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Measurement of the Hydrogen Yield in the Radiolysis of Water by Dissolved Fission Products

Description: Hydrogen from the radiolysis of water by dissolved fission products is stripped from the solution and collected by bubbling carbon dioxide through the solution. Quantitative measurements of the G value for hydrogen show that the yield is essentially the same as would be obtained by external gamma radiolysis of nonradioactive solutions of the same chemical composition. The hydrogen yield can be enhanced by addition of a hydrogen-atom donor, such as formic acid, to the solution. The yield of hydr… more
Date: April 1976
Creator: Sauer, M. C., Jr.; Hart, E. J.; Flynn, K. F. & Gindler, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process : Continuing Development Studies

Description: This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX pro… more
Date: September 1985
Creator: Leonard, R. A.; Vandegrift, G. F.; Kalina, D. G.; Fischer, D. F.; Bane, R. W.; Burris, L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Programs Semiannual Progress Report: October 1991-March 1992

Description: This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
Date: November 1993
Creator: Bates, John K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Programs Semiannual Progress Report: April-September 1992

Description: This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April-September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
Date: May 1994
Creator: Bates, John K.; Bradley, C. R.; Buck, E. C.; Dietz, N. L.; Ebert, William L.; Emery, J. W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Monitoring and Control of TRUEX Processes

Description: The Generic TRUEX Model (GTM) was used to design a flowsheet for the TRUEX solvent extraction process that would be used to determine its instrumentation and control requirements. Sensitivity analyses of the key process variables, namely, the aqueous and organic flow rates, feed compositions, and the number of contactor stages, were carried out to assess their impact on the operation of the TRUEX process. Results of these analyses provide a basis for the selection of an instrument and control s… more
Date: March 1992
Creator: Regalbuto, M. C.; Misra, B.; Chamberlain, D. B.; Leonard, R. A. & Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Methods for Removing Transuranic Elements from Waste Solutions

Description: This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The s… more
Date: November 1994
Creator: Slater, S. L.; Chamberlain, D. B.; Conner, C.; Sedlet, J.; Srinivasan, B. & Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiolytic and Thermal Generation of Gases from Hanford Grout Samples : Interim Report

Description: Gamma irradiation of WHC-supplied samples of grouted Tank 102-AP simulated nonradioactive waste has been carried out at three dose rates, 0.25, 0.63, and 130 krad/hr. The low dose rate corresponds to that in the actual grout vaults; with the high dose rate, doses equivalent to more than 40 years in the grout vault were achieved. An average G(H2) = 0.047 molecules/100 eV was found, independent of dose rate. The rate of H2 production decreases above 80 Mrad. For other gases, G(N2) = 0.12, G(O2) =… more
Date: October 1993
Creator: Meisel, Dan; Jonah, Charles D.; Kapoor, S.; Matheson, Max S. & Mulac, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiolytic and Radiolytically Induced Generation of Gases from Synthetic Wastes : Final Report

Description: To better understand the processes leading to the generation and release of gases from waste tanks, the authors studied the radiolytic and thermal generation of H2, N2O, N2, O2, and NH3 in nonradioactive waste simulant solutions and slurries. The radiolytic sources for H2 are e(sub aq)⁻ and its predecessors and H atoms. Radiolysis of the water generates some H2 and an additional amount comes from the hydrogen abstraction reaction H + RH(yields) H2+R(center_dot). Nitrate scavenges e(sub aq)(sup … more
Date: October 1993
Creator: Meisel, Dan; Jonah, Charles D.; Kapoor, S.; Matheson, Max S. & Sauer, M. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas Generation from Hanford Grout Samples : Final Report

Description: The radiolytic yields of hydrogen nitrogen, oxygen, nitrous oxide, and carbon monoxide from two batches of WHC-supplied samples of grouted simulated waste have been (gamma) irradiated at several dose rates (0.025, 0.63 and 130 krad/h for hydrogen and 130 krad/h for all other gases). In one batch, the liquid waste simulant that was added to the grout included the original components that were added to Tank 102-AP (labeled "virgin" waste.) The second batch included a similar liquid waste simulant… more
Date: March 1994
Creator: Jonah, Charles D.; Kapoor, S.; Matheson, Max S.; Mulac, W. A. & Meisel, Dan
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Plan for Treating Mixed Waste

Description: A preliminary waste treatment plan was developed for disposing of radioactive inorganic liquid wastes that contain hazardous metals and/or hazardous acid concentrations at Argonne National Laboratory. This plan, which involves neutralization and sulfide precipitation followed by filtration, reduces the concentration of hazardous metals and the acidity so that the filtrate liquid is simply a low-level radioactive waste that can be fed to a low-level waste evaporator.
Date: June 1993
Creator: Vandegrift, G. F.; Conner, C.; Hutter, Joseph C.; Leonard, R. A.; Nuñez, Luis; Sedlet, J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proceedings of the Workshop on the Interface Between Radiation Chemistry and Radiation Physics; Held at Argonne National Laboratory, September 9-10, 1982

Description: This conference evolved out of an idea that originated Department of Energy contractor's meeting in Gettysburg to have a conference devoted to topics of interest to both radiation chemists and physicists in radiation research. Radiation chemists tend to operate in a time domain where chemical reactions can be observed and to deduce values from that data. Meanwhile, physicists naturally focus considerable attention on initial energy deposition events and perform calculations which should predict… more
Date: March 1983
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Actinides from TBP-Na₂CO₃ Scrub-Waste Solutions: the ARALEX Process

Description: A flow-sheet for the recovery of actinides from TBP-Na2CO3scrub-waste solutions has been developed, based on batch extraction data, and tested, using laboratory-scale countercurrent extraction techniques. The process, called the ARALEX process, uses 2-ethyl-1-hexanol (2-EHOH) to extract the TBP degradation products (HDBP and H/sub 2/MBP) from acidified Na2CO3scrub waste leaving the actinides in the aqueous phase. Dibutyl and monobutyl phosphoric acids are attached to the 2-EHOH molecules throug… more
Date: August 1979
Creator: Horwitz, E. P.; Bloomquist, C. A. A.; Mason, G. W.; Leonard, R. A. & Ziegler, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Applied Physical Chemistry Progress Report, October 1991 - September 1992

Description: This document reports on the work done in applied physical chemistry at the Chemical Technology Division (CMT), Argonne National Laboratory (ANL), in the period October 1991 through September 1992. this work includes research into the process that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor under development at ANL, and the properties of candidate triti… more
Date: December 1993
Creator: Johnson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Manual of HRE Control and Instrumentation

Description: Technical reports outlining the controls for the Homogeneous Reactor Experiment (HRE); controls are divided into three principal groups. 1. Reactor. 2. Process or auxiliary. 3. Power generation. These are the classifications designating the primary functions of the controls. [From Introduction]
Date: January 23, 1952
Creator: Quarles, L. R. & Walker, W. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending July 31, 1951

Description: Technical report outlining the effect of strain rate on the tensile properties of thorium. It has been found that the yield strength increases slightly with increasing strain rate, and that tensile strength increases but to a less extent. Studies on the fabrication of thorium by extrusion and drawing have continued, as have studies on the extrusion cladding of thorium and uranium with zirconium. [From Summary}
Date: February 6, 1952
Creator: Miller, E. C. & Bridges, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shielding Reactor Corrosion Studies

Description: Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]
Date: July 9, 1951
Creator: Olsen, Arnold R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951

Description: This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.
Date: September 30, 1951
Creator: Lind, Samuel C., (Samuel Colville), 1879-1965; Boyd, G. E. & Bredig, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Beta Radiation as a Hydrogenation Catalyst: Interim Technical Status Report for the Period March 1, 1962 to October 31, 1963

Description: From abstract: The concept of using high intensity beta radiation from an isotopic source, Sr-90, inside a high temperature, high pressure chemical reactor has been developed for potential radiation chemical processes. Distinct advantages include high utilizable intensity from a relatively small source with a minimum of shielding against external radiation.
Date: September 11, 1964
Creator: Yavorsky, P. M. & Gorin, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Chemistry of Synthetic Waste

Description: The yield of hydrogen from radiolysis of aqueous solutions is substantially reduced by the presence of nitrate and nitrite in the waste solutions. Nitrate is more efficient in scavenging the precursors to hydrogen than is nitrite, therefore, the latter should be maintained at higher levels if minimization of radiolytic gas production is required. Nitrate is the major scavenger for e(sub aq)(sup (minus)) and nitrite is the major scavenger for H atoms. At the concentration levels of the waste sol… more
Date: November 1991
Creator: Meisel, Dan; Diamond, H.; Horwitz, E. P.; Jonah, Charles D.; Matheson, Max S.; Sauer, M. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Stability Studies

Description: From abstract: "An investigation of the radiation stabilities of aqueous solutions of sodium ethylenediamine tetraacetate and sodium acetate was made using a 3000-curie Co⁶⁰ source...A study of the behavior of the standard-size Beckman type glass pH electrodes in a solution containing 0.36 curie of Ce¹⁴⁴-Pr¹⁴⁴ activity per milliliter showed the useful electrode life to be of the order of two to eight days."
Date: September 22, 1952
Creator: Blanco, R. E.; Kibbey, A. H. & Pannell, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alpha Particle Radiolysis of Anion Exchange Resins

Description: Technical report. From Abstract : "Irradiation of 'Dowex' 1, 'Permutit' S-1, and 'Permutit' SK anion exchange resins with alpha particles results in losses in ion exchange capacity and in 'apparent per cent crosslinkage'. The order of decreasing radiolytic stability for these properties in 'Permutit" SX > 'Permutit' S-1 > 'Dowex' 1."
Date: November 1961
Creator: Ahrens, Rolland W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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