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Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
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1

TABLE OF RADIOACTIVE ELEMENTS.  

SciTech Connect

For those chemical elements which have no stable nuclides with a terrestrial isotopic composition, the data on radioactive half-lives and relative atomic masses for the nuclides of interest and importance have been evaluated and the recommended values and uncertainties are listed.

HOLDEN,N.E.

2001-06-29T23:59:59.000Z

2

Method for decontamination of radioactive metal surfaces  

DOE Patents (OSTI)

Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

Bray, Lane A. (Richland, WA)

1996-01-01T23:59:59.000Z

3

Method for decontamination of radioactive metal surfaces  

DOE Patents (OSTI)

Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

Bray, L.A.

1996-08-13T23:59:59.000Z

4

DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS  

Science Conference Proceedings (OSTI)

The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this modeling activity is to predict dissolved concentrations or solubility limits for 14 elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) important to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are in the form of tabulated functions with pH and log (line integral) CO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. The output data from this report are fundamental inputs for Total System Performance Assessment for the License Application (TSPA-LA) to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for all of the actinides. These models cover broad ranges of environmental conditions so that they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.

NA

2004-11-22T23:59:59.000Z

5

DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS  

Science Conference Proceedings (OSTI)

The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with {sup 231}Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data from this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.

P. Bernot

2005-07-13T23:59:59.000Z

6

Radioactive scrap metal decontamination technology assessment report  

SciTech Connect

Within the DOE complex there exists a tremendous quantity of radioactive scrap metal. As an example, it is estimated that within the gaseous diffusion plants there exists in excess of 700,000 tons of contaminated stainless steel. At present, valuable material is being disposed of when it could be converted into a high quality product. Liquid metal processing represents a true recycling opportunity for this material. By applying the primary production processes towards the material`s decontamination and re-use, the value of the strategic resource is maintained while drastically reducing the volume of material in need of burial. Potential processes for the liquid metal decontamination of radioactively contaminated metal are discussed and contrasted. Opportunities and technology development issues are identified and discussed. The processes compared are: surface decontamination; size reduction, packaging and burial; melting technologies; electric arc melting; plasma arc centrifugal treatment; air induction melting; vacuum induction melting; and vacuum induction melting and electroslag remelting.

Buckentin, J.M.; Damkroger, B.K.; Schlienger, M.E. [Sandia National Labs., Albuquerque, NM (United States). Liquid Metal Processing Lab.

1996-04-01T23:59:59.000Z

7

Evaluation of radioactive scrap metal recycling  

SciTech Connect

This report evaluates the human health risks and environmental and socio-political impacts of options for recycling radioactive scrap metal (RSM) or disposing of and replacing it. Argonne National Laboratory (ANL) is assisting the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, in assessing the implications of RSM management alternatives. This study is intended to support the DOE contribution to a study of metal recycling being conducted by the Task Group on Recycling and Reuse of the Organization for Economic Cooperation and Development. The focus is on evaluating the justification for the practice of recycling RSM, and the case of iron and steel scrap is used as an example in assessing the impacts. To conduct the evaluation, a considerable set of data was compiled and developed. Much of this information is included in this document to provide a source book of information.

Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

1995-12-01T23:59:59.000Z

8

STATUS OF RADIOACTIVE ELEMENTS IN THE ATOMIC WEIGHTS TABLE.  

SciTech Connect

During discussions within the Inorganic Chemistry Division Committee, that dealt with the Periodic Table of the Chemical Elements and the official IUPAC position on its presentation, the following question was raised. When the various chemical elements are presented, each with their appropriate atomic weight value, how should the radioactive elements be presented? The Atomic Weights Commission has treated this question in a number of different ways during the past century, almost in a random manner. This report reviews the position that the Commission has taken as a function of time, as a prelude to a discussion in Ottawa about how the Commission should resolve this question for the future.

HOLDEN,N.E.

2003-08-08T23:59:59.000Z

9

Radioactive Elements in the Standard Atomic Weights Table.  

Science Conference Proceedings (OSTI)

In the 1949 Report of the Atomic Weights Commission, a series of new elements were added to the Atomic Weights Table. Since these elements had been produced in the laboratory and were not discovered in nature, the atomic weight value of these artificial products would depend upon the production method. Since atomic weight is a property of an element as it occurs in nature, it would be incorrect to assign an atomic weight value to that element. As a result of that discussion, the Commission decided to provide only the mass number of the most stable (or longest-lived) known isotope as the number to be associated with these entries in the Atomic Weights Table. As a function of time, the mass number associated with various elements has changed as longer-lived isotopes of a particular element has been found in nature, or as improved half-life values of an element's isotopes might cause a shift in the longest-lived isotope from one mass to another. In the 1957 Report of the Atomic Weights Commission, it was decided to discontinue the listing of the mass number in the Atomic Weights Table on the grounds that the kind of information supplied by the mass number is inconsistent with the primary purpose of the Table, i.e., to provide accurate values of 'these constants' for use in various chemical calculations. In addition to the Table of Atomic Weights, the Commission included an auxiliary Table of Radioactive Elements for the first time, where the entry would be the isotope of that element which was the most stable, i.e., the one with the longest known half-life. In their 1973 Report, the Commission noted that the users of the main Table of Atomic Weights were dissatisfied with the omission of values for some elements in that Table and it was decided to reintroduce the mass number for the radioactive elements into the main Table. In their 1983 Report, the Commission decided that radioactive elements were considered to lack a characteristic terrestrial isotopic composition, from which an atomic weight value could be calculated to five or more figure accuracy, without prior knowledge of the sample involved. These elements were again listed in the Atomic Weights Table with no further information, i.e., with no mass number or atomic weight value.

Holden,N.E.

2007-08-04T23:59:59.000Z

10

Method for making radioactive metal articles having small dimensions  

SciTech Connect

A method for making a radioactive article such as wire, includes the steps of providing a metal article having a first shape, such a cylinder, that is either radioactive itself or can be converted to a second, radioactive isotope by irradiation; melting the metal article one or more times; optionally adding an alloying metal to the molten metal in order to enhance ductility or other properties; placing the metal article having the first shape (e.g., cylindrical) into a cavity in the interior of an extrusion body (e.g., a cylinder having a cylindrical cavity therein); extruding the extrusion body and the article having the first shape located in the cavity therein, resulting in an elongated extrusion body and an article having a second shape; removing the elongated extrusion body, for example by chemical means, leaving the elongated inner article substantially intact; optionally repeating the extrusion procedure one or more times; and then drawing the elongated article to still further elongate it, into wire, foil, or another desired shape. If the starting metal is enriched in a radioactive isotope or a precursor thereof, the end product can provide a more intense radiation source than conventionally manufactured radioactive wire, foil, or the like.

Ohriner, Evan K. (Knoxville, TN)

2000-01-01T23:59:59.000Z

11

RADIOACTIVE ELEMENTS IN THE STANDARD ATOMIC WEIGHTS TABLE  

Science Conference Proceedings (OSTI)

In the 1949 Report of the Atomic Weights Commission, a series of new elements were added to the Atomic Weights Table. Since these elements had been produced in the laboratory and were not discovered in nature, the atomic weight value of these artificial products would depend upon the production method. Since atomic weight is a property of an element as it occurs in nature, it would be incorrect to assign an atomic weight value to that element. As a result of that discussion, the Commission decided to provide only the mass number of the most stable (or longest-lived) known isotope as the number to be associated with these entries in the Atomic Weights Table. As a function of time, the mass number associated with various elements has changed as longer-lived isotopes of a particular element has been found in nature, or as improved half-life values of an element's isotopes might cause a shift in the longest-lived isotope from one mass to another. In the 1957 Report of the Atomic Weights Commission, it was decided to discontinue the listing of the mass number in the Atomic Weights Table on the grounds that the kind of information supplied by the mass number is inconsistent with the primary purpose of the Table, i.e., to provide accurate values of 'these constants' for use in various chemical calculations. In addition to the Table of Atomic Weights, the Commission included an auxiliary Table of Radioactive Elements for the first time, where the entry would be the isotope of that element which was the most stable, i.e., the one with the longest known half-life. In their 1973 Report, the Commission noted that the users of the main Table of Atomic Weights were dissatisfied with the omission of values for some elements in that Table and it was decided to reintroduce the mass number for the radioactive elements into the main Table. In their 1983 Report, the Commission decided that radioactive elements were considered to lack a characteristic terrestrial isotopic composition, from which an atomic weight value could be calculated to five or more figure accuracy, without prior knowledge of the sample involved. These elements were again listed in the Atomic Weights Table with no further information, i.e., with no mass number or atomic weight value. For the elements, which have no stable characteristic terrestrial isotopic composition, the data on the half-lives and the relative atomic masses for the nuclides of interest for those elements have been evaluated. The values of the half-lives with their uncertainties are listed in the table. The uncertainties are given for the last digit quoted of the half-life and are given in parentheses. A half-life entry for the Table having a value and an uncertainty of 7 {+-} 3 is listed in the half-life column as 7 (3). The criteria to include data in this Table, is to be the same as it has been for over sixty years. It is the same criteria, which are used for all data that are evaluated for inclusion in the Standard Table of Atomic Weights. If a report of data is published in a peer-reviewed journal, that data is evaluated and considered for inclusion in the appropriate table of the biennial report of the Atomic Weights Commission. As better data becomes available in the future, the information that is contained in either of the Tables of Standard Atomic Weights or in the Table of Radioactive Elements may be modified. It should be noted that the appearance of any datum in the Table of the Radioactive Elements is merely for the purposes of calculating an atomic mass value for any sample of a radioactive material, which might have a variety of isotopic compositions and it has no implication as to the priority for claiming discovery of a given element and is not intended to. The atomic mass values have been taken primarily from the 2003 Atomic Mass Table. Mass values for those radioisotopes that do not appear in the 2003 Atomic mass Table have been taken from preliminary data of the Atomic Mass Data Center. Most of the quoted half-lives.

Holden, N.E.; Holden, N.; Holden,N.E.

2011-07-27T23:59:59.000Z

12

Scrap metal management issues associated with naturally occurring radioactive material  

Science Conference Proceedings (OSTI)

Certain industrial processes sometimes generate waste by-products that contain naturally occurring radioactive material (NORM) at elevated concentrations. Some industries, including the water treatment, geothermal energy, and petroleum industries, generate scrap metal that may be contaminated with NORM wastes. Of these three industries, the petroleum industry probably generates the largest quantity of NORM-contaminated equipment, conservatively estimated at 170,000 tons per year. Equipment may become contaminated when NORM-containing scale or sludge accumulates inside water-handling equipment. The primary radionuclides of concern in these NORM wastes are radium-226 and radium-228. NORM-contaminated equipment generated by the petroleum industry currently is managed several ways. Some equipment is routinely decontaminated for reuse; other equipment becomes scrap metal and may be disposed of by burial at a licensed landfill, encapsulation inside the wellbore of an abandoned well, or shipment overseas for smelting. In view of the increased regulatory activities addressing NORM, the economic burden of managing NORM-contaminated wastes, including radioactive scrap metal, is likely to continue to grow. Efforts to develop a cost-effective strategy for managing radioactive scrap metal should focus on identifying the least expensive disposition options that provide adequate protection of human health and the environment. Specifically, efforts should focus on better characterizing the quantity of radioactive scrap available for recycle or reuse, the radioactivity concentration levels, and the potential risks associated with different disposal options.

Smith, K.P.; Blunt, D.L.

1995-08-01T23:59:59.000Z

13

Protocols for implementing DOE authorized release of radioactive scrap metals  

SciTech Connect

A process to implement the US Department of Energy`s (DOE) policy for authorized release of radioactive materials from DOE facilities is provided in the Draft Handbook for Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material, published by DOE in 1997 and distributed to DOE field offices for interim use and implementation. The authorized release of such property is intended to permit its beneficial use across the entire DOE complex. A computerized management tool--P2Pro(RSM)--has been developed to aid in carrying out the release process for radioactive metals. It contains protocols for the authorized release process and relevant information to facilitate the evaluation of scrap metals for reuse and recycle. The P2Pro(RSM) protocols provide DOE and its contractors with an effective, user-friendly tool for managing authorized release activities P2Pro(RSM) is designed to be used in the Windows{sup {trademark}} environment. The protocols incorporate a relational database coupled with a graphic-user interface to guide the user through the appropriate steps so authorized release limits can be developed. With the information provided in the database, an as-low-as-reasonably-achievable (ALARA) optimization process can be easily set up and run for up to 10 alternatives for disposition of radioactive scrap metals. The results of the ALARA optimization process can be printed in a series of reports and submitted as part of the application for the authorized release of the radioactive scrap metals.

Chen, S.Y.; Arnish, J.; Kamboj, S.; Nieves, L.A. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1999-11-01T23:59:59.000Z

14

Radioactively Contaminated Scrap Metal An International Approach to Monitoring, Interception & Managing  

E-Print Network (OSTI)

of uncontrolled radioactive source incidents. Aside from radiation exposure to workers and the public development of a database where countries can report scrap radiation incidents. Training: InternationalRadioactively Contaminated Scrap Metal An International Approach to Monitoring, Interception

15

Assessment of recycling or disposal alternatives for radioactive scrap metal  

Science Conference Proceedings (OSTI)

The US Department of Energy, Office of Environmental Restoration and Waste Management, is participating with the Organization for Economic Cooperation and Development (OECD) is an evaluation of management alternatives for radioactive scarp metals. For this purpose, Argonne National Laboratory is assessing alternatives for radioactive scrap metals. For this purpose, Argonne National Laboratory is assessing environmental and societal implications of recycling and/or disposal process alternatives (with metal replacement). Findings will be presented in a report from the OECD Task Group. This paper focuses on the radiological risk assessment and dose estimate sensitivity analysis. A ``tiered`` concept for release categories, with and without use restrictions, is being developed. Within the tiers, different release limits may be indicated for specific groupings of radionuclides. Depending on the spectrum of radionuclides that are present and the level of residual activity after decontamination and/or smelting, the scrap may be released for unrestricted public use or for specified public uses, or it may be recycled within the nuclear industry. The conversatism of baseline dose estimates is examined, and both more realistic parameter values and protective measures for workers are suggested.

Murphie, W.E.; Lilly, M.J. III [USDOE Assistant Secretary for Environmental Restoration and Waste Management, Washington, DC (United States). Office of Environmental Restoration; Nieves, L.A.; Chen, S.Y. [Argonne National Lab., IL (United States)

1993-10-01T23:59:59.000Z

16

Assessment of recycling or disposal alternatives for radioactive scrap metal  

Science Conference Proceedings (OSTI)

The US Department of Energy, Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, is participating with the Organization for Economic Cooperation and Development in providing analytical support for evaluation of management alternatives for radioactive scrap metals. For this purpose, Argonne National Laboratory is assessing environmental and societal implications of recycling and/or disposal process alternatives. This effort includes development of inventory estimates for contaminated metals; investigation of scrap metal market structure, processes, and trends; assessment of radiological and nonradiological effects of recycling; and investigation of social and political factors that are likely to either facilitate or constrain recycling opportunities. In addition, the option of scrap metal disposal is being assessed, especially with regard to the environmental and health impacts of replacing these metals if they are withdrawn from use. This paper focuses on the radiological risk assessment and dose estimate sensitivity analysis. A {open_quotes}tiered{close_quotes} concept for release categories, with and without use restrictions, is being developed. Within the tiers, different release limits may be indicated for specific groupings of radionuclides. Depending on the spectrum of radionuclides that are present and the level of residual activity after decontamination and/or smelting, the scrap may be released for unrestricted public use or for specified public uses, or it may be recycled within the nuclear industry. The conservatism of baseline dose estimates is examined, and both more realistic parameter values and protective measures for workers are suggested.

Murphie, W.E.; Lilly, M.J. III [US Dept. of Energy, Oak Ridge, TN (United States); Nieves, L.A.; Chen, S.Y. [Argonne National Lab., IL (United States)

1993-11-01T23:59:59.000Z

17

Hydrogen production during processing of radioactive sludge containing noble metals  

DOE Green Energy (OSTI)

Hydrogen was produced when radioactive sludge from Savannah River Site radioactive waste containing noble metals was reacted with formic acid. This will occur in a process tank in the Defense Waste Facility at SRS when waste is vitrified. Radioactive sludges from four tanks were tested in a lab-scale apparatus. Maximum hydrogen generation rates varied from 5 {times}10{sup {minus}7} g H{sub 2}/hr/g of sludge from the least reactive sludge (from Waste Tank 51) to 2 {times}10{sup {minus}4} g H{sub 2}/hr/g of sludge from the most reactive sludge (from Waste Tank 11). The time required for the hydrogen generation to reach a maximum varied from 4.1 to 25 hours. In addition to hydrogen, carbon dioxide and nitrous oxide were produced and the pH of the reaction slurry increased. In all cases, the carbon dioxide and nitrous oxide were generated before the hydrogen. The results are in agreement with large-scale studies using simulated sludges.

Ha, B.C.; Ferrara, D.M.; Bibler, N.E.

1992-01-01T23:59:59.000Z

18

Hydrogen production during processing of radioactive sludge containing noble metals  

DOE Green Energy (OSTI)

Hydrogen was produced when radioactive sludge from Savannah River Site radioactive waste containing noble metals was reacted with formic acid. This will occur in a process tank in the Defense Waste Facility at SRS when waste is vitrified. Radioactive sludges from four tanks were tested in a lab-scale apparatus. Maximum hydrogen generation rates varied from 5 {times}10{sup {minus}7} g H{sub 2}/hr/g of sludge from the least reactive sludge (from Waste Tank 51) to 2 {times}10{sup {minus}4} g H{sub 2}/hr/g of sludge from the most reactive sludge (from Waste Tank 11). The time required for the hydrogen generation to reach a maximum varied from 4.1 to 25 hours. In addition to hydrogen, carbon dioxide and nitrous oxide were produced and the pH of the reaction slurry increased. In all cases, the carbon dioxide and nitrous oxide were generated before the hydrogen. The results are in agreement with large-scale studies using simulated sludges.

Ha, B.C.; Ferrara, D.M.; Bibler, N.E.

1992-09-01T23:59:59.000Z

19

Securing the metal recycling chain for the steel industry by detecting orphan radioactive sources in scrap metal  

SciTech Connect

Experimental tests are reported for the detection of the heavy metal shielding of orphan sources hidden inside scrap metal by using a recently developed muon tomography system. Shielded sources do not trigger alarm in radiation portal commonly employed at the entrance of steel industry using scrap metal. Future systems integrating radiation portals with muon tomography inspection gates will substantially reduce the possibility of accidental melting of radioactive sources securing the use of recycled metal.

Pesente, S.; Benettoni, M.; Checchia, P.; Conti, E.; Gonella, F.; Nebbia, G. [INFN Sezione di Padova, via Marzolo 8, 35131 Padova Italy (Italy); Vanini, S.; Viesti, G.; Zumerle, G. [INFN Sezione di Padova, via Marzolo 8, 35131 Padova Italy (Italy); University of Padova and INFN Sezione di Padova, via Marzolo 8, 35131 Padova Italy (Italy); Bonomi, G.; Zenoni, A. [University of Brescia, via Branze 38, 25123 Brescia and INFN Sezione di Pavia, via Bassi 6, 27100 Pavia (Italy); Calvini, P.; Squarcia, S. [University of Genova and INFN Sezione di Genova, via Dodecaneso 33, 16146 Genova (Italy)

2010-08-04T23:59:59.000Z

20

Molten salt/metal extractions for recovery of transuranic elements  

SciTech Connect

The integral fast reactor (EFR) is an advanced reactor concept that incorporates metallic driver and blanket fuels, an inherently safe, liquid-sodium-cooled, pool-type, reactor design, and on-site pyrochemical reprocessing (including electrorefining) of spent fuels and wastes. This paper describes a pyrochemical method that is being developed at Argonne National Laboratory to recover transuranic elements from the EFR electrorefiner process salt. The method uses multistage extractions between molten chloride salts and cadmium metal at high temperatures. The chemical basis of the salt extraction method, the test equipment, and a test plan are discussed.

Chow, L.S.; Basco, J.K.; Ackerman, J.P.; Johnson, T.R.

1992-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Molten salt/metal extractions for recovery of transuranic elements  

SciTech Connect

The integral fast reactor (EFR) is an advanced reactor concept that incorporates metallic driver and blanket fuels, an inherently safe, liquid-sodium-cooled, pool-type, reactor design, and on-site pyrochemical reprocessing (including electrorefining) of spent fuels and wastes. This paper describes a pyrochemical method that is being developed at Argonne National Laboratory to recover transuranic elements from the EFR electrorefiner process salt. The method uses multistage extractions between molten chloride salts and cadmium metal at high temperatures. The chemical basis of the salt extraction method, the test equipment, and a test plan are discussed.

Chow, L.S.; Basco, J.K.; Ackerman, J.P.; Johnson, T.R.

1992-09-01T23:59:59.000Z

22

Tabulation of thermodynamic data for chemical reactions involving 58 elements common to radioactive waste package systems  

DOE Green Energy (OSTI)

The rate of release and migration of radionuclides from a nuclear waste repository to the biosphere is dependent on chemical interactions between groundwater, the geologic host rock, and the radioactive waste package. For the purpose of this report, the waste package includes the wasteform, canister, overpack, and repository backfill. Chemical processes of interest include sorption (ion exchange), dissolution, complexation, and precipitation. Thermochemical data for complexation and precipitation calculations for 58 elements common to the radioactive waste package are presented. Standard free energies of formation of free ions, complexes, and solids are listed. Common logarithms of equilibrium constants (log K's) for speciation and precipitation reactions are listed. Unless noted otherwise, all data are for 298.15/sup 0/K and one atmosphere.

Benson, L.V.; Teague, L.S.

1980-08-01T23:59:59.000Z

23

Method for detection of antibodies for metallic elements  

DOE Patents (OSTI)

An apparatus and method for detecting antibodies specific to non-protein antigens. The apparatus is an immunological plate containing a plurality of plastic projections coated with a non-protein material. Assays utilizing the plate are capable of stabilizing the non-protein antigens with detection levels for antibodies specific to the antigens on a nanogram level. A screening assay with the apparatus allows for early detection of exposure to non-protein materials. Specifically metallic elements are detected. 10 figures.

Barrick, C.W.; Clarke, S.M.; Nordin, C.W.

1993-11-30T23:59:59.000Z

24

Elemental characterization of LL-MA radioactive waste packages with the associated particle technique  

Science Conference Proceedings (OSTI)

The French Alternative Energies and Atomic Energy Commission (CEA) and National Radioactive Waste Management Agency (ANDRA) are conducting an R and D program to improve the characterization of long-lived and medium activity (LL-MA) radioactive waste packages with analytical methods and with non-destructive nuclear measurements. This paper concerns fast neutron interrogation with the associated particle technique (APT), which brings 3D information about the waste material composition. The characterization of volume elements filled with iron, water, aluminium, and PVC in bituminized and fibre concrete LL-MA waste packages has been investigated with MCNP [1] and MODAR data analysis software [2]. APT provides usable information about major elements presents in the volumes of interest. However, neutron scattering on hydrogen nuclei spreads the tagged neutron beam out of the targeted volume towards surrounding materials, reducing spatial selectivity. Simulation shows that small less than 1 L targets can be characterised up to the half-radius of a 225 L bituminized drum, the matrix of which is very rich in hydrogen. Deeper characterization in concrete is possible but limited by counting statistics due to photon attenuation in this dense matrix and, unless large inspection volumes are considered, by the lack of spatial selectivity of the tagged neutron beam due to neutron scattering. (authors)

Perot, B.; Carasco, C.; Toure, M.; El Kanawati, W.; Eleon, C. [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 Saint-Paul-lez-Durance (France)

2011-07-01T23:59:59.000Z

25

Treatment and Stabilization of Potentially Pyrophoric Radioactive Metal Chips and Turnings  

SciTech Connect

As part of the continuing mission to decontaminate, decommission, and restore environmental quality at multiple sites throughout the U.S. Department of Energy (US DOE) nuclear complex, approximately 2,000 containers of potentially pyrophoric radioactive metal chips and turnings, weighing over 192,000 kilograms have been identified. These wastes, mostly depleted uranium (DU) and thorium metals, must be treated to remove or immobilize a wide range of hazardous and toxic regulated waste constituents without igniting the radioactive metal. Also, the treated metal wastes must be placed in an inert condition to prevent any future pyrophoric problems during storage, transportation, and disposal. All secondary wastes resulting from treatment activities must have a pathway to final disposal or destruction, in accordance with all applicable US federal and state laws, and regulations. To further this mission and to begin reducing the pyrophoric radioactive metal inventories throughout the US DOE system, a contract was awarded to Perma-Fix Environmental Services, Inc. to develop appropriate treatment methods, prove those methods in a First Article Test (FAT), and treat US DOE's existing inventory of pyrophoric radioactive metal wastes. The FAT was performed successfully between October 2002 and December 2002 using four containers of waste from the Rocky Flats Environmental Technology Site. The treated chips and turnings from this FAT were shipped for disposal at a private land disposal facility in the State of Utah. Since the FAT, two full-scale treatment projects have been performed under the contract. Between November 6, 2003 and March 4, 2004, 478 containers of Hanford DU chip wastes in mineral oil and soil matrices were treated. The treated chip waste was returned for disposal at the permitted mixed waste landfill at the Hanford Site. Between February 5, 2004, and February 25, 2005, another 222 containers of Rocky Flats DU chip waste, comprised of three distinct physical waste forms, were treated and disposed at the same land disposal facility in Utah. Complicating this task was the wide variety of hazardous and toxic contaminants, and great variability in the physical waste form. The chemical contaminants included mineral oil, polychlorinated biphenyls (PCBs), numerous volatile and semi-volatile organic contaminants, and toxic metals. Three main physical waste forms were included in the US DOE pyrophoric radioactive metal waste inventory: (1) chips and turnings in oil, (2) chips and turnings in soil, and (3) chips and turnings in sludge. The successful treatment method had to be capable of removing oil, PCBs, and volatile organics without resulting in ignition of the pyrophoric metals. After successful removal of hazardous and toxic organic contaminants, the toxic metals remaining in the waste required further stabilization to limit their potential for long-term leaching in land disposal facilities. The final waste form and its packaging also had to comply with the waste acceptance criteria of the land disposal facilities at the US DOE Hanford Site, in Richland, Washington, and the private disposal facility in Utah. This paper will describe the treatment process, the challenges encountered and overcome, the lessons learned, and final quality of the treated chip waste. Disposal and/or destruction of secondary wastes from the treatment process will also be discussed. (authors)

Crocker, B.R.; Grondin, R.; Yarbrough, T. [Perma-Fix Environmental Services Inc., 701 Scarboro Road, Suite 300, Oak Ridge, TN (United States)

2006-07-01T23:59:59.000Z

26

Beneficial reuse `96: The fourth annual conference on the recycle and reuse of radioactive scrap metal  

SciTech Connect

From October 22-24, 1996 the University of Tennessee`s Energy, Environment and Resources Center and the Oak Ridge National Laboratory`s Center for Risk Management cosponsored Beneficial Reuse `96: The Fourth Annual Conference on the Recycle and Reuse of Radioactive Materials. Along with the traditional focus on radioactive scrap metals, this year`s conference included a wide range of topics pertaining to naturally occurring radioactive materials (NORM), and contaminated concrete reuse applications. As with previous Beneficial Reuse conferences, the primary goal of this year`s conference was to bring together stakeholder representatives for presentations, panel sessions and workshops on significant waste minimization issues surrounding the recycle and reuse of contaminated metals and other materials. A wide range of industry, government and public stakeholder groups participated in this year`s conference. An international presence from Canada, Germany and Korea helped to make Beneficial Reuse `96 a well-rounded affair. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

NONE

1997-02-01T23:59:59.000Z

27

Features of adsorbed radioactive chemical elements and their isotopes distribution in iodine air filters AU-1500 at nuclear power plants  

E-Print Network (OSTI)

The main aim of research is to investigate the physical features of spatial distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the iodine air filters of the type of AU1500 in the forced exhaust ventilation systems at the nuclear power plant. The gamma activation analysis method is applied to accurately characterize the distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the AU1500 iodine air filter after its long term operation at the nuclear power plant. The typical spectrum of the detected chemical elements and their isotopes in the AU1500 iodine air filter, which was exposed to the bremsstrahlung gamma quantum irradiation, produced by the accelerating electrons in the tantalum target, are obtained. The spatial distributions of the detected chemical element 127I and some other chemical elements and their isotopes in the layer of absorber, which was made of the cylindrical coal granules of the type of SKT3, in the AU1500 iodine air filter are also researched. The possible influences by the standing acoustic wave of air pressure in the iodine air filter on the spatial distribution of the chemical elements and their isotopes in the iodine air filter are discussed. The comprehensive analysis of obtained research results on the distribution of the adsorbed chemical elements and their isotopes in the absorber of iodine air filter is performed.

I. M. Neklyudov; A. N. Dovbnya; N. P. Dikiy; O. P. Ledenyov; Yu. V. Lyashko

2013-06-21T23:59:59.000Z

28

It's Elemental - The Element Francium  

NLE Websites -- All DOE Office Websites (Extended Search)

Radon Radon Previous Element (Radon) The Periodic Table of Elements Next Element (Radium) Radium The Element Francium [Click for Isotope Data] 87 Fr Francium 223 Atomic Number: 87 Atomic Weight: 223 Melting Point: 300 K (27°C or 81°F) Boiling Point: Unknown Density: Unknown Phase at Room Temperature: Solid Element Classification: Metal Period Number: 7 Group Number: 1 Group Name: Alkali Metal Radioactive What's in a name? Named for the country of France. Say what? Francium is pronounced as FRAN-see-em. History and Uses: Francium was discovered by Marguerite Catherine Perey, a French chemist, in 1939 while analyzing actinium's decay sequence. Although considered a natural element, scientists estimate that there is no more than one ounce of francium in the earth's crust at one time. Since there is so little

29

Analysis of the application of decontamination technologies to radioactive metal waste minimization using expert systems  

Science Conference Proceedings (OSTI)

Radioactive metal waste makes up a significant portion of the waste currently being sent for disposal. Recovery of this metal as a valuable resource is possible through the use of decontamination technologies. Through the development and use of expert systems a comparison can be made of laser decontamination, a technology currently under development at Ames Laboratory, with currently available decontamination technologies for applicability to the types of metal waste being generated and the effectiveness of these versus simply disposing of the waste. These technologies can be technically and economically evaluated by the use of expert systems techniques to provide a waste management decision making tool that generates, given an identified metal waste, waste management recommendations. The user enters waste characteristic information as input and the system then recommends decontamination technologies, determines residual contamination levels and possible waste management strategies, carries out a cost analysis and then ranks, according to cost, the possibilities for management of the waste. The expert system was developed using information from literature and personnel experienced in the use of decontamination technologies and requires validation by human experts and assignment of confidence factors to the knowledge represented within.

Bayrakal, S.

1993-09-30T23:59:59.000Z

30

Variations of decay rates of radio-active elements and their connections with global anisotropy of physical space  

E-Print Network (OSTI)

The analysis of correlations between fluctuations of alpha- and beta-decay rates for different radio-active elements is carried out. These fluctuations exceed significantly errors of measurements in many cases. They have the periodical character and reveal definite spatial directions. We suggest that the observed fluctuations are caused by the unique physical reason connected with the global anisotropy of physical space and by the new force.

Yu. A. Baurov; I. F. Malov

2010-01-29T23:59:59.000Z

31

PROCESSING OF URANIUM-METAL-CONTAINING FUEL ELEMENTS  

DOE Patents (OSTI)

A process is given for recovering uranium from neutronbombarded uranium- aluminum alloys. The alloy is dissolved in an aluminum halide--alkali metal halide mixture in which the halide is a mixture of chloride and bromide, the aluminum halide is present in about stoichiometric quantity as to uranium and fission products and the alkali metal halide in a predominant quantity; the uranium- and electropositive fission-products-containing salt phase is separated from the electronegative-containing metal phase; more aluminum halide is added to the salt phase to obtain equimolarity as to the alkali metal halide; adding an excess of aluminum metal whereby uranium metal is formed and alloyed with the excess aluminum; and separating the uranium-aluminum alloy from the fission- productscontaining salt phase. (AEC)

Moore, R.H.

1962-10-01T23:59:59.000Z

32

Physical features of accumulation and distribution processes of small disperse coal dust precipitations and absorbed radioactive chemical elements in iodine air filter at nuclear power plant  

E-Print Network (OSTI)

The physical features of absorption process of radioactive chemical elements and their isotopes in the iodine air filters of the type of AU-1500 at the nuclear power plants are researched. It is shown that the non-homogenous spatial distribution of absorbed radioactive chemical elements and their isotopes in the iodine air filter, probed by the gamma-activation analysis method, is well correlated with the spatial distribution of small disperse coal dust precipitations in the iodine air filter. This circumstance points out to an important role by the small disperse coal dust fractions of absorber in the absorption process of radioactive chemical elements and their isotopes in the iodine air filter. The physical origins of characteristic interaction between the radioactive chemical elements and the accumulated small disperse coal dust precipitations in an iodine air filter are considered. The analysis of influence by the researched physical processes on the technical characteristics and functionality of iodine ...

Ledenyov, Oleg P; Poltinin, P Ya; Fedorova, L I

2012-01-01T23:59:59.000Z

33

Assessment of potential radiation exposures by uncontrolled recycle or reuse of radioactive scrap metals  

Science Conference Proceedings (OSTI)

With current waste monitoring technology it is reasonable to assume that much of the material designated as low-level waste, generated within nuclear facilities, is in fact uncontaminated. A criterion for uncontrolled disposal of low-level radioactive contaminated waste is that the radiation exposure of the public and of each individual caused by this disposal is so low that radiation protection measures need not be taken. The International Atomic Energy Agency (IAEA) suggests an annual effective dose of 10 {micro}Sv as a limit for the individual radiation dose and derived the initial control levels of residual radioactivity based on the Publication 30 of the International Commission on Radiological Protection (ICRP). In 1990, new recommendations on radiation protection standards were developed by ICRP to take into account new biological information related to the detriment associated with radiation exposure. Adoption of these recommendations necessitated a revision of the Commission's secondary limits contained in Publication 30. This study summarizes the potential radiation exposure from valuable scrap metal considered for uncontrolled recycle by new ICRP recommendations. Potential exposure pathways to people were analyzed and concentrations leading to an individual dose of 10 {micro}Sv/year were calculated for 14 key radionuclides. These potential radiation doses are compared with the results of previous study.

Lee, S.Y.; Lee, K.J.

1999-07-01T23:59:59.000Z

34

THE KINETICS OF THE ELECTROCHEMICAL DEPOSITION OF RADIOACTIVE IONS ON METAL SURFACES  

SciTech Connect

The Nernst-Brunner equation hss been applied to the electrochemical deposition of carrier-free radioactive ions on metal foils in a modified form to include decay and growth. The modified equation was shown to hold for the depesition of B/sup 212/(ThC) and Bi/sup 210/(RaE) on nickel foils from weak hydrochloric acid solutions under the following conditions: pure Bl/sup 212/ in equilibrium with Pb/sup 212/(ThB), Bi/sup 212/ in equilibrium with Th/sup 228/ (RdTh), and Bi/sup 210/ in equilibrium with Pb/sup 210/(RaD), Some indications of the purity of the deposited radio-bismuth are given. (auth)

Fahland, J.; Herrmann, G.; Strassmann, F.

1958-10-01T23:59:59.000Z

35

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1995-10-24T23:59:59.000Z

36

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

37

Galactic Chemical Evolution of the Iron Peak Elements in the Lowest Metallicity Regimes  

Science Conference Proceedings (OSTI)

We use the nucleosynthetic yields of Chieffi & Limongi (2004) in conjunction with a Salpeter initial mass function (IMF) to determine the evolution of iron peak element abundances ( Z ?=?2128) as a function of metallicity. Since we will focus on the extremely metal poor region below [ Fe / H ]?=??1.5 we will consider input from core collapse supernovae (SNe) only

Jennifer Sobeck; Carla Frohlich; Jim Truran; Yeunjin Kim

2010-01-01T23:59:59.000Z

38

Development of DOE complex wide authorized release protocols for radioactive scrap metals.  

SciTech Connect

Within the next few decades, several hundred thousand tons of metal are expected to be removed from nuclear facilities across the U.S. Department of Energy (DOE) complex as a result of decontamination and decommissioning (D&D) activities. These materials, together with large quantities of tools, equipment, and other items that are commonly recovered from site cleanup or D&D activities, constitute non-real properties that warrant consideration for reuse or recycle, as permitted and practiced under the current DOE policy. The provisions for supporting this policy are contained in the Draft Handbook for Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material published by DOE in 1997 and distributed to DOE field offices for interim use and implementation. The authorized release of such property is intended to permit its beneficial use across the entire DOE complex. The objective of this study is to develop readily usable computer-based release protocols to facilitate implementation of the Handbook in evaluating the scrap metals for reuse and recycle. The protocols provide DOE with an effective oversight tool for managing release activities.

Chen, S. Y.

1998-11-23T23:59:59.000Z

39

Canister arrangement for storing radioactive waste  

DOE Patents (OSTI)

The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

Lorenzo, Donald K. (Knoxville, TN); Van Cleve, Jr., John E. (Kingston, TN)

1982-01-01T23:59:59.000Z

40

Canister arrangement for storing radioactive waste  

DOE Patents (OSTI)

The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

Lorenzo, D.K.; Van Cleve, J.E. Jr.

1980-04-23T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Approach and issues toward development of risk-based release standards for radioactive scrap metal recycle and reuse  

Science Conference Proceedings (OSTI)

The decontamination and decommissioning of nuclear facilities is expected to generate large amounts of slightly radioactive scrap metal (RSM). It is likely that some of these materials will be suitable for recycling and reuse. The amount of scrap steel from DOE facilities, for instance, is estimated to be more than one million tons (Hertzler 1993). However, under current practice and without the establishment of acceptable recycling standards, the RSM would be disposed of primarily as radioactive low-level waste (LLW). In the United States, no specific standards have been developed for the unrestricted release of bulk contaminated materials. Although standards for unrestricted release of radioactive surface contamination (NRC 1974) have existed for about 20 years, the release of materials is not commonly practiced because of the lack of risk-based justifications. Recent guidance from international bodies (IAEA 1988) has established a basis for deriving risk-based release limits for radioactive materials. It is important, therefore, to evaluate the feasibility of recycling and associated issues necessary for the establishment of risk-based release limits for the radioactive metals.

Chen, S.Y.; Nieves, L.A.; Nabelssi, B.K.; LePoire, D.J.

1994-03-01T23:59:59.000Z

42

Process and apparatus for generating elemental sulfur and re-usable metal oxide from spent metal sulfide sorbents  

DOE Patents (OSTI)

A process and apparatus for generating elemental sulfur and re-usable metal oxide from spent metal-sulfur compound. Spent metal-sulfur compound is regenerated to re-usable metal oxide by moving a bed of spent metal-sulfur compound progressively through a single regeneration vessel having a first and second regeneration stage and a third cooling and purging stage. The regeneration is carried out and elemental sulfur is generated in the first stage by introducing a first gas of sulfur dioxide which contains oxygen at a concentration less than the stoichiometric amount required for complete oxidation of the spent metal-sulfur compound. A second gas containing sulfur dioxide and excess oxygen at a concentration sufficient for complete oxidation of the partially spent metal-sulfur compound, is introduced into the second regeneration stage. Gaseous sulfur formed in the first regeneration stage is removed prior to introducing the second gas into the second regeneration stage. An oxygen-containing gas is introduced into the third cooling and purging stage. Except for the gaseous sulfur removed from the first stage, the combined gases derived from the regeneration stages which are generally rich in sulfur dioxide and lean in oxygen, are removed from the regenerator as an off-gas and recycled as the first and second gas into the regenerator. Oxygen concentration is controlled by adding air, oxygen-enriched air or pure oxygen to the recycled off-gas.

Ayala, Raul E. (Clifton Park, NY); Gal, Eli (Lititz, PA)

1995-01-01T23:59:59.000Z

43

It's Elemental - The Element Technetium  

NLE Websites -- All DOE Office Websites (Extended Search)

Molybdenum Molybdenum Previous Element (Molybdenum) The Periodic Table of Elements Next Element (Ruthenium) Ruthenium The Element Technetium [Click for Isotope Data] 43 Tc Technetium 98 Atomic Number: 43 Atomic Weight: 98 Melting Point: 2430 K (2157°C or 3915°F) Boiling Point: 4538 K (4265°C or 7709°F) Density: 11 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 5 Group Number: 7 Group Name: none Radioactive and Artificially Produced What's in a name? From the Greek word for artificial, technetos. Say what? Technetium is pronounced as tek-NEE-she-em. History and Uses: Technetium was the first artificially produced element. It was isolated by Carlo Perrier and Emilio Segrè in 1937. Technetium was created by bombarding molybdenum atoms with deuterons that had been accelerated by a

44

Spray forming metallic support bands on ceramic elements  

SciTech Connect

A study was conducted to assess the feasibility of spray depositing a metal ring on the end of ceramic tubes using a low temperature spray forming process developed at the INEL. 1/16 in.--1.8 in. thick x 1/2 in. wide tin, zinc, and aluminum alloy rings were spray formed using a bench-scale nozzle without damaging the ceramic. Analysis of the deposits indicated that they were suitably dense and exhibited good adherence to the ceramic material.

McHugh, K.D.

1994-02-10T23:59:59.000Z

45

Radioactive scrap metal (RSM) inventory & tracking system and prototype RSM field survey  

SciTech Connect

Based on very preliminary information, it has been estimated that the radioactive scrap metal (RSM) inventories at DOE facilities amount to about 1.5 million tons and a much larger amount will be generated from decontamination and decommissioning of surplus DOE facilities. To implement a national DOE program for beneficial reuse of RSM, it will be necessary to known the location and characteristics of RSM inventories that are available and will be generated to match them with product demands. It is the intent of this task to provide a standardized methodology via a RSM database for recording, tracking, and reporting data on RSM inventories. A multiple relational database in dBASE IV was designed and a PC-based code was written in Clipper 5.0 syntax to expedite entry, editing, querying, and reporting of RSM survey data. The PC based-code, the multiple relational database files, and other external files used by the code to generate reports and queries constitute a customized software application called the RSM Inventory & Tracking System (RSM I&TS). A prototype RSM field survey was conducted at the Nevada Test Site (NTS) to demonstrate the field use of the RSM I&TS and logistics of conducting the survey. During the demonstration, about 50 tons of RSM were sized, characterized, sorted, and packaged in transport containers.

Thomas, T.R.

1994-09-01T23:59:59.000Z

46

It's Elemental - The Element Astatine  

NLE Websites -- All DOE Office Websites (Extended Search)

Polonium Polonium Previous Element (Polonium) The Periodic Table of Elements Next Element (Radon) Radon The Element Astatine [Click for Isotope Data] 85 At Astatine 210 Atomic Number: 85 Atomic Weight: 210 Melting Point: 575 K (302°C or 576°F) Boiling Point: Unknown Density: about 7 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Semi-metal Period Number: 6 Group Number: 17 Group Name: Halogen Radioactive What's in a name? From the Greek word for unstable, astatos. Say what? Astatine is pronounced as AS-teh-teen or as AS-teh-ten. History and Uses: Astatine was produced by Dale R. Carson, K.R. MacKenzie and Emilio Segrè by bombarding an isotope of bismuth, bismuth-209, with alpha particles that had been accelerated in a device called a cyclotron. This created

47

It's Elemental - The Element Thorium  

NLE Websites -- All DOE Office Websites (Extended Search)

Actinium Actinium Previous Element (Actinium) The Periodic Table of Elements Next Element (Protactinium) Protactinium The Element Thorium [Click for Isotope Data] 90 Th Thorium 232.03806 Atomic Number: 90 Atomic Weight: 232.03806 Melting Point: 2023 K (1750°C or 3182°F) Boiling Point: 5061 K (4788°C or 8650°F) Density: 11.72 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 7 Group Number: none Group Name: Actinide Radioactive What's in a name? Named for the Scandinavian god of war, Thor. Say what? Thorium is pronounced as THOR-ee-em or as THO-ree-em. History and Uses: Thorium was discovered by Jöns Jacob Berzelius, a Swedish chemist, in 1828. He discovered it in a sample of a mineral that was given to him by the Reverend Has Morten Thrane Esmark, who suspected that it contained an

48

Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste  

DOE Patents (OSTI)

Cesium and strontium are extracted from aqueous acidic radioactive waste containing rare earth elements, technetium and actinides, by contacting the waste with a composition of a complex organoboron compound and polyethylene glycol in an organofluorine diluent mixture. In a preferred embodiment the complex organoboron compound is chlorinated cobalt dicarbollide, the polyethylene glycol has the formula RC.sub.6 H.sub.4 (OCH.sub.2 CH.sub.2).sub.n OH, and the organofluorine diluent is a mixture of bis-tetrafluoropropyl ether of diethylene glycol with at least one of bis-tetrafluoropropyl ether of ethylene glycol and bis-tetrafluoropropyl formal. The rare earths, technetium and the actinides (especially uranium, plutonium and americium), are extracted from the aqueous phase using a phosphine oxide in a hydrocarbon diluent, and reextracted from the resulting organic phase into an aqueous phase by using a suitable strip reagent.

Zaitsev, Boris N. (St. Petersburg, RU); Esimantovskiy, Vyacheslav M. (St. Petersburg, RU); Lazarev, Leonard N. (St. Petersburg, RU); Dzekun, Evgeniy G. (Ozersk, RU); Romanovskiy, Valeriy N. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID); Herbst, Ronald S. (Idaho Falls, ID); Law, Jack D. (Pocatello, ID)

2001-01-01T23:59:59.000Z

49

Finite element analysis of contact stress in a full-metallic pipe joint for hydrogen pipelines  

Science Conference Proceedings (OSTI)

Hydrogen gas has been widely recognized as an environmentally clean and renewable energy fuel, and it provides a way to reduce greenhouse gas and air pollution emission. A great deal of effort has been made to develop new techniques in the field of hydrogen ... Keywords: contact stress analyses, finite element model (FEM), hydrogen pipelines, metallic gasket, pipe joint

Nan Bu; Naohiro Ueno; Osamu Fukuda

2010-02-01T23:59:59.000Z

50

NEW HUBBLE SPACE TELESCOPE OBSERVATIONS OF HEAVY ELEMENTS IN FOUR METAL-POOR STARS  

Science Conference Proceedings (OSTI)

Elements heavier than the iron group are found in nearly all halo stars. A substantial number of these elements, key to understanding neutron-capture nucleosynthesis mechanisms, can only be detected in the near-ultraviolet. We report the results of an observing campaign using the Space Telescope Imaging Spectrograph on board the Hubble Space Telescope to study the detailed heavy-element abundance patterns in four metal-poor stars. We derive abundances or upper limits from 27 absorption lines of 15 elements produced by neutron-capture reactions, including seven elements (germanium, cadmium, tellurium, lutetium, osmium, platinum, and gold) that can only be detected in the near-ultraviolet. We also examine 202 heavy-element absorption lines in ground-based optical spectra obtained with the Magellan Inamori Kyocera Echelle Spectrograph on the Magellan-Clay Telescope at Las Campanas Observatory and the High Resolution Echelle Spectrometer on the Keck I Telescope on Mauna Kea. We have detected up to 34 elements heavier than zinc. The bulk of the heavy elements in these four stars are produced by r-process nucleosynthesis. These observations affirm earlier results suggesting that the tellurium found in metal-poor halo stars with moderate amounts of r-process material scales with the rare earth and third r-process peak elements. Cadmium often follows the abundances of the neighboring elements palladium and silver. We identify several sources of systematic uncertainty that must be considered when comparing these abundances with theoretical predictions. We also present new isotope shift and hyperfine structure component patterns for Lu II and Pb I lines of astrophysical interest.

Roederer, Ian U.; Thompson, Ian B. [Carnegie Observatories, Pasadena, CA 91101 (United States); Lawler, James E. [Department of Physics, University of Wisconsin, Madison, WI 53706 (United States); Sobeck, Jennifer S. [Department of Astronomy and Astrophysics, University of Chicago, Chicago, IL 60637 (United States); Beers, Timothy C. [National Optical Astronomy Observatory, Tucson, AZ 85719 (United States); Cowan, John J. [Homer L. Dodge Department of Physics and Astronomy, University of Oklahoma, Norman, OK 73019 (United States); Frebel, Anna [Massachusetts Institute of Technology, Kavli Institute for Astrophysics and Space Research, Cambridge, MA 02139 (United States); Ivans, Inese I. [Department of Physics and Astronomy, University of Utah, Salt Lake City, UT 84112 (United States); Schatz, Hendrik [Department of Physics and Astronomy, Michigan State University, E. Lansing, MI 48824 (United States); Sneden, Christopher [Department of Astronomy, University of Texas at Austin, Austin, TX 78712 (United States)

2012-12-15T23:59:59.000Z

51

Heavy Element Dispersion in the Metal-Poor Globular Cluster M92  

E-Print Network (OSTI)

Dispersion among the light elements is common in globular clusters (GCs), while dispersion among heavier elements is less common. We present detection of r-process dispersion relative to Fe in 19 red giants of the metal-poor GC M92. Using spectra obtained with the Hydra multi-object spectrograph on the WIYN Telescope at Kitt Peak National Observatory, we derive differential abundances for 21 species of 19 elements. The Fe-group elements, plus Y and Zr, are homogeneous at a level of 0.07-0.16 dex. The heavy elements La, Eu, and Ho exhibit clear star-to-star dispersion spanning 0.5-0.8 dex. The abundances of these elements are correlated with one another, and we demonstrate that they were produced by r-process nucleosynthesis. This r-process dispersion is not correlated with the dispersion in C, N, or Na in M92, indicating that r-process inhomogeneities were present in the gas throughout star formation. The r-process dispersion is similar to that previously observed in the metal-poor GC M15, but its origin in M...

Roederer, Ian U

2011-01-01T23:59:59.000Z

52

HEAVY-ELEMENT DISPERSION IN THE METAL-POOR GLOBULAR CLUSTER M92  

SciTech Connect

Dispersion among the light elements is common in globular clusters (GCs), while dispersion among heavier elements is less common. We present detection of r-process dispersion relative to Fe in 19 red giants of the metal-poor GC M92. Using spectra obtained with the Hydra multi-object spectrograph on the WIYN Telescope at Kitt Peak National Observatory, we derive differential abundances for 21 species of 19 elements. The Fe-group elements, plus Y and Zr, are homogeneous at a level of 0.07-0.16 dex. The heavy-elements La, Eu, and Ho exhibit clear star-to-star dispersion spanning 0.5-0.8 dex. The abundances of these elements are correlated with one another, and we demonstrate that they were produced by r-process nucleosynthesis. This r-process dispersion is not correlated with the dispersion in C, N, or Na in M92, indicating that r-process inhomogeneities were present in the gas throughout star formation. The r-process dispersion is similar to that previously observed in the metal-poor GC M15, but its origin in M15 or M92 is unknown at present.

Roederer, Ian U. [Carnegie Observatories, 813 Santa Barbara Street, Pasadena, CA 91101 (United States); Sneden, Christopher, E-mail: iur@obs.carnegiescience.edu [Department of Astronomy, University of Texas at Austin, 1 University Station, C1400, Austin, TX 78712 (United States)

2011-07-15T23:59:59.000Z

53

Distribution of small dispersive coal dust particles and absorbed radioactive chemical elements in conditions of forced acoustic resonance in iodine air filter at nuclear power plant  

E-Print Network (OSTI)

The physical features of distribution of the small dispersive coal dust particles and the adsorbed radioactive chemical elements and their isotopes in the absorber with the granular filtering medium with the cylindrical coal granules were researched in the case of the intensive air dust aerosol stream flow through the iodine air filter (IAF). It was shown that, at the certain aerodynamic conditions in the IAF, the generation of the acoustic oscillations is possible. It was found that the acoustic oscillations generation results in an appearance of the standing acoustic waves of the air pressure (density) in the IAF. In the case of the intensive blow of the air dust aerosol, it was demonstrated that the standing acoustic waves have some strong influences on both: 1) the dynamics of small dispersive coal dust particles movement and their accumulation in the IAF; 2) the oversaturation of the cylindrical coal granules by the adsorbed radioactive chemical elements and their isotopes in the regions, where the antin...

Ledenyov, Oleg P

2013-01-01T23:59:59.000Z

54

Distribution of small dispersive coal dust particles and absorbed radioactive chemical elements in conditions of forced acoustic resonance in iodine air filter at nuclear power plant  

E-Print Network (OSTI)

The physical features of distribution of the small dispersive coal dust particles and the adsorbed radioactive chemical elements and their isotopes in the absorber with the granular filtering medium with the cylindrical coal granules were researched in the case of the intensive air dust aerosol stream flow through the iodine air filter (IAF). It was shown that, at the certain aerodynamic conditions in the IAF, the generation of the acoustic oscillations is possible. It was found that the acoustic oscillations generation results in an appearance of the standing acoustic waves of the air pressure (density) in the IAF. In the case of the intensive blow of the air dust aerosol, it was demonstrated that the standing acoustic waves have some strong influences on both: 1) the dynamics of small dispersive coal dust particles movement and their accumulation in the IAF; 2) the oversaturation of the cylindrical coal granules by the adsorbed radioactive chemical elements and their isotopes in the regions, where the antinodes of the acoustic waves are positioned. Finally, we completed the comparative analysis of the theoretical calculations with the experimental results, obtained for the cases of: 1) the experimental aerodynamic modeling of physical processes of the absorbed radioactive chemical elements and their isotopes distribution in the IAF; and 2) the gamma-activation spectroscopy analysis of the absorbed radioactive chemical elements and their isotopes distribution in the IAF. We made the innovative propositions on the necessary technical modifications with the purpose to improve the IAF technical characteristics and increase its operational time at the nuclear power plant (NPP), going from the completed precise characterization of the IAF parameters at the long term operation.

Oleg P. Ledenyov; Ivan M. Neklyudov

2013-06-14T23:59:59.000Z

55

CRITICAL EXPERIMENTS ON SLIGHTLY ENRICHED URANIUM METAL FUEL ELEMENTS IN GRAPHITE LATTICES  

SciTech Connect

A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt% enriched, uranium metal, hollow cylinder, fuel elements in AGOT graphite moderator. Six lattice spacings were used, varying from 6.93 to 16.0 in. on a triangular pitch. Critical loadings and fuel element worths were determined and compared to the results of 4-group diffusion theory. Calculations utilized TEMPEST, S/sub 4/, FORM, and AIM-5 programs on the IBM 7090. The calculated K/sub eff/ compared well with experiments over the full range of moderator-to-fuel volume ratios when using a 2200 m/sec graphite absorption cross section of 4.07 mb. The sensitivity of the calculation to variations in the graphite absorption cross section was examined and the experimental error due to inventory uncertainties was assessed. The differential worths of both the central and peripheral fuel elements were obtained and agreed in general with AIM- 5 calculations. The thermal flux traverse of a unit cell was shown to agree best with a Wilkins' spectrum option of TEMPEST. Details of both the experimental and theoretical methods are given. (auth) The work functions of cesiated and cesium- hydridecoated surfaces are studied. A thermionlc cell for performance analyses is described. Design characteristics of water-cooled and liquid-metal-cooled nuclearthermionic generators for naval power applications are compared. (T.F.H.)

Campbell, R.W.; Doyas, R.J.; Field, H.C.; Guderjahn, C.A.; Guenther, R.L.; Hausknecht, D.E.; Mayer, M.S.; Morewitz, H.A.

1963-06-30T23:59:59.000Z

56

Melting of low-level radioactive non-ferrous metal for release  

SciTech Connect

Siempelkamp Nukleartechnik GmbH has gained lots of experience from melting ferrous metals for recycling in the nuclear cycle as well as for release to general reuse. Due to the fact that the world market prices for non-ferrous metals like copper, aluminium or lead raised up in the past and will remain on a high level, recycling of low-level contaminated or activated metallic residues from nuclear decommissioning becomes more important. Based on the established technology for melting of ferrous metals in a medium frequency induction furnace, different melt treatment procedures for each kind of non-ferrous metals were developed and successfully commercially converted. Beside different procedures also different melting techniques such as crucibles, gas burners, ladles etc. are used. Approximately 340 Mg of aluminium, a large part of it with a uranium contamination, have been molten successfully and have met the release criteria of the German Radiation Protection Ordinance. The experience in copper and brass melting is based on a total mass of 200 Mg. Lead melting in a special ladle by using a gas heater results in a total of 420 Mg which could be released. The main goal of melting of non-ferrous metals is release for industrial reuse after treatment. Especially for lead, a cooperation with a German lead manufacturer also for recycling of non releasable lead is being planned. (authors)

Quade, Ulrich; Kluth, Thomas; Kreh, Rainer [Siempelkamp Nukleartechnik GmbH (Germany)

2007-07-01T23:59:59.000Z

57

Preparation of Metal Filter Element for Fail Safety in IGCC Filter Unit  

SciTech Connect

Metal filter elements as the fail safety filter are fabricated by the methods using cold isostatic pressure (compress method) and binder (binder method) to form the filter element and tested in a experimental and bench units. The fail safety filter on the filtration system is mounted additionally in order to intercept the particle leak when the main filter element is broken. So it should have two contrary functions of a high permeability and being plugged easily. The filter element having high porosity and high plugging property was fabricated by the bind method. It has the porosity more than 50%, showed very small pressure drop less than 10mmH2O at the face velocity of 0.15m/s, and plugged within 5 minutes with the inhibition of the particle leak larger than 4 {micro}m. The test result of corrosion tendency in IGCC gas stream at 500 C shows SUS310L material is very reasonable among SUS310, SUS316, Inconel 600, and Hastelloy X.

Choi, J-H.; Ahn, I-S.; Bak, Y-C.; Bae, S-Y.; Ha, S-J.; Jang, H-J.

2002-09-18T23:59:59.000Z

58

AN EVALUATION OF POTENTIAL LINER MATERIALS FOR ELIMINATING FCCI IN IRRADIATED METALLIC NUCLEAR FUEL ELEMENTS  

Science Conference Proceedings (OSTI)

Metallic nuclear fuels are being looked at as part of the Global Nuclear Energy Program for transmuting longlive transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. In order to optimize the performance of these fuels, the concept of using liners to eliminate the fuel/cladding chemical interactions that can occur during irradiation of a fuel element has been investigated. The potential liner materials Zr and V have been tested using solid-solid diffusion couples, consisting of liner materials butted against fuel alloys and against cladding materials. The couples were annealed at the relatively high temperature of 700C. This temperature would be the absolute maximum temperature present at the fuel/cladding interface for a fuel element in-reactor. Analysis was performed using a scanning electron microscope equipped with energy-dispersive and wavelengthdispersive spectrometers (SEM/EDS/WDS) to evaluate any developed diffusion structures. At 700C, minimal interaction was observed between the metallic fuels and either Zr or V. Similarly, limited interaction was observed between the Zr and V and the cladding materials. The best performing liner material appeared to be the V, based on amounts of interaction.

D. D. Keiser; J. I. Cole

2007-09-01T23:59:59.000Z

59

Removal of radioactive materials and heavy metals from water using magnetic resin  

DOE Patents (OSTI)

Magnetic polymer resins capable of efficient removal of actinides and heavy metals from contaminated water are disclosed together with methods for making, using, and regenerating them. The resins comprise polyamine-epichlorohydrin resin beads with ferrites attached to the surfaces of the beads. Markedly improved water decontamination is demonstrated using these magnetic polymer resins of the invention in the presence of a magnetic field, as compared with water decontamination methods employing ordinary ion exchange resins or ferrites taken separately.

Kochen, Robert L. (Boulder, CO); Navratil, James D. (Simi Valley, CA)

1997-01-21T23:59:59.000Z

60

Preferential Acidic, Alkaline and Neutral Solubility of Metallic Elements In Fly Ash  

NLE Websites -- All DOE Office Websites (Extended Search)

Preferential Acidic, Alkaline and Neutral Solubility of Preferential Acidic, Alkaline and Neutral Solubility of Metallic Elements in Fly Ash Ann G. Kim 1 1 ORISE Research Fellow, National Energy Technology Laboratory, US Department of Energy, 626 Cochrans Mill Rd., Pittsburgh, PA 15236-0940 KEYWORDS: Coal Utilization By-Products, leaching, pH ABSTRACT In the US, over 100 million tons of coal utilization by-products (CUB) are generated annually. To determine if exposure of these materials to aqueous fluids poses an environmental threat, researchers at the National Energy Technology Laboratory (NETL) have conducted extensive leaching tests. Five 1 kg samples of 35 PC fly ashes have been leached with acid, neutral and alkaline solutions at an approximate rate of 130 mL/d for 1 to 3 months. The leachates are

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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61

DETECTION OF ELEMENTS AT ALL THREE r-PROCESS PEAKS IN THE METAL-POOR STAR HD 160617  

SciTech Connect

We report the first detection of elements at all three r-process peaks in the metal-poor halo star HD 160617. These elements include arsenic and selenium, which have not been detected previously in halo stars, and the elements tellurium, osmium, iridium, and platinum, which have been detected previously. Absorption lines of these elements are found in archive observations made with the Space Telescope Imaging Spectrograph on board the Hubble Space Telescope. We present up-to-date absolute atomic transition probabilities and complete line component patterns for these elements. Additional archival spectra of this star from several ground-based instruments allow us to derive abundances or upper limits of 45 elements in HD 160617, including 27 elements produced by neutron-capture reactions. The average abundances of the elements at the three r-process peaks are similar to the predicted solar system r-process residuals when scaled to the abundances in the rare earth element domain. This result for arsenic and selenium may be surprising in light of predictions that the production of the lightest r-process elements generally should be decoupled from the heavier r-process elements.

Roederer, Ian U. [Carnegie Observatories, Pasadena, CA 91101 (United States); Lawler, James E., E-mail: iur@obs.carnegiescience.edu, E-mail: jelawler@wisc.edu [Department of Physics, University of Wisconsin, Madison, WI 53706 (United States)

2012-05-01T23:59:59.000Z

62

P2Pro(RSM) : a computerized management tool for implementing DOE's authorized release process for radioactive scrap metals.  

SciTech Connect

Within the next few decades, several hundred thousand tons of metal and several million cubic meters of concrete are expected to be removed from nuclear facilities across the US Department of Energy (DOE) complex as a result of decontamination and decommissioning (D&D) activities. These materials, together with large quantities of tools, equipment, and other items that are commonly recovered from site cleanup or D&D activities, constitute non-real properties that warrant consideration for release from regulatory control for reuse or recycle, as permitted and practiced under current DOE policy. The provisions for implementing this policy are contained in the Draft Handbook for Controlling Release for Reuse or Recycle of Non-Real Property Containing Residual Radioactive Material published by DOE in 1997 and distributed to DOE Field Offices for interim use and implementation. This manual describes a computer management tool, P2Pro(RSM), that implements the first 5 steps of the 10-step process stipulated by the Handbook. P2Pro(RSM) combines an easy-to-use Windows interface with a comprehensive database to facilitate the development of authorized release limits for non-real property.

Arnish, J.; Chen, S. Y.; Kamboj, S.; Nieves, L.

1999-07-22T23:59:59.000Z

63

SUB-LEU-METAL-THERM-001 SUBCRITICAL MEASUREMENTS OF LOW ENRICHED TUBULAR URANIUM METAL FUEL ELEMENTS BEFORE & AFTER IRRADIATION  

Science Conference Proceedings (OSTI)

With the shutdown of the Hanford PUREX (Plutonium-Uranium Extraction Plant) reprocessing plant in the 1970s, adequate storage capacity for spent Hanford N Reactor fuel elements in the K and N Reactor pools became a concern. To maximize space utilization in the pools, accounting for fuel burnup was considered. Calculations indicated that at typical fuel exposures for N Reactor, the spent-fuel critical mass would be twice the critical mass for green fuel. A decision was reached to test the calculational result with a definitive experiment. If the results proved positive, storage capacity could be increased and N Reactor operation could be prolonged. An experiment to be conducted in the N Reactor spent-fuel storage pool was designed and assembled and the services of the Battelle Northwest Laboratories (BNWL) (now Pacific Northwest National Laboratory [PNNL]) critical mass laboratory were procured for the measurements. The experiments were performed in April 1975 in the Hanford N Reactor fuel storage pool. The fuel elements were MKIA fuel assemblies, comprising two concentric tubes of low-enriched metallic uranium. Two separate sets of measurements were performed: one with ''green'' (fresh) fuel and one with spent fuel. Both the green and spent fuel, were measured in the same geometry. The spent-fuel MKIA assemblies had an average burnup of 2865 MWd (megawatt days)/t. A constraint was imposed restricting the measurements to a subcritical limit of k{sub eff} = 0.97. Subcritical count rate data was obtained with pulsed-neutron and approach-to-critical measurements. Ten (10) configurations with green fuel and nine (9) configurations with spent fuel are described and evaluated. Of these, 3 green fuel and 4 spent fuel loading configurations were considered to serve as benchmark models. However, shortcomings in experimental data failed to meet the high standards for a benchmark problem. Nevertheless, the data provided by these subcritical measurements can supply useful information to analysts evaluating spent fuel subcriticality. The original purpose of the subcritical measurements was to validate computer model predictions that spent N Reactor fuel of a particular, typical exposure (2740 MWd/t) had a critical mass equal to twice that of unexposed fuel of the same type. The motivation for performing this work was driven by the need to increase spent fuel storage limits. These subcritical measurements confirmed the computer model predictions.

SCHWINKENDORF, K.N.

2006-05-12T23:59:59.000Z

64

RESRAD-RECYCLE : a computer model for analyzing radiation exposures resulting from recycling radioactively contaminated scrap metals or reusing ratioactively surface-contaminated materials and equipment.  

Science Conference Proceedings (OSTI)

RESRAD-RECYCLE is a computer code designed by Argonne National Laboratory (ANL) to be used in making decisions about the disposition of radioactively contaminated materials and scrap metals. It implements a pathway analysis methodology to evaluate potential radiation exposures resulting from the recycling of contaminated scrap metals and the reuse of surface-contaminated materials and equipment. For modeling purposes, it divides the entire metal recycling process into six steps: (1) scrap delivery, (2) scrap melting, (3) ingot delivery, (4) product fabrication, (5) product distribution, and (6) use of finished product. RESRAD-RECYCLE considers the reuse of surface-contaminated materials in their original forms. It contains representative exposure scenarios for each recycling step and the reuse process; users can also specify scenarios if desired. The model calculates individual and collective population doses for workers involved in the recycling process and for the public using the finished products. The results are then used to derive clearance levels for the contaminated materials on the basis of input dose restrictions. The model accounts for radiological decay and ingrowth, dilution and partitioning during melting, and distribution of refined metal in the various finished products, as well as the varying densities and geometries of the radiation sources during the recycling process. A complete material balance in terms of mass and radioactivity during the recycling process can also be implemented. In an international validation study, the radiation doses calculated by RESRAD-RECYCLE were shown to agree fairly well with actual measurement data.

Cheng, J. J.; Kassas, B.; Yu, C.; Arnish, J. J.; LePoire, D.; Chen, S.-Y.; Williams, W. A.; Wallo, A.; Peterson, H.; Environmental Assessment; DOE; Univ. of Texas

2004-11-01T23:59:59.000Z

65

Metal decontamination for waste minimization using liquid metal refining technology  

Science Conference Proceedings (OSTI)

The current Department of Energy Mixed Waste Treatment Project flowsheet indicates that no conventional technology, other than surface decontamination, exists for metal processing. Current Department of Energy guidelines require retrievable storage of all metallic wastes containing transuranic elements above a certain concentration. This project is in support of the National Mixed Low Level Waste Treatment Program. Because of the high cost of disposal, it is important to develop an effective decontamination and volume reduction method for low-level contaminated metals. It is important to be able to decontaminate complex shapes where surfaces are hidden or inaccessible to surface decontamination processes and destruction of organic contamination. These goals can be achieved by adapting commercial metal refining processes to handle radioactive and organic contaminated metal. The radioactive components are concentrated in the slag, which is subsequently vitrified; hazardous organics are destroyed by the intense heat of the bath. The metal, after having been melted and purified, could be recycled for use within the DOE complex. In this project, we evaluated current state-of-the-art technologies for metal refining, with special reference to the removal of radioactive contaminants and the destruction of hazardous organics. This evaluation was based on literature reports, industrial experience, plant visits, thermodynamic calculations, and engineering aspects of the various processes. The key issues addressed included radioactive partitioning between the metal and slag phases, minimization of secondary wastes, operability of the process subject to widely varying feed chemistry, and the ability to seal the candidate process to prevent the release of hazardous species.

Joyce, E.L. Jr.; Lally, B. [Los Alamos National Lab., NM (United States); Ozturk, B.; Fruehan, R.J. [Carnegie-Mellon Univ., Pittsburgh, PA (United States). Dept. of Materials Science and Engineering

1993-09-01T23:59:59.000Z

66

METHOD AND APPARATUS FOR EXAMINING FUEL ELEMENTS FOR LEAKAGE  

DOE Patents (OSTI)

A process and a device for the continuous monitoring of fuel elements while in use in a liquid-metal-cooled, argonblanketed nuclear reactor are presented. A fraction of the argon gas is withdrawn, contacted with a negative electrical charge for attraction of any alkali metal formed from argon by neutron reaction, and recycled into the reactor. The electrical charge is introduced into water, and the water is examined for radioactive alkali metals. (AEC)

Smith, R.R.; Echo, M.W.; Doe, C.B.

1963-12-31T23:59:59.000Z

67

New Hubble Space Telescope Observations of Heavy Elements in Four Metal-Poor Stars  

E-Print Network (OSTI)

Elements heavier than the iron group are found in nearly all halo stars. A substantial number of these elements, key to understanding neutron-capture nucleosynthesis mechanisms, can only be detected in the near-ultraviolet. ...

Roederer, Ian U.

68

Materials Reliability Program: Welding Residual Stress Dissimilar Metal Butt-Weld Finite Element Modeling Handbook (MRP-317)  

Science Conference Proceedings (OSTI)

The residual stresses imparted by the welding process are a principal factor in the process of primary water stress corrosion cracking (PWSCC) of Alloy 82/182 nickel-alloy (i.e., dissimilar metal) piping butt welds in pressurized water reactors (PWRs). Numerical methods by finite element analyses are frequently used to simulate the welding process in order to predict the residual stress distribution in the weld and base material as an input to crack growth calculations. The crack growth calculations, in ...

2011-12-22T23:59:59.000Z

69

It's Elemental - The Element Tungsten  

NLE Websites -- All DOE Office Websites (Extended Search)

melting point of all metallic elements and is used to make filaments for incandescent light bulbs, fluorescent light bulbs and television tubes. Tungsten expands at nearly the...

70

Detection of the Second R-Process Peak Element Tellurium in Metal-Poor Stars  

E-Print Network (OSTI)

Using near-ultraviolet spectra obtained with the Space Telescope Imaging Spectrograph on board the Hubble Space Telescope, we detect neutral tellurium in three metal-poor stars enriched by products of r-process nucleosynthesis, ...

Roederer, Ian U.

71

Great thermoelectric power factor enhancement of CoSb{sub 3} through the lightest metal element filling  

Science Conference Proceedings (OSTI)

Lithium, the lightest metal element with a small ionic radius, is successfully filled into the voids of CoSb{sub 3} by utilizing the high pressure synthesis technique. The synthesized Li{sub 0.4}Co{sub 4}Sb{sub 12} shows the largest thermoelectric power factor of 6000 {mu}W m{sup -1} K{sup -2} among all elemental filled CoSb{sub 3} materials. This significantly enhanced thermoelectric power factor is attributed to the large carrier mobility of Li{sub 0.4}Co{sub 4}Sb{sub 12}, 61 cm{sup 2} V{sup -1} s{sup -1}, featuring a good electron crystal property for the Li-filled CoSb{sub 3} samples.

Zhang Jianjun; Xu Bo; Wang Limin; Yu Dongli; Liu Zhongyuan; He Julong; Tian Yongjun [State Key Laboratory of Metastable Materials Science and Technology, Yanshan University, Qinhuangdao, Hebei 066004 (China)

2011-02-14T23:59:59.000Z

72

RESULTS FROM ANALYSIS OF THE FIRST AND SECOND STRIP EFFLUENT COALESCER ELEMENTS FROM RADIOACTIVE OPERATIONS OF THE MODULAR CAUSTIC-SIDE SOLVENT EXTRACTION UNIT  

Science Conference Proceedings (OSTI)

The coalescer elements for the Strip Effluent (SE) acid within the Modular Caustic-Side Solvent Extraction Unit (MCU) experienced elevated differential pressure drop during radioactive operations. Following the end of operations for the first Macrobatch campaign and soon after start of the second Macrobatch campaign, personnel removed the coalescer media and provided to Savannah River National Laboratory (SRNL) for diagnostic investigation of the causes of reduced flow. This report summarizes those studies. Two Strip Effluent (SE) coalescers were delivered to the Savannah River National Laboratory (SRNL). One was removed from the Modular Caustic-Side Solvent Extraction Unit (MCU) between processing of Macrobatch 1 and 2 (coalescer 'Alpha'), and the second was removed from MCU after processing of {approx}24,000 gallons of salt solution (coalescer 'Beta'). Both coalescers underwent the same general strip acid flush program to reduce the dose and were delivered to SRNL for analysis of potential occluding solids. Analysis of Coalescer Alpha indicates the presence of aluminum hydroxide solids and aluminosilicate solids, while analysis of Coalescer Beta indicates the presence of aluminum hydroxide solids, but no aluminosilicates. Leaching studies on sections of both coalescers were performed. The results indicate that the coalescers had different amounts of solids present on them at the time of removal. Finally, samples of free liquids retrieved from both coalescers indicate no excessive amounts of CSSX solvent present. Given the strip acid flushing that occurred in the SE coalescers, the solids we detected on the coalescers are probably indicative of a larger quantity of these solids present before the strip acid flushing. Under this scenario, the excessive pressure drops are due to the solids and not from organic fouling.

Peters, T.; Fondeur, F.; Fink, S.

2011-06-28T23:59:59.000Z

73

Control of high level radioactive waste-glass melters. Part 6, Noble metal catalyzed formic acid decomposition, and formic acid/denitration  

DOE Green Energy (OSTI)

A necessary step in Defense Waste Processing Facility (DWPF) melter feed preparation for the immobilization of High Level Radioactive Waste (HLW) is reduction of Hg(II) to Hg(0), permitting steam stripping of the Hg. Denitrition and associated NOx evolution is a secondary effect of the use of formic acid as the mercury-reducing agent. Under certain conditions the presence of transition or noble metals can result in significant formic acid decomposition, with associated CO{sub 2} and H{sub 2} evolution. These processes can result in varying redox properties of melter feed, and varying sequential gaseous evolution of oxidants and hydrogen. Electrochemical methods for monitoring the competing processes are discussed. Laboratory scale techniques have been developed for simulating the large-scale reactions, investigating the relative effectiveness of the catalysts, and the effectiveness of catalytic poisons. The reversible nitrite poisoning of formic acid catalysts is discussed.

Bickford, D.F.; Coleman, C.J.; Hsu, C.L.W.; Eibling, R.E.

1990-12-31T23:59:59.000Z

74

Materials Reliability Program: Finite-Element Model Validation for Dissimilar Metal Butt-Welds (MRP-316)  

Science Conference Proceedings (OSTI)

Residual stresses imparted by the welding process are a principal factor in the process of primary water stress corrosion cracking (PWSCC) of Alloy 82/182 nickel-alloy dissimilar metal (DM) piping butt welds in pressurized water reactors (PWRs). Analytical models are frequently used to simulate the welding process in order to predict the residual stress distribution in the weld and base material as an input to crack growth calculations. The crack growth calculations, in turn, have demonstrated a high sen...

2011-12-20T23:59:59.000Z

75

Stellar abundances and ages for metal-rich Milky Way globular clusters - Stellar parameters and elemental abundances for 9 HB stars in NGC6352  

E-Print Network (OSTI)

[ABRIDGED] Metal-rich globular clusters provide important tracers of the formation of our Galaxy. Moreover, and not less important, they are very important calibrators for the derivation of properties of extra-galactic metal-rich stellar populations. Nonetheless, only a few of the metal-rich globular clusters in the Milky Way have been studied using high-resolution stellar spectra to derive elemental abundances. In this paper we present elemental abundances for nine HB stars in the metal-rich globular cluster NGC6352. The elemental abundances are based on high-resolution, high signal-to-noise spectra obtained with VLT/UVES. The elemental abundances have been derived using standard LTE calculations. We find that NGC6352 has [Fe/H]= -0.55, is enhanced in the alpha-elements to about +0.2 dex for Ca, Si, and Ti relative to Fe. For the iron-peak elements we find solar values. Based on the spectroscopically derived stellar parameters we find that an E(B-V)=0.24 and (m-M) roughly equal to 14.05 better fits the data ...

Feltzing, S; Johnson, R A

2008-01-01T23:59:59.000Z

76

Laminated metal composite formed from low flow stress layers and high flow stress layers using flow constraining elements and method of making same  

DOE Patents (OSTI)

This invention relates to a laminated metal composite, comprising alternating layers of low flow stress material and high flow stress material, and formed using flow constraining elements around each low flow stress layer; and a method of making same. A composite is a combination of at least two chemically distinct materials with a distinct interface separating the two materials. A metal matrix composite (MMC) is a composite material composed of a metal and a nonmetallic reinforcing agent such as silicon carbide (SiC) or graphite in continuous or discontinuous fiber, whisker, or discrete particulate form. A laminate is a material composed of several bonded layers. It is possible to have a laminate composed of multi-layers of a single type of material bonded to each other. However, such a laminate would not be considered to be a composite. The term {open_quotes}laminated metal composite{close_quotes} (LMC), as used herein, is intended to include a structural material composed of: (1) layers of metal or metal alloys interleaved with (2) a different metal, a metal alloy, or a metal matrix composite (MMC) containing strengthening agents.

Syn, C.K.; Lesuer, D.R.

1994-12-31T23:59:59.000Z

77

It's Elemental - The Element Potassium  

NLE Websites -- All DOE Office Websites (Extended Search)

Argon Argon Previous Element (Argon) The Periodic Table of Elements Next Element (Calcium) Calcium The Element Potassium [Click for Isotope Data] 19 K Potassium 39.0983 Atomic Number: 19 Atomic Weight: 39.0983 Melting Point: 336.53 K (63.38°C or 146.08°F) Boiling Point: 1032 K (759°C or 1398°F) Density: 0.89 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 1 Group Name: Alkali Metal What's in a name? From the English word potash. Potassium's chemical symbol comes from the Latin word for alkali, kalium. Say what? Potassium is pronounced as poh-TASS-ee-em. History and Uses: Although potassium is the eighth most abundant element on earth and comprises about 2.1% of the earth's crust, it is a very reactive element

78

It's Elemental - The Element Magnesium  

NLE Websites -- All DOE Office Websites (Extended Search)

Sodium Sodium Previous Element (Sodium) The Periodic Table of Elements Next Element (Aluminum) Aluminum The Element Magnesium [Click for Isotope Data] 12 Mg Magnesium 24.3050 Atomic Number: 12 Atomic Weight: 24.3050 Melting Point: 923 K (650°C or 1202°F) Boiling Point: 1363 K (1090°C or 1994°F) Density: 1.74 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 3 Group Number: 2 Group Name: Alkaline Earth Metal What's in a name? For Magnesia, a district in the region of Thessaly, Greece. Say what? Magnesium is pronounced as mag-NEE-zhi-em. History and Uses: Although it is the eighth most abundant element in the universe and the seventh most abundant element in the earth's crust, magnesium is never found free in nature. Magnesium was first isolated by Sir Humphry Davy, an

79

Process for producing elements from a fused bath using a metal strap and ceramic electrode body nonconsumable electrode assembly  

DOE Patents (OSTI)

A nonconsumable electrode assembly is described suitable for use in the production of metal by electrolytic reduction of a metal compound dissolved in a molten salt, the assembly comprising a ceramic electrode body and a metal subassembly of a metal conductor rod and at least one metal strap affixed to an end of the rod with opposing portions extending radially outwardly from the rod axis and having the ends of the strap attached to the electrode body. 7 figs.

Byrne, S.C.

1984-07-03T23:59:59.000Z

80

It's Elemental - The Element Sodium  

NLE Websites -- All DOE Office Websites (Extended Search)

Neon Neon Previous Element (Neon) The Periodic Table of Elements Next Element (Magnesium) Magnesium The Element Sodium [Click for Isotope Data] 11 Na Sodium 22.98976928 Atomic Number: 11 Atomic Weight: 22.98976928 Melting Point: 370.95 K (97.80°C or 208.04°F) Boiling Point: 1156 K (883°C or 1621°F) Density: 0.97 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 3 Group Number: 1 Group Name: Alkali Metal What's in a name? From the English word soda and from the Medieval Latin word sodanum, which means "headache remedy." Sodium's chemical symbol comes from the Latin word for sodium carbonate, natrium. Say what? Sodium is pronounced as SO-dee-em. History and Uses: Although sodium is the sixth most abundant element on earth and comprises

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

It's Elemental - The Element Barium  

NLE Websites -- All DOE Office Websites (Extended Search)

Cesium Cesium Previous Element (Cesium) The Periodic Table of Elements Next Element (Lanthanum) Lanthanum The Element Barium [Click for Isotope Data] 56 Ba Barium 137.327 Atomic Number: 56 Atomic Weight: 137.327 Melting Point: 1000 K (727°C or 1341°F) Boiling Point: 2170 K (1897°C or 3447°F) Density: 3.62 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 2 Group Name: Alkaline Earth Metal What's in a name? From the Greek word for heavy, barys. Say what? Barium is pronounced as BAR-ee-em. History and Uses: Barium was first isolated by Sir Humphry Davy, an English chemist, in 1808 through the electrolysis of molten baryta (BaO). Barium is never found free in nature since it reacts with oxygen in the air, forming barium oxide

82

It's Elemental - The Element Gold  

NLE Websites -- All DOE Office Websites (Extended Search)

Platinum Platinum Previous Element (Platinum) The Periodic Table of Elements Next Element (Mercury) Mercury The Element Gold [Click for Isotope Data] 79 Au Gold 196.966569 Atomic Number: 79 Atomic Weight: 196.966569 Melting Point: 1337.33 K (1064.18°C or 1947.52°F) Boiling Point: 3129 K (2856°C or 5173°F) Density: 19.282 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 11 Group Name: none What's in a name? From the Sanskrit word Jval and the Anglo-Saxon word gold. Gold's chemical symbol comes from the the latin word for gold, aurum. Say what? Gold is pronounced as GOLD. History and Uses: An attractive and highly valued metal, gold has been known for at least 5500 years. Gold is sometimes found free in nature but it is usually found

83

It's Elemental - The Element Iron  

NLE Websites -- All DOE Office Websites (Extended Search)

Manganese Manganese Previous Element (Manganese) The Periodic Table of Elements Next Element (Cobalt) Cobalt The Element Iron [Click for Isotope Data] 26 Fe Iron 55.845 Atomic Number: 26 Atomic Weight: 55.845 Melting Point: 1811 K (1538°C or 2800°F) Boiling Point: 3134 K (2861°C or 5182°F) Density: 7.874 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 8 Group Name: none What's in a name? From the Anglo-Saxon word iron. Iron's chemical symbol comes from the Latin word for iron, ferrum. Say what? Iron is pronounced as EYE-ern. History and Uses: Archaeological evidence suggests that people have been using iron for at least 5000 years. Iron is the cheapest and one of the most abundant of all metals, comprising nearly 5.6% of the earth's crust and nearly all of the

84

It's Elemental - The Element Cesium  

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Xenon Xenon Previous Element (Xenon) The Periodic Table of Elements Next Element (Barium) Barium The Element Cesium [Click for Isotope Data] 55 Cs Cesium 132.9054519 Atomic Number: 55 Atomic Weight: 132.9054519 Melting Point: 301.59 K (28.44°C or 83.19°F) Boiling Point: 944 K (671°C or 1240°F) Density: 1.93 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 1 Group Name: Alkali Metal What's in a name? From the Latin word for sky blue, caesius. Say what? Cesium is pronounced as SEE-zee-em. History and Uses: Cesium was discovered by Robert Wilhelm Bunsen and Gustav Robert Kirchhoff, German chemists, in 1860 through the spectroscopic analysis of Durkheim mineral water. They named cesium after the blue lines they observed in its

85

It's Elemental - The Element Europium  

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Samarium Samarium Previous Element (Samarium) The Periodic Table of Elements Next Element (Gadolinium) Gadolinium The Element Europium [Click for Isotope Data] 63 Eu Europium 151.964 Atomic Number: 63 Atomic Weight: 151.964 Melting Point: 1095 K (822°C or 1512°F) Boiling Point: 1802 K (1529°C or 2784°F) Density: 5.24 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: none Group Name: Lanthanide What's in a name? Named after the continent of Europe. Say what? Europium is pronounced as yoo-RO-pee-em. History and Uses: Europium was discovered by Eugène-Antole Demarçay, a French chemist, in 1896. Demarçay suspected that samples of a recently discovered element, samarium, were contaminated with an unknown element. He was able to produce

86

It's Elemental - The Element Sulfur  

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Phosphorus Phosphorus Previous Element (Phosphorus) The Periodic Table of Elements Next Element (Chlorine) Chlorine The Element Sulfur [Click for Isotope Data] 16 S Sulfur 32.065 Atomic Number: 16 Atomic Weight: 32.065 Melting Point: 388.36 K (115.21°C or 239.38°F) Boiling Point: 717.75 K (444.60°C or 832.28°F) Density: 2.067 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Non-metal Period Number: 3 Group Number: 16 Group Name: Chalcogen What's in a name? From the Sanskrit word sulvere and the Latin word sulphurium. Say what? Sulfur is pronounced as SUL-fer. History and Uses: Sulfur, the tenth most abundant element in the universe, has been known since ancient times. Sometime around 1777, Antoine Lavoisier convinced the rest of the scientific community that sulfur was an element. Sulfur is a

87

It's Elemental - The Element Cobalt  

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Iron Iron Previous Element (Iron) The Periodic Table of Elements Next Element (Nickel) Nickel The Element Cobalt [Click for Isotope Data] 27 Co Cobalt 58.933195 Atomic Number: 27 Atomic Weight: 58.933195 Melting Point: 1768 K (1495°C or 2723°F) Boiling Point: 3200 K (2927°C or 5301°F) Density: 8.86 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 9 Group Name: none What's in a name? From the German word for goblin or evil spirit, kobald and the Greek word for mine, cobalos. Say what? Cobalt is pronounced as KO-bolt. History and Uses: Cobalt was discovered by Georg Brandt, a Swedish chemist, in 1739. Brandt was attempting to prove that the ability of certain minerals to color glass blue was due to an unknown element and not to bismuth, as was commonly

88

It's Elemental - The Element Bromine  

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Selenium Selenium Previous Element (Selenium) The Periodic Table of Elements Next Element (Krypton) Krypton The Element Bromine [Click for Isotope Data] 35 Br Bromine 79.904 Atomic Number: 35 Atomic Weight: 79.904 Melting Point: 265.95 K (-7.2°C or 19.0°F) Boiling Point: 331.95 K (58.8°C or 137.8°F) Density: 3.11 grams per cubic centimeter Phase at Room Temperature: Liquid Element Classification: Non-metal Period Number: 4 Group Number: 17 Group Name: Halogen What's in a name? From the Greek word for stench, bromos. Say what? Bromine is pronounced as BRO-meen. History and Uses: The only nonmetallic element that is a liquid at normal room temperatures, bromine was produced by Carl Löwig, a young chemistry student, the summer before starting his freshman year at Heidelberg. When he showed his

89

It's Elemental - The Element Oxygen  

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Nitrogen Nitrogen Previous Element (Nitrogen) The Periodic Table of Elements Next Element (Fluorine) Fluorine The Element Oxygen [Click for Isotope Data] 8 O Oxygen 15.9994 Atomic Number: 8 Atomic Weight: 15.9994 Melting Point: 54.36 K (-218.79°C or -361.82°F) Boiling Point: 90.20 K (-182.95°C or -297.31°F) Density: 0.001429 grams per cubic centimeter Phase at Room Temperature: Gas Element Classification: Non-metal Period Number: 2 Group Number: 16 Group Name: Chalcogen What's in a name? From the greek words oxys and genes, which together mean "acid forming." Say what? Oxygen is pronounced as OK-si-jen. History and Uses: Oxygen had been produced by several chemists prior to its discovery in 1774, but they failed to recognize it as a distinct element. Joseph

90

It's Elemental - The Element Manganese  

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Chromium Chromium Previous Element (Chromium) The Periodic Table of Elements Next Element (Iron) Iron The Element Manganese [Click for Isotope Data] 25 Mn Manganese 54.938045 Atomic Number: 25 Atomic Weight: 54.938045 Melting Point: 1519 K (1246°C or 2275°F) Boiling Point: 2334 K (2061°C or 3742°F) Density: 7.3 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 7 Group Name: none What's in a name? From the Latin word for magnet, magnes. Say what? Manganese is pronounced as MAN-ge-nees. History and Uses: Proposed to be an element by Carl Wilhelm Scheele in 1774, manganese was discovered by Johan Gottlieb Gahn, a Swedish chemist, by heating the mineral pyrolusite (MnO2) in the presence of charcoal later that year.

91

It's Elemental - The Element Titanium  

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Scandium Scandium Previous Element (Scandium) The Periodic Table of Elements Next Element (Vanadium) Vanadium The Element Titanium [Click for Isotope Data] 22 Ti Titanium 47.867 Atomic Number: 22 Atomic Weight: 47.867 Melting Point: 1941 K (1668°C or 3034°F) Boiling Point: 3560 K (3287°C or 5949°F) Density: 4.5 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 4 Group Name: none What's in a name? From the Greek word Titans, the mythological "first sons of the Earth." Say what? Titanium is pronounced as tie-TAY-nee-em. History and Uses: Titanium was discovered in 1791 by the Reverend William Gregor, an English pastor. Pure titanium was first produced by Matthew A. Hunter, an American metallurgist, in 1910. Titanium is the ninth most abundant element in the

92

It's Elemental - The Element Nitrogen  

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Carbon Carbon Previous Element (Carbon) The Periodic Table of Elements Next Element (Oxygen) Oxygen The Element Nitrogen [Click for Isotope Data] 7 N Nitrogen 14.0067 Atomic Number: 7 Atomic Weight: 14.0067 Melting Point: 63.15 K (-210.00°C or -346.00°F) Boiling Point: 77.36 K (-195.79°C or -320.44°F) Density: 0.0012506 grams per cubic centimeter Phase at Room Temperature: Gas Element Classification: Non-metal Period Number: 2 Group Number: 15 Group Name: Pnictogen What's in a name? From the Greek words nitron and genes, which together mean "saltpetre forming." Say what? Nitrogen is pronounced as NYE-treh-gen. History and Uses: Nitrogen was discovered by the Scottish physician Daniel Rutherford in 1772. It is the fifth most abundant element in the universe and makes up

93

It's Elemental - The Element Phosphorus  

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Silicon Silicon Previous Element (Silicon) The Periodic Table of Elements Next Element (Sulfur) Sulfur The Element Phosphorus [Click for Isotope Data] 15 P Phosphorus 30.973762 Atomic Number: 15 Atomic Weight: 30.973762 Melting Point: 317.30 K (44.15°C or 111.47°F) Boiling Point: 553.65 K (280.5°C or 536.9°F) Density: 1.82 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Non-metal Period Number: 3 Group Number: 15 Group Name: Pnictogen What's in a name? From the Greek word for light bearing, phosphoros. Say what? Phosphorus is pronounced as FOS-fer-es. History and Uses: In what is perhaps the most disgusting method of discovering an element, phosphorus was first isolated in 1669 by Hennig Brand, a German physician and alchemist, by boiling, filtering and otherwise processing as many as 60

94

It's Elemental - The Element Cerium  

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Lanthanum Lanthanum Previous Element (Lanthanum) The Periodic Table of Elements Next Element (Praseodymium) Praseodymium The Element Cerium [Click for Isotope Data] 58 Ce Cerium 140.116 Atomic Number: 58 Atomic Weight: 140.116 Melting Point: 1071 K (798°C or 1468°F) Boiling Point: 3697 K (3424°C or 6195°F) Density: 6.770 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: none Group Name: Lanthanide What's in a name? Named for the asteroid Ceres. Say what? Cerium is pronounced as SER-ee-em. History and Uses: Cerium was discovered by Jöns Jacob Berzelius and Wilhelm von Hisinger, Swedish chemists, and independently by Martin Heinrich Klaproth, a German chemist, in 1803. Cerium is the most abundant of the rare earth elements

95

It's Elemental - The Element Indium  

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Cadmium Cadmium Previous Element (Cadmium) The Periodic Table of Elements Next Element (Tin) Tin The Element Indium [Click for Isotope Data] 49 In Indium 114.818 Atomic Number: 49 Atomic Weight: 114.818 Melting Point: 429.75 K (156.60°C or 313.88°F) Boiling Point: 2345 K (2072°C or 3762°F) Density: 7.31 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 5 Group Number: 13 Group Name: none What's in a name? Named after the bright indigo line in its spectrum. Say what? Indium is pronounced as IN-dee-em. History and Uses: Indium was discovered by the German chemists Ferdinand Reich and Hieronymus Theodor Richter in 1863. Reich and Richter had been looking for traces of the element thallium in samples of zinc ores. A brilliant indigo line in

96

It's Elemental - The Element Neon  

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Fluorine Fluorine Previous Element (Fluorine) The Periodic Table of Elements Next Element (Sodium) Sodium The Element Neon [Click for Isotope Data] 10 Ne Neon 20.1797 Atomic Number: 10 Atomic Weight: 20.1797 Melting Point: 24.56 K (-248.59°C or -415.46°F) Boiling Point: 27.07 K (-246.08°C or -410.94°F) Density: 0.0008999 grams per cubic centimeter Phase at Room Temperature: Gas Element Classification: Non-metal Period Number: 2 Group Number: 18 Group Name: Noble Gas What's in a name? From the Greek word for new, neos. Say what? Neon is pronounced as NEE-on. History and Uses: Neon was discovered by Sir William Ramsay, a Scottish chemist, and Morris M. Travers, an English chemist, shortly after their discovery of the element krypton in 1898. Like krypton, neon was discovered through the

97

Thermodynamic estimation of minor element distribution between immiscible liquids in Fe-Cu-based metal phase generated in melting treatment of municipal solid wastes  

SciTech Connect

Graphical abstract: Display Omitted Highlights: Black-Right-Pointing-Pointer Two liquids separation of metal occurs in the melting of municipal solid waste. Black-Right-Pointing-Pointer The distribution of PGMs etc. between two liquid metal phases is studied. Black-Right-Pointing-Pointer Quite simple thermodynamic model is applied to predict the distribution ratio. Black-Right-Pointing-Pointer Au and Ag originated from WEEE are found to be concentrated into Cu-rich phase. - Abstract: Waste electrical and electronic equipment (WEEE) has become an important target in managing material cycles from the viewpoint of not only waste management and control of environmental pollution but also resource conservation. This study investigated the distribution tendency of trace elements in municipal solid waste (MSW) or incinerator ash, including valuable non-ferrous metals (Ni, Co, Cr, Mn, Mo, Ti, V, W, Zr), precious group metals (PGMs) originated from WEEE (Ag, Au, Pd, Pt), and others (Al, B, Pb, Si), between Fe-rich and Cu-rich metal phases by means of simple thermodynamic calculations. Most of the typical alloying elements for steel (Co, Cr, Mo, Nb, Ni, Si, Ti, V, and W) and Rh were preferentially distributed into the Fe-rich phase. PGMs, such as Au, Ag, and Pd, were enriched in the Cu-rich phase, whereas Pt was almost equally distributed into both phases. Since the primary metallurgical processing of Cu is followed by an electrolysis for refining, and since PGMs in crude copper have been industrially recovered from the resulting anode slime, our results indicated that Ag, Au, and Pd could be effectively recovered from MSW if the Cu-rich phase could be selectively collected.

Lu, X. [School of Metallurgical and Ecological Engineering, The University of Science and Technology Beijing, 30 Xueyuan Road, Haidian District, Beijing 100083 (China); Nakajima, K.; Sakanakura, H. [Research Center for Material Cycles and Waste Management, National Institute for Environmental Studies (NIES), 16-2 Onogawa, Tsukuba 305-8506 (Japan); Matsubae, K. [Graduate School of Engineering, Tohoku University, 6-6-11 Aza-Aoba, Aramaki, Sendai 980-8579 (Japan); Bai, H. [School of Metallurgical and Ecological Engineering, The University of Science and Technology Beijing, 30 Xueyuan Road, Haidian District, Beijing 100083 (China); Nagasaka, T., E-mail: t-nagasaka@m.tohoku.ac.jp [Graduate School of Engineering, Tohoku University, 6-6-11 Aza-Aoba, Aramaki, Sendai 980-8579 (Japan)

2012-06-15T23:59:59.000Z

98

An Evaluation of the Concept of Transuranic Burning Using Liquid Metal Reactors  

Science Conference Proceedings (OSTI)

This evaluation investigates the potential benefits of separating the transuranic elements from spent reactor fuel before it is disposed of in geologic repositories. It addresses the question: Would the benefits to radioactive waste disposal justify both processing the spent fuel and deploying liquid metal reactors (LMRs) to transmute the separated transuranics?

1991-03-25T23:59:59.000Z

99

RADIOACTIVE BATTERY  

DOE Patents (OSTI)

A radioactive battery which includes a capsule containing the active material and a thermopile associated therewith is presented. The capsule is both a shield to stop the radiations and thereby make the battery safe to use, and an energy conventer. The intense radioactive decay taking place inside is converted to useful heat at the capsule surface. The heat is conducted to the hot thermojunctions of a thermopile. The cold junctions of the thermopile are thermally insulated from the heat source, so that a temperature difference occurs between the hot and cold junctions, causing an electrical current of a constant magnitude to flow.

Birden, J.H.; Jordan, K.C.

1959-11-17T23:59:59.000Z

100

It's Elemental - The Element Platinum  

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Iridium Iridium Previous Element (Iridium) The Periodic Table of Elements Next Element (Gold) Gold The Element Platinum [Click for Isotope Data] 78 Pt Platinum 195.084 Atomic Number: 78 Atomic Weight: 195.084 Melting Point: 2041.55 K (1768.4°C or 3215.1°F) Boiling Point: 4098 K (3825°C or 6917°F) Density: 21.46 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 10 Group Name: none What's in a name? From the Spainsh word for silver, platina. Say what? Platinum is pronounced as PLAT-en-em. History and Uses: Used by the pre-Columbian Indians of South America, platinum wasn't noticed by western scientists until 1735. Platinum can occur free in nature and is sometimes found in deposits of gold-bearing sands, primarily those found in

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101

It's Elemental - The Element Arsenic  

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Germanium Germanium Previous Element (Germanium) The Periodic Table of Elements Next Element (Selenium) Selenium The Element Arsenic [Click for Isotope Data] 33 As Arsenic 74.92160 Atomic Number: 33 Atomic Weight: 74.92160 Melting Point: 1090 K (817°C or 1503°F) Boiling Point: 887 K (614°C or 1137°F) Density: 5.776 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Semi-metal Period Number: 4 Group Number: 15 Group Name: Pnictogen What's in a name? From the Latin word arsenicum, the Greek word arsenikon and the Arabic word Az-zernikh. Say what? Arsenic is pronounced as AR-s'n-ik. History and Uses: Although arsenic compounds were mined by the early Chinese, Greek and Egyptian civilizations, it is believed that arsenic itself was first identified by Albertus Magnus, a German alchemist, in 1250. Arsenic occurs

102

It's Elemental - The Element Rhenium  

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Tungsten Tungsten Previous Element (Tungsten) The Periodic Table of Elements Next Element (Osmium) Osmium The Element Rhenium [Click for Isotope Data] 75 Re Rhenium 186.207 Atomic Number: 75 Atomic Weight: 186.207 Melting Point: 3459 K (3186°C or 5767°F) Boiling Point: 5869 K (5596°C or 10105°F) Density: 20.8 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 7 Group Name: none What's in a name? From the Latin word for the Rhine River, Rhenus. Say what? Rhenium is pronounced as REE-nee-em. History and Uses: Rhenium was discovered by the German chemists Ida Tacke-Noddack, Walter Noddack and Otto Carl Berg in 1925. They detected rhenium spectroscopically in platinum ores and in the minerals columbite ((Fe, Mn, Mg)(Nb, Ta)2O6),

103

It's Elemental - The Element Osmium  

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Rhenium Rhenium Previous Element (Rhenium) The Periodic Table of Elements Next Element (Iridium) Iridium The Element Osmium [Click for Isotope Data] 76 Os Osmium 190.23 Atomic Number: 76 Atomic Weight: 190.23 Melting Point: 3306 K (3033°C or 5491°F) Boiling Point: 5285 K (5012°C or 9054°F) Density: 22.57 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 8 Group Name: none What's in a name? From the Greek word for a smell, osme. Say what? Osmium is pronounced as OZ-mee-em. History and Uses: Osmium and iridium were discovered at the same time by the British chemist Smithson Tennant in 1803. Osmium and iridium were identified in the black residue remaining after dissolving platinum ore with aqua regia, a mixture

104

It's Elemental - The Element Antimony  

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Tin Tin Previous Element (Tin) The Periodic Table of Elements Next Element (Tellurium) Tellurium The Element Antimony [Click for Isotope Data] 51 Sb Antimony 121.760 Atomic Number: 51 Atomic Weight: 121.760 Melting Point: 903.78 K (630.63°C or 1167.13°F) Boiling Point: 1860 K (1587°C or 2889°F) Density: 6.685 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Semi-metal Period Number: 5 Group Number: 15 Group Name: Pnictogen What's in a name? From the Greek words anti and monos, which together mean "not alone." Antimony's chemical symbol comes from its historic name, Stibium. Say what? Antimony is pronounced as AN-the-MOH-nee. History and Uses: Antimony has been known since ancient times. It is sometimes found free in nature, but is usually obtained from the ores stibnite (Sb2S3) and

105

It's Elemental - The Element Copper  

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Nickel Nickel Previous Element (Nickel) The Periodic Table of Elements Next Element (Zinc) Zinc The Element Copper [Click for Isotope Data] 29 Cu Copper 63.546 Atomic Number: 29 Atomic Weight: 63.546 Melting Point: 1357.77 K (1084.62°C or 1984.32°F) Boiling Point: 2835 K (2562°C or 4644°F) Density: 8.933 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 11 Group Name: none What's in a name? From the Latin word cuprum, which means "from the island of Cyprus." Say what? Copper is pronounced as KOP-er. History and Uses: Archaeological evidence suggests that people have been using copper for at least 11,000 years. Relatively easy to mine and refine, people discovered methods for extracting copper from its ores at least 7,000 years ago. The

106

It's Elemental - The Element Gadolinium  

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Europium Europium Previous Element (Europium) The Periodic Table of Elements Next Element (Terbium) Terbium The Element Gadolinium [Click for Isotope Data] 64 Gd Gadolinium 157.25 Atomic Number: 64 Atomic Weight: 157.25 Melting Point: 1586 K (1313°C or 2395°F) Boiling Point: 3546 K (3273°C or 5923°F) Density: 7.90 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: none Group Name: Lanthanide What's in a name? Named for the mineral gadolinite which was named after Johan Gadolin, a Finnish chemist. Say what? Gadolinium is pronounced as GAD-oh-LIN-ee-em. History and Uses: Spectroscopic evidence for the existence of gadolinium was first observed by the Swiss chemist Jean Charles Galissard de Marignac in the minerals

107

It's Elemental - The Element Mercury  

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Gold Gold Previous Element (Gold) The Periodic Table of Elements Next Element (Thallium) Thallium The Element Mercury [Click for Isotope Data] 80 Hg Mercury 200.59 Atomic Number: 80 Atomic Weight: 200.59 Melting Point: 234.32 K (-38.83°C or -37.89°F) Boiling Point: 629.88 K (356.73°C or 674.11°F) Density: 13.5336 grams per cubic centimeter Phase at Room Temperature: Liquid Element Classification: Metal Period Number: 6 Group Number: 12 Group Name: none What's in a name? Named after the planet Mercury. Mercury's chemical symbol comes from the Greek word hydrargyrum, which means "liquid silver." Say what? Mercury is pronounced as MER-kyoo-ree. History and Uses: Mercury was known to the ancient Chinese and Hindus and has been found in 3500 year old Egyptian tombs. Mercury is not usually found free in nature

108

It's Elemental - The Element Hafnium  

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Lutetium Lutetium Previous Element (Lutetium) The Periodic Table of Elements Next Element (Tantalum) Tantalum The Element Hafnium [Click for Isotope Data] 72 Hf Hafnium 178.49 Atomic Number: 72 Atomic Weight: 178.49 Melting Point: 2506 K (2233°C or 4051°F) Boiling Point: 4876 K (4603°C or 8317°F) Density: 13.3 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 4 Group Name: none What's in a name? From the Latin word for the city of Copenhagen, Hafnia. Say what? Hafnium is pronounced as HAF-neeem. History and Uses: Hafnium was discovered by Dirk Coster, a Danish chemist, and Charles de Hevesy, a Hungarian chemist, in 1923. They used a method known as X-ray spectroscopy to study the arrangement of the outer electrons of atoms in

109

It's Elemental - The Element Boron  

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Beryllium Beryllium Previous Element (Beryllium) The Periodic Table of Elements Next Element (Carbon) Carbon The Element Boron [Click for Isotope Data] 5 B Boron 10.811 Atomic Number: 5 Atomic Weight: 10.811 Melting Point: 2348 K (2075°C or 3767°F) Boiling Point: 4273 K (4000°C or 7232°F) Density: 2.37 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Semi-metal Period Number: 2 Group Number: 13 Group Name: none What's in a name? From the Arabic word Buraq and the Persian word Burah, which are both words for the material "borax." Say what? Boron is pronounced as BO-ron. History and Uses: Boron was discovered by Joseph-Louis Gay-Lussac and Louis-Jaques Thénard, French chemists, and independently by Sir Humphry Davy, an English chemist,

110

It's Elemental - The Element Chromium  

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Vanadium Vanadium Previous Element (Vanadium) The Periodic Table of Elements Next Element (Manganese) Manganese The Element Chromium [Click for Isotope Data] 24 Cr Chromium 51.9961 Atomic Number: 24 Atomic Weight: 51.9961 Melting Point: 2180 K (1907°C or 3465°F) Boiling Point: 2944 K (2671°C or 4840°F) Density: 7.15 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 6 Group Name: none What's in a name? From the Greek word for color, chroma. Say what? Chromium is pronounced as KROH-mee-em. History and Uses: Chromium was discovered by Louis-Nicholas Vauquelin while experimenting with a material known as Siberian red lead, also known as the mineral crocoite (PbCrO4), in 1797. He produced chromium oxide (CrO3) by mixing

111

It's Elemental - The Element Molybdenum  

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Niobium Niobium Previous Element (Niobium) The Periodic Table of Elements Next Element (Technetium) Technetium The Element Molybdenum [Click for Isotope Data] 42 Mo Molybdenum 95.96 Atomic Number: 42 Atomic Weight: 95.96 Melting Point: 2896 K (2623°C or 4753°F) Boiling Point: 4912 K (4639°C or 8382°F) Density: 10.2 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 5 Group Number: 6 Group Name: none What's in a name? From the Greek word for lead, molybdos. Say what? Molybdenum is pronounced as meh-LIB-deh-nem. History and Uses: Molybdenum was discovered by Carl Welhelm Scheele, a Swedish chemist, in 1778 in a mineral known as molybdenite (MoS2) which had been confused as a lead compound. Molybdenum was isolated by Peter Jacob Hjelm in 1781. Today,

112

It's Elemental - The Element Iridium  

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Osmium Osmium Previous Element (Osmium) The Periodic Table of Elements Next Element (Platinum) Platinum The Element Iridium [Click for Isotope Data] 77 Ir Iridium 192.217 Atomic Number: 77 Atomic Weight: 192.217 Melting Point: 2719 K (2446°C or 4435°F) Boiling Point: 4701 K (4428°C or 8002°F) Density: 22.42 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 9 Group Name: none What's in a name? From the Latin word for rainbow, iris. Say what? Iridium is pronounced as i-RID-ee-em. History and Uses: Iridium and osmium were discovered at the same time by the British chemist Smithson Tennant in 1803. Iridium and osmium were identified in the black residue remaining after dissolving platinum ore with aqua regia, a mixture

113

Bulk Metallic Glasses IX  

Science Conference Proceedings (OSTI)

... of elements to form metallic-glass alloys] have resulted in the required cooling rate ... Bauschinger Effect in Metallic Glass Nanowires under Cyclic Loading.

114

NATURE OF RADIOACTIVE WASTES  

SciTech Connect

The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of U and Th fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic neutron capture. In addition, the origin of concentrated fission product wastes is examined, as well as characteristics of present wastes and the level of fission products in wastes. Also, comments are included on high-level wastes from processes other than solvent extraction, active gaseous wastes, and low- to intermediate-level liquid wastes. (J.R.D.)

Culler, F.L. Jr.

1959-01-26T23:59:59.000Z

115

Radioactive waste material melter apparatus  

DOE Patents (OSTI)

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

Newman, D.F.; Ross, W.A.

1990-04-24T23:59:59.000Z

116

Radioactive waste material melter apparatus  

DOE Patents (OSTI)

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

1990-01-01T23:59:59.000Z

117

It's Elemental - The Element Zinc  

NLE Websites -- All DOE Office Websites (Extended Search)

Copper Copper Previous Element (Copper) The Periodic Table of Elements Next Element (Gallium) Gallium The Element Zinc [Click for Isotope Data] 30 Zn Zinc 65.38 Atomic Number: 30 Atomic Weight: 65.38 Melting Point: 692.68 K (419.53°C or 787.15°F) Boiling Point: 1180 K (907°C or 1665°F) Density: 7.134 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 4 Group Number: 12 Group Name: none What's in a name? From the German word zink. Say what? Zinc is pronounced as ZINK. History and Uses: Although zinc compounds have been used for at least 2,500 years in the production of brass, zinc wasn't recognized as a distinct element until much later. Metallic zinc was first produced in India sometime in the 1400s by heating the mineral calamine (ZnCO3) with wool. Zinc was rediscovered by

118

Radioactivity and Radiation  

NLE Websites -- All DOE Office Websites (Extended Search)

Radioactivity and Radiation Radioactivity and Radiation Uranium and Its Compounds line line What is Uranium? Chemical Forms of Uranium Properties of Uranium Compounds Radioactivity and Radiation Uranium Health Effects Radioactivity and Radiation Discussion of radioactivity and radiation, uranium and radioactivity, radiological health risks of uranium isotopes and decay products. Radioactivity Radioactivity is the term used to describe the natural process by which some atoms spontaneously disintegrate, emitting both particles and energy as they transform into different, more stable atoms. This process, also called radioactive decay, occurs because unstable isotopes tend to transform into a more stable state. Radioactivity is measured in terms of disintegrations, or decays, per unit time. Common units of radioactivity

119

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1998-05-12T23:59:59.000Z

120

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1998-05-12T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Trace Impurities and Activation Products in Base Metals  

Science Conference Proceedings (OSTI)

This report documents the results of research related to the concentrations of trace impurities and activation products in stainless steel alloys used for reactor vessels and internals. While present in extremely low concentrations, these trace elements and radionuclides can impact radioactive waste disposal of the components upon decommissioning.BackgroundThe primary basis of activity in a decommissioning source term is activated metals from the reactor and ...

2012-10-30T23:59:59.000Z

122

REACTOR FUEL ELEMENTS TESTING CONTAINER  

DOE Patents (OSTI)

This patent shows a method for detecting leaks in jacketed fuel elements. The element is placed in a sealed tank within a nuclear reactor, and, while the reactor operates, the element is sparged with gas. The gas is then led outside the reactor and monitored for radioactive Xe or Kr. (AEC)

Whitham, G.K.; Smith, R.R.

1963-01-15T23:59:59.000Z

123

DOE - Office of Legacy Management -- Nuclear Metals Inc - MA 09  

Office of Legacy Management (LM)

Metals Inc - MA 09 Metals Inc - MA 09 FUSRAP Considered Sites Site: NUCLEAR METALS, INC. (MA.09) Eliminated from consideration under FUSRAP - Licensed facility - included in NRC action plan (Site Decommissioning Management Plan) in 1990 for cleanup Designated Name: Not Designated Alternate Name: None Location: 1555 Massachusetts Ave. , Cambridge , Massachusetts MA.09-2 Evaluation Year: 1987 MA.09-1 Site Operations: Produced natural uranium tubes for Savannah River reactor program and fabricated power reactor fuel elements under AEC/NRC license. MA.09-4 MA.09-3 Site Disposition: Eliminated - No Authority under FUSRAP - AEC licensed operation MA.09-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium, Thorium MA.09-1 Radiological Survey(s): None Indicated

124

ELECTRONIC ANALOG COMPUTER FOR DETERMINING RADIOACTIVE DISINTEGRATION  

DOE Patents (OSTI)

A computer is presented for determining growth and decay curves for elements in a radioactive disintegration series wherein one unstable element decays to form a second unstable element or isotope, which in turn forms a third element, etc. The growth and decay curves of radioactive elements are simulated by the charge and discharge curves of a resistance-capacitance network. Several such networks having readily adjustable values are connected in series with an amplifier between each successive pair. The time constant of each of the various networks is set proportional to the half-life of a corresponding element in the series represented and the charge and discharge curves of each of the networks simulates the element growth and decay curve.

Robinson, H.P.

1959-07-14T23:59:59.000Z

125

It's Elemental - The Element Fluorine  

NLE Websites -- All DOE Office Websites (Extended Search)

Oxygen Oxygen Previous Element (Oxygen) The Periodic Table of Elements Next Element (Neon) Neon The Element Fluorine [Click for Isotope Data] 9 F Fluorine 18.9984032 Atomic Number: 9 Atomic Weight: 18.9984032 Melting Point: 53.53 K (-219.62°C or -363.32°F) Boiling Point: 85.03 K (-188.12°C or -306.62°F) Density: 0.001696 grams per cubic centimeter Phase at Room Temperature: Gas Element Classification: Non-metal Period Number: 2 Group Number: 17 Group Name: Halogen What's in a name? From the Latin and French words for flow, fluere. Say what? Fluorine is pronounced as FLU-eh-reen or as FLU-eh-rin. History and Uses: Fluorine is the most reactive of all elements and no chemical substance is capable of freeing fluorine from any of its compounds. For this reason, fluorine does not occur free in nature and was extremely difficult for

126

It's Elemental - The Element Chlorine  

NLE Websites -- All DOE Office Websites (Extended Search)

Sulfur Sulfur Previous Element (Sulfur) The Periodic Table of Elements Next Element (Argon) Argon The Element Chlorine [Click for Isotope Data] 17 Cl Chlorine 35.453 Atomic Number: 17 Atomic Weight: 35.453 Melting Point: 171.65 K (-101.5°C or -150.7°F) Boiling Point: 239.11 K (-34.04°C or -29.27°F) Density: 0.003214 grams per cubic centimeter Phase at Room Temperature: Gas Element Classification: Non-metal Period Number: 3 Group Number: 17 Group Name: Halogen What's in a name? From the Greek word for greenish yellow, chloros. Say what? Chlorine is pronounced as KLOR-een or as KLOR-in. History and Uses: Since it combines directly with nearly every element, chlorine is never found free in nature. Chlorine was first produced by Carl Wilhelm Scheele, a Swedish chemist, when he combined the mineral pyrolusite (MnO2) with

127

Radioactive waste systems and radioactive effluents  

SciTech Connect

Radioactive waste systems for handling gaseous, liquid, and solid wastes generated at light and pressurized water reactors are described. (TFD)

Row, T.H.

1973-01-01T23:59:59.000Z

128

Process for decontaminating radioactive liquids using a calcium cyanamide-containing composition. [Patent application  

DOE Patents (OSTI)

The present invention provides a process for decontaminating a radioactive liquid containing a radioactive element capable of forming a hydroxide. This process includes the steps of contacting the radioactive liquid with a decontaminating composition and separating the resulting radioactive sludge from the resulting liquid. The decontaminating composition contains calcium cyanamide.

Silver, G.L.

1980-09-24T23:59:59.000Z

129

It's Elemental - The Element Iodine  

NLE Websites -- All DOE Office Websites (Extended Search)

Tellurium Tellurium Previous Element (Tellurium) The Periodic Table of Elements Next Element (Xenon) Xenon The Element Iodine [Click for Isotope Data] 53 I Iodine 126.90447 Atomic Number: 53 Atomic Weight: 126.90447 Melting Point: 386.85 K (113.7°C or 236.7°F) Boiling Point: 457.55 K (184.4°C or 364.0°F) Density: 4.93 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Non-metal Period Number: 5 Group Number: 17 Group Name: Halogen What's in a name? From the Greek word for violet, iodes. Say what? Iodine is pronounced as EYE-eh-dine or as EYE-eh-din. History and Uses: Iodine was discovered by the French chemist Barnard Courtois in 1811. Courtois was extracting sodium and potassium compounds from seaweed ash. Once these compounds were removed, he added sulfuric acid (H2SO4) to

130

It's Elemental - The Element Lead  

NLE Websites -- All DOE Office Websites (Extended Search)

Thallium Thallium Previous Element (Thallium) The Periodic Table of Elements Next Element (Bismuth) Bismuth The Element Lead [Click for Isotope Data] 82 Pb Lead 207.2 Atomic Number: 82 Atomic Weight: 207.2 Melting Point: 600.61 K (327.46°C or 621.43°F) Boiling Point: 2022 K (1749°C or 3180°F) Density: 11.342 grams per cubic centimeter Phase at Room Temperature: Solid Element Classification: Metal Period Number: 6 Group Number: 14 Group Name: none What's in a name? From the Anglo-Saxon word lead. Lead's chemical symbol comes from the Latin word for waterworks, plumbum. Say what? Lead is pronounced as LED. History and Uses: Lead has been known since ancient times. It is sometimes found free in nature, but is usually obtained from the ores galena (PbS), anglesite (PbSO4), cerussite (PbCO3) and minum (Pb3O4). Although lead makes up only

131

Melt processing of radioactive waste: A technical overview  

Science Conference Proceedings (OSTI)

Nuclear operations have resulted in the accumulation of large quantities of contaminated metallic waste which are stored at various DOE, DOD, and commercial sites under the control of DOE and the Nuclear Regulatory Commission (NRC). This waste will accumulate at an increasing rate as commercial nuclear reactors built in the 1950s reach the end of their projected lives, as existing nuclear powered ships become obsolete or unneeded, and as various weapons plants and fuel processing facilities, such as the gaseous diffusion plants, are dismantled, repaired, or modernized. For example, recent estimates of available Radioactive Scrap Metal (RSM) in the DOE Nuclear Weapons Complex have suggested that as much as 700,000 tons of contaminated 304L stainless steel exist in the gaseous diffusion plants alone. Other high-value metals available in the DOE complex include copper, nickel, and zirconium. Melt processing for the decontamination of radioactive scrap metal has been the subject of much research. A major driving force for this research has been the possibility of reapplication of RSM, which is often very high-grade material containing large quantities of strategic elements. To date, several different single and multi-step melting processes have been proposed and evaluated for use as decontamination or recycling strategies. Each process offers a unique combination of strengths and weaknesses, and ultimately, no single melt processing scheme is optimum for all applications since processes must be evaluated based on the characteristics of the input feed stream and the desired output. This paper describes various melt decontamination processes and briefly reviews their application in developmental studies, full scale technical demonstrations, and industrial operations.

Schlienger, M.E.; Buckentin, J.M.; Damkroger, B.K.

1997-04-01T23:59:59.000Z

132

Neutronic fuel element fabrication  

SciTech Connect

This disclosure describes a method for metallurgically bonding a complete leak-tight enclosure to a matrix-type fuel element penetrated longitudinally by a multiplicity of coolant channels. Coolant tubes containing solid filler pins are disposed in the coolant channels. A leak-tight metal enclosure is then formed about the entire assembly of fuel matrix, coolant tubes and pins. The completely enclosed and sealed assembly is exposed to a high temperature and pressure gas environment to effect a metallurgical bond between all contacting surfaces therein. The ends of the assembly are then machined away to expose the pin ends which are chemically leached from the coolant tubes to leave the coolant tubes with internal coolant passageways. The invention described herein was made in the course of, or under, a contract with the U.S. Atomic Energy Commission. It relates generally to fuel elements for neutronic reactors and more particularly to a method for providing a leak-tight metal enclosure for a high-performance matrix-type fuel element penetrated longitudinally by a multiplicity of coolant tubes. The planned utilization of nuclear energy in high-performance, compact-propulsion and mobile power-generation systems has necessitated the development of fuel elements capable of operating at high power densities. High power densities in turn require fuel elements having high thermal conductivities and good fuel retention capabilities at high temperatures. A metal clad fuel element containing a ceramic phase of fuel intimately mixed with and bonded to a continuous refractory metal matrix has been found to satisfy the above requirements. Metal coolant tubes penetrate the matrix to afford internal cooling to the fuel element while providing positive fuel retention and containment of fission products generated within the fuel matrix. Metal header plates are bonded to the coolant tubes at each end of the fuel element and a metal cladding or can completes the fuel-matrix enclosure by encompassing the sides of the fuel element between the header plates.

Korton, George (Cincinnati, OH)

2004-02-24T23:59:59.000Z

133

Twelve Year Study of Underground Corrosion of Activated Metals  

Science Conference Proceedings (OSTI)

The subsurface radioactive disposal facility located at the U.S. Department of Energys Idaho site contains neutron-activated metals from non-fuel nuclear-reactor-core components. A long-term corrosion study is being conducted to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements in an arid vadose zone environment. The study uses non-radioactive metal coupons representing the prominent neutron-activated material buried at the disposal location, namely, two types of stainless steels, welded stainless steel, welded nickel-chromium steel alloy, zirconium alloy, beryllium, and aluminum. Additionally, carbon steel (the material used in cask disposal liners and other disposal containers) and duplex stainless steel (high-integrity containers) are also included in the study. This paper briefly describes the test program and presents the corrosion rate results through twelve years of underground exposure.

M. Kay Adler Flitton; Timothy S. Yoder

2012-03-01T23:59:59.000Z

134

Defining a metal-based waste form for IFR pyroprocessing wastes  

SciTech Connect

Pyrochemical electrorefining to recover actinides from metal nuclear fuel is a key element of the Integral Fast Reactor (IFR) fuel cycle. The process separates the radioactive fission products from the long-lived actinides in a molten LiCl-KCl salt, and it generates a lower waste volume with significantly less long-term toxicity as compared to spent nuclear fuel. The process waste forms include a mineral-based waste form that will contain fission products removed from an electrolyte salt and a metal-based waste form that will contain metallic fission products and the fuel cladding and process materials. Two concepts for the metal-based waste form are being investigated: (1) encapsulating the metal constituents in a Cu-Al alloy and (2) alloying the metal constituents into a uniform stainless steel-based waste form. Results are given from our recent studies of these two concepts.

McDeavitt, S.M.; Park, J.Y.; Ackerman, J.P.

1994-01-01T23:59:59.000Z

135

Midwestern Radioactive Materials Transportation Committee Agenda...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation...

136

It's Elemental - The Element Fermium  

NLE Websites -- All DOE Office Websites (Extended Search)

Einsteinium Previous Element (Einsteinium) The Periodic Table of Elements Next Element (Mendelevium) Mendelevium The Element Fermium Click for Isotope Data 100 Fm Fermium 257...

137

It's Elemental - The Element Neptunium  

NLE Websites -- All DOE Office Websites (Extended Search)

Uranium Previous Element (Uranium) The Periodic Table of Elements Next Element (Plutonium) Plutonium The Element Neptunium Click for Isotope Data 93 Np Neptunium 237 Atomic...

138

It's Elemental - The Element Ruthenium  

NLE Websites -- All DOE Office Websites (Extended Search)

Technetium Previous Element (Technetium) The Periodic Table of Elements Next Element (Rhodium) Rhodium The Element Ruthenium Click for Isotope Data 44 Ru Ruthenium 101.07 Atomic...

139

It's Elemental - The Element Actinium  

NLE Websites -- All DOE Office Websites (Extended Search)

Radium Previous Element (Radium) The Periodic Table of Elements Next Element (Thorium) Thorium The Element Actinium Click for Isotope Data 89 Ac Actinium 227 Atomic Number: 89...

140

Method for immobilizing radioactive iodine  

DOE Patents (OSTI)

Radioactive iodine, present as alkali metal iodides or iodates in an aqueous solution, is incorporated into an inert solid material for long-term storage by adding to the solution a stoichiometric amount with respect to the formation of a sodalite (3M.sub.2 O.3Al.sub.2 O.sub.3. 6SiO.sub.2.2MX, where M=alkali metal; X=I.sup.- or IO.sub.3.sup.-) of an alkali metal, alumina and silica, stirring the solution to form a homogeneous mixture, drying the mixture to form a powder, compacting and sintering the compacted powder at 1073 to 1373 K (800.degree. to 1100.degree. C.) for a time sufficient to form sodalite.

Babad, Harry (Richland, WA); Strachan, Denis M. (Richland, WA)

1980-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

RADIO-ACTIVE TRANSDUCER  

DOE Patents (OSTI)

ABS>ure the change in velocity of a moving object. The transducer includes a radioactive source having a collimated beam of radioactive particles, a shield which can block the passage of the radioactive beam, and a scintillation detector to measure the number of radioactive particles in the beam which are not blocked by the shield. The shield is operatively placed across the radioactive beam so that any motion normal to the beam will cause the shield to move in the opposite direction thereby allowing more radioactive particles to reach the detector. The number of particles detected indicates the acceleration. (AEC)

Wanetick, S.

1962-03-01T23:59:59.000Z

142

Radioactive Waste Management (Minnesota)  

Energy.gov (U.S. Department of Energy (DOE))

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

143

Radioactivity in consumer products  

SciTech Connect

Papers presented at the conference dealt with regulations and standards; general and biological risks; radioluminous materials; mining, agricultural, and construction materials containing radioactivity; and various products containing radioactive sources.

Moghissi, A.A.; Paras, P.; Carter, M.W.; Barker, R.F. (eds.)

1978-08-01T23:59:59.000Z

144

HISTORY OF THE ORIGIN OF THE CHEMICAL ELEMENTS AND THEIR DISCOVERIES.  

SciTech Connect

The origin of the chemical elements show a wide diversity with some of these elements having their origin in antiquity. Still other elements have been synthesized within the past fifty years via nuclear reactions on heavy elements, because these other elements are unstable and radioactive and do not exist in nature. The names of the elements come from many sources including mythological concepts or characters; places, areas or countries; properties of the element or its compounds, such as color, smell or its inability to combine; and the names of scientists. There are also some miscellaneous names as well as some obscure names for particular elements. The claim of discovery of an element has varied over the centuries. Many claims, e.g., the discovery of certain rare earth elements of the lanthanide series, involved the discovery of a mineral ore from which an element was later extracted. The honor of discovery has often been accorded not to the person who first isolated the element but to the person who discovered the original mineral itself, even when the ore was impure and contained many elements. The reason for this is that in the case of these rare earth elements, the ''earth'' now refers to oxides of a metal not to the metal itself. This fact was not realized at the time of their discovery, until the English chemist Humphry Davy showed that earths were compounds of oxygen and metals in 1808. In the early discoveries, the atomic weight of an element and spectral analysis of the element were not available. Later both of these elemental properties would be required before discovery of the element would be accepted. In general, the requirements for discovery claims have tightened through the years and claims that were previously accepted would no longer meet the minimum constraints now imposed. There are cases where the honor of discovery is not given to the first person to actually discover the element but to the first person to claim the discovery in print. If a publication was delayed, the discoverer has often historically been ''scooped'' by another scientist.

HOLDEN,N.E.

2001-06-29T23:59:59.000Z

145

Integrated decontamination process for metals  

DOE Patents (OSTI)

An integrated process for decontamination of metals, particularly metals that are used in the nuclear energy industry contaminated with radioactive material. The process combines the processes of electrorefining and melt refining to purify metals that can be decontaminated using either electrorefining or melt refining processes.

Snyder, Thomas S. (Oakmont, PA); Whitlow, Graham A. (Murrysville, PA)

1991-01-01T23:59:59.000Z

146

Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination oaf plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1999-03-16T23:59:59.000Z

147

Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1999-03-16T23:59:59.000Z

148

Electrochemical Decontamination of Painted and Heavily Corroded Metals  

SciTech Connect

The radioactive metal wastes that are generated from nuclear fuel plants and radiochemical laboratories are mainly contaminated by the surface deposition of radioactive isotopes. There are presently several techniques used in removing surface contamination involving physical and chemical processes. However, there has been very little research done in the area of soiled, heavily oxidized, and painted metals. Researchers at Los Alamos National Laboratory have been developing electrochemical procedures for the decontamination of bare and painted metal objects. These methods have been found to be effective on highly corroded as well as relatively new metals. This study has been successful in decontaminating projectiles and shrapnel excavated during environmental restoration projects after 40+ years of exposure to the elements. Heavily corroded augers used in sampling activities throughout the area were also successfully decontaminated. This process has demonstrated its effectiveness and offers several advantages over the present metal decontamination practices of media blasting and chemical solvents. These advantages include the addition of no toxic or hazardous chemicals, low operating temperature and pressure, and easily scaleable equipment. It is in their future plans to use this process in the decontamination of gloveboxes destined for disposal as TRU waste.

Marczak, S.; Anderson, J.; Dziewinski, J.

1998-09-08T23:59:59.000Z

149

Processing & Applications IV: Radioactive Metals Processing  

Science Conference Proceedings (OSTI)

The compatibility between erbium oxide and molten cerium, as a surrogate for ... A key process step involving molten salt electrorefining to separate actinides...

150

What are Spent Nuclear Fuel and High-Level Radioactive Waste ?  

Science Conference Proceedings (OSTI)

Spent nuclear fuel and high-level radioactive waste are materials from nuclear power plants and government defense programs. These materials contain highly radioactive elements, such as cesium, strontium, technetium, and neptunium. Some of these elements will remain radioactive for a few years, while others will be radioactive for millions of years. Exposure to such radioactive materials can cause human health problems. Scientists worldwide agree that the safest way to manage these materials is to dispose of them deep underground in what is called a geologic repository.

DOE

2002-12-01T23:59:59.000Z

151

Multilayered nuclear fuel element  

DOE Patents (OSTI)

A nuclear fuel element is described which is suitable for high temperature applications comprised of a kernel of fissile material overlaid with concentric layers of impervious graphite, vitreous carbon, pyrolytic carbon and metal carbide. The kernel of fissile material is surrounded by a layer of impervious graphite. The layer of impervious graphite is then surrounded by a layer of vitreous carbon. Finally, an outer shell which includes alternating layers of pyrolytic carbon and metal carbide surrounds the layer of vitreous carbon.

Schweitzer, Donald G.; Sastre, Cesar

1996-12-01T23:59:59.000Z

152

ORNL radioactive waste operations  

SciTech Connect

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards.

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01T23:59:59.000Z

153

Radioactive Waste Management Basis  

SciTech Connect

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03T23:59:59.000Z

154

WEB RESOURCE: Radioactive Waste  

Science Conference Proceedings (OSTI)

May 8, 2007 ... This resource offers a a very broad explanation of how the Belgian Agency for Management of Radioactive Waste and Enriched Fissile Material...

155

SCAVENGING OF RADIOACTIVE AEROSOLS  

DOE Patents (OSTI)

A process of decontaminatinig an atmosphere from suspended radioactive particles by introducing silicon tetrafluoride whereby the particles precipitate and are removed, is described. (AEC)

Rosinski, J.; Werle, D.K.

1963-12-01T23:59:59.000Z

156

Nuclear fuel element  

DOE Patents (OSTI)

A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has a composite cladding having a substrate and a metal barrier metallurgically bonded on the inside surface of the substrate so that the metal barrier forms a shield between the substrate and the nuclear fuel material held within the cladding. The metal barrier forms about 1 to about 30 percent of the thickness of the cladding and is comprised of a low neutron absorption metal of substantially pure zirconium. The metal barrier serves as a preferential reaction site for gaseous impurities and fission products and protects the substrate from contact and reaction with such impurities and fission products. The substrate of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy. Methods of manufacturing the composite cladding are also disclosed.

Armijo, Joseph S. (Saratoga, CA); Coffin, Jr., Louis F. (Schenectady, NY)

1983-01-01T23:59:59.000Z

157

Oak Ridge National Laboratory shipping containers for radioactive materials  

Science Conference Proceedings (OSTI)

The types of containers used at ORNL for the transport of radioactive materials are described. Both returnable and non-returnable types are included. Containers for solids, liquids and gases are discussed. Casks for the shipment of uranium, irradiated fuel elements, and non-irradiated fuel elements are also described. Specifications are provided. (DC)

Schaich, R.W.

1980-05-01T23:59:59.000Z

158

Radioactive waste disposal package  

DOE Patents (OSTI)

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

159

Photovoltaic radiation detector element  

DOE Patents (OSTI)

A radiation detector element is formed of a body of semiconductor material, a coating on the body which forms a photovoltaic junction therewith, and a current collector consisting of narrow metallic strips, the aforesaid coating having an opening therein the edge of which closely approaches but is spaced from the current collector strips.

Agouridis, Dimitrios C. (Oak Ridge, TN)

1983-01-01T23:59:59.000Z

160

Photovoltaic radiation detector element  

DOE Patents (OSTI)

A radiation detector element is formed of a body of semiconductor material, a coating on the body which forms a photovoltaic junction therewith, and a current collector consisting of narrow metallic strips, the aforesaid coating having an opening therein in the edge of which closely approaches but is spaced from the current collector strips.

Agouridis, D.C.

1980-12-17T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

It's Elemental - The Element Lithium  

NLE Websites -- All DOE Office Websites (Extended Search)

(Helium) The Periodic Table of Elements Next Element (Beryllium) Beryllium The Element Lithium Click for Isotope Data 3 Li Lithium 6.941 Atomic Number: 3 Atomic Weight: 6.941...

162

Questions and Answers - Are nitrogen, arsenic, and tantalum radioactive?  

NLE Websites -- All DOE Office Websites (Extended Search)

How many neutrons can you add to anatom without it getting unbalanced? How many neutrons can you add to an<br>atom without it getting unbalanced? Previous Question (How many neutrons can you add to an atom without it getting unbalanced?) Questions and Answers Main Index Next Question (How long is the life span of an atom?) How long is the life span of an atom? Are nitrogen, arsenic, and tantalum radioactive? The answer is yes and no. Let's see why. When you want to know about elements, you go look in the periodic table. But what you see listed in the periodic table of the elements is only part of the picture. For every element listed, there are different "flavors" called isotopes. All of the elements have at least one isotope that is radioactive. So, we can say that there is such a thing as radioactive nitrogen, arsenic and tantalum. Some

163

Treatment of Radioactive Reactive Mixed Waste  

Science Conference Proceedings (OSTI)

PacificEcoSolutions, Inc. (PEcoS) has installed a plasma gasification system that was recently modified and used to destroy a trimethyl-aluminum mixed waste stream from Los Alamos National Laboratory (LANL.) The unique challenge in handling reactive wastes like trimethyl-aluminum is their propensity to flame instantly on contact with air and to react violently with water. To safely address this issue, PacificEcoSolutions has developed a new feed system to ensure the safe containment of these radioactive reactive wastes during transfer to the gasification unit. The plasma gasification system safely processed the radioactively contaminated trimethyl-metal compounds into metal oxides. The waste stream came from LANL research operations, and had been in storage for seven years, pending treatment options. (authors)

Colby, S.; Turner, Z.; Utley, D. [Pacific EcoSolutions, Inc., 2025 Battelle Boulevard, Richland, Washington 99354 (United States); Duy, C. [Los Alamos National Laboratory - LA-UR-05-8410, Post Office Box 1663 MS J595, Los Alamos, New Mexico 97545 (United States)

2006-07-01T23:59:59.000Z

164

It's Elemental - The Element Plutonium  

NLE Websites -- All DOE Office Websites (Extended Search)

Next Element (Americium) Americium The Element Plutonium Click for Isotope Data 94 Pu Plutonium 244 Atomic Number: 94 Atomic Weight: 244 Melting Point: 913 K (640C or...

165

Apparatus for injection casting metallic nuclear energy fuel ...  

Molds for making metallic nuclear fuel rods are provided which present reduced risks to the environment by reducing radioactive waste. In one embodiment, the mold is ...

166

Monitoring arrangement for vented nuclear fuel elements  

DOE Patents (OSTI)

In a nuclear fuel reactor core, fuel elements are arranged in a closely packed hexagonal configuration, each fuel element having diametrically opposed vents permitting 180.degree. rotation of the fuel elements to counteract bowing. A grid plate engages the fuel elements and forms passages for communicating sets of three, four or six individual vents with respective monitor lines in order to communicate vented radioactive gases from the fuel elements to suitable monitor means in a manner readily permitting detection of leakage in individual fuel elements.

Campana, Robert J. (Solana Beach, CA)

1981-01-01T23:59:59.000Z

167

Criteria determining the selection of slags for the melt decontamination of radioactively contaminated stainless steel by electroslag remelting  

Science Conference Proceedings (OSTI)

Electroslag remelting is an excellent process choice for the melt decontamination of radioactively contaminated metals. ESR furnaces are easily enclosed and do not make use of refractories which could complicate thermochemical interactions between molten metal and slag. A variety of cleaning mechanisms are active during melting; radionuclides may be partitioned to the slag by means of thermochemical reaction, electrochemical reaction, or mechanical entrapment. At the completion of melting, the slag is removed from the furnace in solid form. The electroslag process as a whole is greatly affected by the chemical and physical properties of the slag used. When used as a melt decontamination scheme, the ESR process may be optimized by selection of the slag. In this research, stainless steel bars were coated with non-radioactive surrogate elements in order to simulate surface contamination. These bars were electroslag remelted using slags of various chemistries. The slags investigated were ternary mixtures of calcium fluoride, calcium oxide, and alumina. The final chemistries of the stainless steel ingots were compared with those predicted by the use of a Free Energy Minimization Modeling technique. Modeling also provided insight into the chemical mechanisms by which certain elements are captured by a slag. Slag selection was also shown to have an impact on the electrical efficiency of the process as well as the surface quality of the ingots produced.

Buckentin, J.M.R.; Damkroger, B.K.; Shelmidine, G.J. [Sandia National Labs., Albuquerque, NM (United States); Atteridge, D.G. [Oregon Graduate Inst. of Science and Technology, Beaverton, OR (United States)

1997-03-01T23:59:59.000Z

168

It's Elemental - The Element Polonium  

NLE Websites -- All DOE Office Websites (Extended Search)

16 Group Name: Chalcogen Radioactive What's in a name? Named for the country of Poland. Say what? Polonium is pronounced as peh-LOW-nee-em. History and Uses: Polonium was...

169

It's Elemental - The Element Einsteinium  

NLE Websites -- All DOE Office Websites (Extended Search)

by a team of scientists led by Albert Ghiorso in 1952 while studying the radioactive debris produced by the detonation of the first hydrogen bomb. The isotope they discovered,...

170

First stars VI - Abundances of C, N, O, Li, and mixing in extremely metal-poor giants. Galactic evolution of the light elements  

E-Print Network (OSTI)

We have investigated the poorly-understood origin of nitrogen in the early Galaxy by determining N abundances in 35 extremely metal-poor halo giants (22 stars have [Fe/H]N conversion through CN cycling and strong Li dilution, a signature of mixing. The second group shows no evidence for C to N conversion, and Li is only moderately diluted, and we conclude that their C and N abundances are very close to those of the gas from which they formed in the early Galaxy. These "unmixed" stars reflect the abundances in the early Galaxy: the [C/Fe] ratio is constant (about +0.2 dex) and the [C/Mg] ratio is close to solar at low metallicity, favouring a high C production by massive zero-metal supernovae. The [N/Fe] and [N/Mg] ratios scatter widely. The larger values of these ratios define a flat upper plateau ([N/Mg]= 0.0, [N/Fe]= +0.1), which could reflect higher values within a wide range of yields of zero-metal Sne II. Alternatively, by analogy with the DLA's, the lower abundances ([N/Mg]= -1.1, [N/Fe]= -0.7) could reflect generally low yields from the first Sne II, the other stars being N enhanced by winds of massive Asymptotic Giant Branch (AGB) stars. At present it cannot be decided whether primary N is produced primarily in SNe II or in massive AGB stars, or in both. The stellar N abundances and [N/O] ratios are compatible with those found in Damped Lyman-alpha (DLA) systems.

M. Spite; R. Cayrel; B. Plez; V. Hill; F. Spite; E. Depagne; P. Francois; P. Bonifacio; B. Barbuy; T. Beers; J. Andersen; P. Molaro; B. Nordstroem; F. Primas

2004-09-22T23:59:59.000Z

171

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network (OSTI)

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid scintillation vials must be collected separately. 5. Any "mixed waste" must be cleared with the RSO and labeled

172

FUEL ELEMENTS CONFERENCE, PARIS, NOVEMBER 18-23, 1957  

SciTech Connect

Papers are presented in the following major categories: applied metallurgical research, natural-uranium metallic fuel elements, enriched-uranium metallic fuel elements, nonmetallic fuel elements, corrosion of U alloys, irradiation effects on U, its alloys, and its compounds, and Pu fuel elements. (M.H.R.)

1958-10-31T23:59:59.000Z

173

Nuclear fuel element  

DOE Patents (OSTI)

A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has an improved composite cladding comprised of a moderate purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube. The metal barrier forms a shield between the alloy tube and a core of nuclear fuel material enclosed in the composite cladding. There is a gap between the cladding and the core. The metal barrier forms about 1 to about 30 percent of the thickness of the composite cladding and has low neutron absorption characteristics. The metal barrier serves as a preferential reaction site for gaseous impurities and fission products and protects the alloy tube from contact and reaction with such impurities and fission products. Methods of manufacturing the composite cladding are also disclosed.

Armijo, Joseph S. (Saratoga, CA); Coffin, Jr., Louis F. (Schenectady, NY)

1980-04-29T23:59:59.000Z

174

Radioactivity in Nature  

NLE Websites -- All DOE Office Websites (Extended Search)

Fig. 3-8. The ratio of uranium to lead present on Earth today gives us an estimate of its age (4.5 billion years). Given Earths age, any much shorter lived radioactive nuclei...

175

Understanding radioactive waste  

SciTech Connect

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Murray, R.L.

1981-12-01T23:59:59.000Z

176

Container for radioactive materials  

DOE Patents (OSTI)

A container for housing a plurality of canister assemblies containing radioactive material and disposed in a longitudinally spaced relation within a carrier to form a payload package concentrically mounted within the container. The payload package includes a spacer for each canister assembly, said spacer comprising a base member longitudinally spacing adjacent canister assemblies from each other and a sleeve surrounding the associated canister assembly for centering the same and conducting heat from the radioactive material in a desired flow path.

Fields, Stanley R. (Richland, WA)

1985-01-01T23:59:59.000Z

177

Dynamic radioactive particle source  

SciTech Connect

A method and apparatus for providing a timed, synchronized dynamic alpha or beta particle source for testing the response of continuous air monitors (CAMs) for airborne alpha or beta emitters is provided. The method includes providing a radioactive source; placing the radioactive source inside the detection volume of a CAM; and introducing an alpha or beta-emitting isotope while the CAM is in a normal functioning mode.

Moore, Murray E.; Gauss, Adam Benjamin; Justus, Alan Lawrence

2012-06-26T23:59:59.000Z

178

SPONTANEOUS PION EMISSION DURING FISSION A NEW NUCLEAR RADIOACTIVITY  

E-Print Network (OSTI)

In this paper a short review of the theoretical problems of the pionic radioactivity is presented. The essential experimental results obtained in the 18 years of existence of the nuclear pionic radioactivity are reviewed. Moreover, using the recent results on the spontaneous fission half lives TSF of the heavy nuclei with Z ? 100 new predictions on the pionic yields in the region of superheavy elements are established. 1

D. B. Ion; Reveica Ion-mihai; M. L. Ion; Adriana I. Sandru

2008-01-01T23:59:59.000Z

179

Background X-ray Spectrum of Radioactive Samples  

Science Conference Proceedings (OSTI)

An energy-dispersive X-ray spectrometer (EDS) is commonly used with a scanning electron microscope (SEM) to analyze the elemental compositions and microstructures of a variety of samples. For example, the microstructures of nuclear fuels are commonly investigated with this technique. However, the radioactivity of some materials introduces additional X-rays that contribute to the EDS background spectrum. These X-rays are generally not accounted for in spectral analysis software, and can cause misleading results. X-rays from internal conversion [1], Bremsstrahlung [2] radiation associated with alpha ionizations and beta particle interactions [3], and gamma rays from radioactive decay can all elevate the background of radioactive materials.

Shannon Yee; Dawn E. Janney

2008-02-01T23:59:59.000Z

180

An integrated decontamination process for metals  

DOE Patents (OSTI)

An integrated process for decontamination of metals, particularly metals that are used in the nuclear energy industry contaminated with radioactive material. The process combines the processes of electrorefining and melt refining to purify metals that can be decontaminated using either electrorefining or melt refining processes.

Snyder, T.S.; Whitlow, G.A.

1989-06-08T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

A portable optical emission spectroscopy-cavity ringdown spectroscopy dual-mode plasma spectrometer for measurements of environmentally important trace heavy metals: Initial test with elemental Hg  

SciTech Connect

A portable optical emission spectroscopy-cavity ringdown spectroscopy (OES-CRDS) dual-mode plasma spectrometer is described. A compact, low-power, atmospheric argon microwave plasma torch (MPT) is utilized as the emission source when the spectrometer is operating in the OES mode. The same MPT serves as the atomization source for ringdown measurements in the CRDS mode. Initial demonstration of the instrument is carried out by observing OES of multiple elements including mercury (Hg) in the OES mode and by measuring absolute concentrations of Hg in the metastable state 6s6p {sup 3}P{sub 0} in the CRDS mode, in which a palm-size diode laser operating at a single wavelength 405 nm is incorporated in the spectrometer as the light source. In the OES mode, the detection limit for Hg is determined to be 44 parts per 10{sup 9} (ppb). A strong radiation trapping effect on emission measurements of Hg at 254 nm is observed when the Hg solution concentration is higher than 50 parts per 10{sup 6} (ppm). The radiation trapping effect suggests that two different transition lines of Hg at 253.65 nm and 365.01 nm be selected for emission measurements in lower (<50 ppm) and higher concentration ranges (>50 ppm), respectively. In the CRDS mode, the detection limit of Hg in the metastable state 6s6p {sup 3}P{sub 0} is achieved to be 2.24 parts per 10{sup 12} (ppt) when the plasma is operating at 150 W with sample gas flow rate of 480 mL min{sup -1}; the detection limit corresponds to 50 ppm in Hg sample solution. Advantage of this novel spectrometer has two-fold, it has a large measurement dynamic range, from a few ppt to hundreds ppm and the CRDS mode can serve as calibration for the OES mode as well as high sensitivity measurements. Measurements of seven other elements, As, Cd, Mn, Ni, P, Pb, and Sr, using the OES mode are also carried out with detection limits of 1100, 33, 30, 144, 576, 94, and 2 ppb, respectively. Matrix effect in the presence of other elements on Hg measurements has been found to increase the detection limit to 131 ppb. These elements in lower concentrations can also be measured in the CRDS mode when a compact laser source is available to be integrated into the spectrometer in the future. This exploratory study demonstrates a new instrument platform using an OES-CRDS dual-mode technique for potential field applications.

Sahay, Peeyush; Scherrer, Susan T.; Wang Chuji [Department of Physics and Astronomy, Mississippi State University, Starkville, Mississippi 39759 (United States)

2012-09-15T23:59:59.000Z

182

It's Elemental - Element Concentration Game  

NLE Websites -- All DOE Office Websites (Extended Search)

symbols of the elements. After you have had time to study the cards, the computer will flip them over and ask you to find a particular element. Click on the card that contains...

183

Radioactivity in food crops  

SciTech Connect

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for /sup 137/Cs, /sup 40/K, /sup 90/Sr, /sup 226/Ra, /sup 228/Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for /sup 241/Am, /sup 7/Be, /sup 60/Co, /sup 55/Fe, /sup 3/H, /sup 131/I, /sup 54/Mn, /sup 95/Nb, /sup 210/Pb, /sup 210/Po, /sup 106/Ru, /sup 125/Sb, /sup 228/Th, /sup 232/Th, and /sup 95/Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g/sup -1/ (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins.

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01T23:59:59.000Z

184

DETECTOR FOR RADIOACTIVE HYDROGEN  

SciTech Connect

A device of the Geiger-Mueller type is designed for detecting radioactive hydrogen in the presence of other radioactive substances. The device comprises an envelope with thin (1 to 5 mil thick) Ni or Pd windows at the ends, an anode and a cathode spaced apart in the envelope, and a counting gas within the envelope. In operation, the suspect atmosphere is blown against one of the windows, whereby only the hydrogen diffuses into the envelope for counting. Means is provided for heating the windows to the desired temperatures. (D.L.C.)

Christianson, C.; Gilman, M.; Maggio, R.C.

1963-12-10T23:59:59.000Z

185

Container for radioactive materials  

DOE Patents (OSTI)

A container is claimed for housing a plurality of canister assemblies containing radioactive material. The several canister assemblies are stacked in a longitudinally spaced relation within a carrier to form a payload concentrically mounted within the container. The payload package includes a spacer for each canister assembly, said spacer comprising a base member longitudinally spacing adjacent canister assemblies from each other and sleeve surrounding the associated canister assembly for centering the same and conducting heat from the radioactive material in a desired flow path. 7 figures.

Fields, S.R.

1984-05-30T23:59:59.000Z

186

Liquid metal hydrogen barriers  

DOE Patents (OSTI)

Hydrogen barriers which comprise liquid metals in which the solubility of hydrogen is low and which have good thermal conductivities at operating temperatures of interest. Such barriers are useful in nuclear fuel elements containing a metal hydride moderator which has a substantial hydrogen dissociation pressure at reactor operating temperatures.

Grover, George M. (Los Alamos, NM); Frank, Thurman G. (Los Alamos, NM); Keddy, Edward S. (Los Alamos, NM)

1976-01-01T23:59:59.000Z

187

Phytoremediation of Trace Elements by Wetland Plants  

Science Conference Proceedings (OSTI)

Some plants naturally absorb and hyperaccumulate trace elements in their tissues. In a process known as phytoremediation, scientists are harnessing this ability to remove toxic heavy metals and trace elements from contaminated soils and waters. This screening program quantified the capacity of various wetland plant species for removing trace elements from polluted water.

2001-08-23T23:59:59.000Z

188

It's Elemental - Isotopes of the Element Neptunium  

NLE Websites -- All DOE Office Websites (Extended Search)

Uranium Previous Element (Uranium) The Periodic Table of Elements Next Element (Plutonium) Plutonium Isotopes of the Element Neptunium Click for Main Data Most of the isotope...

189

It's Elemental - Isotopes of the Element Nobelium  

NLE Websites -- All DOE Office Websites (Extended Search)

Mendelevium Previous Element (Mendelevium) The Periodic Table of Elements Next Element (Lawrencium) Lawrencium Isotopes of the Element Nobelium Click for Main Data Most of the...

190

It's Elemental - Isotopes of the Element Fermium  

NLE Websites -- All DOE Office Websites (Extended Search)

Einsteinium Previous Element (Einsteinium) The Periodic Table of Elements Next Element (Mendelevium) Mendelevium Isotopes of the Element Fermium Click for Main Data Most of the...

191

It's Elemental - Isotopes of the Element Sulfur  

NLE Websites -- All DOE Office Websites (Extended Search)

Phosphorus Previous Element (Phosphorus) The Periodic Table of Elements Next Element (Chlorine) Chlorine Isotopes of the Element Sulfur Click for Main Data Most of the isotope...

192

It's Elemental - Isotopes of the Element Argon  

NLE Websites -- All DOE Office Websites (Extended Search)

Chlorine Previous Element (Chlorine) The Periodic Table of Elements Next Element (Potassium) Potassium Isotopes of the Element Argon Click for Main Data Most of the isotope data...

193

It's Elemental - Isotopes of the Element Ruthenium  

NLE Websites -- All DOE Office Websites (Extended Search)

Technetium Previous Element (Technetium) The Periodic Table of Elements Next Element (Rhodium) Rhodium Isotopes of the Element Ruthenium Click for Main Data Most of the isotope...

194

It's Elemental - Isotopes of the Element Molybdenum  

NLE Websites -- All DOE Office Websites (Extended Search)

Niobium Previous Element (Niobium) The Periodic Table of Elements Next Element (Technetium) Technetium Isotopes of the Element Molybdenum Click for Main Data Most of the isotope...

195

It's Elemental - Isotopes of the Element Protactinium  

NLE Websites -- All DOE Office Websites (Extended Search)

Thorium Previous Element (Thorium) The Periodic Table of Elements Next Element (Uranium) Uranium Isotopes of the Element Protactinium Click for Main Data Most of the isotope data...

196

Nuclear fuel element  

DOE Patents (OSTI)

A nuclear fuel element and a method of manufacturing the element. The fuel element is comprised of a metal primary container and a fuel pellet which is located inside it and which is often fragmented. The primary container is subjected to elevated pressure and temperature to deform the container such that the container conforms to the fuel pellet, that is, such that the container is in substantial contact with the surface of the pellet. This conformance eliminates clearances which permit rubbing together of fuel pellet fragments and rubbing of fuel pellet fragments against the container, thus reducing the amount of dust inside the fuel container and the amount of dust which may escape in the event of container breach. Also, as a result of the inventive method, fuel pellet fragments tend to adhere to one another to form a coherent non-fragmented mass; this reduces the tendency of a fragment to pierce the container in the event of impact.

Zocher, Roy W. (Los Alamos, NM)

1991-01-01T23:59:59.000Z

197

Synthesis of transactinide nuclei in cold fusion reactions using radioactive beams  

SciTech Connect

Chances of synthesis of transactinide nuclei in cold fusion reactions (one-neutron-out reactions) using radioactive beams are evaluated. Because in most of the cases intensities of radioactive beams are significantly less than those of the stable beams, reactions with the greatest radioactive-beam intensities for the particular elements are considered. The results are compared with the recent ones obtained by Loveland [Phys. Rev. C 76, 014612 (2007)], who investigated the same nuclei.

Smolanczuk, Robert [Theoretical Physics Department, Soltan Institute for Nuclear Studies, Hoza 69, PL-00-681 Warszawa (Poland)

2010-06-15T23:59:59.000Z

198

RADIOACTIVITY (NATURAL) Synonyms Definition  

Science Conference Proceedings (OSTI)

rays to the natural dose of radioactivity is strongly depen- dent on altitude and ... a noble gas, and its migration in groundwater and soil gas is of ..... trometers available on the market. ... example, using an oil immersion objective (NA 1.4) with.

199

The Uses of Rare Earth Element Activated Micrometer and ...  

Science Conference Proceedings (OSTI)

... lighting industries, detecting systems, security applications (marking objects and currency) and ... Assessment and Management of Radioactivity in Rare Earth Element Production ... Inorganic Functional Materials for Environmental Protection ... Oxides for Nuclear Waste Sequestration Applications by X-ray Spectroscopy...

200

It's Elemental - The Element Darmstadtium  

NLE Websites -- All DOE Office Websites (Extended Search)

Roentgenium The Element Darmstadtium Click for Isotope Data 110 Ds Darmstadtium 281 Atomic Number: 110 Atomic Weight: 281 Melting Point: Unknown Boiling Point: Unknown...

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

It's Elemental - The Element Berkelium  

NLE Websites -- All DOE Office Websites (Extended Search)

Californium The Element Berkelium Click for Isotope Data 97 Bk Berkelium 247 Atomic Number: 97 Atomic Weight: 247 Melting Point: 1323 K (1050C or 1922F) Boiling...

202

RADIOACTIVITY STORED UP BY ALGAE  

SciTech Connect

A fast radiometric method of measuring radioactivity uptake by marine organisms is described. (R.V.J.)

Akamsin, A.D.; Parchevskii, V.P.; Polikarpov, G.G.

1960-02-01T23:59:59.000Z

203

Method for calcining radioactive wastes  

DOE Patents (OSTI)

This invention relates to a method for the preparation of radioactive wastes in a low leachability form by calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined waste to melter to form a homogeneous melt of the glass and the calcined waste, and then solidifying the melt to encapsulate the radioactive calcine in a glass matrix.

Bjorklund, William J. (Richland, WA); McElroy, Jack L. (Richland, WA); Mendel, John E. (Kennewick, WA)

1979-01-01T23:59:59.000Z

204

DEVELOPMENT OF EQUIPMENT FOR THE RETRIEVAL & STABILIZATION & ENCAPSULATION OF RADIOACTIVE SLUDGE AT THE HANFORD SITE  

SciTech Connect

This poster presentation describes and illustrates some of the equipment and tools that Fluor Hanford and BNG America have developed and designed to remove, transport, stabilize and encapsulate radioactive sludge from the K Basins at the Hanford nuclear site in Washington State, U.S.A. K Basins were built in the early 1950s to temporarily store irradiated nuclear fuel prior to chemical processing to remove plutonium for nuclear weapons. The sludge is the result of corrosion of these fuel elements and its removal is the final stage before the basin water can be drained and the basins decommissioned. The sludge is hydrogen-generating because of its uranium metal content and account has to be taken also of its heat generating capacity and criticality potential as it is moved from one containment to another. The paper describes all stages of sludge treatment from the use of vacuum wands to suck up the sludge, through consolidating the sludge in temporary underwater containers, transporting it though flexible, temporary pipe systems, acceleration of the corrosion of uranium to reduce hydrogen generation, measuring the fissile content and finally encapsulation in a cement grout. Emphasis is placed on the use of existing, transportable and temporary equipment. This not only saves initial costs but it also reduces the total amount of equipment needed to be disposed of as radioactive waste at the end of the job. The processes, equipment and tools described potentially have a broad applicability to nuclear site decommissioning and cleanup worldwide.

ROOSENDAAL, G.D.

2005-07-05T23:59:59.000Z

205

Finding Aids: Radioactive Fallout  

NLE Websites -- All DOE Office Websites (Extended Search)

A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing Table of Contents INTRODUCTION Argonne National Laboratory Bancroft Library, University of California Boeing Aircraft Company Brookhaven National Laboratory Coordination and Information Center (CIC) Eastman Kodak EG&G, Energy Measurements Holmes and Narver Lawrence Livermore National Laboratory Los Alamos National Laboratory Manuscript Division, Library of Congress National Academy of Sciences Archives Oak Ridge National Laboratory Pacific Northwest Laboratory Sandia National Laboratories Scripps Institution of Oceanography Archives Smithsonian Institution Archives U.S. Air Force Brooks Air Force Base Kirtland Air Force Base USAF Historical Research Center U.S. Army Chemical Corps (Aberdeen Proving Ground)

206

PROCESSING OF RADIOACTIVE WASTE  

DOE Patents (OSTI)

A process for treating radioactive waste solutions prior to disposal is described. A water-soluble phosphate, borate, and/or silicate is added. The solution is sprayed with steam into a space heated from 325 to 400 deg C whereby a powder is formed. The powder is melted and calcined at from 800 to 1000 deg C. Water vapor and gaseous products are separated from the glass formed. (AEC)

Johnson, B.M. Jr.; Barton, G.B.

1961-11-14T23:59:59.000Z

207

System for handling and storing radioactive waste  

DOE Patents (OSTI)

A system and method are claimed for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, J.K.; Lindemann, P.E.

1982-07-19T23:59:59.000Z

208

System for handling and storing radioactive waste  

DOE Patents (OSTI)

A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, John K. (San Diego, CA); Lindemann, Paul E. (Escondido, CA)

1984-01-01T23:59:59.000Z

209

Fusion Induced by Radioactive Ion Beams  

E-Print Network (OSTI)

The use of radioactive beams opens a new frontier for fusion studies. The coupling to the continuum can be explored with very loosely bound nuclei. Experiments were performed with beams of nuclei at or near the proton and neutron drip-lines to measure fusion and associated reactions in the vicinity of the Coulomb barrier. In addition, the fusion yield is predicted to be enhanced in reactions involving very neutron-rich unstable nuclei. Experimental measurements were carried out to investigate if it is feasible to use such beams to produce new heavy elements. The current status of these experimental activities is given in this review.

J. F. Liang; C. Signorini

2005-04-26T23:59:59.000Z

210

Radioactive waste storage issues  

SciTech Connect

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

211

It's Elemental - The Element Calcium  

NLE Websites -- All DOE Office Websites (Extended Search)

little demand for metallic calcium. It is used in some chemical processes to refine thorium, uranium and zirconium. Calcium is also used to remove oxygen, sulfur and carbon from...

212

Environmental geochemistry of radioactive contamination.  

Science Conference Proceedings (OSTI)

This report attempts to describe the geochemical foundations of the behavior of radionuclides in the environment. The information is obtained and applied in three interacting spheres of inquiry and analysis: (1) experimental studies and theoretical calculations, (2) field studies of contaminated and natural analog sites and (3) model predictions of radionuclide behavior in remediation and waste disposal. Analyses of the risks from radioactive contamination require estimation of the rates of release and dispersion of the radionuclides through potential exposure pathways. These processes are controlled by solubility, speciation, sorption, and colloidal transport, which are strong functions of the compositions of the groundwater and geomedia as well as the atomic structure of the radionuclides. The chemistry of the fission products is relatively simple compared to the actinides. Because of their relatively short half-lives, fission products account for a large fraction of the radioactivity in nuclear waste for the first several hundred years but do not represent a long-term hazard in the environment. The chemistry of the longer-lived actinides is complex; however, some trends in their behavior can be described. Actinide elements of a given oxidation state have either similar or systematically varying chemical properties due to similarities in ionic size, coordination number, valence, and electron structure. In dilute aqueous systems at neutral to basic pH, the dominant actinide species are hydroxy- and carbonato-complexes, and the solubility-limiting solid phases are commonly oxides, hydroxides or carbonates. In general, actinide sorption will decrease in the presence of ligands that complex with the radionuclide; sorption of the (IV) species of actinides (Np, Pu, U) is generally greater than of the (V) species. The geochemistry of key radionuclides in three different environments is described in this report. These include: (1) low ionic strength reducing waters from crystalline rocks at nuclear waste research sites in Sweden; (2) oxic water from the J-13 well at Yucca Mountain, Nevada, the site of a proposed repository for high level nuclear waste (HLW) in tuffaceous rocks; and (3) reference brines associated with the Waste Isolation Pilot Plant (WIPP). The transport behaviors of radionuclides associated with the Chernobyl reactor accident and the Oklo Natural Reactor are described. These examples span wide temporal and spatial scales and include the rapid geochemical and physical processes important to nuclear reactor accidents or industrial discharges as well as the slower processes important to the geologic disposal of nuclear waste. Application of geochemical information to remediating or assessing the risk posed by radioactive contamination is the final subject of this report. After radioactive source terms have been removed, large volumes of soil and water with low but potentially hazardous levels of contamination may remain. For poorly-sorbing radionuclides, capture of contaminated water and removal of radionuclides may be possible using permeable reactive barriers and bioremediation. For strongly sorbing radionuclides, contaminant plumes will move very slowly. Through a combination of monitoring, regulations and modeling, it may be possible to have confidence that they will not be a hazard to current or future populations. Abstraction of the hydrogeochemical properties of real systems into simple models is required for probabilistic risk assessment. Simplifications in solubility and sorption models used in performance assessment calculations for the WIPP and the proposed HLW repository at Yucca Mountain are briefly described.

Bryan, Charles R.; Siegel, Malcolm Dean

2003-09-01T23:59:59.000Z

213

METHOD OF MAKING FUEL ELEMENTS  

DOE Patents (OSTI)

A method is described for fabricating fuel elements, particularly for enclosing a plate of metal with a second metal by inserting the plate into an aperture of a frame of a second plate, placing a sheet of the second metal on each of opposite faces of the assembled plate and frame, purging with an inert gas the air from the space within the frame and the sheets while sealing the seams between the frame and the sheets, exhausting the space, purging the space with air, re-exhausting the spaces, sealing the second aperture, and applying heat and pressure to bond the sheets, the plate, and the frame to one another.

Bean, C.H.; Macherey, R.E.

1959-12-01T23:59:59.000Z

214

Metal Aminoboranes  

Metal aminoboranes of the formula M(NH.sub.2BH.sub.3).sub.n have been synthesized. Metal aminoboranes are hydrogen storage materials. Metal aminoboranes are also precursors for synthesizing other metal aminoboranes. Metal aminoboranes can be ...

215

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS  

Science Conference Proceedings (OSTI)

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-02-27T23:59:59.000Z

216

It's Elemental - The Element Lutetium  

NLE Websites -- All DOE Office Websites (Extended Search)

(Hafnium) Hafnium The Element Lutetium Click for Isotope Data 71 Lu Lutetium 174.9668 Atomic Number: 71 Atomic Weight: 174.9668 Melting Point: 1936 K (1663C or 3025F)...

217

It's Elemental - The Element Holmium  

NLE Websites -- All DOE Office Websites (Extended Search)

(Erbium) Erbium The Element Holmium Click for Isotope Data 67 Ho Holmium 164.93032 Atomic Number: 67 Atomic Weight: 164.93032 Melting Point: 1747 K (1474C or 2685F)...

218

It's Elemental - The Element Promethium  

NLE Websites -- All DOE Office Websites (Extended Search)

(Samarium) Samarium The Element Promethium Click for Isotope Data 61 Pm Promethium 145 Atomic Number: 61 Atomic Weight: 145 Melting Point: 1315 K (1042C or 1908F) Boiling...

219

It's Elemental - The Element Cadmium  

NLE Websites -- All DOE Office Websites (Extended Search)

(Indium) Indium The Element Cadmium Click for Isotope Data 48 Cd Cadmium 112.411 Atomic Number: 48 Atomic Weight: 112.411 Melting Point: 594.22 K (321.07C or 609.93F)...

220

It's Elemental - The Element Praseodymium  

NLE Websites -- All DOE Office Websites (Extended Search)

Today, praseodymium is primarily obtained through an ion exchange process from monazite sand ((Ce, La, Th, Nd, Y)PO4), a material rich in rare earth elements. Praseodymium's...

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

It's Elemental - The Element Neodymium  

NLE Websites -- All DOE Office Websites (Extended Search)

Today, neodymium is primarily obtained from through an ion exchange process monazite sand ((Ce, La, Th, Nd, Y)PO4), a material rich in rare earth elements. Neodymium makes up...

222

It's Elemental - The Element Samarium  

NLE Websites -- All DOE Office Websites (Extended Search)

1879. Today, samarium is primarily obtained through an ion exchange process from monazite sand ((Ce, La, Th, Nd, Y)PO4), a material rich in rare earth elements that can contain as...

223

It's Elemental - The Element Lanthanum  

NLE Websites -- All DOE Office Websites (Extended Search)

Today, lanthanum is primarily obtained through an ion exchange process from monazite sand ((Ce, La, Th, Nd, Y)PO4), a material rich in rare earth elements that can contain as...

224

Advanced technologies for decomtamination and conversion of scrap metal  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) faces the task of decommissioning much of the vast US weapons complex. One challenge of this effort includes the disposition of large amounts of radioactively contaminated scrap metal (RSM) including but not limited to steel, nickel, copper, and aluminum. The decontamination and recycling of RSM has become a key element in the DOE's strategy for cleanup of contaminated sites and facilities. Recycling helps to offset the cost of decommissioning and saves valuable space in the waste disposal facilities. It also reduces the amount of environmental effects associated with mining new metals. Work on this project is geared toward finding decontamination and/or recycling alternatives for the RSM contained in the decommissioned gaseous diffusion plants including approximately 40,000 tons of nickel. The nickel is contaminated with Technetium-99, and is difficult to remove using traditional decontamination technologies. The project, titled ``Advanced Technologies for Decontamination and Conversion of Scrap Metal'' was proposed as a four phase project. Phase 1 and 2 are complete and Phase 3 will complete May 31, 1999. Stainless steel made from contaminated nickel barrier was successfully produced in Phase 1. An economic evaluation was performed and a market study of potential products from the recycled metal was completed. Inducto-slag refining, after extensive testing, was eliminated as an alternative to remove technetium contamination from nickel. Phase 2 included successful lab scale and pilot scale demonstrations of electrorefining to separate technetium from nickel. This effort included a survey of available technologies to detect technetium in volumetrically contaminated metals. A new process to make sanitary drums from RSM was developed and implemented. Phase 3 included a full scale demonstration of electrorefining, an evaluation of electro-refining alternatives including direct dissolution, melting of nickel into anodes, a laser cutting demonstration, an investigation of commercial markets for RSM, and refinement of methods to quantify isotopic elements.

Valerie MacNair; Steve Sarten; Thomas Muth; Brajendra Mishra

1999-05-27T23:59:59.000Z

225

FUEL ELEMENT  

DOE Patents (OSTI)

A ceramic fuel element for a nuclear reactor that has improved structural stability as well as improved cooling and fission product retention characteristics is presented. The fuel element includes a plurality of stacked hollow ceramic moderator blocks arranged along a tubular raetallic shroud that encloses a series of axially apertured moderator cylinders spaced inwardly of the shroud. A plurality of ceramic nuclear fuel rods are arranged in the annular space between the shroud and cylinders of moderator and appropriate support means and means for directing gas coolant through the annular space are also provided. (AEC)

Bean, R.W.

1963-11-19T23:59:59.000Z

226

Influence of heavy natural radioactive nuclides introduced in soil with labelled fertilizers and ameliorants on cytogenetic effects in plants  

Science Conference Proceedings (OSTI)

The effect of heavy natural radioactive nuclides (STYU, STSTh, SSWRa, S Po, and S Pb) in labeled fertilizers and ameliorants on the number of meiotic chromosome aberrations was studied in field experiments on the major crop plants, wheat, barley and corn. The mining and use of coal and oil and the processing of raw materials in the production of rare and nonferrous metals produce high quantities of wastes with an elevated content of natural radionuclides. One possible way for technogenically altering the natural radiation background of soil is the active utilization of phosphorus fertilizers in agriculture, and also the use, as fertilizers and ameliorants of wastes from nonferrous metallurgy, of the ash from heat and power plants and various intermediates from the chemical industry. The authors conclude that the introduction of labeled ammophos, nitrophos and phosphogypsum, which raised the soil background concentration of the specified elements, produced an increase in the number of cells with meiotic chromosome aberrations.

Arkhipov, N.P.; Bazylev, V.V.; Bobrikova, E.T.; Fevraleva, L.T.; Kal'chenko, VA.; Shevchenko, V.A.

1985-05-01T23:59:59.000Z

227

It's Elemental - Isotopes of the Element Thorium  

NLE Websites -- All DOE Office Websites (Extended Search)

Table of Elements Next Element (Protactinium) Protactinium Isotopes of the Element Thorium Click for Main Data Most of the isotope data on this site has been obtained from...

228

Bacteria eats radioactive waste  

NLE Websites -- All DOE Office Websites (Extended Search)

Bacteria eats radioactive waste Bacteria eats radioactive waste Name: deenaharper Status: N/A Age: N/A Location: N/A Country: N/A Date: Around 1993 Question: In my studies, I have found that everything in this world is balanced. When something dies it is converted into life. Is there anything out there that could convert radioactive material into a harmless substance? Some sort of bacteria that consumes radiation? Replies: The reason why radiation is so harmful is that is produces free radicals in living tissue, that is, it de-stabilizes molecules by tearing off electrons due to intense energies. These free radicals start a chain reaction of destruction, de-stabilizing neighboring molecules. If this continues unchecked, cells die, genetic material are mutated, and tissue aging accelerates. It is somewhat like being burned. Fire oxidizes by a similar free radical reaction. (Hence the term "sun burn.") The natural defenses against free radical reactions in biological systems are antioxidants, which are enzymes, nutrients, and other chemicals, which quench free radical reactions. Without them, life would very quickly cease. To my knowledge, no microorganism has an antioxidant capacity great enough to withstand even minimal exposure to any type of radiation. Microorganisms are actually very susceptible to radiation, which is why heat and gamma irradiation are used to sterilize food, instruments, etc. However, you raise an interesting possibility in that perhaps one can be genetically engineered to have super- antioxidant capacity, but that may be beyond current technology. Plus, if any got loose, given the exponential rate of reproduction, they may become an uncontrollable health hazard, as it would be very difficult to destroy them!

229

Element Crossword Puzzles  

NLE Websites -- All DOE Office Websites (Extended Search)

Crossword Puzzles Crossword Puzzles Welcome to It's Elemental - Element Crossword Puzzles! Use the clues provided to solve each crossword puzzle. To place letters on the puzzle, first select the clue you are answering from the pull-down menu and then enter your answer in the text box. Press the 'return' key on your keyboard when you are done. Correct letters will be green while incorrect letters will be red. Good luck and have fun! If you are reading this, your browser is NOT running JavaScript. JavaScript MUST be enabled for this section of our site to work. Once you have turned JavaScript on, reload this page and this warning will go away. Puzzle 1 - It's a Gas! Puzzle 2 - Easy Symbols Puzzle 3 - Strange Symbols Puzzle 4 - Known to the Ancients Puzzle 5 - The Alkali Metals

230

FUEL ELEMENT CONSTRUCTION  

DOE Patents (OSTI)

Fuel elements having a solid core of fissionable material encased in a cladding material are described. A conversion material is provided within the cladding to react with the fission products to form stable, relatively non- volatile compounds thereby minimizing the migration of the fission products into the coolant. The conversion material is preferably a metallic fluoride, such as lead difluoride, and may be in the form of a coating on the fuel core or interior of the cladding, or dispersed within the fuel core. (AEC)

Zumwalt, L.R.

1961-08-01T23:59:59.000Z

231

Base Elements  

Science Conference Proceedings (OSTI)

Table 4   Principal effects of superalloy base elements on alloy characteristics...to γ? or γ? Requires fcc stabilizer Cobalt prices have been known to be volatile in the past. Suitable for creep-resistant applications with low stresses or

232

Automated Fuel Element Closure Welding System  

SciTech Connect

The Automated Fuel Element Closure Welding System is a robotic device that will load and weld top end plugs onto nuclear fuel elements in a highly radioactive and inert gas environment. The system was developed at Argonne National Laboratory-West as part of the Fuel Cycle Demonstration. The welding system performs four main functions, it (1) injects a small amount of a xenon/krypton gas mixture into specific fuel elements, and (2) loads tiny end plugs into the tops of fuel element jackets, and (3) welds the end plugs to the element jackets, and (4) performs a dimensional inspection of the pre- and post-welded fuel elements. The system components are modular to facilitate remote replacement of failed parts. The entire system can be operated remotely in manual, semi-automatic, or fully automatic modes using a computer control system. The welding system is currently undergoing software testing and functional checkout.

Wahlquist, D.R.

1993-01-01T23:59:59.000Z

233

Automated Fuel Element Closure Welding System  

SciTech Connect

The Automated Fuel Element Closure Welding System is a robotic device that will load and weld top end plugs onto nuclear fuel elements in a highly radioactive and inert gas environment. The system was developed at Argonne National Laboratory-West as part of the Fuel Cycle Demonstration. The welding system performs four main functions, it (1) injects a small amount of a xenon/krypton gas mixture into specific fuel elements, and (2) loads tiny end plugs into the tops of fuel element jackets, and (3) welds the end plugs to the element jackets, and (4) performs a dimensional inspection of the pre- and post-welded fuel elements. The system components are modular to facilitate remote replacement of failed parts. The entire system can be operated remotely in manual, semi-automatic, or fully automatic modes using a computer control system. The welding system is currently undergoing software testing and functional checkout.

Wahlquist, D.R.

1993-03-01T23:59:59.000Z

234

Radioactive waste processing apparatus  

DOE Patents (OSTI)

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container.

Nelson, Robert E. (Lombard, IL); Ziegler, Anton A. (Darien, IL); Serino, David F. (Maplewood, MN); Basnar, Paul J. (Western Springs, IL)

1987-01-01T23:59:59.000Z

235

Badly Shaped Elements (BadlyShapedElements)  

Science Conference Proceedings (OSTI)

... shaped elements. Synopsis. BadlyShapedElements ( threshold ). Details. Base class: SkelModTargets; Parameters: threshold The threshold shape ...

2013-07-05T23:59:59.000Z

236

EA-1919: Recycle of Scrap Metals Originating from Radiological Areas  

Energy.gov (U.S. Department of Energy (DOE))

This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.)

237

FUEL ELEMENT  

DOE Patents (OSTI)

A fuel element was developed for a gas cooled nuclear reactor. The element is constructed in the form of a compacted fuel slug including carbides of fissionable material in some cases with a breeder material carbide and a moderator which slug is disposed in a canning jacket of relatively impermeable moderator material. Such canned fuel slugs are disposed in an elongated shell of moderator having greater gas permeability than the canning material wherefore application of reduced pressure to the space therebetween causes gas diffusing through the exterior shell to sweep fission products from the system. Integral fission product traps and/or exterior traps as well as a fission product monitoring system may be employed therewith. (AEC)

Fortescue, P.; Zumwalt, L.R.

1961-11-28T23:59:59.000Z

238

Standard Elements  

Science Conference Proceedings (OSTI)

Table 1   ASTM standards applicable to element-level testing of composites...Composite Plates Subjected to a Distributed Load Plate flexure D 6484 Open-Hole Compression Strength of Polymer Matrix Composites Open-hole compression strength Z 5370Z Compression After Impact Strength of Fiber-Resin Composites Compression after impact Z 7225Z Mixed Mode I-Mode II...

239

Significance of radiation effects in solid radioactive waste  

SciTech Connect

Proposed NRC criteria for disposal of high-level nuclear waste require development of waste packages to contain radionuclide for at least 1000 years, and design of repositories to prevent radionuclide release at an annual rate greater than 1 part in 100,000 of the total activity. The high-level wastes that are now temporarily stored as aqueous salts, sludges, and calcines must be converted to high-integrity solid forms that resist deterioration from radiation and other effects of long-term storage. Spent fuel may be encapsulated for similar long-term storage. Candidate waste forms beside the spent fuel elements themselves, include borosilicate and related glasses, mineral-like crystalline ceramics, concrete formulations, and metal-matrix glass or ceramic composites. these waste forms will sustain damage produced by beta-gamma radiation up to 10/sup 12/ rads, by alpha radiation up to 10/sup 19/ particles/g, by internal helium generation greater than about 0.1 atom percent, and by the atom transmutations accompanying radioactive decay. Current data indicate that under these conditions the glass forms suffer only minor volume changes, stored energy deposition, and leachability effects. The crystalline ceramics appear susceptible to the potentially more severe alterations accompanying metamictization and natural analogs of candidate materials are being examined to establish their suitability as waste forms. Helium concentrations in the waste forms are generally below thresholds for severe damage in either glass or crystalline ceramics at low temperatures, but microstructural effects are not well characterized. Transmutation effects remain to be established.

Permar, P H; McDonell, W R

1980-01-01T23:59:59.000Z

240

Radioactive isotopes on the Moon  

SciTech Connect

A limited review of experiments and studies of radioactivity and isotope ratios in lunar materials is given. Observations made on the first few millimeters of the surface where the effects of solar flare particles are important, some measurements on individual rocks, and some studies of radioactivities produced deep in the lunar soil by galactic cosmic rays, are among the experiments discussed. (GHT)

Davis, R. Jr.

1975-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

FAQ 5-Is uranium radioactive?  

NLE Websites -- All DOE Office Websites (Extended Search)

Is uranium radioactive? Is uranium radioactive? Is uranium radioactive? All isotopes of uranium are radioactive, with most having extremely long half-lives. Half-life is a measure of the time it takes for one half of the atoms of a particular radionuclide to disintegrate (or decay) into another nuclear form. Each radionuclide has a characteristic half-life. Half-lives vary from millionths of a second to billions of years. Because radioactivity is a measure of the rate at which a radionuclide decays (for example, decays per second), the longer the half-life of a radionuclide, the less radioactive it is for a given mass. The half-life of uranium-238 is about 4.5 billion years, uranium-235 about 700 million years, and uranium-234 about 25 thousand years. Uranium atoms decay into other atoms, or radionuclides, that are also radioactive and commonly called "decay products." Uranium and its decay products primarily emit alpha radiation, however, lower levels of both beta and gamma radiation are also emitted. The total activity level of uranium depends on the isotopic composition and processing history. A sample of natural uranium (as mined) is composed of 99.3% uranium-238, 0.7% uranium-235, and a negligible amount of uranium-234 (by weight), as well as a number of radioactive decay products.

242

Low Radioactivity in CANDLES  

SciTech Connect

CANDLES is the project to search for double beta decay of 48Ca by using CaF2 crystals. Double beta decay of 48Ca has the highest Q value among all nuclei whose double beta decay is energetically allowed. This feature makes the study almost background free and becomes important once the study is limited by the backgrounds. We studied double beta decays of 48Ca by using ELEGANTS VI detector system which features CaF2(Eu) crystals. We gave the best limit on the lifetime of neutrino-less double beta decay of 48Ca although further development is vital to reach the neutrino mass of current interest for which CANDLES is designed. In this article we present how CANDLES can achieve low radioactivity, which is the key for the future double beta decay experiment.

Kishimoto, T.; Ogawa, I.; Hazama, R.; Yoshida, S.; Umehara, S.; Matsuoka, K.; Sakai, H.; Yokoyama, D.; Mukaida, K.; Ichihara, K.; Tatewaki, Y.; Kishimoto, K.; Hirano, Y.; Yanagisawa, A.; Ajimura, S. [Department of Physics, Osaka University, Toyonaka, Osaka, 560-0043 (Japan)

2005-09-08T23:59:59.000Z

243

Radioactive waste processing apparatus  

DOE Patents (OSTI)

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

244

Materials Sustainability: Digital Resource Center - Radioactivity in ...  

Science Conference Proceedings (OSTI)

Jun 26, 2008 ... This video introduces terms and concepts associated with radioactivity and shows how to identify radioactive substances that might enter a...

245

FAQ 4-What is radioactivity and radiation?  

NLE Websites -- All DOE Office Websites (Extended Search)

and radiation? What is radioactivity and radiation? Radioactivity is the term used to describe the natural process by which some atoms spontaneously disintegrate, emitting both...

246

i TP?TT<$wft Environmental Radioactivity  

E-Print Network (OSTI)

Abstract. Measurements of fallout radioactivity in the North Atlantic region including the Faroe Islands FALLOUT; GREENLAND; MAN; MILK; PLANTS; PLUTONIUM 239; PLU- TONIUM 240; RADIOACTIVITY; SEAWATER; SEAWEEDS

247

Environmental Radioactivity in the North Atlantic Region.  

E-Print Network (OSTI)

Radioactivity, Monaco Abstract. Measurements of fallout radioactivity in the North Atlantic region including ISLANDS; FOOD CHAINS; GLOBAL FALLOUT GREENLAND; LEAD 210; MAN; MILK; MOLLUSCS; POLONIUM 210; PLANTS

248

EIS-0327: Disposition of Scrap Metals Programmatic EIS  

Energy.gov (U.S. Department of Energy (DOE))

This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS.

249

SELF SINTERING OF RADIOACTIVE WASTES  

DOE Patents (OSTI)

A method is described for disposal of radioactive liquid waste materials. The wastes are mixed with clays and fluxes to form a ceramic slip and disposed in a thermally insulated container in a layer. The temperature of the layer rises due to conversion of the energy of radioactivity to heat boillng off the liquid to fomn a dry mass. The dry mass is then covered with thermal insulation, and the mass is self-sintered into a leach-resistant ceramic cake by further conversion of the energy of radioactivity to heat.

McVay, T.N.; Johnson, J.R.; Struxness, E.G.; Morgan, K.Z.

1959-12-29T23:59:59.000Z

250

Crystallization of sodium nitrate from radioactive waste  

SciTech Connect

From the 1940s to the 1980s, the Institute of Physical Chemistry of the Russian Academy of Sciences (IPC/RAS) conducted research and development on processes to separate acetate and nitrate salts and acetic acid from radioactive wastes by crystallization. The research objective was to decrease waste volumes and produce the separated decontaminated materials for recycle. This report presents an account of the IPC/RAS experience in this field. Details on operating conditions, waste and product compositions, decontamination factors, and process equipment are described. The research and development was generally related to the management of intermediate-level radioactive wastes. The waste solutions resulted from recovery and processing of uranium, plutonium, and other products from irradiated nuclear fuel, neutralization of nuclear process solutions after extractant recovery, regeneration of process nitric acid, equipment decontamination, and other radiochemical processes. Waste components include nitric acid, metal nitrate and acetate salts, organic impurities, and surfactants. Waste management operations generally consist of two stages: volume reduction and processing of the concentrates for storage, solidification, and disposal. Filtration, coprecipitation, coagulation, evaporation, and sorption were used to reduce waste volume. 28 figs., 40 tabs.

Krapukhin, V.B.; Krasavina, E.P. Pikaev, A.K. [Russian Academy of Sciences, Moscow (Russian Federation). Institute of Physical Chemistry

1997-07-01T23:59:59.000Z

251

Ductile transplutonium metal alloys  

DOE Patents (OSTI)

Alloys of Ce with transplutonium metals such as Am, Cm, Bk and Cf have properties making them highly suitable as souces of the transplutonium element, e.g., for use in radiation detector technology or as radiation sources. The alloys are ductile, homogeneous, easy to prepare and have a fairly high density.

Conner, W.V.

1981-10-09T23:59:59.000Z

252

Radioactive decay data tables  

SciTech Connect

The estimation of radiation dose to man from either external or internal exposure to radionuclides requires a knowledge of the energies and intensities of the atomic and nuclear radiations emitted during the radioactive decay process. The availability of evaluated decay data for the large number of radionuclides of interest is thus of fundamental importance for radiation dosimetry. This handbook contains a compilation of decay data for approximately 500 radionuclides. These data constitute an evaluated data file constructed for use in the radiological assessment activities of the Technology Assessments Section of the Health and Safety Research Division at Oak Ridge National Laboratory. The radionuclides selected for this handbook include those occurring naturally in the environment, those of potential importance in routine or accidental releases from the nuclear fuel cycle, those of current interest in nuclear medicine and fusion reactor technology, and some of those of interest to Committee 2 of the International Commission on Radiological Protection for the estimation of annual limits on intake via inhalation and ingestion for occupationally exposed individuals.

Kocher, D.C.

1981-01-01T23:59:59.000Z

253

It's Elemental - Isotopes of the Element Mendelevium  

NLE Websites -- All DOE Office Websites (Extended Search)

The Periodic Table of Elements Next Element (Nobelium) Nobelium Isotopes of the Element Mendelevium Click for Main Data Most of the isotope data on this site has been obtained...

254

It's Elemental - Isotopes of the Element Uranium  

NLE Websites -- All DOE Office Websites (Extended Search)

Periodic Table of Elements Next Element (Neptunium) Neptunium Isotopes of the Element Uranium Click for Main Data Most of the isotope data on this site has been obtained from...

255

It's Elemental - Isotopes of the Element Lithium  

NLE Websites -- All DOE Office Websites (Extended Search)

Periodic Table of Elements Next Element (Beryllium) Beryllium Isotopes of the Element Lithium Click for Main Data Most of the isotope data on this site has been obtained from...

256

It's Elemental - Isotopes of the Element Hydrogen  

NLE Websites -- All DOE Office Websites (Extended Search)

The Periodic Table of Elements Next Element (Helium) Helium Isotopes of the Element Hydrogen Click for Main Data Most of the isotope data on this site has been obtained from...

257

Metal Aminoboranes  

NLE Websites -- All DOE Office Websites (Extended Search)

Metal Aminoboranes Metal Aminoboranes Metal Aminoboranes Metal aminoboranes of the formula M(NH.sub.2BH.sub.3).sub.n have been synthesized. June 25, 2013 Metal Aminoboranes Metal aminoboranes of the formula M(NH.sub.2BH.sub.3).sub.n have been synthesized. Available for thumbnail of Feynman Center (505) 665-9090 Email Metal Aminoboranes Metal aminoboranes of the formula M(NH.sub.2BH.sub.3).sub.n have been synthesized. Metal aminoboranes are hydrogen storage materials. Metal aminoboranes are also precursors for synthesizing other metal aminoboranes. Metal aminoboranes can be dehydrogenated to form hydrogen and a reaction product. The reaction product can react with hydrogen to form a hydrogen storage material. Metal aminoboranes can be included in a kit. U.S. Patent No.: 7,713,506 (DOE S-112,798)

258

The largest radioactive waste glassification  

NLE Websites -- All DOE Office Websites (Extended Search)

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

259

Development of long-term performance models for radioactive waste forms  

SciTech Connect

The long-term performance of solid radioactive waste is measured by the release rate of radionuclides into the environment, which depends on corrosion or weathering rates of the solid waste form. The reactions involved depend on the characteristics of the solid matrix containing the radioactive waste, the radionuclides of interest, and their interaction with surrounding geologic materials. This chapter describes thermo-hydro-mechanical and reactive transport models related to the long-term performance of solid radioactive waste forms, including metal, ceramic, glass, steam reformer and cement. Future trends involving Monte-Carlo simulations and coupled/multi-scale process modeling are also discussed.

Bacon, Diana H.; Pierce, Eric M.

2011-03-22T23:59:59.000Z

260

FUEL ELEMENTS FOR THERMAL-FISSION NUCLEAR REACTORS  

DOE Patents (OSTI)

Fuel elements for thermal-fission nuclear reactors are described. The fuel element is comprised of a core of alumina, a film of a metal of the class consisting of copper, silver, and nickel on the outer face of the core, and a coating of an oxide of a metal isotope of the class consisting of Un/sup 235/, U/ sup 233/, and Pu/sup 239/ on the metal f ilm.

Flint, O.

1961-01-10T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

NUCLEAR REACTOR FUEL ELEMENTS AND METHOD OF PREPARATION  

DOE Patents (OSTI)

A fuel element consisting of uranium nitride and uranium carbide in the form of discrete particles in a solid coherent matrix of a metal such as steel, beryllium, uranium, or zirconium and clad with a metal such as steel, aluminum, zirconium, or beryllium is described. The element is made by mixing powdered uranium nitride and uranium carbide with powdered matrix metal, then compacting and sintering the mixture. (AEC)

Kingston, W.E.; Kopelman, B.; Hausner, H.H.

1963-07-01T23:59:59.000Z

262

Process for removing technetium from iron and other metals  

DOE Patents (OSTI)

Technetium is a radioactive product of the nuclear fission process. During reprocessing of spent or partially spent fuel from nuclear reactors, the technetium can be released and contaminate other, otherwise good, metals. A specific example is equipment in gaseous diffusion uranium enrichment cascades which have been used to process fuel which was returned from reactors, so-called reactor returns. These returns contained volatile technetium compounds which contaminated the metals in the equipment. Present regulations require that technetium be removed before the metal can be re-used at non-radioactive sites. Removing the technetium from contaminated metals has two desirable results. First, the large amount of nonradioactive metal produced by the process herein described can be recycled at a much lower cost than virgin metal can be produced. Second, large amounts of radioactively contaminated metal can be reduced to relatively small amounts of radioactive slag and large amounts of essentially uncontaminated metal. A new and improved process for removing technetium from iron and other metals is described in which between 1/10 atom % and 5 atom % of manganese is added to the contaminated metal in order to replace the technetium.

Leitnaker, James M.; Trowbridge, Lee D.

1997-12-01T23:59:59.000Z

263

Radioactivity of the Cooling Water  

DOE R&D Accomplishments (OSTI)

The most important source of radioactivity at the exit manifold of the pile will be due to O{sup 19}, formed by neutron absorption of O{sup 18}. A recent measurement of Fermi and Weil permits to estimate that it will be safe to stay about 80 minutes daily close to the exit manifolds without any shield. Estimates are given for the radioactivities from other sources both in the neighborhood and farther away from the pile.

Wigner, E. P.

1943-03-01T23:59:59.000Z

264

Storage depot for radioactive material  

Science Conference Proceedings (OSTI)

Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

Szulinski, Milton J. (Richland, WA)

1983-01-01T23:59:59.000Z

265

Storage depot for radioactive material  

SciTech Connect

Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

Szulinski, M.J.

1983-10-18T23:59:59.000Z

266

Emergency Responder Radioactive Material Quick Reference Sheet...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Transportation Emergency Preparedness Program (TEPP) Emergency Responder Radioactive Material Quick Reference Sheet...

267

Emergency Tests Focus on Lab Radioactivity Analyses  

Science Conference Proceedings (OSTI)

Emergency Tests Focus on Lab Radioactivity Analyses. For Immediate ... Berne. Radioanalytical emergency response exercise. Journal ...

2013-09-05T23:59:59.000Z

268

CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect

The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to advance nuclear science. It was this defense application that formed the basis for the commercial nuclear power industry.

Marra, J.

2010-05-05T23:59:59.000Z

269

Introduction to naturally occurring radioactive material  

SciTech Connect

Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our bodies, the food we eat, the places where we live and work, and in products we use. We are also bathed in a sea of natural radiation coming from the sun and deep space. Living systems have adapted to these levels of radiation and radioactivity. But some industrial practices involving natural resources concentrate these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. Other activities, such as flying at high altitudes, expose us to elevated levels of NORM. This session will concentrate on diffuse sources of technologically-enhanced (TE) NORM, which are generally large-volume, low-activity waste streams produced by industries such as mineral mining, ore benefication, production of phosphate Fertilizers, water treatment and purification, and oil and gas production. The majority of radionuclides in TENORM are found in the uranium and thorium decay chains. Radium and its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of TENORM in the environment by human activity. We will briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms and volumes, but the levels of radioactivity in TENORM vary. Current discussions about the validity of the linear no dose threshold theory are central to the TENORM issue. TENORM is not regulated by the Atomic Energy Act or other Federal regulations. Control and regulation of TENORM is not consistent from industry to industry nor from state to state. Proposed regulations are moving from concentration-based standards to dose-based standards. So when is TENORM a problem? Where is it a problem? That depends on when, where, and whom you talk to! We will start by reviewing background radioactivity, then we will proceed to the geology, mobility, and variability of these radionuclides. We will then review some of the industrial sectors affected by TENORM, followed by a brief discussion on regulatory aspects of the issue.

Egidi, P.

1997-08-01T23:59:59.000Z

270

Control of the Accumulation of Non-Process Elements in Pulp Mills with Bleach Filtrate Reuse: A Chemical Equilibrium Approach to Predicting the Partitioning of Metals in Pulp Mill and Bleach Plant Streams  

DOE Green Energy (OSTI)

The overall goal of this project was to develop fundamental, experimentally based methods for predicting the solubility or organic and inorganic matter and their interactions in recycled effluent from kraft pulp mills and bleach plants. This included: characterizing the capacity of wood pulp and dissolved organic matter to bind metal ions, developing a thermodynamic database of properties needed to describe the solubility of inorganic matter in pulp mill streams, incorporation of the database into equilibrium calculation software for predicting the solubility of the metals of interest, and evaluating its capability to predict the distribution of the metals between pulp fibers, inorganic precipitates, and solution.

Frederick, W.J. Jr.; Rudie, A.W.; Schmidl, G.W.; Sinquefield, S.A.; Rorrer, G.L.; Laver, M.L.; Yantasee, W.; Ming, D.

2000-08-01T23:59:59.000Z

271

PROCESSING OF RADIOACTIVE WASTE  

DOE Patents (OSTI)

A process for concentrating fission-product-containing waste solutions from fuel element processing is described. The process comprises the addition of sugar to the solution, preferably after it is made alkaline; spraying the solution into a heated space whereby a dry powder is formed; heating the powder to at least 220 deg C in the presence of oxygen whereby the powder ignites, the sugar is converted to carbon, and the salts are decomposed by the carbon; melting the powder at between 800 and 900 deg C; and cooling the melt. (AEC) antidiuretic hormone from the blood by the liver. Data are summarized from the following: tracer studies on cardiovascular functions; the determination of serum protein-bound iodine; urinary estrogen excretion in patients with arvanced metastatic mammary carcinoma; the relationship between alheroclerosis aad lipoproteins; the physical chemistry of lipoproteins; and factors that modify the effects of densely ionizing radia

Allemann, R.T.; Johnson, B.M. Jr.

1961-10-31T23:59:59.000Z

272

Technical assessment of processes to enable recycling of low-level contaminated metal waste  

Science Conference Proceedings (OSTI)

Accumulations of metal waste exhibiting low levels of radioactivity (LLCMW) have become a national burden, both financially and environmentally. Much of this metal could be considered as a resource. The Department of Energy was assigned the task of inventorying and classifying LLCMW, identifying potential applications, and applying and/or developing the technology necessary to enable recycling. One application for recycled LLCMW is high-quality canisters for permanent repository storage of high-level waste (HLW). As many as 80,000 canisters will be needed by 2035. Much of the technology needed to decontaminate LLCMW has already been developed, but no integrated process has been described, even on a pilot scale, for recycling LLCMW into HLW canisters. This report reviews practices for removal of radionuclides and for producing low carbon stainless steel. Contaminants that readily form oxides may be reduced to below de minimis levels and combined with a slag. Most of the radioactivity remaining in the ingot is concentrated in the inclusions. Radionuclides that chemically resemble the elements that comprise stainless steel can not be removed effectively. Slag compositions, current melting practices, and canister fabrication techniques were reviewed.

Reimann, G.A.

1991-10-01T23:59:59.000Z

273

Spontaneous Muon Emission during Fission, a New Nuclear Radioactivity  

E-Print Network (OSTI)

In this paper the essential theoretical predictions for the nuclear muonic radioactivity are presented by using a special fission-like model similar with that used in description of the pionic emission during fission. Hence, a fission-like model for the muonic radioactivity takes into account the essential degree of freedom of the system: muon-fissility, muon-fission barrier height, etc. Using this model it was shown that most of the SHE-nuclei lie in the region where the muonic fissility parameters attain their limiting value X=1. Hence, the SHE-region is characterized by the absence of a classical barrier toward spontaneous muon and pion emissions. Numerical estimations on the yields for the natural muonic radioactivities of the transuranium elements as well numerical values for barrier heights are given only for even-even parent nuclei. Some experimental results from LCP-identification emission spectrum are reviewed. Also, the experimental results obtained by Khryachkov et al, using new spectrometer for investigation of ternary nuclear fission, are presented. The OPERA-experiment proposed to perform search for muonic radioactivity from lead nuclei, in the low background conditions offered by the Gran Sasso underground Laboratory (LNGS), is discussed.

D. B. Ion; M. L. D. Ion; Reveica Ion-Mihai

2011-01-24T23:59:59.000Z

274

Storage containers for radioactive material  

DOE Patents (OSTI)

A radioactive material storage system is claimed for use in the laboratory having a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof, a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate, the groove and the gasket, and a clamp for maintaining the cover and the plate sealed together. The plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage.

Groh, E.F.; Cassidy, D.A.; Dates, L.R.

1980-07-31T23:59:59.000Z

275

Investigations on the sediment chronology and trace metal accumulation in Sabine-Neches estuary, Beaumont, Texas  

E-Print Network (OSTI)

The accumulation rates of sediments and trace metals (Co, Cr, Cu, Ni, Pb, Zn) were measured along with the concentrations of Al, Fe, Mn and organic carbon in four sediment cores from Sabine-Neches estuary, near Beaumont, Texas. A reliable geochronology of sediments and reconstruction of the history of trace metal inputs into this shallow estuarine environment was possible because the 239,240pu profiles closely tracked the bomb fallout history into the environment. The sedimentation rate was estimated to be about 4-5 mm/yr. Due to the very low and variable activities of excess 21OPb in the sediments, the 21OPb dating method did not prove to be very useful in the study area. One difficulty had to do with the large variability of grain size parameters in the sediments. The amount of fines varied from 90% within a single core. The activities of excess 21OPb and the concentrations of Al, Fe, organic carbon, and trace metals varied as a function of the amount of fine particles. 21OPb at the bottom of the sediment cores was in secular equilibrium with 226Ra, 23OTh, and 234U in some cores, while in others, this was not the case. The reasons for disagreement between 21OPb and 226Ra concentrations at depth were investigated. The mixing rates of surface sediments were low and was about 0.16-0.40 cm2yr-1. Down core variations of aluminum normalized enrichment factors for trace metals demonstrated that, since 1860, the sediments of this estuary have remained relatively "pristine" with respect to trace metal concentrations. While the concentrations of Pb and Zn in some sections of the sediment column were slightly enriched, Co, Cr, Cu, and Ni were depleted in all sediment cores analyzed. No significant enrichment of light rare earth elements was observed. Enrichment might have been expected from inputs of cracking catalysts used in refineries. Therefore REEs could not be used as non-steady tracers. The lack of strong enrichment of trace metals, light rare earth elements, and low inventories of radioisotopes could be a result of the short residence time of the estuarine water, long removal residence times of trace metals and radioactive elements in the water column, low salinity conditions, and possibly, complexation of these metals with dissolved organic matter.

Ravichandran, Mahalingam

1994-01-01T23:59:59.000Z

276

PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM CONTAMINATING ELEMENTS  

DOE Patents (OSTI)

This patent relates to an improved method for the decontamination of plutonium. The process consists broadly in an improvement in a method for recovering plutonium from radioactive uranium fission products in aqueous solutions by decontamination steps including byproduct carrier precipitation comprising the step of introducing a preformed aqueous slurry of a hydroxide of a metal of group IV B into any aqueous acidic solution which contains the plutonium in the hexavalent state, radioactive uranium fission products contaminant and a by-product carrier precipitate and separating the metal hydroxide and by-product precipitate from the solution. The process of this invention is especially useful in the separation of plutonium from radioactive zirconium and columbium fission products.

Sutton, J.B.

1958-02-18T23:59:59.000Z

277

INSPECTION OF THE ACCOUNTABILITY AND CONTROL OF SEALED RADIOACTIVE...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

OF THE ACCOUNTABILITY AND CONTROL OF SEALED RADIOACTIVE SOURCES AT SELECTED DEPARTMENT OF ENERGY SITES, IG-0544 Sealed radioactive sources consist of radioactive material either...

278

Feasibility analysis of recycling radioactive scrap steel  

SciTech Connect

The purpose of this study is to: (1) establish a conceptual design that integrates commercial steel mill technology with radioactive scrap metal (RSM) processing to produce carbon and stainless steel sheet and plate at a grade suitable for fabricating into radioactive waste containers; (2) determine the economic feasibility of building a micro-mill in the Western US to process 30,000 tons of RSM per year from both DOE and the nuclear utilities; and (3) provide recommendations for implementation. For purposes of defining the project, it is divided into phases: economic feasibility and conceptual design; preliminary design; detail design; construction; and operation. This study comprises the bulk of Phase 1. It is divided into four sections. Section 1 provides the reader with a complete overview extracting pertinent data, recommendations and conclusions from the remainder of the report. Section 2 defines the variables that impact the design requirements. These data form the baseline to create a preliminary conceptual design that is technically sound, economically viable, and capitalizes on economies of scale. Priorities governing the design activities are: (1) minimizing worker exposure to radionuclide hazards, (2) maximizing worker safety, (3) minimizing environmental contamination, (4) minimizing secondary wastes, and (5) establishing engineering controls to insure that the plant will be granted a license in the state selected for operation. Section 3 provides details of the preliminary conceptual design that was selected. The cost of project construction is estimated and the personnel needed to support the steel-making operation and radiological and environmental control are identified. Section 4 identifies the operational costs and supports the economic feasibility analysis. A detailed discussion of the resulting conclusions and recommendations is included in this section.

Nichols, F. [Manufacturing Sciences Corp., Woodland, WA (United States); Balhiser, B. [MSE, Inc., Butte, MT (United States); Cignetti, N. [Cignetti Associates, North Canton, OH (United States)] [and others

1995-09-01T23:59:59.000Z

279

THE USE OF POLYMERS IN RADIOACTIVE WASTE PROCESSING SYSTEMS  

SciTech Connect

The Savannah River Site (SRS), one of the largest U.S. Department of Energy (DOE) sites, has operated since the early 1950s. The early mission of the site was to produce critical nuclear materials for national defense. Many facilities have been constructed at the SRS over the years to process, stabilize and/or store radioactive waste and related materials. The primary materials of construction used in such facilities are inorganic (metals, concrete), but polymeric materials are inevitably used in various applications. The effects of aging, radiation, chemicals, heat and other environmental variables must therefore be understood to maximize service life of polymeric components. In particular, the potential for dose rate effects and synergistic effects on polymeric materials in multivariable environments can complicate compatibility reviews and life predictions. The selection and performance of polymeric materials in radioactive waste processing systems at the SRS are discussed.

Skidmore, E.; Fondeur, F.

2013-04-15T23:59:59.000Z

280

The New Element Californium (Atomic Number 98)  

DOE R&D Accomplishments (OSTI)

Definite identification has been made of an isotope of the element with atomic number 98 through the irradiation of Cm{sup 242} with about 35-Mev helium ions in the Berkeley Crocker Laboratory 60-inch cyclotron. The isotope which has been identified has an observed half-life of about 45 minutes and is thought to have the mass number 244. The observed mode of decay of 98{sup 244} is through the emission of alpha-particles, with energy of about 7.1 Mev, which agrees with predictions. Other considerations involving the systematics of radioactivity in this region indicate that it should also be unstable toward decay by electron capture. The chemical separation and identification of the new element was accomplished through the use of ion exchange adsorption methods employing the resin Dowex-50. The element 98 isotope appears in the eka-dysprosium position on elution curves containing berkelium and curium as reference points--that is, it precedes berkelium and curium off the column in like manner that dysprosium precedes terbium and gadolinium. The experiments so far have revealed only the tripositive oxidation state of eka-dysprosium character and suggest either that higher oxidation states are not stable in aqueous solutions or that the rates of oxidation are slow. The successful identification of so small an amount of an isotope of element 98 was possible only through having made accurate predictions of the chemical and radioactive properties.

Seaborg, G. T.; Thompson, S. G.; Street, K. Jr.; Ghiroso, A.

1950-06-19T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Environmental Radioactivity in the Faroes  

E-Print Network (OSTI)

IN THE FAROES IN 1979 A. Aarkroo and J. Lippert Abstract. Measurements of fallout radioactivity in the Faroes Descriptors [0] DIET, ENVIRONMENT, EXPERIMENTAL DATA, FAROE ISLANDS, FISHES, FOOD, FOOD CHAINS, GLOBAL FALLOUT 62°N #12;- 7 - 1. INTRODUCTION 1*1*. The fallout programme for the Faroes, which was initiated

282

Nonaqueous method for dissolving lanthanide and actinide metals  

DOE Patents (OSTI)

Lanthanide and actinide beta-diketonate complex molecular compounds are produced by reacting a beta-diketone compound with a lanthanide or actinide element in the elemental metallic state in a mixture of carbon tetrachloride and methanol.

Crisler, L.R.

1975-11-11T23:59:59.000Z

283

Properties of Energetic Materials Reinforced by Open-Cell Metal ...  

Science Conference Proceedings (OSTI)

Thus the idea of using open-cell metal foams as heat conducting elements seems ... Composites Fabricated by Mechanical Alloying and Vacuum Hot Pressing.

284

The Radioactive Beam Program at Argonne  

E-Print Network (OSTI)

In this talk I will present selected topics of the ongoing radioactive beam program at Argonne and discuss the capabilities of the CARIBU radioactive ion production facility as well as plans for construction of a novel superconducting solenoid spectrometer.

B. B. Back

2006-06-06T23:59:59.000Z

285

Numerical simulation of high-level radioactive nuclear waste glass production  

SciTech Connect

Vitrification of radioactive waste has become an international approach for converting highly radioactive wastes into a durable solid prior to placing them in a permanent disposal repository. The technology for the process is not new. The conversion melter is a direct descendant of all electric melters used for manufacturing of some commercial glass types. Therefore, the vitrification process of radioactive wastes inherits typical problems of all electric furnaces and creates some other specific problems such as noble metal sedimentation. The noble metals and nickel sulfides in the melter are heavier than molten glass and have a low solubility. In a reducing condition, these metals amalgamate and tend to settle on the melter floor. The metal deposit resulting from this settling has a potential to short circuit the melter. The objective of this paper is to identify the typical problems that have been encountered in the waste melter operations and to address how these problems can be tackled using state-of-the-art numerical simulation techniques. It is believed that the large amount of pilot-scale melter experience throughout the world, combined with the knowledge gained from state-of-the-art computer modeling techniques would give assurance that the existing and future radioactive wastes can be effectively converted into a durable glass material and safely placed in a permanent repository.

Choi, I.G. (Westinghouse Savannah River Co., Aiken, SC (United States)); Ungan, A. (Purdue Univ., Indianapolis, IN (United States). Dept. of Mechanical Engineering)

1991-01-01T23:59:59.000Z

286

Numerical simulation of high-level radioactive nuclear waste glass production  

SciTech Connect

Vitrification of radioactive waste has become an international approach for converting highly radioactive wastes into a durable solid prior to placing them in a permanent disposal repository. The technology for the process is not new. The conversion melter is a direct descendant of all electric melters used for manufacturing of some commercial glass types. Therefore, the vitrification process of radioactive wastes inherits typical problems of all electric furnaces and creates some other specific problems such as noble metal sedimentation. The noble metals and nickel sulfides in the melter are heavier than molten glass and have a low solubility. In a reducing condition, these metals amalgamate and tend to settle on the melter floor. The metal deposit resulting from this settling has a potential to short circuit the melter. The objective of this paper is to identify the typical problems that have been encountered in the waste melter operations and to address how these problems can be tackled using state-of-the-art numerical simulation techniques. It is believed that the large amount of pilot-scale melter experience throughout the world, combined with the knowledge gained from state-of-the-art computer modeling techniques would give assurance that the existing and future radioactive wastes can be effectively converted into a durable glass material and safely placed in a permanent repository.

Choi, I.G. [Westinghouse Savannah River Co., Aiken, SC (United States); Ungan, A. [Purdue Univ., Indianapolis, IN (United States). Dept. of Mechanical Engineering

1991-12-31T23:59:59.000Z

287

UK Radioactive Waste: Classification, Sources and Management ...  

Science Conference Proceedings (OSTI)

Paper contents outlook: Introduction; Radioactive waste classification; Sources of waste (Nuclear power plant operation/decommissioning, Reprocessing and...

288

NNSA: Securing Domestic Radioactive Material | National Nuclear...  

National Nuclear Security Administration (NNSA)

Securing Domestic Radioactive Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

289

4. Nuclei and Radioactivity Paradoxes and Puzzles  

E-Print Network (OSTI)

radioactivity, it may not be legally sold in the United States. 4. Of those killed by the Hiroshima atomic bomb anecdotes and say, "Of course." Radioactivity Radioactivity is the explosion of the nucleus of the atom nucleus of one atom is about million times greater than in a chemical explosion of a single atom

Browder, Tom

290

Supercritical Carbon Dioxide-Soluble Ligands for Extracting Actinide Metal Ions from Porous Solids  

SciTech Connect

Numerous types of actinide-bearing waste materials are found throughout the DOE complex. Most of these wastes consist of large volumes of non-hazardous materials contaminated with relatively small quantities of actinide elements. Separation of these wastes into their inert and radioactive components would dramatically reduce the costs of stabilization and disposal. For example, the DOE is responsible for decontaminating concrete within 7000 surplus contaminated buildings. The best technology now available for removing surface contamination from concrete involves removing the surface layer by grit blasting, which produces a large volume of blasting residue containing a small amount of radioactive material. Disposal of this residue is expensive because of its large volume and fine particulate nature. Considerable cost savings would result from separation of the radioactive constituents and stabilization of the concrete dust. Similarly, gas diffusion plants for uranium enrichment contain valuable high-purity nickel in the form of diffusion barriers. Decontamination is complicated by the extremely fine pores in these barriers, which are not readily accessible by most cleaning techniques. A cost-effective method for the removal of radioactive contaminants would release this valuable material for salvage. The objective of this project is to develop novel, substituted diphosphonic acid ligands that can be used for supercritical carbon dioxide extraction of actinide ions from solid wastes. Specifically, selected diphosphonic acids, which are known to form extremely stable complexes with actinides in aqueous and organic solution, are to be rendered carbon dioxide-soluble by the introduction of appropriate alkyl- or silicon-containing substituents. The metal complexation chemistry of these new ligands in SC-CO2 will then be investigated and techniques for their use in actinide extraction from porous solids developed.

Dietz, Mark L.

2001-06-01T23:59:59.000Z

291

Dispersal of radioactivity by wildlife from contaminated sites in a forested landscape  

SciTech Connect

Oak Ridge National Laboratory (ORNL) is located within the Valley and Ridge Physiographic Province of eastern Tennessee (USA). Wildlife populations have access to some radioactively contaminated sites at ORNL. Contaminated animals or animal nests within the Laboratory's boundaries have been found to contain {sup 90}Sr or {sup 137}Cs on the order of 10{sup -2}-10{sup 4} Bqg{sup -1} and trace amounts of other radionuclides (including transuranic elements). Animals that are capable of flight and animals with behavior patterns or developmental life stages involving contact with sediments in radioactive ponds, like benthic invertebrates, present the greatest potential for dispersal of radioactivity. The emigration of frogs and turtles from waste ponds also presents a potential for dispersal of radioactivity but over distances < 5 km. Mud-dauber wasps (Hymenoptera) and swallows (Hirundinidae) may transport radioactive mud for nest building, but also over relatively short distances (0.2-1 km). Movement by small mammals is limited by several factors, including physical barriers and smaller home ranges. Larger animals, like white-tailed deer (Odocoileus virginianus), are potential vectors of radioactivity due to their greater body size, longer life expectancy, and larger home range. Larger animals contain greater amounts of total radioactivity than smaller animals, but tissue concentrations of {sup 137}Cs generally decline with body size.

Garten Jr, Charles T [ORNL

1995-12-01T23:59:59.000Z

292

Light Metals  

Science Conference Proceedings (OSTI)

Alternative processes; Anode design and operation; Cell fundamentals and ... Hot-rolling technologies; Deformation of materials; Primary metal production.

293

TRACE ELEMENT ANALYSES OF URANIUM MATERIALS  

SciTech Connect

The Savannah River National Laboratory (SRNL) has developed an analytical method to measure many trace elements in a variety of uranium materials at the high part-per-billion (ppb) to low part-per-million (ppm) levels using matrix removal and analysis by quadrapole ICP-MS. Over 35 elements were measured in uranium oxides, acetate, ore and metal. Replicate analyses of samples did provide precise results however none of the materials was certified for trace element content thus no measure of the accuracy could be made. The DOE New Brunswick Laboratory (NBL) does provide a Certified Reference Material (CRM) that has provisional values for a series of trace elements. The NBL CRM were purchased and analyzed to determine the accuracy of the method for the analysis of trace elements in uranium oxide. These results are presented and discussed in the following paper.

Beals, D; Charles Shick, C

2008-06-09T23:59:59.000Z

294

WINCO Metal Recycle annual report, FY 1993  

Science Conference Proceedings (OSTI)

This report is a summary of the first year progress of the WINCO Metal Recycle Program. Efforts were directed towards assessment of radioactive scrap metal inventories, economics and concepts for recycling, technology development, and transfer of technology to the private sector. Seven DOE laboratories worked together to develop a means for characterizing scrap metal. Radioactive scrap metal generation rates were established for several of these laboratories. Initial cost estimates indicate that recycle may be preferable over burial if sufficient decontamination factors can be achieved during melt refining. Radiation levels of resulting ingots must be minimized in order to keep fabrication costs low. Industry has much of the expertise and capability to execute the recycling of radioactive scrap metal. While no single company can sort, melt, refine, roll and fabricate, a combination of two to three can complete this operation. The one process which requires development is in melt refining for removal of radionuclides other than uranium. WINCO is developing this capability in conjunction with academia and industry. This work will continue into FY-94.

Bechtold, T.E. [ed.

1993-12-01T23:59:59.000Z

295

Radioactive Waste Management BasisApril 2006  

Science Conference Proceedings (OSTI)

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2011-08-31T23:59:59.000Z

296

Laser ion source development at Holifield Radioactive Ion Beam Facility  

Science Conference Proceedings (OSTI)

This report describes the efforts made to develop a resonant-ionization laser ion source based on tunable Ti:sapphire lasers for nuclear physics and astrophysics research at Holifield Radioactive Ion Beam Facility. Three Ti:sapphire lasers have been upgraded with individual pump lasers to eliminate laser power losses due to synchronization delays. Ionization schemes for 14 elements have been obtained. Off-line studies show that the overall efficiency of the laser ion source can be as high as 40%. TaC surface coatings have been investigated for minimizing surface and bulk trapping of the atoms of interest.

Liu, Y.; Havener, C. C.; Beene, J. R. [Physics Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States); Gottwald, T.; Mattolat, C.; Vane, C. R.; Wendt, K. [Institute of Physics, University of Mainz, D-55099 Mainz (Germany); Howe, J. Y.; Kiggans, J. [Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

2012-02-15T23:59:59.000Z

297

Recoverable immobilization of transuranic elements in sulfate ash  

DOE Patents (OSTI)

Disclosed is a method of reversibly immobilizing sulfate ash at least about 20% of which is sulfates of transuranic elements. The ash is mixed with a metal which can be aluminum, cerium, samarium, europium, or a mixture thereof, in amounts sufficient to form an alloy with the transuranic elements, plus an additional amount to reduce the transuranic element sulfates to elemental form. Also added to the ash is a fluxing agent in an amount sufficient to lower the percentage of the transuranic element sulfates to about 1% to about 10%. The mixture of the ash, metal, and fluxing agent is heated to a temperature sufficient to melt the fluxing agent and the metal. The mixture is then cooled and the alloy is separated from the remainder of the mixture.

Greenhalgh, Wilbur O. (Richland, WA)

1985-01-01T23:59:59.000Z

298

Reduction of Metal Oxide to Metal using Ionic Liquids  

Science Conference Proceedings (OSTI)

A novel pathway for the high efficiency production of metal from metal oxide means of electrolysis in ionic liquids at low temperature was investigated. The main emphasis was to eliminate the use of carbon and high temperature application in the reduction of metal oxides to metals. The emphasis of this research was to produce metals such as Zn, and Pb that are normally produced by the application of very high temperatures. The reduction of zinc oxide to zinc and lead oxide to lead were investigated. This study involved three steps in accomplishing the final goal of reduction of metal oxide to metal using ionic liquids: 1) Dissolution of metal oxide in an ionic liquid, 2) Determination of reduction potential using cyclic voltammetry (CV) and 3) Reduction of the dissolved metal oxide. Ionic liquids provide additional advantage by offering a wide potential range for the deposition. In each and every step of the process, more than one process variable has been examined. Experimental results for electrochemical extraction of Zn from ZnO and Pb from PbO using eutectic mixtures of Urea ((NH2)2CO) and Choline chloride (HOC2H4N(CH3)3+Cl-) or (ChCl) in a molar ratio 2:1, varying voltage and temperatures were carried out. Fourier Transform Infra-Red (FTIR) spectroscopy studies of ionic liquids with and without metal oxide additions were conducted. FTIR and induction coupled plasma spectroscopy (ICPS) was used in the characterization of the metal oxide dissolved ionic liquid. Electrochemical experiments were conducted using EG&G potentiostat/galvanostat with three electrode cell systems. Cyclic voltammetry was used in the determination of reduction potentials for the deposition of metals. Chronoamperometric experiments were carried out in the potential range of -0.6V to -1.9V for lead and -1.4V to -1.9V for zinc. The deposits were characterized using XRD and SEM-EDS for phase, morphological and elemental analysis. The results showed that pure metal was deposited on the cathode. Successful extraction of metal from metal oxide dissolved in Urea/ChCl (2:1) was accomplished. The current efficiencies were relatively high in both the metal deposition processes with current efficiency greater than 86% for lead and 95% for zinc. This technology will advance the metal oxide reduction process by increasing the process efficiency and also eliminate the production of CO2 which makes this an environmentally benign technology for metal extraction.

Dr. Ramana Reddy

2012-04-12T23:59:59.000Z

299

Radioactivity  

Science Conference Proceedings (OSTI)

... Mixed-alpha-emitting sources may be calibrated using the 2 ? proportional counter and the percentage per radionuclide is determined using a ...

2013-07-27T23:59:59.000Z

300

Radioactivity  

NLE Websites -- All DOE Office Websites (Extended Search)

and allows the nucleus to achieve a more stable, lower energy configuration. Spontaneous fission of a large-mass nucleus into smaller-mass products is also a form of...

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

The Eight New Synthetic Elements  

SciTech Connect

In an early continuation of the investigation of the radioactive isotopes of element number 43 (technetium) Segre and Seaborg produced by the deuteron and neutron bombardment of molybdenum the isotope Tc{sup 99}, which they observed to decay by means of an isomeric transition with a half-life of 6.6 hours to a lower isomeric state with a half-life greater than 40 years. The upper isomeric state of this isotope was observed by Segre and C. S. Wu to be produced in the fission of uranium and more recently R. P. Schumann and also D. C. Lincoln and W. H Sullivan working on the Plutonium Project of the Manhattan District have independently observed the beta-particles of half-life about 10 years due to the lower isomeric state. Later work by E. E. Motta and G. E. Boyd sets a more accurate value of 9.4 x 10{sup 5} years for this half-life. Since this isotope is formed in rather large amounts, namely, a fission yield of 6.2%, in the slow neutron induced fission of uranium it is now possible to isolate technetium in weighable amounts and in rather substantial quantities. For example, a uranium pile operating at a power level of 10{sup 5} kw would produce about four grams of technetium, as the isotope T{sup 99}, per day. With such a long half-life the radioactivity associated with convenient amounts (some mg.) would be so small in intensity as to not create a problem provided reasonable care in handling were exercised.

Seaborg, Glenn T.

1947-11-01T23:59:59.000Z

302

Precious Metals  

Science Conference Proceedings (OSTI)

"Advances in the Extractive Metallurgy of Selected Rare and Precious Metals" ( 1991 Review of Extractive Metallurgy), J.E. Hoffmann, April 1991, pp. 18-23.

303

Radioactive Waste Management BasisSept 2001  

SciTech Connect

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Goodwin, S S

2011-08-31T23:59:59.000Z

304

Process for reducing radioactive contamination in phosphogypsum  

Science Conference Proceedings (OSTI)

A process of two crystallization stages for reducing radioactive contamination of phosphogypsum is disclosed. In the process anhydrite crystals are obtained through dehydration of the radiation containing phosphogypsum in strong sulfuric acid; a portion of the anhydrite crystals containing the radioactive contamination is converted to substantially radiation free gypsum by crystallizing out on a large solids concentration of radiation free gypsum seed crystals; and coarse radiation free gypsum crystals are separated from small anhydrite crystal relics containing substantially all of the radioactive contamination.

Gaynor, J.C.; Palmer, J.W.

1983-06-14T23:59:59.000Z

305

WEB RESOURCE: Radioactive Waste Management in Australia  

Science Conference Proceedings (OSTI)

May 8, 2007 ... A glossary of terms and public discussion papers on current and past projects are included. Citation: "Radioactive Waste Management in...

306

Uranium Compounds and Other Natural Radioactivities  

NLE Websites -- All DOE Office Websites (Extended Search)

X-ray Science Division XSD Groups Industry Argonne Home Advanced Photon Source Uranium Compounds and Other Natural Radioactivities Uranium containing compounds and other...

307

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

of radioactive material are determined by the Nuclear Regulatory Commission (NRC), Department of Transportation (DOT), Department of Energy (DOE), and U.S. Postal...

308

Radioactive Material or Multiple Hazardous Materials Decontamination  

Energy.gov (U.S. Department of Energy (DOE))

The purpose of this procedure is to provide guidance for performing decontamination ofindividuals who have entered a hot zone during transportation incidents involving radioactive.

309

Radiation Machines and Radioactive Materials (Iowa)  

Energy.gov (U.S. Department of Energy (DOE))

These chapters describe general provisions and regulatory requirements; registration, licensure, and transportation of radioactive materials; and exposure standards for radiation protection.

310

Radiation Sources and Radioactive Materials (Connecticut)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations apply to persons who receive, transfer, possess, manufacture, use, store, handle, transport or dispose of radioactive materials and/or sources of ionizing radiation. Some...

311

Riso-R-489LK Environmental Radioactivity  

E-Print Network (OSTI)

Abstract. Measurements of fallout radioactivity in Greenland in 1982 are reported. Strontium-90 (and Cesium Descriptors [0] DEER, DIET, ENVIRONMENT, EXPERIMENTAL DATA, FISHES, POOD CHAINS, GLOBAL FALLOUT, GRAPHS

312

'^^ Ris-R-449 Environmental Radioactivity  

E-Print Network (OSTI)

, Sweden Abstract. Measurements of fallout radioactivity in Greenland in 1980 are reported. Strontium-90. INIS Descriptors [O] DEER, DIET, ENVIRONMENT, EXPERIMENTAL DATA, PISHES, POOD CHAINS, GLOBAL FALLOUT

313

Radioactive Materials Transportation and Incident Response  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

FEMA 358, 0510 Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program U.S. Department of Energy TRANSPORTATION AND INCIDENT RESPONSE Q&A About Incident Response Q...

314

It's Elemental - Isotopes of the Element Boron  

NLE Websites -- All DOE Office Websites (Extended Search)

Beryllium Beryllium Previous Element (Beryllium) The Periodic Table of Elements Next Element (Carbon) Carbon Isotopes of the Element Boron [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 10 19.9% STABLE 11 80.1% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 6 No Data Available Double Proton Emission (suspected) No Data Available 7 3.255×10-22 seconds Proton Emission No Data Available Alpha Decay No Data Available 8 770 milliseconds Electron Capture 100.00% Electron Capture with delayed Alpha Decay 100.00% 9 8.439×10-19 seconds Proton Emission 100.00% Double Alpha Decay 100.00%

315

It's Elemental - Isotopes of the Element Tungsten  

NLE Websites -- All DOE Office Websites (Extended Search)

Tantalum Tantalum Previous Element (Tantalum) The Periodic Table of Elements Next Element (Rhenium) Rhenium Isotopes of the Element Tungsten [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 180 0.12% >= 6.6×10+17 years 182 26.50% STABLE 183 14.31% > 1.3×10+19 years 184 30.64% STABLE 186 28.43% > 2.3×10+19 years Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 157 275 milliseconds Electron Capture No Data Available 158 1.25 milliseconds Alpha Decay 100.00% 158m 0.143 milliseconds Isomeric Transition No Data Available Alpha Decay No Data Available 159 7.3 milliseconds Alpha Decay ~ 99.90%

316

It's Elemental - Isotopes of the Element Radon  

NLE Websites -- All DOE Office Websites (Extended Search)

Astatine Astatine Previous Element (Astatine) The Periodic Table of Elements Next Element (Francium) Francium Isotopes of the Element Radon [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Radon has no naturally occurring isotopes. Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 193 1.15 milliseconds Alpha Decay 100.00% 194 0.78 milliseconds Alpha Decay 100.00% 195 6 milliseconds Alpha Decay 100.00% 195m 5 milliseconds Alpha Decay 100.00% 196 4.4 milliseconds Alpha Decay 99.90% Electron Capture ~ 0.10% 197 53 milliseconds Alpha Decay 100.00% 197m 25 milliseconds Alpha Decay 100.00% 198 65 milliseconds Alpha Decay No Data Available

317

It's Elemental - Isotopes of the Element Carbon  

NLE Websites -- All DOE Office Websites (Extended Search)

Boron Boron Previous Element (Boron) The Periodic Table of Elements Next Element (Nitrogen) Nitrogen Isotopes of the Element Carbon [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 12 98.93% STABLE 13 1.07% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 8 1.981×10-21 seconds Proton Emission 100.00% Alpha Decay No Data Available 9 126.5 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 61.60% Electron Capture with delayed Alpha Decay 38.40% 10 19.308 seconds Electron Capture 100.00% 11 20.334 minutes Electron Capture 100.00% 12 STABLE - -

318

It's Elemental - Isotopes of the Element Rhenium  

NLE Websites -- All DOE Office Websites (Extended Search)

Tungsten Tungsten Previous Element (Tungsten) The Periodic Table of Elements Next Element (Osmium) Osmium Isotopes of the Element Rhenium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 185 37.40% STABLE 187 62.60% 4.33×10+10 years Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 159 No Data Available No Data Available No Data Available 160 0.82 milliseconds Proton Emission 91.00% Alpha Decay 9.00% 161 0.44 milliseconds Proton Emission 100.00% Alpha Decay <= 1.40% 161m 14.7 milliseconds Alpha Decay 93.00% Proton Emission 7.00% 162 107 milliseconds Alpha Decay 94.00% Electron Capture 6.00%

319

It's Elemental - Isotopes of the Element Magnesium  

NLE Websites -- All DOE Office Websites (Extended Search)

Sodium Sodium Previous Element (Sodium) The Periodic Table of Elements Next Element (Aluminum) Aluminum Isotopes of the Element Magnesium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 24 78.99% STABLE 25 10.00% STABLE 26 11.01% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 19 4.0 picoseconds Double Proton Emission 100.00% 20 90.8 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission ~ 27.00% 21 122 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 32.60% Electron Capture with delayed Alpha Decay < 0.50%

320

It's Elemental - Isotopes of the Element Chlorine  

NLE Websites -- All DOE Office Websites (Extended Search)

Sulfur Sulfur Previous Element (Sulfur) The Periodic Table of Elements Next Element (Argon) Argon Isotopes of the Element Chlorine [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 35 75.76% STABLE 37 24.24% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 28 No Data Available Proton Emission (suspected) No Data Available 29 < 20 nanoseconds Proton Emission No Data Available 30 < 30 nanoseconds Proton Emission No Data Available 31 150 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 0.70% 32 298 milliseconds Electron Capture 100.00%

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

It's Elemental - Isotopes of the Element Potassium  

NLE Websites -- All DOE Office Websites (Extended Search)

Argon Argon Previous Element (Argon) The Periodic Table of Elements Next Element (Calcium) Calcium Isotopes of the Element Potassium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 39 93.2581% STABLE 40 0.0117% 1.248×10+9 years 41 6.7302% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 32 No Data Available Proton Emission (suspected) No Data Available 33 < 25 nanoseconds Proton Emission No Data Available 34 < 25 nanoseconds Proton Emission No Data Available 35 178 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 0.37% 36 342 milliseconds Electron Capture 100.00%

322

It's Elemental - Isotopes of the Element Phosphorus  

NLE Websites -- All DOE Office Websites (Extended Search)

Silicon Silicon Previous Element (Silicon) The Periodic Table of Elements Next Element (Sulfur) Sulfur Isotopes of the Element Phosphorus [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 31 100% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 24 No Data Available Electron Capture (suspected) No Data Available Proton Emission (suspected) No Data Available 25 < 30 nanoseconds Proton Emission 100.00% 26 43.7 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission No Data Available 27 260 milliseconds Electron Capture 100.00% Electron Capture with

323

It's Elemental - Isotopes of the Element Francium  

NLE Websites -- All DOE Office Websites (Extended Search)

Radon Radon Previous Element (Radon) The Periodic Table of Elements Next Element (Radium) Radium Isotopes of the Element Francium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Francium has no naturally occurring isotopes. Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 199 12 milliseconds Alpha Decay > 0.00% Electron Capture No Data Available 200 49 milliseconds Alpha Decay 100.00% 201 62 milliseconds Alpha Decay 100.00% 201m 19 milliseconds Alpha Decay 100.00% 202 0.30 seconds Alpha Decay 100.00% 202m 0.29 seconds Alpha Decay 100.00% 203 0.55 seconds Alpha Decay <= 100.00% 204 1.8 seconds Alpha Decay 92.00%

324

It's Elemental - Isotopes of the Element Oxygen  

NLE Websites -- All DOE Office Websites (Extended Search)

Nitrogen Nitrogen Previous Element (Nitrogen) The Periodic Table of Elements Next Element (Fluorine) Fluorine Isotopes of the Element Oxygen [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 16 99.757% STABLE 17 0.038% STABLE 18 0.205% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 12 1.139×10-21 seconds Proton Emission No Data Available 13 8.58 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 100.00% 14 70.620 seconds Electron Capture 100.00% 15 122.24 seconds Electron Capture 100.00% 16 STABLE - - 17 STABLE - - 18 STABLE - - 19 26.88 seconds Beta-minus Decay 100.00%

325

It's Elemental - Isotopes of the Element Gallium  

NLE Websites -- All DOE Office Websites (Extended Search)

Zinc Zinc Previous Element (Zinc) The Periodic Table of Elements Next Element (Germanium) Germanium Isotopes of the Element Gallium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 69 60.108% STABLE 71 39.892% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 56 No Data Available Proton Emission (suspected) No Data Available 57 No Data Available Proton Emission (suspected) No Data Available 58 No Data Available Proton Emission (suspected) No Data Available 59 No Data Available Proton Emission (suspected) No Data Available 60 70 milliseconds Electron Capture 98.40%

326

It's Elemental - Isotopes of the Element Sodium  

NLE Websites -- All DOE Office Websites (Extended Search)

Neon Neon Previous Element (Neon) The Periodic Table of Elements Next Element (Magnesium) Magnesium Isotopes of the Element Sodium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 23 100% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 18 1.3×10-21 seconds Proton Emission 100.00% 19 < 40 nanoseconds Proton Emission No Data Available 20 447.9 milliseconds Electron Capture with delayed Alpha Decay 20.05% Electron Capture 100.00% 21 22.49 seconds Electron Capture 100.00% 22 2.6027 years Electron Capture 100.00% 23 STABLE - - 24 14.997 hours Beta-minus Decay 100.00%

327

It's Elemental - Isotopes of the Element Neon  

NLE Websites -- All DOE Office Websites (Extended Search)

Fluorine Fluorine Previous Element (Fluorine) The Periodic Table of Elements Next Element (Sodium) Sodium Isotopes of the Element Neon [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 20 90.48% STABLE 21 0.27% STABLE 22 9.25% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 16 9×10-21 seconds Double Proton Emission 100.00% 17 109.2 milliseconds Electron Capture with delayed Alpha Decay No Data Available Electron Capture 100.00% Electron Capture with delayed Proton Emission 100.00% 18 1.6670 seconds Electron Capture 100.00% 19 17.22 seconds Electron Capture 100.00% 20 STABLE - -

328

It's Elemental - Isotopes of the Element Copper  

NLE Websites -- All DOE Office Websites (Extended Search)

Nickel Nickel Previous Element (Nickel) The Periodic Table of Elements Next Element (Zinc) Zinc Isotopes of the Element Copper [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 63 69.15% STABLE 65 30.85% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 52 No Data Available Proton Emission No Data Available 53 < 300 nanoseconds Electron Capture No Data Available Proton Emission No Data Available 54 < 75 nanoseconds Proton Emission No Data Available 55 27 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 15.0% 56 93 milliseconds Electron Capture 100.00%

329

Amorphous metal formulations and structured coatings for corrosion and wear resistance  

DOE Patents (OSTI)

A system for coating a surface comprising providing a source of amorphous metal that contains more than 11 elements and applying the amorphous metal that contains more than 11 elements to the surface by a spray. Also a coating comprising a composite material made of amorphous metal that contains more than 11 elements. An apparatus for producing a corrosion-resistant amorphous-metal coating on a structure comprises a deposition chamber, a deposition source in the deposition chamber that produces a deposition spray, the deposition source containing a composite material made of amorphous metal that contains more than 11 elements, and a system that directs the deposition spray onto the structure.

Farmer, Joseph C. (Tracy, CA)

2011-12-13T23:59:59.000Z

330

NEUTRONIC REACTOR CONTROL ELEMENT  

DOE Patents (OSTI)

A boron-10 containing reactor control element wherein the boron-10 is dispersed in a matrix material is describeri. The concentration of boron-10 in the matrix varies transversely across the element from a minimum at the surface to a maximum at the center of the element, prior to exposure to neutrons. (AEC)

Beaver, R.J.; Leitten, C.F. Jr.

1962-04-17T23:59:59.000Z

331

Measurement and finite element analysis of temperature distribution in arc welding process  

Science Conference Proceedings (OSTI)

This presentation describes both the experimental measurement and finite element analysis used to study the temperature distribution during a metal inert gas (MIG) welding process, including the cooling down period. Welding was carried out on ... Keywords: FEA, MIG welding, arc welding, cracking, finite element analysis, metal inert gas welding, residual stress, simulation, temperature distribution, weldment temperature

C. K. Lee; J. Candy; C. P. H. Tan

2004-12-01T23:59:59.000Z

332

Coming up with platinum substitutes may be elemental  

NLE Websites -- All DOE Office Websites (Extended Search)

Coming up with platinum substitutes may be elemental Coming up with platinum substitutes may be elemental Community Connections: Our link to Northern New Mexico Communities Latest Issue:Dec. 2013 - Jan. 2014 All Issues » submit Coming up with platinum substitutes may be elemental Lab researchers are working with an abundant element to take their place: cobalt. February 1, 2013 dummy image Read our archives. Contacts Editor Linda Anderman Email Community Programs Office Kurt Steinhaus Email Initial findings by a Los Alamos team indicate that if a cobalt atom is captured within a complex molecule, it can mimic the reactivity of platinum group metals. Platinum and some related precious metals (palladium, iridium, rhodium and ruthenium) are frequently used as chemical catalysts and for countless laboratory processes. As rare metals, they are also expensive. To ensure

333

Remote real time x-ray examination of fuel elements in a hot cell environment  

Science Conference Proceedings (OSTI)

This report discusses the Remote Real Time X-ray System which will allow for detailed examination of fuel elements. This task will be accomplished in a highly radioactive hot cell environment. Two remote handling systems win be utilized at the examination station. One handling system will transfer the fuel element to and from the shielded x-ray system. A second handling system will allow for vertical and rotational inspection of the fuel elements. The process win include removing a single nuclear fuel element from a element fabrication magazine(EFM), positioning the fuel element within the shielding envelope of the x-ray system and transferring the fuel element from the station manipulator to the x-ray system manipulator, performing the x-ray inspection, and then transferring the fuel element to either the element storage magazine(ESM) or a reject bin.

Yapuncich, F.L.

1993-01-01T23:59:59.000Z

334

Remote real time x-ray examination of fuel elements in a hot cell environment  

SciTech Connect

This report discusses the Remote Real Time X-ray System which will allow for detailed examination of fuel elements. This task will be accomplished in a highly radioactive hot cell environment. Two remote handling systems win be utilized at the examination station. One handling system will transfer the fuel element to and from the shielded x-ray system. A second handling system will allow for vertical and rotational inspection of the fuel elements. The process win include removing a single nuclear fuel element from a element fabrication magazine(EFM), positioning the fuel element within the shielding envelope of the x-ray system and transferring the fuel element from the station manipulator to the x-ray system manipulator, performing the x-ray inspection, and then transferring the fuel element to either the element storage magazine(ESM) or a reject bin.

Yapuncich, F.L.

1993-03-01T23:59:59.000Z

335

DISCHARGE DEVICE FOR RADIOACTIVE MATERIAL  

DOE Patents (OSTI)

A device is described fur unloading bodies of fissionable material from a neutronic reactor. It is comprised essentially of a wheeled flat car having a receptacle therein containing a liquid coolant fur receiving and cooling the fuel elements as they are discharged from the reactor, and a reciprocating plunger fur supporting the fuel element during discharge thereof prior to its being dropped into the coolant. The flat car is adapted to travel along the face of the reactor adjacent the discharge ends of the coolant tubes.

Ohlinger, L.A.

1958-09-23T23:59:59.000Z

336

Catalyst for elemental sulfur recovery process  

DOE Patents (OSTI)

A catalytic reduction process is described for the direct recovery of elemental sulfur from various SO[sub 2]-containing industrial gas streams. The catalytic process provides high activity and selectivity, as well as stability in the reaction atmosphere, for the reduction of SO[sub 2] to elemental sulfur product with carbon monoxide or other reducing gases. The reaction of sulfur dioxide and reducing gas takes place over a metal oxide composite catalyst having one of the following empirical formulas: [(FO[sub 2])[sub 1[minus]n](RO)[sub n

Flytzani-Stephanopoulos, M.; Liu, W.

1995-01-24T23:59:59.000Z

337

Compilation of current literature on seals, closures, and leakage for radioactive material packagings  

SciTech Connect

This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs.

Warrant, M.M.; Ottinger, C.A.

1989-01-01T23:59:59.000Z

338

HIGH TEMPERATURE TREATMENT OF INTERMEDIATE-LEVEL RADIOACTIVE WASTES - SIA RADON EXPERIENCE  

SciTech Connect

This review describes high temperature methods of low- and intermediate-level radioactive waste (LILW) treatment currently used at SIA Radon. Solid and liquid organic and mixed organic and inorganic wastes are subjected to plasma heating in a shaft furnace with formation of stable leach resistant slag suitable for disposal in near-surface repositories. Liquid inorganic radioactive waste is vitrified in a cold crucible based plant with borosilicate glass productivity up to 75 kg/h. Radioactive silts from settlers are heat-treated at 500-700 0C in electric furnace forming cake following by cake crushing, charging into 200 L barrels and soaking with cement grout. Various thermochemical technologies for decontamination of metallic, asphalt, and concrete surfaces, treatment of organic wastes (spent ion-exchange resins, polymers, medical and biological wastes), batch vitrification of incinerator ashes, calcines, spent inorganic sorbents, contaminated soil, treatment of carbon containing 14C nuclide, reactor graphite, lubricants have been developed and implemented.

Sobolev, I.A.; Dmitriev, S.A.; Lifanov, F.A.; Kobelev, A.P.; Popkov, V.N.; Polkanov, M.A.; Savkin, A.E.; Varlakov, A.P.; Karlin, S.V.; Stefanovsky, S.V.; Karlina, O.K.; Semenov, K.N.

2003-02-27T23:59:59.000Z

339

Diverter assembly for radioactive material  

DOE Patents (OSTI)

A diverter assembly for diverting a pneumatically conveyed holder for a radioactive material between a central conveying tube and one of a plurality of radially offset conveying tubes includes an airtight container. A diverter tube having an offset end is suitably mounted in the container for rotation. A rotary seal seals one end of the diverter tube during and after rotation of the diverter tube while a spring biased seal seals the other end of the diverter tube which moves between various offset conveying tubes. An indexing device rotatably indexes the diverter tube and this indexing device is driven by a suitable drive. The indexing mechanism is preferably a geneva-type mechanism to provide a locking of the diverter tube in place. 3 figs.

Andrews, K.M.; Starenchak, R.W.

1988-04-11T23:59:59.000Z

340

Radioactive Samples / Materials at the APS  

NLE Websites -- All DOE Office Websites (Extended Search)

Using Radioactive Samples / Materials at the APS Using Radioactive Samples / Materials at the APS The use of radioactive samples requires additional information for review and approval. All proposed experiments involving radioactive samples will be reviewed by the APS Radioactive Sample Safety Review Committee (RSSRC). The review will be on a graded basis. Hence, the experimenters are strongly advised to send in the experiment proposal in detail at least 2 months before the expected scheduled date of the experiment. Previously approved containment, isotopes and weights can be submitted as late as 2 weeks in advance. If your ESAF was submitted less than seven (7) days in advance of its scheduled start date you may be delayed to allow time for a safety review. The following guidelines are to be followed for all experiments with

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

APS Radioactive Sample Safety Review Committee  

NLE Websites -- All DOE Office Websites (Extended Search)

Radioactive Sample Safety Review Committee Radioactive Sample Safety Review Committee March 6, 2012 1. Purpose The APS Safety Radioactive Sample Safety Review Committee (RSSRC) advises the AES Division Director on the radioactive samples to be used at the APS and the adequacy of controls in place for the duration of their use. The RSSRC reviews the radioactive material samples proposed to be run at the APS to ensure that they fall within established safety envelopes of the APS. 2. Membership The RSSRC members are appointed by the AES Division Director. The current members of the RSRC are: B. Glagola AES - Chair S. Davey AES G. Pile AES L. Soderholm CHM J. Vacca RSO W. VanWingeren AES M. Beno XSD E. Alp XSD M. Rivers PUC 3. Method The AES User Safety Coordinator will notify the RSSRC of any samples

342

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

SAFE are radioactive material transportations packages? SAFE are radioactive material transportations packages? RAM PACKAGES TESTING & CERTIFICATION REGULATIONS & GUIDANCE SITE MAP This graphic was generated from a computer analysis and shows the results from a regulatory puncture test of a stainless steel packaging dropping 40 inches (10 MPH) onto a 6 inch diameter steel spike. U.S. DOE | Office of Civilian Radioactive Waste Management (OCRWM) Sandia National Laboratories | Nuclear Energy & Fuel Cucle Programs © Sandia Corporation | Site Contact | Sandia Site Map | Privacy and Security An internationally recognized web-site from PATRAM 2001 - the 13th International Symposium on the Packaging and Transportation of Radioactive Material. Recipient of the AOKI AWARD. PATRAM, sponsored by the U.S. Department of Energy in cooperation with the International Atomic Energy Agency brings government and industry leaders together to share information on innovations, developments, and lessons learned about radioactive materials packaging and transportation.

343

Apparatus and method for radioactive waste screening  

DOE Patents (OSTI)

An apparatus and method relating to screening radioactive waste are disclosed for ensuring that at least one calculated parameter for the measurement data of a sample falls within a range between an upper limit and a lower limit prior to the sample being packaged for disposal. The apparatus includes a radiation detector configured for detecting radioactivity and radionuclide content of the of the sample of radioactive waste and generating measurement data in response thereto, and a collimator including at least one aperture to direct a field of view of the radiation detector. The method includes measuring a radioactive content of a sample, and calculating one or more parameters from the radioactive content of the sample.

Akers, Douglas W.; Roybal, Lyle G.; Salomon, Hopi; Williams, Charles Leroy

2012-09-04T23:59:59.000Z

344

Lithium metal oxide electrodes for lithium batteries  

DOE Patents (OSTI)

An uncycled electrode for a non-aqueous lithium electrochemical cell including a lithium metal oxide having the formula Li.sub.(2+2x)/(2+x)M'.sub.2x/(2+x)M.sub.(2-2x)/(2+x)O.sub.2-.delta., in which 0.ltoreq.x<1 and .delta. is less than 0.2, and in which M is a non-lithium metal ion with an average trivalent oxidation state selected from two or more of the first row transition metals or lighter metal elements in the periodic table, and M' is one or more ions with an average tetravalent oxidation state selected from the first and second row transition metal elements and Sn. Methods of preconditioning the electrodes are disclosed as are electrochemical cells and batteries containing the electrodes.

Thackeray, Michael M. (Naperville, IL); Kim, Jeom-Soo (Naperville, IL); Johnson, Christopher S. (Naperville, IL)

2008-01-01T23:59:59.000Z

345

DISPERSION ELEMENT CONSISTING OF CHROMIUM COATED UO$sup 2$ PARTICLES UNIFORMLY DISTRIBUTED IN A ZIRCALOY MATRIX  

DOE Patents (OSTI)

A nuclear fuel element consisting of metal coated UO/sub 2/ particles dispersed in a matrix of Zircalloy and having a cladding of Zircalloy is presented. (AEC)

Cain, F.M. Jr.; Eck, J.E.

1963-05-01T23:59:59.000Z

346

Radioactive material package closures with the use of shape memory alloys  

SciTech Connect

When heated from room temperature to 165 C, some shape memory metal alloys such as titanium-nickel alloys have the ability to return to a previously defined shape or size with dimensional changes up to 7%. In contrast, the thermal expansion of most metals over this temperature range is about 0.1 to 0.2%. The dimension change of shape memory alloys, which occurs during a martensite to austenite phase transition, can generate stresses as high as 700 MPa (100 kspi). These properties can be used to create a closure for radioactive materials packages that provides for easy robotic or manual operations and results in reproducible, tamper-proof seals. This paper describes some proposed closure methods with shape memory alloys for radioactive material packages. Properties of the shape memory alloys are first summarized, then some possible alternative sealing methods discussed, and, finally, results from an initial proof-of-concept experiment described.

Koski, J.A.; Bronowski, D.R.

1997-11-01T23:59:59.000Z

347

WM'05 Conference, February 27 March 3, 2005, Tucson, AZ WM-5202 INTERNATIONAL APPROACH TO MONITORING FOR RADIOACTIVELY  

E-Print Network (OSTI)

acceptable scrap metal radiation monitoring and response protocol. Second, international training programs radiation exposure to workers and the public, this unwanted radioactive scrap material causes environmentalWM'05 Conference, February 27 ­ March 3, 2005, Tucson, AZ WM-5202 1 INTERNATIONAL APPROACH

348

Oxidation of hydrogen halides to elemental halogens  

DOE Patents (OSTI)

A process for oxidizing hydrogen halides having substantially no sulfur impurities by means of a catalytically active molten salt is disclosed. A mixture of the subject hydrogen halide and an oxygen bearing gas is contacted with a molten salt containing an oxidizing catalyst and alkali metal normal sulfates and pyrosulfates to produce an effluent gas stream rich in the elemental halogen and substantially free of sulfur oxide gases.

Rohrmann, Charles A. (Kennewick, WA); Fullam, Harold T. (Richland, WA)

1985-01-01T23:59:59.000Z

349

Finite element simulation of microphotonic lasing system  

SciTech Connect

We present a method for performing time domain simulations of a microphotonic system containing a four level gain medium based on the finite element method. This method includes an approximation that involves expanding the pump and probe electromagnetic fields around their respective carrier frequencies, providing a dramatic speedup of the time evolution. Finally, we present a two dimensional example of this model, simulating a cylindrical spaser array consisting of a four level gain medium inside of a metal shell.

Fietz, Chris; Soukoulis, Costas M.

2012-05-04T23:59:59.000Z

350

EA-1919: Recycle of Scrap Metals Originating from Radiological Areas |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EA-1919: Recycle of Scrap Metals Originating from Radiological EA-1919: Recycle of Scrap Metals Originating from Radiological Areas EA-1919: Recycle of Scrap Metals Originating from Radiological Areas Summary This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.) PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD December 28, 2012 EA-1919: Notice of Public Comment Period Extension Recycling of Scrap Metals Originating from Radiological Areas December 12, 2012 EA-1919: Notice of Availability of a Draft Programmatic Environmental

351

Metal-isonitrile adducts for preparing radionuclide complexes for labelling and imaging agents  

DOE Patents (OSTI)

A method for preparing a coordination complex of an isonitrile ligand and radionuclide such as Tc, Ru, Co, Pt, Fe, Os, Ir, W, Re, Cr, Mo, Mn, Ni, Rh, Pd, Nb and Ta is disclosed. The method comprises preparing a soluble metal adduct of said isonitrile ligand by admixing said ligand with a salt of a displaceable metal having a complete d-electron shell selected from the group consisting of Zn, Ga, Cd, In, Sn, Hg, Tl, Pb and Bi to form a soluble metal-isonitrile salt, and admixing said metal isonitrile salt with a salt comprising said radioactive metal in a suitable solvent to displace said displaceable metal with the radioactive metal thereby forming said coordination. The complex is useful as a diagnostic agent for labelling liposomes or vesicles, and selected living cells containing lipid membranes, such as blood clots, myocardial tissue, gall bladder tissue, etc.

Jones, Alun G. (Newton Centre, MA); Davison, Alan (Needham, MA); Abrams, Michael J. (Westchester, PA)

1987-01-01T23:59:59.000Z

352

The synthetic elements  

Science Conference Proceedings (OSTI)

Prior to 1940, the heaviest element known was uranium, discovered in 1789. Since that time the elements 93 through 109 have been synthesized and identified and the elements 43, 61, 85, and 87 which were missing form the periodic tables of the 1930's have been discovered. The techniques and problems involved in these discoveries and the placement of the transuranium elements in the periodic table will be discussed. The production and positive identification of elements heavier than Md (Z=101), which have very short half-lives and can only be produced an atom-at-a-time, are very difficult and there have been controversies concerning their discovery. Some of the new methods which have been developed and used in these studies will be described. The prospects for production of still heavier elements will be considered.

Hoffman, D.C.

1990-05-01T23:59:59.000Z

353

Enhancements to System for Tracking Radioactive Waste Shipments...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users...

354

EA-1146: Radioactive Waste Storage at Rocky Flats Environmental...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

46: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site,...

355

CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT This Fiscal Year...

356

RESRAD Computer Code- Evaluation of Radioactively Contaminated Sites  

Energy.gov (U.S. Department of Energy (DOE))

The evaluation of sites with radioactive contamination was a problem until the RESidual RADioactivity (RESRAD) Computer Code was first released in 1989.

357

Information-Sharing Protocol for the Transportation of Radioactive...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Preliminary Draft for Review Only Information-Sharing for Transportation of Radioactive Waste to Yucca Mountain Office of Logistics Management Office of Civilian Radioactive Waste...

358

Southeast Interstate Low-Level Radioactive Waste Management Compact...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Southeast Interstate Low-Level Radioactive Waste Management Compact (multi-state) Southeast Interstate Low-Level Radioactive Waste Management Compact (multi-state) Eligibility...

359

Northwest Interstate Compact on Low-Level Radioactive Waste Management...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Northwest Interstate Compact on Low-Level Radioactive Waste Management (Multiple States) Northwest Interstate Compact on Low-Level Radioactive Waste Management (Multiple States)...

360

Atlantic Interstate Low-Level Radioactive Waste Management Compact...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Atlantic Interstate Low-Level Radioactive Waste Management Compact (South Carolina) Atlantic Interstate Low-Level Radioactive Waste Management Compact (South Carolina) Eligibility...

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Public Preferences Related to Consent-Based Siting of Radioactive...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal Public Preferences Related to Consent-Based Siting of Radioactive Waste...

362

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste...

363

Nuclear fuel elements made from nanophase materials  

SciTech Connect

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000.degree. F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics.

Heubeck, Norman B. (Schenectady, NY)

1998-01-01T23:59:59.000Z

364

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain-related failure even at high temperatures, in the order of about 3,000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion and mechanical characteristics.

Heubeck, Norman B.

1997-12-01T23:59:59.000Z

365

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics. 5 figs.

Heubeck, N.B.

1998-09-08T23:59:59.000Z

366

Amorphous semiconducting and conducting transparent metal oxide thin films and production thereof  

DOE Patents (OSTI)

Metal oxide thin films and production thereof are disclosed. An exemplary method of producing a metal oxide thin film may comprise introducing at least two metallic elements and oxygen into a process chamber to form a metal oxide. The method may also comprise depositing the metal oxide on a substrate in the process chamber. The method may also comprise simultaneously controlling a ratio of the at least two metallic elements and a stoichiometry of the oxygen during deposition. Exemplary amorphous metal oxide thin films produced according to the methods herein may exhibit highly transparent properties, highly conductive properties, and/or other opto-electronic properties.

Perkins, John (Boulder, CO); Van Hest, Marinus Franciscus Antonius Maria (Lakewood, CO); Ginley, David (Evergreen, CO); Taylor, Matthew (Golden, CO); Neuman, George A. (Holland, MI); Luten, Henry A. (Holland, MI); Forgette, Jeffrey A. (Hudsonville, MI); Anderson, John S. (Holland, MI)

2010-07-13T23:59:59.000Z

367

Zone refining of plutonium metal  

Science Conference Proceedings (OSTI)

The zone refining process was applied to Pu metal containing known amounts of impurities. Rod specimens of plutonium metal were melted into and contained in tantalum boats, each of which was passed horizontally through a three-turn, high-frequency coil in such a manner as to cause a narrow molten zone to pass through the Pu metal rod 10 times. The impurity elements Co, Cr, Fe, Ni, Np, U were found to move in the same direction as the molten zone as predicted by binary phase diagrams. The elements Al, Am, and Ga moved in the opposite direction of the molten zone as predicted by binary phase diagrams. As the impurity alloy was zone refined, {delta}-phase plutonium metal crystals were produced. The first few zone refining passes were more effective than each later pass because an oxide layer formed on the rod surface. There was no clear evidence of better impurity movement at the slower zone refining speed. Also, constant or variable coil power appeared to have no effect on impurity movement during a single run (10 passes). This experiment was the first step to developing a zone refining process for plutonium metal.

Blau, M.S.

1994-08-01T23:59:59.000Z

368

FUEL ELEMENT INTERLOCKING ARRANGEMENT  

DOE Patents (OSTI)

This patent relates to a system for mutually interlocking a multiplicity of elongated, parallel, coextensive, upright reactor fuel elements so as to render a laterally selfsupporting bundle, while admitting of concurrent, selective, vertical withdrawal of a sizeable number of elements without any of the remaining elements toppling, Each element is provided with a generally rectangular end cap. When a rank of caps is aligned in square contact, each free edge centrally defines an outwardly profecting dovetail, and extremitally cooperates with its adjacent cap by defining a juxtaposed half of a dovetail- receptive mortise. Successive ranks are staggered to afford mating of their dovetails and mortises. (AEC)

Fortescue, P.; Nicoll, D.

1963-01-01T23:59:59.000Z

369

ElementNodeIterator  

Science Conference Proceedings (OSTI)

... iter=element->node_iterator(); !iter.end(); ++iter) { Node *node = iter.node(); // do something ... node returns a pointer to the iterator's current Node . ...

2013-08-23T23:59:59.000Z

370

Elements of arc welding  

SciTech Connect

This paper looks at the following arc welding techniques: (1) shielded metal-arc welding; (2) submerged-arc welding; (3) gas metal-arc welding; (4) flux-cored arc welding; (5) electrogas welding; (6) gas tungsten-arc welding; and (7) plasma-arc welding.

1993-07-01T23:59:59.000Z

371

It's Elemental - Isotopes of the Element Nitrogen  

NLE Websites -- All DOE Office Websites (Extended Search)

Carbon Carbon Previous Element (Carbon) The Periodic Table of Elements Next Element (Oxygen) Oxygen Isotopes of the Element Nitrogen [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 14 99.636% STABLE 15 0.364% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 10 No Data Available Proton Emission 100.00% 11 5.49×10-22 seconds Proton Emission 100.00% 12 11.000 milliseconds Electron Capture 100.00% 13 9.965 minutes Electron Capture 100.00% 14 STABLE - - 15 STABLE - - 16 7.13 seconds Beta-minus Decay 100.00% Beta-minus Decay with delayed Alpha Decay 1.2×10-3 % 17 4.173 seconds Beta-minus Decay 100.00%

372

METHOD OF CLEANING METAL SURFACES  

DOE Patents (OSTI)

Cleaning fluids for removing deposits from metal surfaces are described. The cleaning agents of the invention consist of aqueous nitric acid and an amhydrous nitrate salt of a metal which is lower in the electromotive series than the element of the deposit to be removed. In general, the salt content of thc cleaning agents ranged from 10 to 90%, preferably from 10 to 40% by weight; and the balance of the composition comprises nitric acid of any strength from extremely dilute up to concentrated strength.

Winkler, H.W.; Morfitt, J.W.; Little, T.H.

1959-05-19T23:59:59.000Z

373

Radioactive anomaly discrimination from spectral ratios  

DOE Patents (OSTI)

A method for discriminating a radioactive anomaly from naturally occurring radioactive materials includes detecting a first number of gamma photons having energies in a first range of energy values within a predetermined period of time and detecting a second number of gamma photons having energies in a second range of energy values within the predetermined period of time. The method further includes determining, in a controller, a ratio of the first number of gamma photons having energies in the first range and the second number of gamma photons having energies in the second range, and determining that a radioactive anomaly is present when the ratio exceeds a threshold value.

Maniscalco, James; Sjoden, Glenn; Chapman, Mac Clements

2013-08-20T23:59:59.000Z

374

Simplified scheme or radioactive plume calculations  

SciTech Connect

A simplified mathematical scheme to estimate external whole-body $gamma$ radiation exposure rates from gaseous radioactive plumes was developed for the Rio Blanco Gas Field Nuclear Stimulation Experiment. The method enables one to calculate swiftly, in the field, downwind exposure rates knowing the meteorological conditions and $gamma$ radiation exposure rates measured by detectors positioned near the plume source. The method is straightforward and easy to use under field conditions without the help of mini-computers. It is applicable to a wide range of radioactive plume situations. It should be noted that the Rio Blanco experiment was detonated on May 17, 1973, and no seep or release of radioactive material occurred. (auth)

Gibson, T.A.; Montan, D.N.

1976-11-21T23:59:59.000Z

375

Comparison of borosilicate glass and synthetic minerals as media for the immobilization of high-level radioactive waste  

Science Conference Proceedings (OSTI)

In this paper, the structure and properties of the different solid forms currently being developed for high-level radioactive waste disposal are compared. Good capacity to accept all the elements in the waste and flexibility of composition range to accommodate variations in the waste, are primarily discussed. 13 refs.

Tempest, P.A.

1981-03-01T23:59:59.000Z

376

Method for solidification of radioactive and other hazardous waste  

SciTech Connect

Solidification of liquid radioactive waste, and other hazardous wastes, is accomplished by the method of the invention by incorporating the waste into a porous glass crystalline molded block. The porous block is first loaded with the liquid waste and then dehydrated and exposed to thermal treatment at 50-1,000.degree. C. The porous glass crystalline molded block consists of glass crystalline hollow microspheres separated from fly ash (cenospheres), resulting from incineration of fossil plant coals. In a preferred embodiment, the porous glass crystalline blocks are formed from perforated cenospheres of grain size -400+50, wherein the selected cenospheres are consolidated into the porous molded block with a binder, such as liquid silicate glass. The porous blocks are then subjected to repeated cycles of saturating with liquid waste, and drying, and after the last cycle the blocks are subjected to calcination to transform the dried salts to more stable oxides. Radioactive liquid waste can be further stabilized in the porous blocks by coating the internal surface of the block with metal oxides prior to adding the liquid waste, and by coating the outside of the block with a low-melting glass or a ceramic after the waste is loaded into the block.

Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana A. (Krasnoyarsk, RU); Voskresenskaya, Elena N. (Krasnoyarsk, RU); Kostin, Eduard M. (Zheleznogorsk, RU); Pavlov, Vyacheslav F. (Krasnoyarsk, RU); Revenko, Yurii A. (Zheleznogorsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Sharonova, Olga M. (Krasnoyarsk, RU); Aloy, Albert S. (Saint-Petersburg, RU); Sapozhnikova, Natalia V. (Saint-Petersburg, RU); Knecht, Dieter A. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID); Macheret, Yevgeny (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

377

Control of high level radioactive waste-glass melters  

DOE Green Energy (OSTI)

A necessary step in Defense Waste Processing Facility (DWPF) melter feed preparation for the immobilization of High Level Radioactive Waste (HLW) is reduction of Hg(II) to Hg(0), permitting steam stripping of the Hg. Denitrition and associated NOx evolution is a secondary effect of the use of formic acid as the mercury-reducing agent. Under certain conditions the presence of transition or noble metals can result in significant formic acid decomposition, with associated CO{sub 2} and H{sub 2} evolution. These processes can result in varying redox properties of melter feed, and varying sequential gaseous evolution of oxidants and hydrogen. Electrochemical methods for monitoring the competing processes are discussed. Laboratory scale techniques have been developed for simulating the large-scale reactions, investigating the relative effectiveness of the catalysts, and the effectiveness of catalytic poisons. The reversible nitrite poisoning of formic acid catalysts is discussed.

Bickford, D.F.; Coleman, C.J.; Hsu, C.L.W.; Eibling, R.E.

1990-01-01T23:59:59.000Z

378

High power X-ray welding of metal-matrix composites  

DOE Patents (OSTI)

A method for joining metal-matrix composites (MMCs) by using high power x-rays as a volumetric heat source is provided. The method involves directing an x-ray to the weld line between two adjacent MMCs materials to create an irradiated region or melt zone. The x-rays have a power density greater than about 10{sup 4} watts/cm{sup 2} and provide the volumetric heat required to join the MMC materials. Importantly, the reinforcing material of the metal-matrix composites remains uniformly distributed in the melt zone, and the strength of the MMCs are not diminished. In an alternate embodiment, high power x-rays are used to provide the volumetric heat required to weld metal elements, including metal elements comprised of metal alloys. In an alternate embodiment, high power x-rays are used to provide the volumetric heat required to weld metal elements, including metal elements comprised of metal alloys.

Rosenberg, Richard A.; Goeppner, George A.; Noonan, John R.; Farrell, William J.; Ma, Qing

1997-12-01T23:59:59.000Z

379

High power x-ray welding of metal-matrix composites  

DOE Patents (OSTI)

A method for joining metal-matrix composites (MMCs) by using high power x-rays as a volumetric heat source is provided. The method involves directing an x-ray to the weld line between two adjacent MMCs materials to create an irradiated region or melt zone. The x-rays have a power density greater than about 10.sup.4 watts/cm.sup.2 and provide the volumetric heat required to join the MMC materials. Importantly, the reinforcing material of the metal-matrix composites remains uniformly distributed in the melt zone, and the strength of the MMCs are not diminished. In an alternate embodiment, high power x-rays are used to provide the volumetric heat required to weld metal elements, including metal elements comprised of metal alloys. In an alternate embodiment, high power x-rays are used to provide the volumetric heat required to weld metal elements, including metal elements comprised of metal alloys.

Rosenberg, Richard A. (Naperville, IL); Goeppner, George A. (Orland Park, IL); Noonan, John R. (Naperville, IL); Farrell, William J. (Flossmoor, IL); Ma, Qing (Westmont, IL)

1999-01-01T23:59:59.000Z

380

NEUTRONIC REACTOR FUEL ELEMENT  

DOE Patents (OSTI)

A reactor fuel element of the capillary tube type is described. The element consists of a thin walled tube, sealed at both ends, and having an interior coatlng of a fissionable material, such as uranium enriched in U-235. The tube wall is gas tight and is constructed of titanium, zirconium, or molybdenum.

Kesselring, K.A.; Seybolt, A.U.

1958-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Trace element emissions  

SciTech Connect

The Energy & Environmental Research Center (EERC) is carrying out an investigation that will provide methods to predict the fate of selected trace elements in integrated gasification combined cycle (IGCC) and integrated gasification fuel cell (IGFC) systems to aid in the development of methods to control the emission of trace elements determined to be air toxics. The goal of this project is to identify the effects of critical chemical and physical transformations associated with trace element behavior in IGCC and IGFC systems. The trace elements included in this project are arsenic, chromium, cadmium, mercury, nickel, selenium, and lead. The research seeks to identify and fill, experimentally and/or theoretically, data gaps that currently exist on the fate and composition of trace elements. The specific objectives are to (1) review the existing literature to identify the type and quantity of trace elements from coal gasification systems, (2) perform laboratory-scale experimentation and computer modeling to enable prediction of trace element emissions, and (3) identify methods to control trace element emissions.

Benson, S.A.; Erickson, T.A.; Steadman, E.N.; Zygarlicke, C.J.; Hauserman, W.B.; Hassett, D.J.

1994-10-01T23:59:59.000Z

382

Geochemistry of the Dakota Formation of Northwestern New Mexico: Relevance to Radioactive Waste Studies  

Science Conference Proceedings (OSTI)

Technical Paper / The Backfill as an Engineered Barrier for Radioactive Waste Management / Radioactive Waste Management

Douglas G. Brookins

383

Metal resistance sequences and transgenic plants  

DOE Patents (OSTI)

The present invention provides nucleic acid sequences encoding a metal ion resistance protein, which are expressible in plant cells. The metal resistance protein provides for the enzymatic reduction of metal ions including but not limited to divalent Cu, divalent mercury, trivalent gold, divalent cadmium, lead ions and monovalent silver ions. Transgenic plants which express these coding sequences exhibit increased resistance to metal ions in the environment as compared with plants which have not been so genetically modified. Transgenic plants with improved resistance to organometals including alkylmercury compounds, among others, are provided by the further inclusion of plant-expressible organometal lyase coding sequences, as specifically exemplified by the plant-expressible merB coding sequence. Furthermore, these transgenic plants which have been genetically modified to express the metal resistance coding sequences of the present invention can participate in the bioremediation of metal contamination via the enzymatic reduction of metal ions. Transgenic plants resistant to organometals can further mediate remediation of organic metal compounds, for example, alkylmetal compounds including but not limited to methyl mercury, methyl lead compounds, methyl cadmium and methyl arsenic compounds, in the environment by causing the freeing of mercuric or other metal ions and the reduction of the ionic mercury or other metal ions to the less toxic elemental mercury or other metals.

Meagher, Richard Brian (Athens, GA); Summers, Anne O. (Athens, GA); Rugh, Clayton L. (Athens, GA)

1999-10-12T23:59:59.000Z

384

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification.

Albert, R.

1992-06-30T23:59:59.000Z

385

Microbial effects on radioactive wastes at SLB sites  

DOE Green Energy (OSTI)

The objectives of this study are to determine the significance of microbial degradation of organic wastes on radionuclide migration on shallow land burial for humid and arid sites, establish which mechanisms predominate and ascertain the conditions under which these mechanisms operate. Factors contolling gaseous eminations from low-level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide and possibly hydrogen from the site stems from the inclusion of tritium and/or /sup 14/C into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste materials, primary emphasis of the study involved on examination of the biochemical pathways producing methane, carbon dioxide and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Although the methane and carbon dioxide production rate indicates the degradation rate of the organic substances in the waste, it does not predict the methane evolution rate from the trench site. Methane fluxes from the soil surface are equivalent to the net synthesis minus the quantity oxidized by the microbial community as the gas passes through the soil profile. Gas studies were performed at three commercial low-level radioactive waste disposal sites (West Valley, New York; Beatty, Nevada; Maxey Flats, Kentucky) during the period 1976 to 1978. The results of these studies are presented. 3 tables.

Colombo, P.

1982-01-01T23:59:59.000Z

386

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Radioactive materials are carried by road, rail, water, and air. There are strict regulations that originate from the International Atomic Energy Agency (IAEA) which cover the packaging and transportation of radioactive materials. Road Rail Water Air [Road transport] Click to view picture [Rail transport] Click to view picture [Sea transport] Click to view picture [Air transport] Click to view picture 1998 DOE Radioactive Shipments in the United States Out of the 3 million hazardous material shipments are made each year, DOE accounts for less than 1% of all radioactive materials shipments and 75% of the total curies shipped in the United States Ship 0 Train 308

387

Using Neutrons to Study Radioactive Materials  

Science Conference Proceedings (OSTI)

Symposium, Applied Neutron Scattering in Engineering and Materials Science Research ... to the unique infrastructure and specialized staff of the Nuclear Laboratory. Shielded cells enable neutron diffraction studies on highly radioactive...

388

ORISE: Radiation and Radioactive Contamination FAQ  

NLE Websites -- All DOE Office Websites (Extended Search)

take potassium iodide, also known as KI? A: KI is a medication that blocks the thyroid gland from absorbing radioactive iodine. It works by providing all the iodine the gland...

389

Radioactive materials shipping cask anticontamination enclosure  

DOE Patents (OSTI)

An anticontamination device for use in storing shipping casks for radioactive materials comprising (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

Belmonte, Mark S. (Irwin, PA); Davis, James H. (Pittsburgh, PA); Williams, David A. (Pittsburgh, PA)

1982-01-01T23:59:59.000Z

390

Environmental Radioactivity in Greenland in 1981  

E-Print Network (OSTI)

. Measurements of fallout radioactivity in Greenland in 1981 are reported. Strontium-90 (and Cesium-137 in most. INIS Descriptors [0] DEER, DIET, ENVIRONMENT, EXPERIMENTAL DATA, FISHES, POOD CHAINS, GLOBAL FALLOUT

391

Method for storing radioactive combustible waste  

DOE Patents (OSTI)

A method is described for preventing pressure buildup in sealed containers which contain radioactively contaminated combustible waste material by adding an oxide getter material to the container so as to chemically bind sorbed water and combustion product gases. (Official Gazette)

Godbee, H.W.; Lovelace, R.C.

1973-10-01T23:59:59.000Z

392

Categorical Exclusion Determinations: Civilian Radioactive Waste...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

B5.1 Date: 04052011 Location(s): Hot Springs, Arkansas Office(s): Civilian Radioactive Waste Management, Energy Efficiency and Renewable Energy March 25, 2011 CX-005570:...

393

Principles for Sampling Airborne Radioactivity from Stacks  

SciTech Connect

This book chapter describes the special processes involved in sampling the airborne effluents from nuclear faciities. The title of the book is Radioactive Air Sampling Methods. The abstract for this chapter was cleared as PNNL-SA-45941.

Glissmeyer, John A.

2010-10-18T23:59:59.000Z

394

Radioactive waste disposal characteristics of candidate tokamak demonstration reactors  

SciTech Connect

Results from the current physics, materials and blanket R and D programs are combined with physics and engineering design constraints to characterize candidate tokamak demonstration plant (DEMO) designs. Blanket designs based on the principal structural materials, breeding materials and coolants being developed for the DEMO were adapted from the literature. Neutron flux and activation calculations were performed, and several radioactive waste disposal indices were evaluated, for each design. Of the primary low-activation structural materials under development in the US, it appears that vanadium and ferritic steel alloys, and possibly silicon carbide, could lead to DEMO designs which could satisfy realistic low-level waste (LLW) criteria, provided that impurities can be controlled within plausible limits. Allowable LLW concentrations are established for the limiting alloying and impurity elements. All breeding materials and neutron multipliers considered meet the LLW criterion.

Hoffman, E.A.; Stacey, W.M.; Hertel, N.E.

1998-08-01T23:59:59.000Z

395

WEB RESOURCE: MIL-HDBK-5H: Metallic Materials and ... - TMS  

Science Conference Proceedings (OSTI)

Feb 9, 2007 ... This handbook contains standardized design values and related design information for metallic materials and structural elements used in...

396

Vitrification of hazardous and radioactive wastes  

SciTech Connect

Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification.

Bickford, D.F.; Schumacher, R.

1995-12-31T23:59:59.000Z

397

The IAEA and Control of Radioactive SourcesThe  

SciTech Connect

This presentation discusses the International Atomic Energy Agency (IAEA) and the control of radioactive sources.

Dodd, B.

2004-10-03T23:59:59.000Z

398

How to deal with laboratory waste Radioactive waste  

E-Print Network (OSTI)

How to deal with laboratory waste Radioactive waste: Any laboratory waste, whether chemical or biological, containing radioactive material, should be disposed as radioactive waste. Radioactive waste should be removed from the laboratory to the departmental waste area, soon after finishing the experiment

Maoz, Shahar

399

Amorphous metal alloy and composite  

DOE Patents (OSTI)

Amorphous metal alloys of the iron-chromium and nickel-chromium type have excellent corrosion resistance and high temperature stability and are suitable for use as a protective coating on less corrosion resistant substrates. The alloys are stabilized in the amorphous state by one or more elements of titanium, zirconium, hafnium, niobium, tantalum, molybdenum, and tungsten. The alloy is preferably prepared by sputter deposition.

Wang, Rong (Richland, WA); Merz, Martin D. (Richland, WA)

1985-01-01T23:59:59.000Z

400

SRP RADIOACTIVE WASTE RELEASES S  

Office of Scientific and Technical Information (OSTI)

. . . . . . -- SRP RADIOACTIVE WASTE RELEASES S t a r t u p t h r o u g h 1 9 5 9 September 1 9 6 0 _- R E C O R D - W O R K S T E C H N I C A L D E P A R T M E N T 1 J. E. C o l e , W i l n i 1 4 W. P. 3ebbii 3 H. Worthington, Wilm 16 C. $?. P~.t-Lei-s~:; - 5 J. D. E l l e t t - 17 E. C. Morris 6 F. H. Endorf 19 3 . L. &tier 7 K. W. F r e n c h 20 bi. C . 3 e i n i g 8 J. K. Lower 2 1 2. 3 . 3 G : - x r 9 K. W. M i l l e t t 22 R . FJ . V 2 x 7 : W ~ ~ C k 1 c - 2 J. B. Tinker, W i h L-, i . c . E?-ens 4 W F i l e P. 3 . K t B U ? & J. A. Monier, Jr. 13. : . A. KcClesrer. 1 0 M. 2 . Wahl . - 23 C. Ashley C. W. J. Wende 24 T I S F i l e 11 J. W. Morris - 2s T'pC File D. E. Waters 26 P3D F i l e , 736-C R. B. Fenninger 33 V l ~ a l Records F i l e 12 W. P. Overbeck - 27 -23 P3D % x : r a Czpies P33 2e:ol.d C ~ p l *iB+ ' / - - & OF THIS DQCUMENT I S UNuMITEI) E. 1. ciu /'(I,\ 7' d

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Thermostat Metals  

Science Conference Proceedings (OSTI)

...A thermostat metal is a composite material (usually in the form of sheet or strip) that consists of two or more materials bonded together, of which one can be a nonmetal. Because the materials bonded together to form the composite differ in

402

METAL COMPOSITIONS  

DOE Patents (OSTI)

Alloys of uranium which are strong, hard, and machinable are presented, These alloys of uranium contain bctween 0.1 to 5.0% by weight of at least one noble metal such as rhodium, palladium, and gold. The alloys may be heat treated to obtain a product with iniproved tensile and compression strengths,

Seybolt, A.U.

1959-02-01T23:59:59.000Z

403

VENTED FUEL ELEMENT FOR GAS-COOLED NEUTRONIC REACTORS  

DOE Patents (OSTI)

A hollow, porous-walled fuel element filled with fissionable fuel and provided with an outlet port through its wall is described. In operation in a gas-cooled reactor, the element is connected, through its outlet port, to the vacuum side of a pump that causes a portion of the coolant gas flowing over the exterior surface of the element to be drawn through the porous walls thereof and out through the outlet port. This continuous purging gas flow sweeps away gaseous fission products as they are released by the fissioning fuel. (AEC) A fuel element for a nuclear reactor incorporating a body of metal of melting point lower than the temperature of operation of the reactor and a nuclear fuel in finely divided form dispersed in the body of metal as a settled slurry is presented. (AEC)

Furgerson, W.T.

1963-12-17T23:59:59.000Z

404

NEUTRONIC REACTOR FUEL ELEMENT  

DOE Patents (OSTI)

A fuel element possessing good stability and heat conducting properties is described. The fuel element comprises an outer tube formed of material selected from the group consisting of stainhess steel, V, Ti. Mo. or Zr, a fuel tube concentrically fitting within the outer tube and containing an oxide of an isotope selected from the group consisting of U/sup 235/, U/sup 233/, and Pu/sup 239/, and a hollow, porous core concentrically fitting within the fuel tube and formed of an oxide of an element selected from the group consisting of Mg, Be, and Zr.

Shackleford, M.H.

1958-12-16T23:59:59.000Z

405

EIS-0327: Disposition of Scrap Metals Programmatic EIS | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

27: Disposition of Scrap Metals Programmatic EIS 27: Disposition of Scrap Metals Programmatic EIS EIS-0327: Disposition of Scrap Metals Programmatic EIS Summary This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download December 19, 2011 EA-1919: Notice of Revision to Clearance Policy Recycle of Scrap Metals Originating from Radiological Areas (December 2011) July 12, 2001 EIS-0327: Notice of Intent to Prepare a Programmatic Environmental Impact Statement and Announcement of Public Scoping Meetings Disposition of Scrap Metals

406

Initial report on the application of laser ablation - inductively coupled plasma mass spectrometry for the analysis of radioactive Hanford Tank Waste materials  

Science Conference Proceedings (OSTI)

Initial LA/MS analyses of Hanford tank waste samples were performed successfully using laboratory and hot cell LA/MS instrumentation systems. The experiments described in this report have demonstrated that the LA/MS data can be used to provide rapid analysis of solid, radioactive Hanford tank waste samples to identify major, minor, and trace constituents (elemental and isotopic) and fission products and radioactive isotopes. The ability to determine isotopic constituents using the LA/MS method yielded significant advantages over ICP/AES analysis by providing valuable information on fission products and radioactive constituents.

Smith, M.R.; Hartman, J.S.; Alexander, M.L.; Mendoza, A.; Hirt, E.H.; Stewart, T.L.; Hansen, M.A.; Park, W.R.; Peters, T.J.; Burghard, B.J.

1996-12-01T23:59:59.000Z

407

Element Word Search  

NLE Websites -- All DOE Office Websites (Extended Search)

or, if you wish, you can download your very own copy of the Table of Elements. Download this Activity Lab Page Puzzle Puzzle Sample AnswersAnswer Key Answer Key Answer Key...

408

Public involvement in radioactive waste management decisions  

SciTech Connect

Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

NONE

1994-04-01T23:59:59.000Z

409

Trace metals in sediments of coastal Siberia  

E-Print Network (OSTI)

For the work described in this thesis, a total of 218 samples from 104 cores from the East Siberian, Laptev, Kara, and Pechora Seas and the Ob and Yenisei Rivers were analyzed for the trace metals Ag, As, Ba, Cd, Cr, Cu, Fe, Hg, Ni, Pb, Sb, and Zn. To make comparisons between locations easier, the concentration of all elements was normalized to Fe to account for variability in grain size and mineralogy. For the metals Ag, Cd, and Hg there was poor correlation with Fe, likely partially due to analytical variations caused by the low concentrations of these elements. Copper, Ni and Zn showed good correlation with Fe, suggesting these elements are from natural inputs to the sediments. Arsenic, Ba, Cr, Pb, and Sb showed variable correlations, suggesting a more mafic (basaltic) mineral phase at some locations and/or diagenetic redistribution of these metals. No statistically significant differences were found between metal to Fe ratios at the surface (0-2.5 cm) of the sediment cores and the bottoms (5- 1 00 cm), with a few exceptions. There was also no statistically significant difference in the average metal to Fe ratios of the East Siberian and Laptev Seas. There was, however, a significant difference when these two seas were compared to the Kara and Pechora Seas, suggesting different mineralogy in the drainage basins of eastern and western Siberia. Sediment from the Kara Sea was similar in trace metal concentration to sediment from its likely source, the Ob and Yenisei rivers.

Esnough, Teresa Elizabeth

1996-01-01T23:59:59.000Z

410

Removal of Retired Alkali Metal Test Systems  

SciTech Connect

This paper describes the successful effort to remove alkali metals, alkali metal residues, and piping and structures from retired non-radioactive test systems on the Hanford Site. These test systems were used between 1965 and 1982 to support the Fast Flux Test Facility and the Liquid Metal Fast Breeder Reactor Program. A considerable volume of sodium and sodium-potassium alloy (NaK) was successfully recycled to the commercial sector; structural material and electrical material such as wiring was also recycled. Innovative techniques were used to safely remove NaK and its residues from a test system that could not be gravity-drained. The work was done safely, with no environmental issues or significant schedule delays.

Brehm, W. F.; Church, W. R.; Biglin, J. W.

2003-02-26T23:59:59.000Z

411

Energy Conservation in Metals  

Science Conference Proceedings (OSTI)

About this Symposium. Meeting, 2010 TMS Annual Meeting & Exhibition. Symposium, Energy Conservation in Metals. Sponsorship, The Minerals, Metals and...

412

Initial Evaluation of Processing Methods for an Epsilon Metal Waste Form  

Science Conference Proceedings (OSTI)

During irradiation of nuclear fuel in a reactor, the five metals, Mo, Pd, Rh, Ru, and Tc, migrate to the fuel grain boundaries and form small metal particles of an alloy known as epsilon metal ({var_epsilon}-metal). When the fuel is dissolved in a reprocessing plant, these metal particles remain behind with a residue - the undissolved solids (UDS). Some of these same metals that comprise this alloy that have not formed the alloy are dissolved into the aqueous stream. These metals limit the waste loading for a borosilicate glass that is being developed for the reprocessing wastes. Epsilon metal is being developed as a waste form for the noble metals from a number of waste streams in the aqueous reprocessing of used nuclear fuel (UNF) - (1) the {var_epsilon}-metal from the UDS, (2) soluble Tc (ion-exchanged), and (3) soluble noble metals (TRUEX raffinate). Separate immobilization of these metals has benefits other than allowing an increase in the glass waste loading. These materials are quite resistant to dissolution (corrosion) as evidenced by the fact that they survive the chemically aggressive conditions in the fuel dissolver. Remnants of {var_epsilon}-metal particles have survived in the geologically natural reactors found in Gabon, Africa, indicating that they have sufficient durability to survive for {approx} 2.5 billion years in a reducing geologic environment. Additionally, the {var_epsilon}-metal can be made without additives and incorporate sufficient foreign material (oxides) that are also present in the UDS. Although {var_epsilon}-metal is found in fuel and Gabon as small particles ({approx}10 {micro}m in diameter) and has survived intact, an ideal waste form is one in which the surface area is minimized. Therefore, the main effort in developing {var_epsilon}-metal as a waste form is to develop a process to consolidate the particles into a monolith. Individually, these metals have high melting points (2617 C for Mo to 1552 C for Pd) and the alloy is expected to have a high melting point as well, perhaps exceeding 1500 C. The purpose of the work reported here is to find a potential commercial process with which {var_epsilon}-metal plus other components of UDS can be consolidated into a solid with minimum surface area and high strength Here, we report the results from the preliminary evaluation of spark-plasma sintering (SPS), hot-isostatic pressing (HIP), and microwave sintering (MS). Since bulk {var_epsilon}-metal is not available and companies could not handle radioactive materials, we prepared mixtures of the five individual metal powders (Mo, Ru, Rh, Pd, and Re) and baddeleyite (ZrO{sub 2}) to send the vendors of SPS, HIP, and MS. The processed samples were then evaluated at the Pacific Northwest National Laboratory (PNNL) for bulk density and phase assemblage with X-ray diffraction (XRD) and phase composition with scanning electron microscopy (SEM). Physical strength was evaluated qualitatively. Results of these scoping tests showed that fully dense cermet (ceramic-metal composite) materials with up to 35 mass% of ZrO{sub 2} were produced with SPS and HIP. Bulk density of the SPS samples ranged from 87 to 98% of theoretical density, while HIP samples ranged from 96 to 100% of theoretical density. Microwave sintered samples containing ZrO{sub 2} had low densities of 55 to 60% of theoretical density. Structurally, the cermet samples showed that the individual metals alloyed in to {var_epsilon}-phase - hexagonal-close-packed (HCP) alloy (4-95 mass %), the {alpha}-phase - face-centered-cubic (FCC) alloy structure (3-86 mass %), while ZrO{sub 2} remained in the monoclinic structure of baddeleyite. Elementally, the samples appeared to have nearly uniform composition, but with some areas rich in Mo and Re, the two components with the highest melting points. The homogeneity in distribution of the elements in the alloy is significantly improved in the presence of ZrO{sub 2}. However, ZrO{sub 2} does not appear to react with the alloy, nor was Zr found in the alloy.

Crum, Jarrod V.; Strachan, Denis M.; Zumhoff, Mac R.

2012-06-11T23:59:59.000Z

413

Nuclear fuel elements having a composite cladding  

DOE Patents (OSTI)

An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a composite cladding of an outer portion forming a substrate having on the inside surface a metal layer selected from the group consisting of copper, nickel, iron and alloys of the foregoing with a gap between the composite cladding and the core of nuclear fuel. The nuclear fuel element comprises a container of the elongated composite cladding, a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity. The metal layer of the composite cladding prevents perforations or failures in the cladding substrate from stress corrosion cracking or from fuel pellet-cladding interaction or both. The substrate of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy.

Gordon, Gerald M. (Fremont, CA); Cowan, II, Robert L. (Fremont, CA); Davies, John H. (San Jose, CA)

1983-09-20T23:59:59.000Z

414

DOE - Office of Legacy Management -- Reynolds Metals Co - VA 04  

Office of Legacy Management (LM)

Reynolds Metals Co - VA 04 Reynolds Metals Co - VA 04 FUSRAP Considered Sites Site: REYNOLDS METALS CO. (VA.04 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Virginia-Carolina Chemical Corporation VA.04-1 Location: 818 Perry Street , Richmond , Virginia VA.04-1 Evaluation Year: 1985 VA.04-2 VA.04-3 Site Operations: Preparatory process development involving only gram quantities of uranium performed in the 1950s. VA.04-1 Site Disposition: Eliminated - Potential for contamination considered remote based on limited materials handled VA.04-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium VA.04-1 Radiological Survey(s): None Indicated VA.04-1 VA.04-4 Site Status: Eliminated from consideration under FUSRAP

415

DOE - Office of Legacy Management -- International Rare Metals Refinery Inc  

Office of Legacy Management (LM)

Rare Metals Refinery Rare Metals Refinery Inc - NY 38 FUSRAP Considered Sites Site: International Rare Metals Refinery, Inc. (NY.38 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Canadian Radium and Uranium Corporation NY.38-1 Location: 69 Kisko Avenue , Mt. Kisko , New York NY.38-1 NY.38-3 Evaluation Year: 1987 NY.38-4 Site Operations: Manufactured and distributed radium and polonium products. NY.38-5 Site Disposition: Eliminated - No Authority - Site was a commercial operation not under the jurisdiction of DOE predecessor agencies NY.38-2 NY.38-4 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Radium, Plutonium NY.38-5 Radiological Survey(s): Yes NY.38-1 NY.38-5 Site Status: Eliminated from consideration under FUSRAP

416

Project Rio Blanco radioactivity and the environment  

SciTech Connect

Data are presented on radiological measurements of the environment and on documenting the transfer to a subsurface disposal well of radioactive water separated from the produced gas stream. Analysis of gas and water through the drilling well control unit revealed the presence of $sup 3$H and $sup 85$Kr in the gas and $sup 3$H, $sup 137$Cs, and $sup 90$Sr in the water. The production test, disposal system, and radiological monitoring system are described. Data on effluents are presented under the headings: gas and water production, radioactivity concentrations in gas, radioactivity concentrations in separator water samples, radioactivity concentrations in injected water volumes, and disposition of radioactivity. Tritium, $sup 39$Ar, $sup 14$C, $sup 85$Kr, and $sup 222$Rn were present in gas. Tritium, $sup 134$CCs, $sup 137$Cs, $sup 90$Sr, $sup 75$Se, and $sup 106$Ru were present in separator water samples. Data on environmental monitoring and RB-AR-2 drilling and testing are presented under the headings air sampling, air moisture and precipitation sampling, soil sampling, water sampling, Fawn Creek sediments and algae/moss samples, bioassays, aerial surveillance, and potential environmental radiation doses. (HLW)

1975-10-01T23:59:59.000Z

417

Process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents (OSTI)

The present invention provides a method for encapsulating and stabilizing radioactive, hazardous and mixed wastes in a modified sulfur cement composition. The waste may be incinerator fly ash or bottom ash including radioactive contaminants, toxic metal salts and other wastes commonly found in refuse. The process may use glass fibers mixed into the composition to improve the tensile strength and a low concentration of anhydrous sodium sulfide to reduce toxic metal solubility. The present invention preferably includes a method for encapsulating radioactive, hazardous and mixed wastes by combining substantially anhydrous wastes, molten modified sulfur cement, preferably glass fibers, as well as anhydrous sodium sulfide or calcium hydroxide or sodium hydroxide in a heated double-planetary orbital mixer. The modified sulfur cement is preheated to about 135.degree..+-.5.degree. C., then the remaining substantially dry components are added and mixed to homogeneity. The homogeneous molten mixture is poured or extruded into a suitable mold. The mold is allowed to cool, while the mixture hardens, thereby immobilizing and encapsulating the contaminants present in the ash.

Colombo, Peter (Patchogue, NY); Kalb, Paul D. (Wading River, NY); Heiser, III, John H. (Bayport, NY)

1997-11-14T23:59:59.000Z

418

Metallic glass composition. [That does not embrittle upon annealing  

DOE Patents (OSTI)

This patent pertains to a metallic glass alloy that is either iron-based or nickel-based or based on a mixture of iron and nickel, containing lesser amounts of elements selected from the group boron, silicon, carbon and phosphorous to which is added an amount of a ductility-enhancing element selected from the group cerium, lanthanum, praseodymium and neodymium sufficient to increase ductility of the metallic glass upon annealing.

Kroeger, D.M.; Koch, C.C.

1984-09-14T23:59:59.000Z

419

Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes  

SciTech Connect

This document details Lawrence Livermore National Laboratory's (LLNL) criteria and processes for determining if potentially volumetrically contaminated or potentially surface contaminated wastes are to be managed as material containing residual radioactivity or as non-radioactive. This document updates and replaces UCRL-AR-109662, Criteria and Procedures for the Certification of Nonradioactive Hazardous Waste (Reference 1), also known as 'The Moratorium', and follows the guidance found in the U.S. Department of Energy (DOE) document, Performance Objective for Certification of Non-Radioactive Hazardous Waste (Reference 2). The 1992 Moratorium document (UCRL-AR-109662) is three volumes and 703 pages. The first volume provides an overview of the certification process and lists the key radioanalytical methods and their associated Limits of Sensitivities. Volumes Two and Three contain supporting documents and include over 30 operating procedures, QA plans, training documents and organizational charts that describe the hazardous and radioactive waste management system in place in 1992. This current document is intended to update the previous Moratorium documents and to serve as the top-tier LLNL institutional Moratorium document. The 1992 Moratorium document was restricted to certification of Resource Conservation and Recovery Act (RCRA), State and Toxic Substances Control Act (TSCA) hazardous waste from Radioactive Material Management Areas (RMMA). This still remains the primary focus of the Moratorium; however, this document increases the scope to allow use of this methodology to certify other LLNL wastes and materials destined for off-site disposal, transfer, and re-use including non-hazardous wastes and wastes generated outside of RMMAs with the potential for DOE added radioactivity. The LLNL organization that authorizes off-site transfer/disposal of a material or waste stream is responsible for implementing the requirements of this document. The LLNL Radioactive and Hazardous Waste Management (RHWM) organization is responsible for the review and maintenance of this document. It should be noted that the DOE metal recycling moratorium is still in effect and is implemented as outlined in reference 17 when metals are being dispositioned for disposal/re-use/recycling off-site. This document follows the same methodology as described in the previously approved 1992 Moratorium document. Generator knowledge and certification are the primary means of characterization. Sampling and analysis are used when there is insufficient knowledge of a waste to determine if it contains added radioactivity. Table 1 (page 12) presents a list of LLNL's analytical methods for evaluating volumetrically contaminated waste and updates the reasonably achievable analytical-method-specific Minimum Detectable Concentrations (MDCs) for various matrices. Results from sampling and analysis are compared against the maximum MDCs for the given analytical method and the sample specific MDC to determine if the sample contains DOE added volumetric radioactivity. The evaluation of an item that has a physical form, and history of use, such that accessible surfaces may be potentially contaminated, is based on DOE Order 5400.5 (Reference 3), and its associated implementation guidance document DOE G 441.1-XX, Control and Release of Property with Residual Radioactive Material (Reference 4). The guidance document was made available for use via DOE Memorandum (Reference 5). Waste and materials containing residual radioactivity transferred off-site must meet the receiving facilities Waste Acceptance Criteria (if applicable) and be in compliance with other applicable federal or state requirements.

Dominick, J

2008-12-18T23:59:59.000Z

420

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

What are the requirements? Safety Record The Agencies that Generate Rules that Promulgate the Transport of Radioactive Materials: Regulations to control the transport of radioactive material were initiated about 1935 by the Postal Service. Over the years, the Interstate Commerce Commission (ICC) became involved and in 1948 promulgated regulations as Title 49 of the Code of Federal Regulations. In 1966, DOT received hazardous materials regulatory authority that had been exercised by the ICC, Federal Aviation Administration (FAA) and United States Costal Guard (USCG). Currently, five groups generate rules governing the transport of radioactive material -- the DOT, NRC, USPS, DOE, and various State agencies. Among these, DOT and NRC are the primary agencies issuing regulations based on the model regulations developed by the International Atomic Energy Agency (IAEA).

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

What are the requirements? What are the requirements? Safety Record Radioactive material has been shipped in the U. S. for more than 50 years with no occurrences of death or serious injury from exposure of the contents of these shipments. Hazardous Material Shipments for 1 Year Internationally 300 million United States 3 million DOE <1% or 5,000 (out of 3 million) [U.S. DOE NTP, 1999, Transporting Radioactive Materials] All radioactive shipments are regulated by the Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). Since transport accidents cannot be prevented, the regulations are primarily designed to: Insure safety in routine handling situations for minimally hazardous material Insure integrity under all circumstances for highly dangerous materials

422

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

When are they used? How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record A radioactive material (RAM) packaging is a container that is used to safely transport radioactive material from one location to another. In RAM transportation the container alone is called the Packaging. The packaging together with its contents is called the Package. Basic types of radioactive material packagings are: Excepted Packaging Industrial Packaging Type A Packaging Type B Packaging [EXCEPTED] Click to view picture [IP] Click to view picture [TYPE A] Click to view picture [TYPE B] Click to view picture Excepted Packagings are designed to survive normal conditions of transport. Excepted packagings are used for transportation of materials that are either Low Specific Activity (LSA) or Surface Contaminated Objects (SCO) and that are limited quantity shipments, instruments or articles, articles manufactured from natural or depleted uranium or natural thorium; empty packagings are also excepted (49CFR 173.421-428).

423

Radioactive Nickel-63 - ORNL Neutron Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Making Radioactive Nickel-63 Making Radioactive Nickel-63 ORNL-Supplied Nickel-63 Enables High-Sensitivity Explosives, Chemical Weapons, and Narcotics Detectors at Airports Explosives and narcotics detector. Detectors based on ion mobility spectrometry using ORNL 63Ni can now satisfy enhanced Homeland Security requirements at airports and other sensitive locations. When Transportation Security Administration (TSA) inspectors swipe a cloth over your luggage and then place it in an analyzer to check for explosives residue, they are using a device containing 63Ni, a radioactive isotope of nickel, made at ORNL. ORNL is the exclusive producer for 63Ni in North America and perhaps worldwide. "Our only competition would probably be Russia. They have high-flux research reactors and may well be supplying the material also,"

424

Excellence in radioactive waste volume reduction  

SciTech Connect

The Brunswick plant is a two-unit boiling water reactor located at the mouth of the Cape Fear River near Wilmington, North Carolina. The plant has a once-through cooling system with highly brackish water. The operations subunit is responsible for liquid radwaste processing. The radiation control subunit is responsible for dry active waste processing and the transportation of all radioactive wast off-site. For the Brunswick plant, the development of an effective radioactive waste volume reduction program was a process involving a tremendous amount of grass-roots worker participation. With radioactive waste responsibilities divided between two separate groups, this process took place on a somewhat different schedule for liquid process waste and dry active waste. However, this development process did not begin until dedicated personnel were assigned to manage radwaste independently of other plant duties.

Henderson, J.

1987-01-01T23:59:59.000Z

425

Radioactive tank waste remediation focus area  

SciTech Connect

EM`s Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form.

1996-08-01T23:59:59.000Z

426

DOE - Office of Legacy Management -- Metals Selling Corp - CT 0-01  

Office of Legacy Management (LM)

Selling Corp - CT 0-01 Selling Corp - CT 0-01 FUSRAP Considered Sites Site: METALS SELLING CORP. (CT.0-01 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Putnam , Connecticut CT.0-01-1 Evaluation Year: 1986 CT.0-01-1 Site Operations: Performed grinding of (non-radioactive) magnesium circa 1950 -1952 as a sub-contractor to Mallinckrodt Corp. CT.0-01-1 Site Disposition: Eliminated - No indication that radioactive materials were handled at this location CT.0-01-1 Radioactive Materials Handled: No Primary Radioactive Materials Handled: None Radiological Survey(s): No Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to METALS SELLING CORP. CT.0-01-1 - DOE Memorandum/Checklist D. Levine to File; Subject -

427

CONSTRUCTION OF NUCLEAR FUEL ELEMENTS  

DOE Patents (OSTI)

>A rib arrangement and an end construction for nuclearfuel elements laid end to end in a coolant tube are described. The rib arrangement is such that each fuel element, when separated from other fuel elements, fits loosely in the coolant tube and so can easily be inserted or withdrawn from the tube. The end construction of the fuel elements is such that the fuel elements when assembled end to end are keyed against relative rotation, and the ribs of each fuel element cooperate with the ribs of the adjacent fuel elements to give the assembled fuel elements a tight fit with the coolant tube. (AEC)

Weems, S.J.

1963-09-24T23:59:59.000Z

428

Advances in metallic nuclear fuel  

Science Conference Proceedings (OSTI)

Metallic nuclear fuels have generated renewed interest for advanced liquid metal reactors (LMRs) due to their physical properties, ease of fabrication, irradiation behavior, and simple reprocessing. Irradiation performance for both steady-state and transient operations is excellent. Ongoing irradiation tests in Argonne-West's Idaho-based Experimental Breeder Reactor II (EBR-II) have surpassed 100,000 MWd/T burnup and are on their way to a lifetime burnup of 150,000 MWd/T or greater. Metallic fuel also has a unique neutronic characteristic that enables benign reactor responses to loss-of-flow without scram and loss-of-heat-sink without scram accident conditions. This inherent safety potential of metallic fuel was demonstrated in EBR-II just one year ago. Safety tests performed in the reactor have also demonstrated that there is ample margin to fuel element cladding failure under transient overpower conditions. These metallic fuel attributes are key ingredients of the integral fast reactor (IFR) concept being developed at Argonne National Laboratory.

Seidel, B.R.; Walters, L.C.; Chang, Y.I.

1987-04-01T23:59:59.000Z

429

Visualizing Brain Metals in Health and Disease  

NLE Websites -- All DOE Office Websites (Extended Search)

Visualizing Brain Metals in Health and Visualizing Brain Metals in Health and Disease figure 1 Fig. 1. Rapid-scanning x-ray fluorescence mapping ex perimental setup. Synchrotron x-rays at 11 keV passed through a 50 µm aperture (Ap). The beam intensity was monitored with a N2-filled ion chamber (I0). The brain slice was mounted vertically on a motorized stage (St) at 45° to the incident x-ray beam and raster scanned in the beam. A 13-element Ge detector (Ge) was positioned at a 90° angle to the beam. We all require iron, copper and zinc for normal brain function but metal metabolism becomes dysregulated in a variety of neurodegenerative diseases. Metals accumulate in Alzheimer's dementia and Parkinson's disease and are deficient in Menkes disease. Whether excess metals appear as a cause or a

430

Elemental sulfur recovery process  

DOE Patents (OSTI)

An improved catalytic reduction process for the direct recovery of elemental sulfur from various SO[sub 2]-containing industrial gas streams. The catalytic process provides combined high activity and selectivity for the reduction of SO[sub 2] to elemental sulfur product with carbon monoxide or other reducing gases. The reaction of sulfur dioxide and reducing gas takes place over certain catalyst formulations based on cerium oxide. The process is a single-stage, catalytic sulfur recovery process in conjunction with regenerators, such as those used in dry, regenerative flue gas desulfurization or other processes, involving direct reduction of the SO[sub 2] in the regenerator off gas stream to elemental sulfur in the presence of a catalyst. 4 figures.

Flytzani-Stephanopoulos, M.; Zhicheng Hu.

1993-09-07T23:59:59.000Z

431

Computing Heavy Elements  

E-Print Network (OSTI)

Reliable calculations of the structure of heavy elements are crucial to address fundamental science questions such as the origin of the elements in the universe. Applications relevant for energy production, medicine, or national security also rely on theoretical predictions of basic properties of atomic nuclei. Heavy elements are best described within the nuclear density functional theory (DFT) and its various extensions. While relatively mature, DFT has never been implemented in its full power, as it relies on a very large number (~ 10^9-10^12) of expensive calculations (~ day). The advent of leadership-class computers, as well as dedicated large-scale collaborative efforts such as the SciDAC 2 UNEDF project, have dramatically changed the field. This article gives an overview of the various computational challenges related to the nuclear DFT, as well as some of the recent achievements.

Schunck, N; Kortelainen, M; McDonnell, J; Mor, J; Nazarewicz, W; Pei, J; Sarich, J; Sheikh, J; Staszczak, A; Stoitsov, M; Wild, S M

2011-01-01T23:59:59.000Z

432

Computing Heavy Elements  

E-Print Network (OSTI)

Reliable calculations of the structure of heavy elements are crucial to address fundamental science questions such as the origin of the elements in the universe. Applications relevant for energy production, medicine, or national security also rely on theoretical predictions of basic properties of atomic nuclei. Heavy elements are best described within the nuclear density functional theory (DFT) and its various extensions. While relatively mature, DFT has never been implemented in its full power, as it relies on a very large number (~ 10^9-10^12) of expensive calculations (~ day). The advent of leadership-class computers, as well as dedicated large-scale collaborative efforts such as the SciDAC 2 UNEDF project, have dramatically changed the field. This article gives an overview of the various computational challenges related to the nuclear DFT, as well as some of the recent achievements.

N. Schunck; A. Baran; M. Kortelainen; J. McDonnell; J. Mor; W. Nazarewicz; J. Pei; J. Sarich; J. Sheikh; A. Staszczak; M. Stoitsov; S. M. Wild

2011-07-25T23:59:59.000Z

433

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

Emergency Response Effects of Radiation History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Agencies U. S. Department of Transportation (DOT), U. S. Nuclear Regulatory Commission (NRC) Postal Services (USPS) U. S. Department of Energy (DOE), National Conference of State Legislatures - Environment, Energy and Transportation Program, Hazardous and Radioactive Materials International Atomic Energy Agency (IAEA) U. S. Environmental Protection Agency (EPA) Regulations Code of Federal Regulations: Title 10 - Energy Code of Federal Regulations: Title 10, PART 71 - Packaging and Transportation of Radioactive Material Code of Federal Regulations: Title 49 - Transportation Code of Federal Regulations: Title 49, PART 173 - Shippers - General

434

ORISE: University Radioactive Ion Beam Consortium  

NLE Websites -- All DOE Office Websites (Extended Search)

UNIRIB UNIRIB Research Overview Physics Topics Equipment Development Education and Training People Publications Overview 2009 Bibliography 2008 Bibliography 2007 Bibliography 2006 Bibliography How to Work With Us Contact Us Oak Ridge Institute for Science Education University Radioactive Ion Beam Consortium The University Radioactive Ion Beam (UNIRIB) consortium is a division of the Oak Ridge Institute for Science and Education (ORISE) focused on cutting-edge nuclear physics research. UNIRIB is a collaborative partnership involving Oak Ridge National Laboratory (ORNL) and nine member universities that leverages national laboratory and university resources to effectively accomplish the U.S. Department of Energy's (DOE) strategic goals in the fundamental structure of nuclei.

435

1969 audit of SRP radioactive waste  

SciTech Connect

This report summarizes releases of radioactive waste to the environs of the Savannah River Plant during the calendar year 1969. Total quantities of radioactive waste released from plant startup through 1969 are also reported. Accuracy is not always implied to the degree indicated by the number of significant figures reported. Values were not rounded off, since data will be used in future cumulative summaries. No explanations are given for unusual releases; this information may be found in the Radiological Sciences Division Monthly Reports and in the Semi-annual and Annual Environmental Monitoring Reports for 1969.

Ashley, C.

1970-04-01T23:59:59.000Z

436

1965 audit of SRP radioactive waste  

SciTech Connect

This report summarizes releases of radioactive waste to the environs of the Savannah River Plant during the calendar year 1965. Total quantities of radioactive waste released from plant startup through 1965 are also reported. Accuracy is not always implied to the degree indicated by the number of significant figures reported. Values were not rounded off, since data will be used in future cumulative summaries. No explanations are given for unusual releases; this information may be found in the Radiological and Environmental Sciences Division Monthly Reports and in the Semi- annual and Annual Environmental Monitoring Reports for 1965.

Ashley, C.

1966-05-01T23:59:59.000Z

437

CRAD, Radioactive Waste Management - June 22, 2009 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radioactive Waste Management - June 22, 2009 Radioactive Waste Management - June 22, 2009 CRAD, Radioactive Waste Management - June 22, 2009 June 22, 2009 Radioactive Waste Management, Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 64-33, Rev. 0) The following provides an overview of the typical activities that will be performed to collect information to evaluate the management of radioactive wastes and implementation of integrated safety management. The following Inspection Activities apply to all Inspection Criteria listed below: Review radioactive waste management and control processes and implementing procedures. Interview personnel including waste management supervision, staff, and subject matter experts. Review project policies, procedures, and corresponding documentation related to ISM core function

438

EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Emer Emer Emer Emer Emer Emergency Response to a T gency Response to a T gency Response to a T gency Response to a T gency Response to a Transportation ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional

439

The Periodic Table of Elements C  

NLE Websites -- All DOE Office Websites (Extended Search)

Atomic Number Chemical Symbol Atomic Weight Chemical Name = Solid at room temperature = Liquid at room temperature = Gas at room temperature = Radioactive = Artificially Made KEY METALS NON-METALS 12.011 http://education.jlab.org/ Last revised on April 3, 2013 [294] H Li Na K Be Mg Ca Sc Ti Rb Cs Fr Sr Y Ba Ra Zr Hf Rf V Nb Ta Db Cr Mo W Sg Mn Tc Re Bh Fe Ru Os Hs Co Rh Ir Mt Ni Pd Pt Ds Cu Ag Au Rg Zn Cd Hg Cn Ga In Tl Uut Ge Sn Pb Fl As Sb Bi Uup Se Te Po Lv Br I At Uus Kr Xe Rn Uuo La Ac Ce Th Pr Pa Nd U Pm Np Sm Pu Eu Am Gd Cm Tb Bk Dy Cf Ho Es Er Fm Tm Md Yb Yb No Lu Lr B Al C Si N P O S F Cl Ne He Ar HYDROGEN LITHIUM SODIUM POTASSIUM BERYLLIUM MAGNESIUM CALCIUM SCANDIUM TITANIUM RUBIDIUM CESIUM FRANCIUM STRONTIUM YTTRIUM BARIUM RADIUM ZIRCONIUM HAFNIUM RUTHERFORDIUM VANADIUM NIOBIUM TANTALUM DUBNIUM CHROMIUM MOLYBDENUM TUNGSTEN SEABORGIUM MANGANESE TECHNETIUM RHENIUM BOHRIUM IRON RUTHENIUM OSMIUM HASSIUM

440

The Periodic Table of Elements C  

NLE Websites -- All DOE Office Websites (Extended Search)

.011 .011 Atomic Number Chemical Symbol Atomic Weight Chemical Name = Solid at room temperature = Liquid at room temperature = Gas at room temperature = Radioactive = Artificially Made KEY METALS NON-METALS http://education.jlab.org/ Last revised on April 3, 2013 [294] H Li Na K Be Mg Ca Sc Ti Rb Cs Fr Sr Y Ba Ra Zr Hf Rf V Nb Ta Db Cr Mo W Sg Mn Tc Re Bh Fe Ru Os Hs Co Rh Ir Mt Ni Pd Pt Ds Cu Ag Au Rg Zn Cd Hg Cn Ga In Tl Uut Ge Sn Pb Fl As Sb Bi Uup Se Te Po Lv Br I At Uus Kr Xe Rn Uuo La Ac Ce Th Pr Pa Nd U Pm Np Sm Pu Eu Am Gd Cm Tb Bk Dy Cf Ho Es Er Fm Tm Md Yb Yb No Lu Lr B Al C Si N P O S F Cl Ne He Ar HYDROGEN LITHIUM SODIUM POTASSIUM BERYLLIUM MAGNESIUM CALCIUM SCANDIUM TITANIUM RUBIDIUM CESIUM FRANCIUM STRONTIUM YTTRIUM BARIUM RADIUM ZIRCONIUM HAFNIUM RUTHERFORDIUM VANADIUM NIOBIUM TANTALUM DUBNIUM CHROMIUM MOLYBDENUM TUNGSTEN SEABORGIUM MANGANESE TECHNETIUM RHENIUM BOHRIUM IRON RUTHENIUM OSMIUM HASSIUM COBALT

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

FUEL ELEMENT CONSTRUCTION  

DOE Patents (OSTI)

A method of preventing diffusible and volatile fission products from diffusing through a fuel element container and contaminating reactor coolant is described. More specifically, relatively volatile and diffusible fission products either are adsorbed by or react with magnesium fluoride or difluoride to form stable, less volatile, less diffusible forms. The magnesium fluoride or difluoride is disposed anywhere inwardly from the outer surface of the fuel element container in order to be contacted by the fission products before they reach and contaminate the reactor coolant. (AEC)

Simnad, M.T.

1961-08-15T23:59:59.000Z

442

Mechanochemical processing for metals and metal alloys  

DOE Patents (OSTI)

A set of processes for preparing metal powders, including metal alloy powders, by ambient temperature reduction of a reducible metal compound by a reactive metal or metal hydride through mechanochemical processing. The reduction process includes milling reactants to induce and complete the reduction reaction. The preferred reducing agents include magnesium and calcium hydride powders. A process of pre-milling magnesium as a reducing agent to increase the activity of the magnesium has been established as one part of the invention.

Froes, Francis H. (Moscow, ID); Eranezhuth, Baburaj G. (Moscow, ID); Prisbrey, Keith (Moscow, ID)

2001-01-01T23:59:59.000Z

443

Environmental restoration and management of low-level radioactive and mixed waste at Oak Ridge National Laboratory  

SciTech Connect

Management of radioactive waste at Oak Ridge National Laboratory (ORNL) must address several major challenges. First, contaminants from some disposed wastes are leaching into the groundwater and these disposal sites must be remediated. Second, some of these ``legacy`` wastes, as well as currently generated radioactive wastes, are also contaminated with chemicals, including polychlorinated biphenyls (PCBs), solvents, and metals (i.e., mixed waste). Third, wastes containing long-lived radionuclides in concentrations above established limits have been determined unsuited for disposal on the Oak Ridge Reservation. Reflecting these challenges, ORNL`s strategy for managing its radioactive wastes continues to evolve with the development of improved technologies and site-specific adaptation of some standard technologies.

Kendrick, C.M.

1994-03-01T23:59:59.000Z

444

DOE - Office of Legacy Management -- Shannon Luminous Metals Co - CA 0-03  

NLE Websites -- All DOE Office Websites (Extended Search)

Shannon Luminous Metals Co - CA Shannon Luminous Metals Co - CA 0-03 FUSRAP Considered Sites Site: SHANNON LUMINOUS METALS CO. (CA.0-03 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Shannon Luminous Metals CA.0-03-3 Location: 7356 Santa Monica Blvd. , Hollywood , California CA.0-03-1 Evaluation Year: 1987 CA.0-03-2 Site Operations: Research and development of uranium use in luminous paint pigments in the 1950s. CA.0-03-1 Site Disposition: Eliminated - No Authority - NRC licensed CA.0-03-3 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium CA.0-03-1 Radiological Survey(s): No Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to SHANNON LUMINOUS METALS CO. CA.0-03-1 - AEC Letter; Burman to Alburger; Subject: AEC License

445

NEUTRONIC REACTOR FUEL ELEMENT  

DOE Patents (OSTI)

A nuclear fuel element comprising a plurality of nuclear fuel bearing strips is presented. The strips are folded along their longitudinal axes to an angle of about 60 deg and are secured at each end by ferrule to form an elongated assembly suitable for occupying a cylindrical coolant channel.

Gurinsky, D.H.; Powell, R.W.; Fox, M.

1959-11-24T23:59:59.000Z

446

Heating element support clip  

DOE Patents (OSTI)

An apparatus for supporting a heating element in a channel formed in a heater base is disclosed. A preferred embodiment includes a substantially U-shaped tantalum member. The U-shape is characterized by two substantially parallel portions of tantalum that each have an end connected to opposite ends of a base portion of tantalum. The parallel portions are each substantially perpendicular to the base portion and spaced apart a distance not larger than a width of the channel and not smaller than a width of a graphite heating element. The parallel portions each have a hole therein, and the centers of the holes define an axis that is substantially parallel to the base portion. An aluminum oxide ceramic retaining pin extends through the holes in the parallel portions and into a hole in a wall of the channel to retain the U-shaped member in the channel and to support the graphite heating element. The graphite heating element is confined by the parallel portions of tantalum, the base portion of tantalum, and the retaining pin. A tantalum tube surrounds the retaining pin between the parallel portions of tantalum.

Sawyer, William C. (Salida, CA)

1995-01-01T23:59:59.000Z

447

All metal valve structure for gas systems  

DOE Patents (OSTI)

A valve assembly with a resilient metal seat member is disclosed for providing a gas-tight seal in a gas handling system. The valve assembly also includes a valve element for sealing against the valve seat member; and an actuating means for operating the valve element. The valve seat member is a one-piece stainless steel ring having a central valve port and peripheral mounting flange, and an annular corrugation in between. A groove between the first and second ridges serves as a flexure zone during operation of the valve member and thus provides the seating pressure between the inner ridge or valve seat and the valve element. The outer annular ridge has a diameter less than said valve element to limit the seating motion of the valve element, preventing non-elastic deformation of the seat member.

Baker, Ray W. (Hamilton, OH); Pawlak, Donald A. (Centerville, OH); Ramey, Alford J. (Miamisburg, OH)

1984-11-13T23:59:59.000Z

448

Mercury and Other Trace Metals in Coal  

Science Conference Proceedings (OSTI)

This document summarizes the trace metal analyses of more than 150 as-received bituminous, sub-bituminous, and lignite coal samples from full-scale power plants. Analyses for mercury, arsenic, beryllium, cadmium, chromium, copper, nickel, and lead offer a benchmark for utilities to compare and contrast their own estimates and measurements of trace element content in coal.

1997-02-25T23:59:59.000Z

449

Mechanical Properties of Cellular Metals: Potential and ...  

Science Conference Proceedings (OSTI)

... emission and decreased consumption of expensive and dwindling resources. ... A Finite Element Analysis for Ring Rolling under a Step-wise Steady State Assumption ... Ab Initio Local Energy and Local Stress Calculations: Applications to .... Multi-resolution Modeling of the Dynamic Loading of Metal Matrix Composites.

450

DOE - Office of Legacy Management -- Metals Disintegrating Co Inc - NJ 0-03  

Office of Legacy Management (LM)

Disintegrating Co Inc - NJ Disintegrating Co Inc - NJ 0-03 FUSRAP Considered Sites Site: METALS DISINTEGRATING CO., INC. (NJ.0-03 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: 271 Grove Avenue , Verona or Elizabeth , New Jersey NJ.0-03-1 NJ.0-03-2 NJ.0-03-3 Evaluation Year: 1987 NJ.0-03-3 Site Operations: Provided nickel to Linde. NJ.0-03-3 NJ.0-03-4 Site Disposition: Eliminated - No radioactive materials were handled at this site. NJ.0-03-3 Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Indicated Radiological Survey(s): None Indicated Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to METALS DISINTEGRATING CO., INC. NJ.0-03-1 - Letter; Goman to Metals Disintegrating Company, Inc.

451

DOE - Office of Legacy Management -- American Machine and Metals Inc - IL  

NLE Websites -- All DOE Office Websites (Extended Search)

Machine and Metals Inc - Machine and Metals Inc - IL 24 FUSRAP Considered Sites Site: American Machine and Metals Inc (IL.24 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: E. Moline , Illinois IL.24-1 Evaluation Year: 1994 IL.24-2 IL.24-3 Site Operations: Tested process for dewatering green salt by centrifugation. IL.24-1 IL.24-2 Site Disposition: Eliminated - Potential for contamination considered remote due to limited amount of radioactive materials handled IL.24-1 IL.24-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium Oxide (Green Salt) IL.24-1 Radiological Survey(s): Health and Safety Monitoring IL.24-1 Site Status: Eliminated from consideration under FUSRAP Also see

452

High-level radioactive wastes. Supplement 1  

SciTech Connect

This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations.

McLaren, L.H. (ed.) [ed.

1984-09-01T23:59:59.000Z

453

A Study of Natural Radioactive Equilibrium  

E-Print Network (OSTI)

minerals are in equilibrium can have significant economic impacts where uranium mining and yellowcake radiometric measurements and the actual uranium content of the ore. Anderson reports that "The miningA Study of Natural Radioactive Equilibrium In Selected Uranium Minerals Erik Hunter Colorado School

454

Radioactive air emissions 1992 summary. Progress report  

Science Conference Proceedings (OSTI)

This report summarizes, by radionuclide or product and by emitting facility, the Laboratory`s 1992 radioactive air emissions. In 1992, the total activity of radionuclides emitted into the air from Laboratory stacks was approximately 73,500 Ci. This was an increase over the activity of the total 1991 radioactive air emissions, which was approximately 62,400 Ci. Total 1992 Laboratory emissions of each radionuclide or product are summarized by tables and graphs in the first section of this report. Compared to 1991 radioactive air emissions, total tritium activity was decreased, total plutonium activity was decreased, total uranium activity was decreased, total mixed fission product activity was increased, total {sup 41}Ar activity was decreased, total gaseous/mixed activation product (except {sup 41}Ar) activity was increased, total particulate/vapor activation product activity was increased, and total {sup 32}P activity was decreased. Radioactive emissions from specific facilities are detailed in this report. Each section provides 1992 data on a single radionuclide or product and is further divided by emitting facility. For each facility from which a particular radionuclide or product was emitted, a bar chart displays the air emissions of each radionuclide or product from each facility over the 12 reporting periods of 1992, a line chart shows the trend in total emissions of that radionuclide or product from that facility for the past three years, the greatest activity during the 1990--1992 period is discussed, and unexpected or unusual results are noted.

Wahl, L. [comp.

1993-10-01T23:59:59.000Z

455

Industry Survey of Radioactive Material Control Practices  

Science Conference Proceedings (OSTI)

Workers and materials entering and exiting the radiation control areas (RCAs) of nuclear power plants are carefully monitored for radioactivity. This report documents a survey developed to evaluate the range of instrumentation and practices used by the industry for performing such measurements.

2003-11-26T23:59:59.000Z

456

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2008  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2008 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

West, B.; Waltz, R.

2009-06-11T23:59:59.000Z

457

CLEANING OF RADIOACTIVE CONTAMINATED OCCUPATIONAL CLOTHING  

SciTech Connect

The soiling and contamination of work clothing and ways of removing this contamination are discussed. Means of disinfection, washing tests with radioactive-contaminated cotton clothing, construction of the laundry, and cleaning protective clothing of plastic and other materials with the help of washing methods and polyphosphates are described. (M.C.G.)

Siewert, G.; Schikora, Th.

1963-11-01T23:59:59.000Z

458

Environmental Radioactivity in Greenland in 1978  

E-Print Network (OSTI)

of fallout radioactivity in Greenland in 1978 are reported. Strontium-90 (and Cesium-137 in most cases, FOOD CHAINS, GLOBAL FALLOUT, GRAPHS, GREENLAND, PLANTS, RADIOAC- TIVITY, SEAWATER, SHEEP, TABLES [1 ' the fallout levels increased similarly from 1977 to 1978. 90 Fig. 2.1 shows the accumulated Sr at the various

459

Environmental Radioactivity in the Faroes in 1978  

E-Print Network (OSTI)

of fallout radioactivity in the Faroes in 137 1978 are presented. Strontium-90 (and Cs in most cases, ENVIRONEMNT, EXPERIMENTAL DATA, FAROE ISLANDS, FISHES, FOOD, FOOD CHAINS, GLOBAL FALLOUT, GRAPHS, MILK, PLANTS to counting) B.D.L. below detection limit #12;5 - 1. INTRODUCTION 1.1. The fallout progress« for the Faroes

460

High-level radioactive waste management alternatives  

SciTech Connect

A summary of a comprehensive overview study of potential alternatives for long-term management of high-level radioactive waste is presented. The concepts studied included disposal in geologic formations, disposal in seabeds, disposal in ice caps, disposal into space, and elimination by transmutation. (TFD)

1974-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive metallic element" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Annual Radioactive Waste Tank Inspection Program - 2000  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2000 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

West, W.R.

2001-04-17T23:59:59.000Z

462

Method for solidifying liquid radioactive wastes  

DOE Patents (OSTI)

The quantity of nitrous oxides produced during the solidification of liquid radioactive wastes containing nitrates and nitrites can be substantially reduced by the addition to the wastes of a stoichiometric amount of urea which, upon heating, destroys the nitrates and nitrites, liberating nontoxic N.sub.2, CO.sub.2 and NH.sub.3.

Berreth, Julius R. (Idaho Fa