr for a duration of one and two months increased the H2 yield in all tests. Increases in the organic carbon yield, the sulfate ion concentration, and the corrosion rate of the coupon were observed in some of the tests. These latter results varied with the combination of waste package components included in the tests. Evidence for the quench effect was observed in tests which included basalt. 12 references, 6 figures, 2 tables
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Source
Bates, J.K.; Seefeldt, W.B. (eds.); Argonne National Lab., IL (USA); p. 623-634; 1987; p. 623-634; Materials Research Society; Pittsburgh, PA (USA); Materials Research Society fall meeting; Boston, MA (USA); 1-5 Dec 1986
Record Type
Book
Literature Type
Conference; Numerical Data
Country of publication
ALKANES, ALLOYS, CARBON ADDITIONS, CHEMICAL RADIATION EFFECTS, CHEMICAL REACTIONS, CLAYS, DATA, DECOMPOSITION, FLUIDS, HYDROCARBONS, HYDROGEN COMPOUNDS, IGNEOUS ROCKS, INFORMATION, INORGANIC ION EXCHANGERS, ION EXCHANGE MATERIALS, IRON ALLOYS, IRON BASE ALLOYS, MANAGEMENT, MATERIALS, MINERALS, NUMERICAL DATA, ORGANIC COMPOUNDS, OXYGEN COMPOUNDS, POLAR SOLVENTS, RADIATION EFFECTS, RADIOACTIVE MATERIALS, ROCKS, SEPARATION PROCESSES, SILICATE MINERALS, SOLVENTS, WASTE DISPOSAL, WASTE MANAGEMENT, WASTES, WATER, WATER TREATMENT
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Lewis, M.A.; Reed, D.T.
Argonne National Lab., IL (USA); Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1986
Argonne National Lab., IL (USA); Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1986
AbstractAbstract
[en] Short-term experiments which studied the effect of gamma radiation on the waste package components of a basaltic repository were completed. Experimental parameters were similar to those expected during the saturated post-closure period of the repository, i.e., a temperature of 2000C and a hydrostatic pressure ≥ 70 bar. The waste package components included low carbon steel pressure vessels, synthetic ground water formulation (GR4), CH4, basalt or packing, and low carbon steel coupons. It was found that gamma radiation at a dose rate of 104 rad/h for a duration of one and two months increased the H2 yield in all tests. Increases in the organic carbon yield, the sulfate ion concentration, and the corrosion rate of the coupon were observed in some of the tests. These latter results varied with the combination of waste package components included in the tests. Evidence for the quench effect was observed in tests which included basalt
Primary Subject
Secondary Subject
Source
1986; 14 p; Materials Research Society fall meeting; Boston, MA (USA); 1-5 Dec 1986; Available from NTIS, PC A02/MF A01; 1 as DE87004866; Portions of this document are illegible in microfiche products.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALKANES, ALLOYS, CARBON ADDITIONS, CHEMICAL RADIATION EFFECTS, CHEMICAL REACTIONS, DECOMPOSITION, ELECTROMAGNETIC RADIATION, ELEMENTS, HYDROCARBONS, HYDROGEN COMPOUNDS, IGNEOUS ROCKS, IONIZING RADIATIONS, IRON ALLOYS, IRON BASE ALLOYS, NONMETALS, ORGANIC COMPOUNDS, OXYGEN COMPOUNDS, POLAR SOLVENTS, RADIATIONS, ROCKS, SOLVENTS, STEELS, SULFUR COMPOUNDS, WATER
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Lewis, M.A.; Warren, D.W.
Argonne National Lab., IL (USA)1989
Argonne National Lab., IL (USA)1989
AbstractAbstract
[en] Cementitious waste forms are being considered for immobilizing nuclear waste before disposal. In earlier work, it was found that irradiation of a mortar formulation consisting of slag, portland cement, fly ash, water, and up to 10 wt% KCl endash LiCl salt resulted in the generation of hydrogen. Yields were relatively high and the rates of generation were constant for the irradiation period investigated. The addition of small amounts of oxygen-rich electron scavengers to the mortar was investigated as a means for reducing hydrogen yields. The addition of NaNO3 reduced the hydrogen yield; changed the radiolytic products from hydrogen to a mixture of hydrogen, nitrogen, and N2O; and reduced the pressurization rate after exposure to 400 Mrads. The addition of NaIO4 and KMnO4 reduced hydrogen yields slightly while the addition of Ag2O increased the yield. Moreover, the addition of FeS to a non-slag mortar changed the radiolysis mechanism but the addition of FeO did not. The results of these experiments provided an insight into the nature of the radiolytic reactions occurring in the mortar formulations and indicated that the radiolytic generation of gases might be controlled with the proper choice of additive. 14 refs., 3 figs., 2 tabs
Primary Subject
Source
1989; 9 p; Scientific basis for nuclear waste management; Boston, MA (USA); 27-30 Nov 1989; CONTRACT W-31109-ENG-38; NTIS, PC A02/MF A01 as DE90007800; OSTI; INIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ADDITIVES, CEMENTS, CHLORINE COMPOUNDS, COBALT 60, COMPILED DATA, DOSE EQUIVALENTS, EVALUATION, FLY ASH, GAMMA RADIATION, HYDROGEN, INTERNAL CONVERSION RADIOISOTO, IRRADIATION, LITHIUM CHLORIDES, MASS SPECTROSCOPY, MINIMIZATION, MORTARS, POTASSIUM CHLORIDES, RADIATION HAZARDS, RADIOACTIVE WASTE DISPOSAL, RADIOACTIVE WASTES, SALTS, SLAGS, WASTE FORMS, WATER
AEROSOL WASTES, ALKALI METAL COMPOUNDS, ASHES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BUILDING MATERIALS, CHLORIDES, COBALT ISOTOPES, COMBUSTION PRODUCTS, DATA, ELECTROMAGNETIC RADIATION, ELEMENTS, HALIDES, HALOGEN COMPOUNDS, HAZARDS, HEALTH HAZARDS, HYDROGEN COMPOUNDS, INFORMATION, INTERMEDIATE MASS NUCLEI, IONIZING RADIATIONS, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LITHIUM COMPOUNDS, LITHIUM HALIDES, MANAGEMENT, MATERIALS, MINUTES LIVING RADIOISOTOPES, NONMETALS, NUCLEI, NUMERICAL DATA, ODD-ODD NUCLEI, OPTIMIZATION, OXYGEN COMPOUNDS, POLAR SOLVENTS, POTASSIUM COMPOUNDS, RADIATIONS, RADIOACTIVE MATERIALS, RADIOISOTOPES, SOLID WASTES, SOLVENTS, SPECTROSCOPY, WASTE DISPOSAL, WASTE MANAGEMENT, WASTES, YEARS LIVING RADIOISOTOPES
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Lewis, M.A.; Warren, D.W.
Argonne National Lab., IL (USA)1989
Argonne National Lab., IL (USA)1989
AbstractAbstract
[en] A mortar formulation capable of immobilizing chloride salts with high levels of radioactivity is being developed. As part of the developmental effort, radiation effects are being investigated. The radiolytic generation of gas(es) from irradiated mortar formulations was determined for several formulations with variable salt loadings at several test temperatures. The irradiation of a mortar formulation consisting of cement, slag, fly ash, water and 0 to 10 wt % salt led to the generation of hydrogen. The rate of generation was approximately constant, steady state pressures were not attained and final pressures were comparatively high. Higher salt concentrations were correlated with higher hydrogen generation rates for experiments at ambient temperature while lower rates were observed at 120/degree/C. The irradiation of a mortar consisting of cement, fly ash, water and salt led to the radiolytic generation of both oxygen and hydrogen. The addition of 2 wt % FeS or CaS inhibited oxygen generation and changed the hydrogen production rate. 10 refs., 4 figs., 3 tabs
Primary Subject
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Source
1989; 18 p; 4. international symposium on ceramics in nuclear waste management; Indianapolis, IN (USA); 23-27 Apr 1989; Available from NTIS, PC A03/MF A01 - OSTI; 1 as DE89013280; Portions of this document are illegible in microfiche products.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
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Jonah, C.D.; Lewis, M.A.
Argonne National Lab., IL (USA)1984
Argonne National Lab., IL (USA)1984
AbstractAbstract
[en] The use of pulse radiolysis to learn about processes which occur before the beginning of chemical times is discussed. Two examples, the distance distribution of positive and negative ions in hydrocarbons, and the state of the dry electron are discussed in detail
Source
1984; 8 p; 3. working meeting on radiation interaction; Leipzig (German Democratic Republic); 24-28 Sep 1984; Available from NTIS, PC A02/MF A01; 1 as DE85000099
Record Type
Report
Literature Type
Conference
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Country of publication
Reference NumberReference Number
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Pereira, C.; Lewis, M.A.; Ackerman, J.P.
Argonne National Lab., IL (United States). Chemical Technology Div. Funding organisation: USDOE, Washington, DC (United States)1996
Argonne National Lab., IL (United States). Chemical Technology Div. Funding organisation: USDOE, Washington, DC (United States)1996
AbstractAbstract
[en] Argonne is developing a method to treat spent nuclear fuel in a molten salt electrorefiner. Wastes from this treatment will be converted into metal and mineral forms for geologic disposal. A glass-bonded zeolite is being developed to serve as the mineral waste form that will contain the fission products that accumulate in the electrorefiner salt. Fission products are ion exchanged from the salt into the zeolite A structure. The crystal structure of the zeolite after ion exchange is filled with salt ions. The salt-loaded zeolite A is mixed with glass frit and hot pressed. During hot pressing, the zeolite A may be converted to sodalite which also retains the waste salt. The glass-bonded zeolite is leach resistant. MCC-1 testing has shown that it has a release rate below 1 g/(m2day) for all elements
Primary Subject
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Source
1996; 9 p; Annual meeting of the American Nuclear Society (ANS); Reno, NV (United States); 16-20 Jun 1996; CONF-9606116--23; CONTRACT W-31109-ENG-38; Also available from OSTI as DE96010793; NTIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
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Lewis, M.A.; Hash, M.; Glandorf, D.
Argonne National Lab., IL (United States). Chemical Technology Div. Funding organisation: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)1996
Argonne National Lab., IL (United States). Chemical Technology Div. Funding organisation: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)1996
AbstractAbstract
[en] A ceramic waste form is being developed for waste generated during electrometallurgical treatment of spent nuclear fuel. The waste is generated when fission products are removed from the electrolyte, LiCl-KCl eutectic. The waste form is a composite fabricated by hot isostatic pressing a mixture of glass frit and zeolite occluded with fission products and salt. Normalized release rate is less than 1 g/m2d for all elements in MCC-1 leach test run for 28 days in deionized water at 90 C. This leach resistance is comparable to that of early Savannah River glasses. We are investigating how leach resistance is affected by changes in cationic form of zeolite and in glass composition. Composites were made with 3 forms of zeolite A and 6 glasses. We used 3-day ASTM C1220-92 (formerly MCC-1) leach tests to screen samples for development purposes only. The leach test results show that the glass composites of zeolites 5A and 4A retain fission products equally well. Loss of Cs is small (0.1-0.5 wt%), while the loss of divalent and trivalent fission products is one or more orders of magnitude smaller. Composites of 5A retain chloride ion better in these short-term screens than 4A and 3A. The more leach resistant composites were made with durable glasses rich in silica and poor in alkaline earth oxides. XRD show that a salt phase was absent in the leach resistant composites of 5A and the better glasses but was present in the other composites with poorer leach performance. Thus, absence of salt phase corresponds to improved leach resistance. Interactions between zeolite and glass depend on composition of both
Primary Subject
Secondary Subject
Source
1996; 9 p; 1996 Fall meeting of the Materials Research Society (MRS); Boston, MA (United States); 2-6 Dec 1996; CONF-961202--29; CONTRACT W-31109-ENG-38; Also available from OSTI as DE97001391; NTIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
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Lewis, M.A.; Fischer, D.F.; Laidler, J.J.
Argonne National Lab., IL (United States). Chemical Technology Div. Funding organisation: USDOE, Washington, DC (United States)1992
Argonne National Lab., IL (United States). Chemical Technology Div. Funding organisation: USDOE, Washington, DC (United States)1992
AbstractAbstract
[en] The pyrometallurgical processing of spent fuel from the Integral Fast Reactor (IFR) results in a waste of LiCl-KCl-NaCl salt containing approximately 10 wt% fission products, primarily CsCl and SrCl2. For disposal, this waste must be immobilized in a form that it is leach resistant. A salt-occluded zeolite has been identified as a potential waste form for the salt. Its leach resistance properties were investigated using powdered samples. The results were that strontium was not released and cesium had a low release, 0.056 g/m2 for the 56 day leach test. The initial release (within 7 days) of alkali metal cations was rapid and subsequent releases were much smaller. The releases of aluminum and silicon were 0.036 and 0.028 g/m2, respectively, and were constant. Neither alkali metal cation hydrolysis nor exchange between cations in the leachate and those in the zeolite was significant. Only sodium release followed t0.5 kinetics. Selected dissolution of the occluded salt was the primary release process. These results confirm that salt-occluded zeolite has promise as the waste form for IFR pyroprocess salt
Primary Subject
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Source
1992; 7 p; 16. Material Research Society international symposium on the scientific basis for nuclear waste management fall meeting; Boston, MA (United States); 30 Nov - 5 Dec 1992; CONF-921101--30; CONTRACT W-31109-ENG-38; OSTI as DE93005573; NTIS; INIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
DISSOLUTION, ENERGY SOURCES, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FUELS, INORGANIC ION EXCHANGERS, ION EXCHANGE MATERIALS, ISOTOPES, MANAGEMENT, MATERIALS, MINERALS, NUCLEAR FUELS, RADIOACTIVE MATERIALS, REACTOR MATERIALS, REACTORS, REPROCESSING, RESEARCH AND TEST REACTORS, SEPARATION PROCESSES, SILICATE MINERALS, WASTE DISPOSAL, WASTE MANAGEMENT, WASTES, ZERO POWER REACTORS
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Lewis, M.A.; Fischer, D.F.; Murhpy, C.D.
Argonne National Lab., IL (United States). Funding organisation: USDOE, Washington, DC (United States)1993
Argonne National Lab., IL (United States). Funding organisation: USDOE, Washington, DC (United States)1993
AbstractAbstract
[en] Pyrochemical processing of spent fuel from the Integral Fast Reactor (IFR) yields a salt waste of LiCl-KCl that contains approximately 6 wt% fission products, primarily as CsCl and SrCl2. Past work has shown that zeolite A will preferentially sorb cesium and strontium and will encapsulate the salt waste in a leach-resistant, radiation-resistant aluminosilicate matrix. However, a method is sill needed to convert the salt-occluded zeolite powders into a form suitable for geologic disposal. We are thus investigating a method that forms bonded zeolite by hot pressing a mixture of glass frit and salt-occluded zeolite powders at 990 K (717 degree C) and 28 MPa. The leach resistance of the bonded zeolite was measured in static leach tests run for 28 days in 363 K (90 degree C) deionized water. Normalized release rates of all elements in the bonded zeolite were low, <1 g/m2 d. Thus, the bonded zeolite may be a suitable waste form for IFR salt waste
Primary Subject
Source
1993; 9 p; Fall meeting of the Materials Research Society (MRS); Boston, MA (United States); 29 Nov - 3 Dec 1993; CONF-931108--4; CONTRACT W-31109-ENG-38; Also available from OSTI as DE94001329; NTIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALKALI METAL COMPOUNDS, ALKALINE EARTH METAL COMPOUNDS, CESIUM COMPOUNDS, CHLORIDES, CHLORINE COMPOUNDS, DISSOLUTION, HALIDES, HALOGEN COMPOUNDS, INORGANIC ION EXCHANGERS, ION EXCHANGE MATERIALS, MANAGEMENT, MATERIALS, MINERALS, SEPARATION PROCESSES, SILICATE MINERALS, STRONTIUM COMPOUNDS, WASTE MANAGEMENT, WASTE PROCESSING, WASTES
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