Molten salt oxidation of chloro-organic compounds: Experimental results for product gas compositions and final forms studies

Rudolph, J.C.; Bell, J.T.; Crosley, S.M.; Calhoun, C.L.; Gorin, A.H.

doi:10.2172/61068

Cited by 9 publications

(5 citation statements)

References 5 publications

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“…Oak Ridge National Laboratory ( O W ) has used a MSO reactor similar to the RI bench-scale design to destroy combustible waste composed of chloroform, 1, 1,l-trichloroethane (TCA), 2,4-dichlorophenol, ethanol, and ethylene glycol (Rudolph et al 1995). Waste material was feed into a Na2C03 molten salt at a rate of 0.4kg/hr to 0.9 kg/hr.…”

Section: Oak Ridge National Laboratorvmentioning

confidence: 99%

Overview of advanced technologies for stabilization of [sup 238]Pu-contaminated waste

Ramsey¹,

Foltyn²,

Heslop³

1998

AIP Conference Proceedings

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. DISCLAIMERThis report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any infomation, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recornmendidion. or favoring by the United States Government or any agency thereof. AbstractThis paper presents an overview of potential technologies for stabilization of usPu-contaminated waste. Los Alamos National Laboratory (LANL) has processed 238Pu02 fuel into heat sources for space and terrestrial uses for the past several decades. The 88-year half-life of usPu and thermal power of approximately 0.6 watts/gram make this isotope ideal for missions requiring many years of dependable service in inaccessible locations. However, the same characteristic which makes usPu attractive for heat source applications, the high Curie content (17 Ci/gram versus 0.06 Ci/gram for 239Pu), makes disposal of usPu-contaminated waste difficult. Specifically, the thermal load limit on drums destined for transport to the Waste Isolation Pilot Plant (WIPP), 0.23 gram per drum for combustible waste, is impossible to meet for nearly all 238Pu-contaminated glovebox waste. Use of advanced waste treatment technologies including Molten Salt Oxidation (MSO) and aqueous chemical separation will eliminate the combustible matrix from 238Pu-contaminated waste and recover kilogram quantities of 238Pu02 from the waste stream. A conceptual design of these advanced waste treatment technologies will be presented.

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Section: Oak Ridge National Laboratorvmentioning

confidence: 99%

Overview of advanced technologies for stabilization of [sup 238]Pu-contaminated waste

Ramsey¹,

Foltyn²,

Heslop³

1998

AIP Conference Proceedings

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“…By referring to the method developed by Lee and Huang for the recycled PCBs using pyrolysis, and for exploring into the chemical kinetic behavior of the DGETBA cements inside PCBs, this study used DGETBA as the subject for the experiment of molten salt pyrolysis method (Upadhye et al, 1992;Gay et al, 1993;Rudolph, 1995;Chien et al, 2000a;Chien et al, 2000b) to simplify the treatment environment, reduce interferences from those factors that prevent easy control, and focus on the core reaction mechanism of DGETBA pyrolysis.…”

Section: Introductionmentioning

confidence: 99%

Pyrolysis of Diglycidyl ether of Tetrabromobisphenol A (DGETBA) using molten salt and its reaction kinetics

Chang

Chen

et al. 2011

Afr. J. Agric. Res.

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Diglycidyl ether of Tetrabromobisphenol A (DGETBA) is mainly for making copper clad laminate (CCL), which is the base of printed circuit board (PCB) in Taiwan. If not properly treated and disposed, waste printed circuit board would make the already polluted environment worse. The objective of this study is to pursue the chemical reaction kinetics for pyrolysis of DGETBA by molten salt. The molten salt used in this study composed of Sodium-nitrate (NaNO 3) and Sodium-nitrite (NaNO 2) with the ratio of 4:1. The following reaction rate equation has been obtained: dC/dt=-kC 0.7 , where k is the reaction rate constant, C is the reactant concentration, t is the reaction time, and which can further be obtained as follows: k=AT b exp (-E/RT)=33.9×T 0.00034 exp (-2118/1.987T), where A is a frequency factor (1/s), b is a empirical parameter temperature function, E is the activation energy (cal/mol), R is universal gas constant (1.987 cal/mol K), and T is the reaction temperature (K).

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“…The exhaust gas streams contain moisture along with small quantities of CO, CO 2 , N 2 , N 2 O, NO, NO 2 , F 2 , Cl 2 , HF, HCl, SO 2 , SO 3 and phosphorus-bearing gases, which can be released into the atmosphere without secondary processing. So far, this technology has been used to process a wide variety of organic and mixed wastes ( − ), and the results suggest that it could be a viable alternative to incineration. No data, however, has been obtained regarding the oxidation of cyanides in molten carbonate baths.…”

Section: Introductionmentioning

confidence: 99%

Cyanide Destruction in Molten Carbonate Bath: Melt and Gas Analyses

Alam

Kamath

1998

Environ. Sci. Technol.

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Oxidation of combustible wastes in molten salt baths is being considered as an alternative to incineration. This paper examines the oxidation of cyanide ions (present in molten carbonate bath) by molecular oxygen as a function of the total gas mixture (O2−Ar) flow rate, input gas composition (vol % O2 in O2−Ar mixtures), melt composition (initial mol % CN- in CN-−CO3 2- baths), and melt temperature. The melts were sampled for the presence of CN-, CNO-, NO2 -, and NO3 - while the gas streams were sampled for N2, N2O, NO, NO2, CO, and CO2. While cyanide destruction proceeds rapidly (>90% loss of CN- at 486 standard cm3 per min, 40 vol % O2, and 1243 K), NO2 and CO emissions remain within the limits of air quality standards. Under all conditions CN- and CNO- were the major components, while NO2 - and NO3 - were the minor components of the melt. The amount of CNO- present in the melt after any period of reaction was always smaller than the amount of CN- lost from the melt during the same time period. The CO + CO2 content of the gas was always much larger than the NO + NO2 content. The CO/CO2 ratio was always small while the NO/NO2 ratio was always large. While N2 content was larger than the NO + NO2 content, no N2O was ever detected. Material balance indicated that most of the nitrogen input to the system remained unaccounted after the reaction. Significance of the data are discussed.

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Molten salt oxidation of chloro-organic compounds: Experimental results for product gas compositions and final forms studies

Cited by 9 publications

References 5 publications

Overview of advanced technologies for stabilization of [sup 238]Pu-contaminated waste

Overview of advanced technologies for stabilization of [sup 238]Pu-contaminated waste

Pyrolysis of Diglycidyl ether of Tetrabromobisphenol A (DGETBA) using molten salt and its reaction kinetics

Cyanide Destruction in Molten Carbonate Bath: Melt and Gas Analyses

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