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AbstractAbstract
[en] A theoretical model simulating the simultaneous heat and mass transfer which takes place during the desublimation of a gas to a solid is presented. Desublimer column loading profiles to experimentally verify the model were obtained using a gamma scintillation technique. The data indicate that, if the physical parameters of the desublimed frost material are known, the model can accurately predict the desublimation phenomenon. The usefulness of the model in different engineering applications is also addressed
Primary Subject
Source
1 Aug 1979; 25 p; 72. AICHE meeting; San Francisco, CA, USA; 25 - 29 Nov 1979; CONF-791108--6; Available from NTIS., PC A02/MF A01
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ACTINIDE COMPOUNDS, DATA, DATA FORMS, DIFFUSION, ENERGY TRANSFER, ENTHALPY, FLUIDS, FLUORIDES, FLUORINE COMPOUNDS, HALIDES, HALOGEN COMPOUNDS, INDUSTRIAL PLANTS, INFORMATION, ISOTOPE SEPARATION PLANTS, NUCLEAR FACILITIES, NUMERICAL DATA, PHYSICAL PROPERTIES, THERMODYNAMIC PROPERTIES, TRANSITION HEAT, TRAPS, URANIUM COMPOUNDS
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AbstractAbstract
[en] A study was conducted to obtain column concentration profiles and point buildup rates for a cold trap freezing out krypton from a nitrogen carrier gas stream and to compare those experimentally obtained profiles with profiles generated from a theoretical model. Profiles were obtained over a range of flow conditions from 0.14 to 1.06 standard cubic feet per minute, krypton feed gas concentrations varied from 5.2 to 13.5%, and cold trap operating temperatures from -281 to -3120F. Gamma scintillation techniques using tracer amounts of krypton-85 provided the major analytical tool employed in the investigation. Data obtained from the experiments indicate that if values for the density and thermal conductivity of the krypton frost are known, the model can accurately predict krypton loading profiles in the cold trap. The frost density and frost conductivity appear to be functions of the freeze-out temperature and condensable krypton concentration. A discussion of cold trapping theory, a description of the experimental apparatus and tests performed, and an explanation of the usefulness of the model as a design tool for engineering use are included
Primary Subject
Secondary Subject
Source
Sep 1978; 139 p; Available from NTIS., PC A07/MF A01
Record Type
Report
Report Number
Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, COUNTING TECHNIQUES, ELEMENTS, EVEN-ODD NUCLEI, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, KRYPTON ISOTOPES, MANAGEMENT, NONMETALS, NUCLEAR FACILITIES, NUCLEI, PHYSICAL PROPERTIES, RADIOISOTOPES, RARE GASES, THERMODYNAMIC PROPERTIES, TRAPS, WASTE MANAGEMENT, WASTE PROCESSING, WASTES, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] The proposal concerns an improved gas absorption method in which a liquid absorbant (e.g. hydrocarbon fluorides) circulates continuously through a closed loop system and has gas-absorption gas-desorption zones as well as absorbant regeneration zones. The emphasized advantage is that the process can take place in a single liquid-gas apparatus which has successive contact zones working under the same pressure. The recovery of krypton 85 from a gas (N2, O2, 14CO2) using dichlorofluoromethane (CCl2F2) is described. The apparatus can also be used in the hot cells. (RW)
[de]
Der Vorschlag betrifft ein verbessertes Gasabsorptionsverfahren, bei dem ein fluessiges Absorptionsmittel (z.B. Fluorkohlenwasserstoffe) kontinuierlich durch ein System mit geschlossener Schleife zirkuliert und Gas-Absorptions-Gas-Desorptions-Zonen sowie Absorptionsmittel-Regenerations-Zonen aufweist. Als Vorteil wird betont, dass das Verfahren in einer einzigen Fluessigkeit-Gas-Vorrichtung ausgefuehrt werden kann, die aufeinanderfolgende Kontaktzonen besitzt, welche unter gleichem Druck arbeiten. Es wird die Krypton-85-Wiedergewinnung aus einem Speisegas (N2, O2, 14CO2) mit Hilfe von Dichlordifluormethan (CCl2F2) beschrieben. Die Apparatur ist auch in heissen Zellen einsetzbar. (RW)Original Title
Gas-Absorptionsverfahren
Primary Subject
Source
18 Jul 1978; 29 p; DE PATENT DOCUMENT 2831564/A/; Available from Deutsches Patentamt, Muenchen, Germany, F.R
Record Type
Patent
Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON COMPOUNDS, CARBON OXIDES, CHALCOGENIDES, ELEMENTS, EVEN-ODD NUCLEI, FLUID FLOW, FLUIDS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, KRYPTON ISOTOPES, LABORATORY EQUIPMENT, MANAGEMENT, NONMETALS, NUCLEI, OXIDES, OXYGEN COMPOUNDS, RADIOACTIVE MATERIALS, RADIOISOTOPES, WASTE MANAGEMENT, WASTE PROCESSING, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
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Stephenson, M.J.; Eby, R.S.; Pashley, J.H.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1976
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1976
AbstractAbstract
[en] Recent progress in the development of a fluorocarbon adsorption process for the recovery of krypton from the off-gas of fuel reprocessing plants is reported. Three packed columns comprise the main working sections of the process. Each column is designed to exploit certain gas-liquid solubility differences that exist between the solvent and the various gas constituents that might be present. The main separation of noble gas is accomplished in the absorber. The other two columns, each fitted with a reboiler and an overhead condenser, comprise the intermediate and final stripper sections of the plant
Primary Subject
Secondary Subject
Source
28 Jan 1976; 13 p; Available from NTIS; Available from NTIS. $4.50.
Record Type
Report
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Country of publication
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Stephenson, M.J.; Eby, R.S.; Huffstetler, V.C.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1977
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1977
AbstractAbstract
[en] A fluorocarbon-based selective absorption process for removing krypton-85, carbon-14, and radon-222 from the off-gas of conventional light water and advanced reactor fuel reprocessing plants is being developed at the Oak Ridge Gaseous Diffusion Plant in conjunction with fuel recycle work at the Oak Ridge National Laboratory and at the Savannah River Laboratory. The process is characterized by an especially high tolerance for many other reprocessing plant off-gas components. This report presents detailed drawings and descriptions of the second generation development pilot plant as it has evolved after three years of operation. The test facility is designed on the basis of removing 99% of the feed gas krypton and 99.9% of the carbon and radon, and can handle a nominal 15 scfm (425 slm) of contaminated gas at pressures from 100 to 600 psig (7.0 to 42.2 kg/cm2) and temperatures from minus 45 to plus 250F (-43 to -40C). Part of the development program is devoted to identifying flowsheet options and simplifications that lead to an even more economical and reliable process. Two of these applicative flowsheets are discussed
Primary Subject
Secondary Subject
Source
Oct 1977; 102 p; Available from NTIS., PC A05/MF A01
Record Type
Report
Report Number
Country of publication
ALPHA DECAY RADIOISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON ISOTOPES, DAYS LIVING RADIOISOTOPES, DIAGRAMS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, FUNCTIONAL MODELS, HEAVY NUCLEI, HOURS LIVING RADIOISOTOPES, INFORMATION, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, KRYPTON ISOTOPES, LIGHT NUCLEI, MANAGEMENT, NUCLEAR FACILITIES, NUCLEI, RADIOISOTOPES, RADON ISOTOPES, WASTE MANAGEMENT, WASTE PROCESSING, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] The Oak Ridge Gaseous Diffusion Plant has the primary responsibility for the development of the FASTER (Fluorocarbon Absorption System for Treating Effluents from Reprocessors) process for application to LMFBR and LWR fuel reprocessing plants. Krypton-85 removals in excess of 99.9% and carbon-14 as carbon dioxide removals greater than 99.99% have been obtained in a development pilot plant. So far, pilot plant tests show that the presence of other reprocessing plant off-gas components does not appreciably affect the general operability or removal efficiency of the process. Tests also indicate that the one process designed for krypton and carbon removal may be even more effective in removing other fission products and objectionable chemical contaminants such as nitrogen dioxide. Elemental and organic iodine removals in excess of 99.99% and nitrogen dioxide removals over 99% were recently achieved. Higher process decontaminations are possible. Trapping studies show that 13X molecular sieves are very effective in removing the fluorocarbon vapor from the process product stream
Primary Subject
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Source
First, M.W. (ed.); Energy Research and Development Administration, Washington, D.C. (USA); Harvard Univ., Boston, Mass. (USA). Harvard Air Cleaning Lab; p. 1017-1033; 1976; p. 1017-1033; 14. US ERDA air cleaning conference; Sun Valley, Idaho, United States of America (USA); 2 - 4 Aug 1976
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BREEDER REACTORS, CARBON ISOTOPES, EPITHERMAL REACTORS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, FAST REACTORS, FBR TYPE REACTORS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, KRYPTON ISOTOPES, LIGHT NUCLEI, LIQUID METAL COOLED REACTORS, MANAGEMENT, NUCLEAR FACILITIES, NUCLEI, RADIOISOTOPES, REACTORS, WASTE MANAGEMENT, WASTE PROCESSING, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] In 1985, the US Department of Energy chose the Atomic Vapor Laser Isotope Separation (AVLIS) process as its advanced uranium enrichment process for the future. Since that time, the AVLIS program has advanced through various stages of development is now geared toward completing a full-scale integrated enrichment demonstration in 1992, leading to a November 1992 decision to deploy an AVLIS production plant with plant startup as early as 1997. This paper will describe the AVLIS process, discuss demonstration and deployment plans, and highlight recent technical progress. Some major accomplishments include: (1) operating the world's highest average power visible light laser system continuously at over 7,000 watts and accumulating more than 1 million hours copper vapor laser head time; (2) vaporizing metric tons of uranium in a full-scale separator unit; and (3) developing new low-cost and low waste producing methods for integrating the metal-based AVLIS system into the nuclear fuel cycle
Primary Subject
Secondary Subject
Source
Anon; 22 p; 1990; p. 20, Paper NUCL 67; American Chemical Society; Washington, DC (USA); 199. national meeting of the American Chemical Society; Boston, MA (USA); 22-27 Apr 1990; CONF-900402--; American Chemical Society, Division of Nuclear Chemistry and Technology, 1155 16th St., N.W. Washington, DC 20036
Record Type
Book
Literature Type
Conference
Country of publication
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Noble gas removal and concentration by combining fluorocarbon absorption and adsorption technologies
Little, D.K.; Eby, R.S.; Norton, J.L.; Patton, J.L.; Schultz, R.M.; Varagona, J.M.
Oak Ridge Gaseous Diffusion Plant, TN (USA)1982
Oak Ridge Gaseous Diffusion Plant, TN (USA)1982
AbstractAbstract
[en] Since the late 1960s, the Oak Ridge Gaseous Diffusion Plant, in conjunction with the Oak Ridge National Laboratory, has developed a fluorocarbon-based selective absorption system for removal of 85Kr and 14CO2 from nuclear fuel reprocessing facilities. Process performance and reliability have been well demonstrated with over 10 years of operation using simulated reactor and reprocessing plant dissolver off-gases and three generations of pilot plant scale equipment. A major development of this work is a combination absorption and stripping column which results in a simplified process with improved reliability and lower cost. The process has shown excellent flexibility in simultaneously removing and concentrating the radioactive gases of interest, i.e., > 99% removal is easily obtainable for Kr, Xe, and CO2. With the incoming feed gas containing around 10 ppM Kr, the product concentration of Kr from the single column is typically in the 1 to 10% range. Additional purification of the single-column product allows nearly pure components (> 90% Kr) to be obtained, thereby minimizing final storage or disposal requirements. Several alternatives for product purification have been investigated. In one system, 13X molecular sieve is used to first remove the process solvent vapor. Selective adsorption on 5A molecular sieves and silver mordenite is then used to separately remove the already concentrated CO2 and Xe, respectively. At this point Kr, which was withdrawn from the column at the present concentration level, has now been further purified by the removal of the other components and can be collected in a cold trap. This paper summarizes the performance capabilities of the single-column and discusses product purification system options, including selective desublimation, solid sorbent, and cryogenic charcoal adsorption techniques
Primary Subject
Secondary Subject
Source
4 Aug 1982; 22 p; 17. DOE nuclear air cleaning conference; Denver, CO (USA); 1 Aug - 6 Sep 1982; CONF-820833--8; Available from NTIS., PC A02/MF A01 as DE82019469
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ADSORBENTS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON COMPOUNDS, CARBON ISOTOPES, CARBON OXIDES, CHALCOGENIDES, COORDINATED RESEARCH PROGRAMS, DATA, DIAGRAMS, ELEMENTS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, FUNCTIONAL MODELS, HOURS LIVING RADIOISOTOPES, INFORMATION, INORGANIC ION EXCHANGERS, INTERMEDIATE MASS NUCLEI, ION EXCHANGE MATERIALS, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, KRYPTON ISOTOPES, LIGHT NUCLEI, MANAGEMENT, MATERIALS, MINERALS, NONMETALS, NUCLEAR FACILITIES, NUCLEI, NUMERICAL DATA, OXIDES, OXYGEN COMPOUNDS, RADIOISOTOPES, RARE GASES, RESEARCH PROGRAMS, WASTE MANAGEMENT, WASTE PROCESSING, WASTES, YEARS LIVING RADIOISOTOPES
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Hargrove, R.S.; Knighton, J.B.; Eby, R.S.; Pashley, J.H.; Norman, R.E.
Oak Ridge Gaseous Diffusion Plant, TN (USA); Lawrence Livermore National Lab., CA (USA)1986
Oak Ridge Gaseous Diffusion Plant, TN (USA); Lawrence Livermore National Lab., CA (USA)1986
AbstractAbstract
[en] AVLIS RD and D efforts are currently proceeding toward full-scale integrated enrichment demonstrations in the late 1980's and potential plant deployment in the mid 1990's. Since AVLIS requires a uranium metal feed and produces an enriched uranium metal product, some change in current uranium processing practices are necessitated. AVLIS could operate with a UF6-in UF6-out interface with little effect to the remainder of the fuel cycle. This path, however, does not allow electric utility customers to realize the full potential of low cost AVLIS enrichment. Several alternative processing methods have been identified and evaluated which appear to provide opportunities to make substantial cost savings in the overall fuel cycle. These alternatives involve varying levels of RD and D resources, calendar time, and technical risk to implement and provide these cost reduction opportunities. Both feed conversion contracts and fuel fabricator contracts are long-term entities. Because of these factors, it is not too early to start planning and making decisions on the most advantageous options so that AVLIS can be integrated cost effectively into the fuel cycle. This should offer economic opportunity to all parties involved including DOE, utilities, feed converters, and fuel fabricators. 10 refs., 11 figs., 2 tabs
Original Title
Effect of AVLIS feed requirements on overall fuel cycle
Primary Subject
Secondary Subject
Source
Aug 1986; 57 p; National meeting of the American Institute of Chemical Engineers; Boston, MA (USA); 24-27 Aug 1986; CONF-860826--13; Available from NTIS, PC A04/MF A01; 1 as DE87010275; Portions of this document are illegible in microfiche products.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
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Miyasaki, R.K.; Pobanz, N.E.; Warren, D.B.; Eby, R.S.; Jamison, J.R.
Bechtel Petroleum, Inc., San Francisco, CA (USA); Oak Ridge Gaseous Diffusion Plant, TN (USA)1983
Bechtel Petroleum, Inc., San Francisco, CA (USA); Oak Ridge Gaseous Diffusion Plant, TN (USA)1983
AbstractAbstract
[en] Dynamic simulation was used to evaluate the design of the Tails (depleted 235U assay) Withdrawal System for an uranium enrichment plant. Desirability of a simulation to check the design was indicated by requirements for a very high system reliability (99.95% availability) over a wide range of system throughput (85:1). Objective of the simulation included: evaluate alternate compressor anti-surge schemes, identify control system sensitivities, examine start-up and shut-down procedures, identify system limitations and testing of proposed design changes, and provide an understanding of system behavior. Three levels of process complexity were modeled: (1) compressions system, (2) combined compressor and liquefaction system, and (3) parallel operation of two compression/liquefaction trains. Two compressor train configurations were evaluated with the simulation mode. A FORTRAN based simulation methodology was used to implement and solve the mathematical models and plot the time history behavior for each test run. Results included discovery that that initial process steady state design would not operate stably. A new steady state was formulated which required some modifications to equipment sizing and control system philosophy. This new design was tested and proven with the simulation. Simulation objectives were achieved. Based on the simulation results, recommendations were made regarding: best compressor configuration, most effective anti-surge control scheme, changes to enhance system reliability and operability, control system sensitivities, control system design to achieve load sharing for parallel trains, and overall system operability with existing design
Primary Subject
Source
23 Mar 1983; 26 p; Summer computer simulation conference; Vancouver (Canada); 11-13 Jul 1983; CONF-830707--1; Available from NTIS, PC A03/MF A01; 1 as DE83009363
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Report
Literature Type
Conference
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