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Release of ammonia from HAN-type PHA

Description: A preliminary design basis for ammonia scrubbers in the DWPF has been issued. This design basis is based on a theoretical model of ammonia evolution from the SRAT, SME and RCT. It is desirable to acquire actual process data on ammonia evolution prior to performing detailed design of scrubbers for DWPF. The evolution of ammonia from the SRAT and SME in the Integrated DWPF Melter System (IDMS) was investigated during the HM4 run. In this run, Precipitate Hydrolysis Aqueous (PHA), which was made i… more
Date: June 10, 1992
Creator: Zamecnik, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of protactinium-231 and thorium-230 from cotter concentrate: pilot plant operatins and process development

Description: The equipment and methods used to recover and purify 339 g of thorium-230 and 890 mg of protactinium-231 from 22 of the 1251 drums of Cotter Concentrate are described. The process developed was (1) dissolution at 100/sup 0/C in concentrated nitric acid and dilution to 2 to 3 molar acid, (2) filtration to remove undissolved solids (mostly silica filter aid), (3) extraction of uranium with di-sec-butyl-phenyl phophonate (DSBPP) in carbon tetrachloride, (4) extraction of both thorium and protactin… more
Date: February 10, 1983
Creator: Hertz, M. R.; Figgins, P. E. & Deal, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of the electrolytic dissolution of plutonium

Description: Experiments have shown that it is possible to dissolve plutonium electrolytically in a nitric acid solution. Parameters such as current density and electrolyte composition have been investigated and are discussed. Also included are suggestions for future work.
Date: June 10, 1978
Creator: DeGrazio, R.P. & Miner, F.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Release of ammonia from HAN-type PHA

Description: A preliminary design basis for ammonia scrubbers in the DWPF has been issued. This design basis is based on a theoretical model of ammonia evolution from the SRAT, SME and RCT. It is desirable to acquire actual process data on ammonia evolution prior to performing detailed design of scrubbers for DWPF. The evolution of ammonia from the SRAT and SME in the Integrated DWPF Melter System (IDMS) was investigated during the HM4 run. In this run, Precipitate Hydrolysis Aqueous (PHA), which was made i… more
Date: June 10, 1992
Creator: Zamecnik, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quality engineering and control semiannual progress report, November--December 1977 and January--April 1978

Description: Determination of ppM concentrations of dibutyl phosphate in aqueous solutions of nitric acid or sodium carbonate is possible after an extraction step with carbon tetrachloride. Ester cleavage of the fatty triglyceride constituents is the principal radiolytic reaction in irradiation of a dolphin-head oil base precision watch oil. Use of a special container and a vacuum-brazing furnace permits the high-temperature dynamic determination of volatile surface contamination from samples of large geome… more
Date: October 10, 1978
Creator: Carpenter, R.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutralization of HNO₃ in Redox ICU an IAW Streams

Description: The following memorandum outlines the procedures used on the neutralization of HNO3 in redox ICU and IAW streams, and the factors influencing their choice. The procedures involve a) hexone removal by evaporation in the presence of a retardant, b) destruction of the retardant, c) nitric acid elimination by boiling with aluminum and d) concentration of the remaining solution by evaporation.
Date: December 10, 1948
Creator: Curtis, M. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LOADING AND ELUTION CHARACTERISTICS OF SOME NATURAL AND SYNTHETIC ZEOLITES

Description: The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied f… more
Date: August 10, 1962
Creator: Ames, L.L. Jr. & Knoll, K.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Bench-Scale Natural-Recirculation Dissolver

Description: A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated M… more
Date: January 10, 1962
Creator: Erickson, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE RECOVERY OF FISSION PRODUCT RARE EARTH SULFATES FROM PUREX 1WW

Description: Cerium- and 144 promethium-147, accompanied by rare earths resulting from fission or decay can be removed from Purex 1WW in>90% yield as an insoluble, crystalline sodium-rare earth double sulfate. Precipitation is initiated by a one-to-three hour equilibration at 90 deg C and centrifugation at 90 deg C to take advantage of the lower solubility of the double sulfate salt at a higher temperature. The sulfate concentration should be one molar and the solution pH at the time of precipitation should… more
Date: May 10, 1961
Creator: Wheelwright, E. J. & Swift, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE EFFECT OF RADIATION AND NITRIC ACID-NITRATE SALT SOLUTION ON SOME NON- METALLIC MATERIALS

Description: Several plastic materials and one ceramic alumina were tested for possible use as electrical insulators and spacers in an electrolytic dissolver for processing irradiated nuclear fuels. They were first screened for chemical resistance to the boiling dissolver product solution composed of 1 M nitric acid and 75 g/l stainless steel metal components as nitrates. Those that were resistant were then exposed simultaneously to the boiling dissolver product solution and a gamma irradiation field. Value… more
Date: December 10, 1962
Creator: Decker, L A
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Mathematical Model for the Solvent Extraction of Uranyl Nitrate and Nitric Acid

Description: A generalized least-squares technique can be used to calculate equilibrium constants in solvent extraction equilibria by minimizing the difference between observed and calculated distribution ratios. The method was successfully applied to the extraction of uranyl nitrate and nitric acid by TBP dissolved in an inert diluent. (auth)
Date: July 10, 1962
Creator: Lietzke, M. H. & Stoughton, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LOW-RADIOACTIVITY-LEVEL WASTE TREATMENT. PART I. LABORATORY DEVELOPMENT OF A SCAVENGING-PRECIPITATION ION-EXCHANGE PROCESS FOR DECONTAMINATION OF PROCESS WATER WASTES

Description: A scavenging-precipitation ion-exchange process using phenolic resins was developed to decontaminate lowradioactivity-level process water waste prior to discharge to the environment. In laboratory and small engineeringscale tests, greater than 99.9% of the cesium and strontium, the principal biological hazards were removed from ORNL low-level waste, and the total activity level was lowered to less than the maximum permissible concentration recommended for populations in the neighborhood of atom… more
Date: July 10, 1963
Creator: Holcomb, R.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A CONTINUOUS DAREX PROCESS FLOWSHEET

Description: A Darex flowsheet is presented wherein dissolution of stainiess steel- type fuel elements in dilute aqua regia, stripping of chloride from spent dissolver solution, adjustment of stripper product composition and rectification of HNO/sub 3/ --H/sub 2/O vapors are accomplished in a completely continuous relatively simple loop process. Product from the loop needs only dilution with water to be made suitable as feed for a solvent extraction processing plant. The proposed scheme differs from earlier… more
Date: October 10, 1957
Creator: Kitts, F.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Silicon in the Reprocessing of a Uranium Aluminum Alloy

Description: The insoluble residues produced during the reprocessing of certain nuclear fuel elements containing aluminum, silicon, and uranium were investigated with respect to particle size, shape and distribution, composition, and surface- active tendencies. The fuel material samples studied contained from 0.4 to 7.0% silicon by weight (the high analysis represents a cast base AlSi alloy). The fuel materials were dissolved in mercury-catalyzed nitric acid. Two types of solid residue were produced by actu… more
Date: May 10, 1958
Creator: Parrett, O. W. & Rohde, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TUNGSTEN SHIELDS FOR CS-137 INLINE MONITORS IN THE CAUSTIC SIDE SOLVENT EXTRACTION PROCESS

Description: The Department of Energy (DOE) selected Caustic-Side Solvent Extraction (CSSX) as the preferred technology for the removal of radioactive cesium from High-Level Waste (HLW) at the Savannah River Site (SRS). The CSSX process is a continuous process that uses a novel solvent to extract cesium from highly radioactive waste and concentrate it in dilute nitric acid. In-line analyses are performed with gamma-ray monitors to measure the C-137 concentration in the decontaminated salt solution (DSS) and… more
Date: May 10, 2007
Creator: Casella, V; Mark Hogue, M; Javier Reyes-Jimenez, J; Paul Filpus-Luyckx, P; Timothy Riley, T; Fred Ogden, F et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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CONCENTRATION AND FINAL PURIFICATION OF NEPTUNIUM BY ANION EXCHANGE

Description: It was demonstrated that neptunium(IV) can be readily absorbed onto anion exchange resins from 6 M HNOsub 3/ containing ferrous sulfamate and hydrazine or semicarbazide, separated from plutonium, uranium, and common metallic impurities by washing the resin at 25 deg C with 6 M HNO/sub 3/ containing ferrous sulfamate and hydrazine or semicarbazide, separated from fission products and thorium by washing the resin at 60 deg C with S M HNO/sub 3/- 0.01 M HF containing hydrazine or semicarbazide, an… more
Date: February 10, 1959
Creator: Ryan, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Uranium From Residues Produced in Hydrochlorination of Nuclear Fuel Alloys

Description: Chlorination at 550 to 600 deg C of Zircex residues with carbon tetrachloride resulted in greater than 99.99% recovery of the uranium. Both the hydrochlorination residue and the solids which remain after leaching the hydrochlorination residue with nitric acid were chlorinated with similar results. By this technique, loss of 1 to 6% of the uranium to the nitric acid insoluble residue, which occurs in simple hydrochlorination and dissolution of STR fuel, is avoided. Other advantages include reduc… more
Date: April 10, 1959
Creator: Gens, T. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NITRO-HYDROLYSIS: AN ENERGY EFFICIENT SOURCE REDUCTION AND CHEMICAL PRODUCTION PROCESS FOR WASTEWATER TREATMENT PLANT BIOSOLIDS

Description: The nitro-hydrolysis process has been demonstrated in the laboratory in batch tests on one municipal waste stream. This project was designed to take the next step toward commercialization for both industrial and municipal wastewater treatment facility (WWTF) by demonstrating the feasibility of the process on a small scale. In addition, a 1-lb/hr continuous treatment system was constructed at University of Tennessee to treat the Kuwahee WWTF (Knoxville, TN) sludge in future work. The nitro-hydro… more
Date: March 10, 2003
Creator: Klasson, KT
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Processing of Non-PFP Plutonium Oxide in Hanford Plants

Description: Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred routinely at Hanford’s Plutonium Finishing Plant (PFP) in glovebox line operations. Plutonium oxide is difficult to dissolve, particularly if it has been high-fired; i.e., calcined to temperatures above about 400°C and much of it was. Dissolution of the PuO2 in the scrap typically was performed in PFP’s Miscellaneous Treatment line using nitric acid (HNO3) containing some source of fluoride ion, … more
Date: March 10, 2011
Creator: Jones, Susan A. & Delegard, Calvin H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EM-31 ALTERNATIVE AND ENHANCED CHEMICAL CLEANING PROGRAM FOR SLUDGE HEEL REMOVAL - 11220

Description: Mixtures of oxalic acid with nitric acid have been shown to be superior to oxalic acid alone for the dissolution of iron-rich High Level Waste sludge heels. Optimized conditions resulting in minimal oxalate usage and stoichiometric iron dissolution (based on added oxalate ion) have been determined for hematite (a primary sludge iron phase) in oxalic/nitric acid mixtures. The acid mixtures performed better than expected based on the solubility of hematite in the individual acids through a synerg… more
Date: December 10, 2010
Creator: King, W.; Hay, M.; Wiersma, B. & Pennebaker, F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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