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Note: This page contains sample records for the topic "naturally radioactive metallic" 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.


1

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

2

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.

3

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

4

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...

5

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...

6

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

7

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

8

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

9

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

10

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

11

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

12

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

13

Naturally Occurring Radioactive Materials in Cargo at US Borders  

Science Conference Proceedings (OSTI)

In the U.S. and other countries, large numbers of vehicles pass through border crossings each day. The illicit movement of radioactive sources is a concern that has resulted in the installation of radiation detection and identification instruments at border crossing points. This activity is judged to be necessary because of the possibility of an act of terrorism involving a radioactive source that may include any number of dangerous radionuclides. The problem of detecting, identifying, and interdicting illicit radioactive sources is complicated by the fact that many materials present in cargo are somewhat radioactive. Some cargo contains naturally occurring radioactive material or technologically-enhanced naturally occurring radioactive material that may trigger radiation portal monitor alarms. Man-made radioactive sources, especially medical isotopes, are also frequently observed and produce alarms. Such nuisance alarms can be an operational limiting factor for screening of cargo at border crossings. Information about the nature of the radioactive materials in cargo that can interfere with the detection of radionuclides of concern is necessary. This paper provides such information for North American cargo, but the information may also be of use to border control officials in other countries. (PIET-43741-TM-361)

Kouzes, Richard T.; Ely, James H.; Evans, John C.; Hensley, Walter K.; Lepel, Elwood A.; McDonald, Joseph C.; Schweppe, John E.; Siciliano, Edward R.; Strom, Daniel J.; Woodring, Mitchell L.

2006-01-01T23:59:59.000Z

14

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

15

Biomedical aspects of natural and manufactured environmental radioactivity  

SciTech Connect

While weapons testing has altered natural radioactivity background, manufactured radioactivity in most parts of the world constitutes but a very small fraction of the total alpha, beta, and gamma radioactivity in soil, air, water, and the biota. For example, in the early 1970s, we found what appeared to be the highest natural concentration of radioactivity ever reported in fish while attempting to measure the manufactured plutonium ({sup 239}Pu and {sup 240}Pu) in organs of oceanic tuna. The natural alpha emitter polonium ({sup 210}Po) was discovered in the same organs at orders of magnitude higher concentrations. In particular, the caecum, which is a digestive organ composed of many small closed-ended sacs, contained concentrations of polonium as high as 79 pCi/g of wet tissue and lesser amounts of two manufactured isotopes: 0.0001 pCi/g of plutonium and 0.01 pCi/g of radiocesium ({sup 137}Cs). This equates to {approximately}80 rem/yr of radiation dose to this organ, overwhelmingly from the natural polonium, or {approximately}5000 times higher than is found in the human liver, the highest polonium concentration in man. The average background radiation for humans, for comparison, is {approximately}0.2 rem/yr, but the dose for Japanese, whose diet is high in seafood, is {approximately}15 rem/yr. The question arose: {open_quotes}Are these high concentrations of natural polonium limited to oceanic fish?{close_quotes} To answer this question, polonium was determined in the organs of striped bass and catfish from Lake Mead. In a related study, the plutonium and radiocesium ({sup 137}Cs) distributions in soils were determined to ascertain the impact of weapons testing on the natural background radioactivity of soils.

Hodge, V. [Univ. of Nevada, Las Vegas, NV (United States)

1996-12-31T23:59:59.000Z

16

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

17

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

18

Naturally occurring crystalline phases: analogues for radioactive waste forms  

SciTech Connect

Naturally occurring mineral analogues to crystalline phases that are constituents of crystalline radioactive waste forms provide a basis for comparison by which the long-term stability of these phases may be estimated. The crystal structures and the crystal chemistry of the following natural analogues are presented: baddeleyite, hematite, nepheline; pollucite, scheelite;sodalite, spinel, apatite, monazite, uraninite, hollandite-priderite, perovskite, and zirconolite. For each phase in geochemistry, occurrence, alteration and radiation effects are described. A selected bibliography for each phase is included.

Haaker, R.F.; Ewing, R.C.

1981-01-01T23:59:59.000Z

19

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

20

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

22

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

23

Is anyone regulating naturally occurring radioactive material? A state survey  

SciTech Connect

As far as we know, naturally occurring radioactive material (NORM) has surrounded humankind since the beginning of time. However, recent data demonstrating that certain activities concentrate NORM have increased concern regarding its proper handling and disposal and precipitated the development of new NORM-related regulations. The regulation of NORM affects the management of government facilities as well as a broad range of industrial processes. Recognizing that NORM regulation at the federal level is extremely limited, Argonne National Laboratory (ANL) conducted a 50-state survey to determine the extent to which states have assumed the responsibility for regulating NORM as well as the NORM standards that are currently being applied at the state level. Though the survey indicates that NORM regulation comprises a broad spectrum of controls from full licensing requirements to virtually no regulation at afl, a trend is emerging toward recognition of the need for increased regulation of potential NORM hazards, particularly in the absence of federal standards.

Gross, E.M.; Barisas, S.G.

1993-08-01T23:59:59.000Z

24

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

25

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

26

Regulatory Initiatives for Control and Release of Technologically Enhanced Naturally-Occurring Radioactive Materials  

Science Conference Proceedings (OSTI)

Current drafts of proposed standards and suggested State regulations for control and release of technologically-enhanced naturally-occurring radioactive material (TENORM), and standards for release of volumetrically-contaminated material in the US are reviewed. These are compared to the recommendations of the International Atomic Energy Association (IAEA) Safety Series and the European Commission (EC) proposals. Past regulatory efforts with respect to TENORM in the US dealt primarily with oil-field related wastes. Currently, nine states (AK, GA, LA, MS, NM, OH, OR SC, TX) have specific regulations pertaining to TENORM, mostly based on uranium mill tailings cleanup criteria. The new US proposals are dose- or risk-based, as are the IAEA and EC recommendations, and are grounded in the linear no threshold hypothesis (LNT). TENORM wastes involve extremely large volumes, particularly scrap metal and mine wastes. Costs to control and dispose of these wastes can be considerable. The current debate over the validity of LNT at low doses and low dose rates is particularly germane to this discussion. Most standards setting organizations and regulatory agencies base their recommendations on the LNT. The US Environmental Protection Agency has released a draft Federal Guidance Report that recommends calculating health risks from low-level exposure to radionuclides based on the LNT. However, some scientific and professional organizations are openly questioning the validity of LNT and its basis for regulations, practices, and costs to society in general. It is not clear at this time how a non-linear regulatory scheme would be implemented.

Egidi, P.V.

1999-03-02T23:59:59.000Z

27

Study finds radioactivity around Los Alamos largely due to natural...  

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

received by Los Alamos residents are natural. Less than 1 percent is due to global fallout resulting from worldwide early-stage nuclear weapons testing. Where the LANL study...

28

Radiological dose assessment related to management of naturally occurring radioactive materials generated by the petroleum industry  

Science Conference Proceedings (OSTI)

A preliminary radiological dose assessment related to equipment decontamination, subsurface disposal, landspreading, equipment smelting, and equipment burial was conducted to address concerns regarding the presence of naturally occurring radioactive materials in production waste streams. The assessment evaluated the relative dose of these activities and included a sensitivity analysis of certain input parameters. Future studies and potential policy actions are recommended.

Smith, K.P.; Blunt, D.L.; Williams, G.P.; Tebes, C.L. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1995-05-01T23:59:59.000Z

29

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

30

Role of natural organic matter in governing the bioavailability of toxic metals to american oysters  

E-Print Network (OSTI)

Colloidal macromolecular organic matter (COM), which makes up a large portion of the bulk dissolved organic matter (DOM) in marine environments, has the capability to modify the bioavailability of potentially toxic metals to aquatic organisms. In order to better understand the bioavailability of some of these metals to estuarine bivalves, American Oysters (Crassostrea virginica) were exposed to different types of natural colloidal (COM) and model (alginic acid, carrageenan, and latex particles) organic biopolymers, tagged with gamma-emitting radioactive metal ions (110mAg, 109Cd, 57Co, 51Cr, 59Fe, 203Hg and 65Zn) or 14C (to sugar OH groups). Natural COM was obtained from Galveston Bay water by 0.5µm filtration, followed by cross-flow ultrafiltration, using a 1kDa ultrafilter, diafiltration and freeze-drying. COM and DOM model compounds were used in the bioavailability experiments at 2 ppm concentrations. Separate 16-hour experiments using varying sizes of latex particles assessed the lowest size of colloids that can be filtered from the water. Results showed that filter-feeding bivalves could efficiently remove particles as small as 0.04µm (40nm) in diameter, with removal halftimes of 2.5 to 5.5 hours, equivalent to filtration rates of about 50±15 ml/hour, or about 3 L d-1 g-1, which are typical values for these oysters. Results of the 20-hour bioavailability experiments demonstrated that oysters could effectively filter metals bound to COM, with the metals bound to alginic acid COM being removed at the highest rates from the water. However, the metals bound to alginic acid were not found in oyster meat in the highest amounts: it was the metals associated with the carrageenan COM. The 14C labeled biopolymer data also showed alginic acid to be removed from the water at the highest rate and, contrary to the metals, was also present in the meat in the greatest amounts. Thus, while previous experiments suggested that the quantity (i.e., concentration) of natural organic matter is important for metal bioavailability, it was shown here that the ?quality?, i.e., the type of natural organic matter, is also a factor for controlling bioavailability, removal and incorporation rates of metals to oysters.

Haye, Jennifer Marcelle

2005-05-01T23:59:59.000Z

31

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

32

Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry  

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

Tebes is affiliated with the University of Illinois. Tebes is affiliated with the University of Illinois. ANL/EAD-2 Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry by K.P. Smith, D.L. Blunt, G.P. Williams, and C.L. Tebes * Environmental Assessment Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 September 1996 Work sponsored by the United States Department of Energy, Office of Policy iii CONTENTS ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii NOTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viii ABSTRACT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

33

Bibliography of reports, papers, and presentations on naturally occurring radioactive material (NORM) in petroleum industry wastes  

Science Conference Proceedings (OSTI)

This bibliography was created to support projects conducted by Argonne National Laboratory (ANL) addressing issues related to naturally occurring radioactive material (NORM) in petroleum industry wastes. The bibliography provides citations for many of the available published reports, papers, articles, and presentations on petroleum industry NORM. In the past few years, the rapid expansion of NORM treatment and disposal technologies, the efforts to characterize NORM wastes and their associated potential risks, and the promulgation of state-level NORM regulatory programs have been well-documented in project reports and in papers presented at technical conferences and symposia. There are 221 citations.

Smith, K.P.; Wilkey, M.L.; Hames, R.D.

1997-07-01T23:59:59.000Z

34

Alternatives for the disposal of NORM (naturally occurring radioactive materials) wastes in Texas  

SciTech Connect

Some of the Texas wastes containing naturally occurring radioactive materials (NORM) have been disposed of in a uranium mill tailings impoundment. There is currently no operating disposal facility in Texas to accept these wastes. As a result, some wastes containing extremely small amounts of radioactivity are sent to elaborate disposal sites at extremely high costs. The Texas Low-Level Radioactive Waste Disposal Authority has sponsored a study to investigate lower cost, alternative disposal methods for certain wastes containing small quantities of NORM. This paper presents the results of a multipathway safety analysis of various scenarios for disposing of wastes containing limited quantities of NORM in Texas. The wastes include pipe scales and sludges from oil and gas production, residues from rare-earth mineral processing, and water treatment resins, but exclude large-volume, diffuse wastes (coal fly ash, phosphogypsum). The purpose of the safety analysis is to define concentration and quantity limits for the key nuclides of NORM that will avoid dangerous radiation exposures under different waste disposal scenarios.

Nielson, K.K.; Rogers, V.C. (Rogers Associates Engineering Corporation, Salt Lake City, UT (USA)); Pollard, C.G. (Texas Low-Level Radioactive Waste Disposal Authority, Austin (USA))

1989-11-01T23:59:59.000Z

35

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

36

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

37

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

38

In-situ remediation of naturally occurring radioactive materials with high-permeability hydraulic fracturing  

E-Print Network (OSTI)

This thesis addresses the problem of removal of Naturally Occurring Radioactive Materials, NORM, and describes an effective alternative to the current treatment method for their removal. High-pen-meability fracturing, recently established in the petroleum industry, is the recommended technique. NORM are found throughout subterranean formations. Whenever fluids from petroleum or water reservoirs are produced NORM are present in varying quantities. NORM can only be sensed with radiation detectors. However, they have proven carcinogens, and the US Environmental Protection Agency has set a limit on the maximum contaminated level of any stream. Until now, the preferred method of treatment was to remove NORM from contaminated waters with specially designed filters, which in turn create a new problem. The same filters that are used to treat the water themselves become highly radioactive with a considerable disposal problem. In the petroleum industry, NORM become concentrated in the scale that is deposited inside the well or surface pipes. When scale is removed, it can be so radioactive that it can only be stored in toxic sites. Additionally, as water is produced along with oil, so are NORM. Until now, for the Gulf of Mexico at least, produced water has been released into the ocean, but the Environmental Protection Agency (EPA) is threatening to change this. In the North Sea the regulations are already stricter. There is then a compelling motivation to remove NORM before they are produced, and thus, eliminate the disposal problem. A high-permeability fracture design is presented which modifies existing petroleum practices by introducing within the proppant pack highly selective radionuclide sorbents. These sorbents, at calculated concentrations, can remove NORM readily for several years from typical flow rates containing typical NORM concentrations.

Demarchos, Andronikos Stavros

1998-01-01T23:59:59.000Z

39

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

40

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

42

The use of natural gas for reduction of metal oxides: constraints and ...  

Science Conference Proceedings (OSTI)

Presentation Title, The use of natural gas for reduction of metal oxides: constraints ... Reaction mechanism and reaction rate of Sn evaporation from liquid steel.

43

Natural radioactivity in geothermal waters, Alhambra Hot Springs and nearby areas, Jefferson County, Montana  

DOE Green Energy (OSTI)

Radioactive hot springs issue from a fault zone in crystalline rock of the Boulder batholith at Alhambra, Jefferson County, in southwestern Montana. The discharge contains high concentrations of radon, and the gross activity and the concentration of radium-226 exceed maximum levels recommended by the Environmental Protection Agency for drinking water. Part of the discharge is diverted for space heating, bathing, and domestic use. The radioactive thermal waters at measured temperatures of about 60/sup 0/C are of the sodium bicarbonate type and saturated with respect to calcium carbonate. Radium-226 in the rock and on fractured surfaces or coprecipitated with calcium carbonate probably is the principal source of radon that is dissolved in the thermal water and discharged with other gases from some wells and springs. Local surface water and shallow ground water are of the calcium bicarbonate type and exhibit low background radioactivity. The temperature, percent sodium, and radioactivity of mixed waters adjacent to the fault zone increase with depth. Samples from most of the major hot springs in southwestern Montana have been analyzed for gross alpha and beta. The high level of radioactivity at Alhambra appears to be related to leaching of radioactive material from fractured siliceous veins by ascending thermal waters, and is not a normal characteristic of hot springs issuing from fractured crystalline rock in Montana.

Leonard, R.B.; Janzer, W.J.

1977-08-01T23:59:59.000Z

44

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

45

Fractal nature of medium-range order in metallic glasses  

Science Conference Proceedings (OSTI)

The atomic structure of metallic glasses has been a long-standing scientific mystery. Unlike crystalline metals, where long-range ordering is established by periodic stacking of fundamental building blocks known as unit cells, a metallic glass has no long-range translational order, although some degrees of short- and medium-range order do exist.1,2,3 Previous studies1,2,3,4 have identified solute-centered clusters, characterized by short-range order (SRO) in favor of unlike bonds, as the fundamental building blocks of metallic glasses. However, how these building blocks are connected or packed to form the medium range order (MRO) remains an open question.1,2,3 Here, based on neutron and x-ray diffraction experiments, we propose a new packing scheme - the self-similar packing of atomic clusters. We show that MRO has the characteristics of a fractal network with a dimension of 2.38, and is described by a power-law correlation function over the medium-range length scale. Our finding provides a new prospective of order in disordered materials and has broad implications for understanding the structure-property relationship in metallic glasses, particularly those involving change in length scales due to phase transformation and mechanical deformation.

Ma, Dong [ORNL; Stoica, Alexandru Dan [ORNL; Wang, Xun-Li [ORNL

2009-01-01T23:59:59.000Z

46

Applying Information From Analogue Systems to the Evaluation of Radioactive Waste Repositories: Proceedings of the EPRI Natural Analogues Workshop - Palo Alto, California - October 9-10, 2003  

Science Conference Proceedings (OSTI)

Natural analogue studies involve investigations of geological, archaeological, or industrial systems that bear some similarity to material components or processes related to a repository or its surrounding environment. Since the initiation of natural analogue studies in the 1970s, their number has grown and their use has matured to become a common and important supporting activity in evaluating the safety of radioactive waste storage or disposal. This report documents the proceedings of EPRI's Natural An...

2003-12-09T23:59:59.000Z

47

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

48

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

49

The importance of transport parameter cross correlations in natural systems radioactive transport models  

Science Conference Proceedings (OSTI)

Transport parameter cross correlations are rarely considered in models used to predict radionuclide transport in natural systems. In this paper, it is shown that parameter cross correlations could have a significant impact on radionuclide transport predictions in saturated media. In fractured rock, the positive correlation between fracture apertures and groundwater residence times is shown to result in significantly less retardation due to matrix diffusion than is predicted without the correlation. The suppression of matrix diffusion is further amplified by a tendency toward larger apertures, smaller matrix diffusion coefficients, and less sorption capacity in rocks of lower matrix porosity. In a hypothetical example, strong cross correlations between these parameters result in a decrease in predicted radionuclide travel times of an order of magnitude or more relative to travel times calculated with uncorrelated parameters. In porous media, expected correlations between permeability, porosity, and sorption capacity also result in shorter predicted travel times than when the parameters are assumed to be uncorrelated. Individual parameter standard deviations can also have a significant influence on predicted radionuclide travel times, particularly when cross correlations are considered.

Reimus, Paul W [Los Alamos National Laboratory

2011-01-03T23:59:59.000Z

50

Transition metal catalysis in the generation of petroleum and natural gas. Progress report, [1992--1993  

DOE Green Energy (OSTI)

A new hypothesis is introduced for the generation of petroleum and natural gas. The transition metals, activated under the reducing conditions of diagenesis, are proposed as catalysts in the generation of light hydrocarbons. The objective of this proposal is to test that hypothesis. Transition metals (Ni, V, Ti, Co, Fe), in kerogen, porphyrins, and as pure compounds, will be tested under catagenic conditions for catalytic activity in the conversion of normal paraffins and hydrogen into light hydrocarbons. If the hypothesis is correct, kerogenous transition metals should become catalytically active under the reducing conditions of diagenesis and catalyze the conversion of paraffins into the light hydrocarbons seen in petroleum. Moreover, the C{sub 1}-C{sub 4} hydrocarbons generated catalytically should be similar in molecular and isotopic compositions to natural gas.

Mango, F.

1993-08-01T23:59:59.000Z

51

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

52

Enhanced Natural Convection in a Metal Layer Cooled by Boiling Water  

Science Conference Proceedings (OSTI)

An experimental study is performed to investigate the natural convection heat transfer characteristics and the solidification of the molten metal pool concurrently with forced convective boiling of the overlying coolant to simulate a severe accident in a nuclear power plant. The relationship between the Nusselt number (Nu) and the Rayleigh number (Ra) in the molten metal pool region is determined and compared with the correlations in the literature and experimental data with subcooled water. Given the same Ra condition, the present experimental results for Nu of the liquid metal pool with coolant boiling are found to be higher than those predicted by the existing correlations or measured from the experiment with subcooled boiling. To quantify the observed effect of the external cooling on the natural convection heat transfer rate from the molten pool, it is proposed to include an additional dimensionless group characterizing the temperature gradients in the molten pool and in the external coolant region. Starting from the Globe and Dropkin correlation, engineering correlations are developed for the enhancement of heat transfer in the molten metal pool when cooled by an overlying coolant. The new correlations for predicting natural convection heat transfer are applicable to low-Prandtl-number (Pr) materials that are heated from below and solidified by the external coolant above. Results from this study may be used to modify the current model in severe accident analysis codes.

Cho, Jae-Seon [Seoul National University (Korea, Republic of); Suh, Kune Y. [Seoul National University (Korea, Republic of); Chung, Chang-Hyun [Seoul National University (Korea, Republic of); Park, Rae-Joon [Korea Atomic Energy Research Institute (Korea, Republic of); Kim, Sang-Baik [Korea Atomic Energy Research Institute (Korea, Republic of)

2004-12-15T23:59:59.000Z

53

Salton Sea Geothermal Field, California, as a near-field natural analog of a radioactive waste repository in salt  

DOE Green Energy (OSTI)

Since high concentrations of radionuclides and high temperatures are not normally encountered in salt domes or beds, finding an exact geologic analog of expected near-field conditions in a mined nuclear waste repository in salt will be difficult. The Salton Sea Geothermal Field, however, provides an opportunity to investigate the migration and retardation of naturally occurring U, Th, Ra, Cs, Sr and other elements in hot brines which have been moving through clay-rich sedimentary rocks for up to 100,000 years. The more than thirty deep wells drilled in this field to produce steam for electrical generation penetrate sedimentary rocks containing concentrated brines where temperatures reach 365/sup 0/C at only 2 km depth. The brines are primarily Na, K, Ca chlorides with up to 25% of total dissolved solids; they also contain high concentrations of metals such as Fe, Mn, Li, Zn, and Pb. This report describes the geology, geophysics and geochemistry of this system as a prelude to a study of the mobility of naturally occurring radionuclides and radionuclide analogs within it. The aim of this study is to provide data to assist in validating quantitative models of repository behavior and to use in designing and evaluating waste packages and engineered barriers. 128 references, 33 figures, 13 tables.

Elders, W.A.; Cohen, L.H.

1983-11-01T23:59:59.000Z

54

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...

55

ALPHA RADIOACTIVITY OF E > 11 MEV IN NATURE A. CHEVALLIER, J. CHEVALLIER, A. PAPE and M. DEBEAUVAIS  

E-Print Network (OSTI)

to the problem, we took as a starting point the research for anomalous a-radioactivities, principally in uranium-thorium containing mine- rals [3] (Monazites from Madagascar). For the present study, electronic counting and nuclear

Paris-Sud XI, Université de

56

EVALUATION OF NATURAL AND IN-SITU REMEDIATION TECHNOLOGIES FOR A COAL-RELATED METALS PLUME  

SciTech Connect

Metals contamination exceeding drinking water standards (MCLs) is associated with acidic leachate generated from a coal pile runoff basin at the Savannah River Site (SRS) in Aiken, South Carolina. The metals plume extends over 100 acres with its' distal boundary about onehalf mile from the Savannah River. Based on the large plume extent and high dissolved iron and aluminum concentrations, conventional treatment technologies are likely to be ineffective and cost prohibitive. In-situ bioremediation using existing groundwater microbes is being evaluated as a promising alternative technology for effective treatment, along with consideration of natural attenuation of the lower concentration portions of the plume to meet remedial goals. Treatment of the high concentration portion of the groundwater plume by sulfate-reducing bacteria (SRB) is being evaluated through laboratory microcosm testing and a field-scale demonstration. Organic substrates are added to promote SRB growth. These bacteria use dissolved sulfate as an electron acceptor and ultimately precipitate dissolved metals as metal sulfides. Laboratory microcosm testing indicate SRB are present in groundwater despite low pH conditions, and that their growth can be stimulated by soybean oil and sodium lactate. The field demonstration consists of substrate injection into a 30-foot deep by 240-foot long permeable trench. Microbial activity is demonstrated by an increase in pH from 3 to 6 within the trench. Downgradient monitoring will be used to evaluate the effectiveness of SRB in reducing metal concentrations. Natural attenuation (NA) is being evaluated for the low concentration portion of the plume. A decrease in metal mobility can occur through a variety of abiotically and/or biotically mediated mechanisms. Quantification of these mechanisms is necessary to more accurately predict contaminant attenuation using groundwater transport models that have historically relied on simplified conservative assumptions. Result s from matched soil/porewater samples indicate higher soil/water partition coefficients (Kds) with increasing distance from the source. In addition, site-specific metals availability is being assessed using sequential extraction techniques, which more accurately represent environmental conditions as compared to default EPA extraction methods. Due to elevated sulfate levels in the plume, SRB are most likely to be the dominant biotic contributor to NA processes.

Ross, Jeffrey A.; Bayer, Cassandra L.; Socha, Ronald P.; Sochor,Cynthia S.; Fliermans, Carl B.; McKinsey, Pamela C.; Millings, Margaret R.; Phifer, Mark A.; Powell, Kimberly R.; Serkiz, Steven M.; Sappington, Frank C.; Turick, Charles E.

2003-02-27T23:59:59.000Z

57

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

58

Natural Circulation and Linear Stability Analysis for Liquid-Metal Reactors with the Effect of Fluid Axial Conduction  

SciTech Connect

The effect of fluid axial thermal conduction on one-dimensional liquid metal natural circulation and its linear stability was performed through nondimensional analysis, steady-state assessment, and linear perturbation evaluation. The Nyquist criterion and a root-search method were employed to find the linear stability boundary of both forward and backward circulations. The study provided a relatively complete analysis method for one-dimensional natural circulation problems with the consideration of fluid axial heat conduction. The results suggest that fluid axial heat conduction in a natural circulation loop should be considered only when the modified Peclet number is {approx}1 or less, which is significantly smaller than the practical value of a lead liquid metal-cooled reactor.

Piyush Sabharwall; Qiao Wu; James J. Sienicki

2012-06-01T23:59:59.000Z

59

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

60

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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.


61

Investigation of the nature of electronic states in the alkali_metal oxides  

Science Conference Proceedings (OSTI)

Hartree-Fock and Density functional theories have been applied to investigate the density of electronic states and electronic band structures. We studied: oxides, peroxides, nadoxides and ozonides, alkali-metal oxides M2O, peroxides M2O2, ...

O. O. Obolonskaya

2010-05-01T23:59:59.000Z

62

Summary of Natural Resources that Potentially Influence Human Intrusion at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada  

DOE Green Energy (OSTI)

In 1993, Raytheon Services Nevada completed a review of natural resource literature and other sources to identify potentially exploitable resources and potential future land uses near the Area 5 Radioactive Waste Management Site (RWMS) of the Nevada Test Site (NTS), Nye County, Nevada, that could lead to future inadvertent human intrusion and subsequent release of radionuclides to the accessible environment. National Security Technologies, LLC, revised the original limited-distribution document to conform to current editorial standards and U.S. Department of Energy requirements for public release. The researchers examined the potential for future development of sand, gravel, mineral, petroleum, water resources, and rural land uses, such as agriculture, grazing, and hunting. The study was part of the performance assessment for Greater Confinement Disposal boreholes. Sand and gravel are not considered exploitable site resources because the materials are common throughout the area and the quality at the Area 5 RWMS is not ideal for typical commercial uses. Site information also indicates a very low mineral potential for the area. None of the 23 mining districts in southern Nye County report occurrences of economic mineral deposits in unconsolidated alluvium. The potential for oil and natural gas is low for southern Nye County. No occurrences of coal, tar sand, or oil shale on the NTS are reported in available literature. Several potential future uses of water were considered. Agricultural irrigation is impractical due to poor soils and existing water supply regulations. Use of water for geothermal energy development is unlikely because temperatures are too low for typical commercial applications using current technology. Human consumption of water has the most potential for cause of intrusion. The economics of future water needs may create a demand for the development of deep carbonate aquifers in the region. However, the Area 5 RWMS is not an optimal location for extraction of groundwater from the deep carbonate aquifer. Grazing and hunting are unlikely to be potential causes for inadvertent human intrusion into waste areas because of vegetation characteristics and lack of significant game animal populations.

NSTec Environmental Management

2007-06-01T23:59:59.000Z

63

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

64

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

65

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

66

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.

67

Natural  

Gasoline and Diesel Fuel Update (EIA)

Summary of U.S. Natural Gas Imports and Exports, 1992-1996 Table 1992 1993 1994 1995 1996 Imports Volume (million cubic feet) Pipeline Canada............................. 2,094,387 2,266,751 2,566,049 2,816,408 2,883,277 Mexico .............................. 0 1,678 7,013 6,722 13,862 Total Pipeline Imports....... 2,094,387 2,268,429 2,573,061 2,823,130 2,897,138 LNG Algeria .............................. 43,116 81,685 50,778 17,918 35,325 United Arab Emirates ....... 0 0 0 0 4,949 Total LNG Imports............. 43,116 81,685 50,778 17,918 40,274 Total Imports......................... 2,137,504 2,350,115 2,623,839 2,841,048 2,937,413 Average Price (dollars per thousand cubic feet) Pipeline Canada............................. 1.84 2.02 1.86 1.48 1.96 Mexico .............................. - 1.94 1.99 1.53 2.25 Total Pipeline Imports.......

68

In Vitro Evolution of a Peptide with a Hematite Binding Motif That May Constitute a Natural Metal-Oxide Binding Archetype  

DOE Green Energy (OSTI)

Phage-display technology was used to evolve peptides that selectively bind to the metal-oxide hematite (Fe2O3) from a library of approximately 3 billion different polypeptides. The sequences of these peptides contained the highly conserved amino acid motif, Ser/Thr-hydrophobic/aromatic-Ser/Thr-Pro-Ser/Thr. To better understand the nature of the peptide?metal oxide binding demonstrated by these experiments, molecular dynamics simulations were carried out for Ser-Pro-Ser at a hematite surface. These simulations show that hydrogen bonding occurs between the two serine amino acids and the hydroxylated hematite surface and that the presence of proline between the hydroxide residues restricts the peptide flexibility, thereby inducing a structural-binding motif. A search of published sequence data revealed that the binding motif (Ser/Thr-Pro-Ser/Thr) is adjacent to the terminal heme-binding domain of both OmcA and MtrC, which are outer membrane cytochromes from the metal-reducing bacterium Shewanella oneidensis MR-1. The entire five amino acid consensus sequence (Ser/Thr-hydrophobic/aromatic-Ser/Thr-Pro-Ser/Thr) was also found as multiple copies in the primary sequences of metal-oxide binding proteins Sil1 and Sil2 from Thalassiosira pseudonana. We suggest that this motif constitutes a natural metal-oxide binding archetype that could be exploited in enzyme-based biofuel cell design and approaches to synthesize tailored metal-oxide nanostructures.

Lower, Brian H.; Lins, Roberto D.; Oestreicher, Zachery W.; Straatsma, TP; Hochella Jr., Michael F.; Shi, Liang; Lower, Steven

2008-05-15T23:59:59.000Z

69

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

70

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

71

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

72

Simulao de redes porosas metal-orgnicas usadas no armazenamento de gs natural.  

E-Print Network (OSTI)

??The natural gas is mainly stored in vessels by its compression at very high pressure. This pressure can be decreased by the natural gas storage (more)

Elisa Soares Leite

2007-01-01T23:59:59.000Z

73

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

74

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!

75

EFFECTS ON CHP PLANT EFFICIENCY OF H2 PRODUCTION THROUGH PARTIAL OXYDATION OF NATURAL GAS OVER TWO GROUP VIII METAL  

E-Print Network (OSTI)

EFFECTS ON CHP PLANT EFFICIENCY OF H2 PRODUCTION THROUGH PARTIAL OXYDATION OF NATURAL GAS OVER TWO with natural gas in spark ignition engines can increase for electric efficiency. In-situ H23 production for spark ignition engines fuelled by natural gas has therefore been investigated recently, and4 reformed

76

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...

77

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

78

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

79

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...

80

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

82

Prompt Neutron Decay for Delayed Critical Bare and Natural-Uranium-Reflected Metal Spheres of Plutonium and Highly Enriched Uranium  

Science Conference Proceedings (OSTI)

Prompt neutron decay at delayed criticality was measured by Oak Ridge National Laboratory for uranium-reflected highly enriched uranium (HEU) and Pu metal spheres (FLATTOP), for an unreflected Pu metal (4.5% {sup 240}Pu) sphere (JEZEBEL) at Los Alamos National Laboratory (LANL) and for an unreflected HEU metal sphere at Oak Ridge Critical Experiments Facility. The average prompt neutron decay constants from hundreds of Rossi-{alpha} and randomly pulsed neutron measurements with {sup 252}Cf at delayed criticality are as follows: 3.8458 {+-} 0.0016 x 10{sup 5} s{sup -1}, 2.2139 {+-} 0.0022 x 10{sup 5} s{sup -1}, 6.3126 {+-} 0.0100 x 10{sup 5} s{sup -1}, and 1.1061 {+-} 0.0009 x 10{sup 6} s{sup -1}, respectively. These values agree with previous measurements by LANL for FLATTOP, JEZEBEL, and GODIVA I as follows: 3.82 {+-} 0.02 x 10{sup 5} s{sup -1} for a uranium core; 2.14 {+-} 0.05 x 10{sup 5} s{sup -1} and 2.29 x 10{sup 5} s{sup -1} (uncertainty not reported) for a plutonium core; 6.4 {+-} 0.1 x 10{sup 5} s{sup -1}, and 1.1 {+-} 0.1 x 10{sup 6} s{sup -1}, respectively, but have smaller uncertainties because of the larger number of measurements. For the FLATTOP and JEZEBEL assemblies, the measurements agree with calculations. Traditionally, the calculated decay constants for the bare uranium metal sphere GODIVA I and the Oak Ridge Uranium Metal Sphere were higher than experimental by {approx}10%. Other energy-dependent quantities for the bare uranium sphere agree within 1%.

Mihalczo, John T [ORNL

2011-01-01T23:59:59.000Z

83

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

84

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...

85

Spitzer Infrared Spectrograph Observations of Magellanic Cloud Planetary Nebulae: the nature of dust in low metallicity circumstellar ejecta  

E-Print Network (OSTI)

We present 5 - 40 micron spectroscopy of 41 planetary nebulae (PNe) in the Magellanic Clouds, observed with the Infrared Spectrograph on board the Spitzer Space Telescope. The spectra show the presence of a combination of nebular emission lines and solid-state features from dust, superimposed on the thermal IR continuum. By analyzing the 25 LMC and 16 SMC PNe in our sample we found that the IR spectra of 14 LMC and 4 SMC PNe are dominated by nebular emission lines, while the other spectra show solid-state features. We observed that the solid-state features are compatible with carbon-rich dust grains (SiC, polycyclic aromatic hydrocarbons (PAHs), etc.) in most cases, except in three PNe showing oxygen-rich dust features. The frequency of carbonaceous dust features is generally higher in LMC than in SMC PNe. The spectral analysis allowed the correlations of the dust characteristics with the gas composition and morphology, and the properties of the central stars. We found that: 1) all PNe with carbonaceous dust features have C/O>1, none of these being bipolar or otherwise highly asymmetric; 2) all PNe with oxygen-rich dust features have C/Oproduction efficiency depends on metallicity, with low metallicity environments not favoring dust production.

L. Stanghellini; P. Garcia-Lario; D. A. Garcia-Hernandez; J. V. Perea-Calderon; J. E. Davies; A. Manchado; E. Villaver; R. A. Shaw

2007-09-04T23:59:59.000Z

86

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

87

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

88

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...

89

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

90

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

91

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).

92

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

93

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

94

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 ...

95

Thermohydraulic investigations by decay heat removal systems; By natural convection for liquid-metal fast breeder reactors  

SciTech Connect

This paper reports, to examine the function of the safety-related SNR-2 decay heat removal concept, natural convection experiments performed in two-and three-dimensional water models, scaled 1:20, under conditions of symmetric and nonsymmetric loads of the immersed coolers installed in the upper plenum at 180-deg positions with respect to each other. The temperature and velocity distributions were measured and the flow patterns recorded for different configurations of the instrumented plug. For symmetric load conditions, symmetric temperature and flow distributions were measured in two- and three-dimensional models. Nonsymmetric load conditions produce remarkable temperature differences between the two separated plenums of the two-dimensional model if fluid circulation is suppressed by a closed plug. An open plug allows fluid to pass through and shows lower temperature differences. In contrast, in the three-dimensional experiment, azimuthal fluid flow inside the plenum prevails even with the plug closed, and identical temperature distributions are measured. The calculations using the COMMIX-1B code are generally in good agreement with the measurements.

Hoffmann, H.; Weinberg, D. (Kernforschungszentrum Karlsruhe GmbH Institut fur Reaktorbaulemente, Postfach 3640, 7500 Karsruhe 1 (DE)); Ieday (Power Reactor and Nuclear Fuel Development Corporation Oarai Engineering Center, Oarai (JP)); Martex, K.; Tschoke, H.H.; Dres, K. (Kernforschungszentrum Karlsruhe GmbH, Institut fur Reaktorbauelemente, Postfach 3640, 7500 Karlsruhe 1 (DE))

1989-10-01T23:59:59.000Z

96

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

97

Disposal of low-level radioactive biomedical wastes: a problem in regulation, not science  

SciTech Connect

The author discusses the public fear of radiation at any level, and shows how small the radioactivity from radioactive medical waste is compared to natural radioactivity. In view of this the author argues for a change in the Nuclear Regulatory Commission rules.

Yalow, R.S.

1981-05-01T23:59:59.000Z

98

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

99

DOE - Safety of Radioactive Material Transportation  

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

Specific Activity Specific Activity Low Specific Activity (LSA) material means Class 7 (radioactive) material with limited specific activity which satisfies the descriptions and limits set forth below. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. LSA material must be in one of three groups: LSA-I (i) Ores containing only naturally occurring radionuclides (e.g., uranium, thorium) and uranium or thorium concentrates of such ores; or (ii) Solid unirradiated natural uranium or depleted uranium or natural thorium or their solid or liquid compounds or mixtures; or (iii) Class 7 (radioactive) material, other than fissile material, for which the A2 value is unlimited; or

100

DOE - Safety of Radioactive Material Transportation  

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

Sources of Radiation Biological Responses Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Radiation is all around us, occurring naturally in the environment. We are always exposed to radiation from: radon in the air uranium, radium and thorium in the earth cosmic rays from outer space and the sun radioactive potassium in our food and water naturally occuring radioactive material within our own bodies. This is commonly called "naturally-occurring background radiation." TYPES OF IONIZING RADIATION Alpha Alpha particles can be shielded by a sheet of paper or by human skin. If alpha emitters are inhaled, ingested, or enter the body through a cut, they can cause cancer. Beta Beta radiation can be stopped by a shield like aluminum foil or wood. If beta emitters are inhaled, ingested, or enter the body through a cut, they can cause cancer.

Note: This page contains sample records for the topic "naturally radioactive metallic" 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.


101

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

102

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

103

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

104

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

105

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

106

Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &  

E-Print Network (OSTI)

;Regulatory Agencies · Radioactive Materials ­ Broad Scope License ­ Issued by GA Department of Natural Resources · X-Ray Machines ­ Units registered with the GA Department of Human Resources ­ They regulate x) · Sealed sources ­ Nickel-63 (Gas chromatograph) ­ Cesium-137 (Liquid Scintillation Counter) ­ Neutron

Löffler, Frank E.

107

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

108

Abrasive blasting, a technique for the industrial decontamination of metal components and concrete blocks from decommissioning to unconditional release levels  

Science Conference Proceedings (OSTI)

When decommissioning nuclear installations, large quantities of metal components are produced as well as significant amounts of other radioactive materials, which mostly show low surface contamination. Having been used or having been brought for a while in a controlled area marks them as 'suspected material'. In view of the very high costs for radioactive waste processing and disposal, alternatives have been considered, and much effort has gone to recycling through decontamination, melting and unconditional release of metals. In a broader context, recycling of materials can considered to be a first order ecological priority in order to limit the quantities of radioactive wastes for final disposal and to reduce the technical and economic problems involved with the management of radioactive wastes. It will help as well to make economic use of primary material and to conserve natural resources of basic material for future generations. In a demonstration programme, Belgoprocess has shown that it is economically interesting to decontaminate metal components to unconditional release levels using dry abrasive blasting techniques, the unit cost for decontamination being only 30 % of the global cost for radioactive waste treatment, conditioning, storage and disposal. As a result, an industrial dry abrasive blasting unit was installed in the Belgoprocess central decontamination infrastructure. At the end of December 2006, more than 1,128 Mg of contaminated metal has been treated as well as 313 Mg of concrete blocks. The paper gives an overview of the experience relating to the decontamination of metal material and concrete blocks at the decommissioning of the Eurochemic reprocessing plant in Dessel, Belgium as well from the decontamination of concrete containers by abrasive blasting. (authors)

Gills, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R. [Belgoprocess N.V., Gravenstraat 73, 2480 Dessel (Belgium)

2007-07-01T23:59:59.000Z

109

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

110

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

111

Rational Design of Metal Ion Sequestering Agents  

DOE Green Energy (OSTI)

The discriminate bonding of metal ions is a challenge to the synthetic chemist and a phenomenon of considerable practical importance.1 An important feature of many technical applications is the specific or preferential binding of a single metal ion in the presence of many metals. Examples range from large-volume uses (e.g. ferric EDTA as a plant food, calcium complexing agents as water softeners or anticaking formulations) to very high technology applications (technetium complexation in radiopharmaceuticals, synthetic metalloenzymes). We are interested in efficient and discriminate binding of actinides for waste stream remediation. Actinides represent a major and long-lived contaminant in nuclear waste. While the separation of actinides from other radioactive components of waste, such as Sr and Cs, is relatively well established, the separation of actinides from each other and in complex solutions (e.g. those found in tank wastes) is not as well resolved. The challenge of designing metal-specific (actinide) ligands is facilitated by examples from nature. Bacteria synthesize Fe(III)-specific ligands, called siderophores, to sequester Fe(III) from the environment and return it to the cell. The similarities between Fe(III) and Pu(IV) (their charge-to-size ratios and acidity), make the siderophores prototypical for designing actinide-specific ligands. The chelating groups present in siderophores are usually hydroxamic acids and catecholamides. We have developed derivatives of these natural products which have improved properties. The catechol derivatives are the 2,3-dihydroxyterephthalamides (TAMs), and 3,4-dihydroxysulfonamides (SFAMs), and the hydroxamic acid derivatives are three isomers of hydroxypyridinones, 1,2- HOPO, 3,2-HOPO, and 3,4-HOPO. All of these ligands are attached to molecular backbones by amides and a very important feature of HOPO and CAM ligands is a strong hydrogen bonds formed between the amide proton and the adjacent phenolic oxygen in the metal complex, thereby enhancing the stability (Figure 1).

Raymond, Kenneth N.

2000-09-30T23:59:59.000Z

112

Hazards from radioactive waste in perspective  

SciTech Connect

This paper compares the hazards from wastes from a 1000-MW(e) nuclear power plant to these from wastes from a 1000-MW(e) coal fueled power plant. The latter hazard is much greater than the former. The toxicity and carcinogenity of the chemicals prodcued in coal burning is emphasized. Comparisions are also made with other toxic chemicals and with natural radioactivity. (DLC)

Cohen, B.L.

1979-02-27T23:59:59.000Z

113

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

114

Apparatus and method for downhole injection of radioactive tracer  

SciTech Connect

The disclosure relates to downhole injection of radioactive .sup.82 Br and monitoring its progress through fractured structure to determine the nature thereof. An ampule containing granular .sup.82 Br is remotely crushed and water is repeatedly flushed through it to cleanse the instrument as well as inject the .sup.82 Br into surrounding fractured strata. A sensor in a remote borehole reads progress of the radioactive material through fractured structure.

Potter, Robert M. (Los Alamos, NM); Archuleta, Jacobo R. (Espanola, NM); Fink, Conrad F. (Los Alamos, NM)

1983-01-01T23:59:59.000Z

115

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

116

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

117

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

118

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)

119

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

120

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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 ...

122

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

123

The Uncertainty of Dosimetry of Radioactive and Non-Radiactive Aerosols  

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

The Uncertainty of Dosimetry of Radioactive and Non-Radiactive Aerosols The Uncertainty of Dosimetry of Radioactive and Non-Radiactive Aerosols Speaker(s): Lev Ruzer Date: September 27, 2001 - 12:00pm Location: Bldg. 90 Seminar Host/Point of Contact: David Faulkner Radioactive aerosols are a substantial risk factor in radiation safety in the atomic industry, mining industry, nuclear warhead depository and nuclear waste storage, as well as the natural radioactivity in houses. Assessment of the exposure, dose and health effect is very important for workers and the general population. In the last 5-10 years the problem of dosimetry of non-radioactive aerosols has become a "hot" topic in environmental health science with emphasis on submicron and even nanometer-sized particles. Both radioactive and non-radioactive aerosols

124

Questions and Answers - How does the radioactivity of an atom affect the  

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

How is radioactivity measured? How is radioactivity measured? Previous Question (How is radioactivity measured?) Questions and Answers Main Index Next Question (Why do we use radioactivity to destroy cancers?) Why do we use radioactivityto destroy cancers? How does the radioactivity of an atom affect the body? You've asked a very broad question, so we'll have to split it up into smaller chunks in order to give you a reasonable answer. This is a topic that is very much misunderstood by most people and it's hard to give a short answer. You may know that all of us have radioactive material in our bodies naturally. There has always been radioactive material on earth (in fact, a million years ago, there was more present than there is today), and people have therefore always been exposed to it. There has also always been cosmic

125

Metal atom oxidation laser  

DOE Patents (OSTI)

A chemical laser which operates by formation of metal or carbon atoms and reaction of such atoms with a gaseous oxidizer in an optical resonant cavity is described. The lasing species are diatomic or polyatomic in nature and are readily produced by exchange or other abstraction reactions between the metal or carbon atoms and the oxidizer. The lasing molecules may be metal or carbon monohalides or monoxides. (auth)

Jensen, R.J.; Rice, W.W.; Beattie, W.H.

1975-10-28T23:59:59.000Z

126

Metal atom oxidation laser  

DOE Patents (OSTI)

A chemical laser which operates by formation of metal or carbon atoms and reaction of such atoms with a gaseous oxidizer in an optical resonant cavity is described. The lasing species are diatomic or polyatomic in nature and are readily produced by exchange or other abstraction reactions between the metal or carbon atoms and the oxidizer. The lasing molecules may be metal or carbon monohalides or monoxides.

Jensen, R.J.; Rice, W.W.; Beattie, W.H.

1975-10-28T23:59:59.000Z

127

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

128

System for disposing of radioactive water  

DOE Patents (OSTI)

A system for reducing radioactivity released to the biosphere in the course of producing natural gas from a reservoir stimulated by the detonation of nuclear explosives therein. Tritiated water produced with the gas is separated out and returned to a nuclear chimney through a string of tubing positioned within the well casing. The tubing string is positioned within the well casing in a manner which enhances separation of the water out of the gas and minimizes entrainment of water into the gas flowing out of the chimney.

Gotchy, Reginald L. (Bethesda, MD)

1976-01-13T23:59:59.000Z

129

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.)

130

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

131

Radioactivity in the environment: Sources, distribution and surveillance  

SciTech Connect

Radioactivity in the Environment provides the background and techniques necessary for understanding and monitoring today's radiological environment. It presents an overview of the entire field, including both natural and manmade sources of radiation, radiation distribution, and methods of environmental dose assessment, surveillance and measurement.

Kathren, R.L.

1984-01-01T23:59:59.000Z

132

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

133

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

134

Electrodynamic separation of metallic granules from mixed waste stream.  

E-Print Network (OSTI)

??Metals are essential, reusable resources. The reusable nature of metal contributes to the sustainability of its use through recycling, which will reduce landfill disposal and (more)

Naidu, Harini

2010-01-01T23:59:59.000Z

135

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste  

SciTech Connect

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

NONE

1994-12-31T23:59:59.000Z

136

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

Science Conference Proceedings (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

137

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...

138

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

139

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

140

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.

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

142

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

143

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)

144

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

145

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

146

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

147

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

148

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

149

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

150

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

151

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...

152

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

153

Past Radioactive Particle Contamination in the Columbia River at the Hanford Site, USA  

SciTech Connect

The Hanford Site was originally established in 1943 as part of the World War II Manhattan Project to produce a nuclear weapon. During the Sites early history, eight single-pass reactors were constructed along the Hanford Reach of the Columbia River to produce plutonium. Reactor coolant effluent was held temporarily in retention basins so that short-lived activation products and temperature could dissipate before discharge to the river. Reactor components included valves and pumps constructed with Stellite, an alloy containing high levels of cobalt and other metals. Neutron activation of these components produced cobalt-60. As these components aged, they deteriorated and released radioactive particles into the liquid effluent. Over the 26 years of reactor operations, relatively small numbers of these particles were released to the Columbia River along with the liquid discharges, and the particles were deposited in sediment along the shoreline and on islands. In 1976, portions of the Hanford Reach were opened for public access and the presence of these radioactive cobalt-60 particles became a concern for public exposure. A survey conducted in 1979 determined that the particles were small, with a diameter of approximately 0.1 mm, and their activity level was estimated to be between 63 and 890 GBq. Dose rates from the particles ranged from 1 to 14 ?Gray/hr. Fourteen particles were collected during the 1979 survey and subsequent monitoring and particle clean-up campaigns continued during the 1980s and 1990s. The presence of radioactive particles in the river environment was a continuing concern as cleanup of the Hanford Site accelerated during the 1990s. Principal issues included: 1) Site management response to the presence of radioactive particles in the Columbia River, 2) methods to monitor this contamination, 3) stakeholder concerns, and 4) anti-nuclear activist intervention. Reducing ecological and human health risk caused by contamination is a major focus of Site cleanup. Because of the 5.3 year half-life of cobalt-60, the radiological risk from these particles is now negligible. Also, at locations where human access is limited, some scientists believe that the reduction in ecological risk gained by cleanup activities is overshadowed by the ecological damage caused by the clean-up activities. Suggestions have been made by scientists and regulatory agencies that it may be economically and environmentally more sound to manage isolated low-level waste sites until the activity decays (i.e., natural attenuation) to levels below health concerns, when the sites can be released.

Poston, Ted M.; Peterson, Robert E.; Cooper, Andrew T.

2007-08-24T23:59:59.000Z

154

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

Science Conference Proceedings (OSTI)

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

155

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

156

Aerodynamic size associations of natural radioactivity with ambient aerosols  

SciTech Connect

The aerodynamic size of /sup 214/Pb, /sup 212/Pb, /sup 210/Pb, /sup 7/Be, /sup 32/P, /sup 35/S (as SO/sub 4//sup 2 -/), and stable SO/sub 4//sup 2 -/ was measured using cascade impactors. The activity distribution of /sup 212/Pb and /sup 214/Pb, measured by alpha spectroscopy, was largely associated with aerosols smaller than 0.52 ..mu..m. Based on 46 measurements, the activity median aerodynamic diameter of /sup 212/Pb averaged 0.13 ..mu..m (sigma/sub g/ = 2.97), while /sup 214/Pb averaged 0.16 ..mu..m (sigma/sub g/ = 2.86). The larger median size of /sup 214/Pb was attributed to ..cap alpha..-recoil depletion of smaller aerosols following decay of aerosol-associated /sup 218/Po. Subsequent /sup 214/Pb condensation on all aerosols effectively enriches larger aerosols. /sup 212/Pb does not undergo this recoil-driven redistribution. Low-pressure impactor measurements indicated that the mass median aerodynamic diameter of SO/sub 4//sup 2 -/ was about three times larger than the activity median diameter /sup 212/Pb, reflecting differences in atmospheric residence times as well as the differences in surface area and volume distributions of the atmospheric aerosol. Cosmogenic radionuclides, especially /sup 7/Be, were associated with smaller aerosols than SO/sub 4//sup 2 -/ regardless of season, while /sup 210/Pb distributions in summer measurements were similar to sulfate but smaller in winter measurements. Even considering recoil following /sup 214/Po ..cap alpha..-decay, the avervage /sup 210/Pb labeled aerosol grows by about a factor of two during its atmospheric lifetime. The presence of 5 to 10% of the /sup 7/Be on aerosols greater than 1 ..mu..m was indicative of post-condensation growth, probably either in the upper atmosphere or after mixing into the boundary layer.

Bondietti, E.A.; Papastefanou, C.; Rangarajan, C.

1986-04-01T23:59:59.000Z

157

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...

158

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

159

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

160

Review of {sup 222}Rn in natural gas produced from unconventional sources  

SciTech Connect

A review of the literature on trace radioactivity in natural gas and natural gas products has been performed and the consequent radioactivity concentrations and dose rates due to natural radioactive elements in natural gas produced from Devonian shale wells, western tight gas sands, geo-pressurized aquifiers and coal beds have been studied. Preliminary data on {sup 222}Rn concentrations from these energy sources fall within the range observed for more conventional sources. Gas produced from reservoirs with higher than average natural /sup 238/U higher than average levels of {sup 222}Rn. Massive fracturing techniques do not appear to raise the relative concentration of radon in natural gas.

Gogolak, C.V.

1980-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

162

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

163

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

164

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

165

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

166

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

167

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...

168

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...

169

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

170

Light Metals  

Science Conference Proceedings (OSTI)

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

171

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

172

Low-level radioactive waste disposal facility closure  

Science Conference Proceedings (OSTI)

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-11-01T23:59:59.000Z

173

Transport Models for Radioactive Carbon Dioxide at RWMC  

SciTech Connect

Radioactive carbon dioxide (formed by oxidation of carbon-14) is a highly mobile, radioactive contaminant released from solid wastes buried at the Subsurface Disposal Area (SDA) at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering and Environmental Laboratory (INEEL). Radioactive CO2 is chemically active in the environment, volatile, water soluble, and subject to adsorption on solids. For this reason, its fate must be understood and controlled to meet radiological requirements (protection of the atmosphere, aquifer, vadose zones, plants and animals). In the present work, the migration of carbon-14 as dissolved bicarbonate was studied using miscible displacement experiments in water-saturated columns containing sediments from RWMC. Dissolved carbon-14 was retarded relative to the movement of water by a factor of about 3.6, which translates to a partition coefficient (Kd) of 0.8 ml/g. Two different adsorption sites were identified, with one site possibly having a nonlinear adsorption isotherm. A conservative tracer gas, sulfur hexafluoride, was used to measure the tortuosity of sedimentary material for gaseous diffusion. The tortuosity of the RWMC sediment (Spreading Area B sediment) was determined to be 3.2, which is slightly greater than predicted by the commonly used Millington-Quirk equation. In terms of affecting the migration of carbon-14 to the aquifer, the relative importance of the parameters studied is: (1) natural moisture content of the sediments, (2) sediment tortuosity to gas-phase diffusion, and (3) adsorption onto solid phases.

Hull, Laurence Charles; Hohorst, Frederick August

2001-12-01T23:59:59.000Z

174

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

175

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

176

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

177

Metal-Ceramic Composites from Natural Scaffolds  

Science Conference Proceedings (OSTI)

Functional Composites: Fluorescent Carbon Nanotubes in Silica Aerogel ... Novel Metallo-Organic Derived Ti-Si-Cr-C-N Nanocomposite Coatings: Part II...

178

Environmental review of options for managing radioactively contaminated carbon steel  

SciTech Connect

The U.S. Department of Energy (DOE) is proposing to develop a strategy for the management of radioactively contaminated carbon steel (RCCS). Currently, most of this material either is placed in special containers and disposed of by shallow land burial in facilities designed for low-level radioactive waste (LLW) or is stored indefinitely pending sufficient funding to support alternative disposition. The growing amount of RCCS with which DOE will have to deal in the foreseeable future, coupled with the continued need to protect the human and natural environment, has led the Department to evaluate other approaches for managing this material. This environmental review (ER) describes the options that could be used for RCCS management and examines the potential environmental consequences of implementing each. Because much of the analysis underlying this document is available from previous studies, wherever possible the ER relies on incorporating the conclusions of those studies as summaries or by reference.

NONE

1996-10-01T23:59:59.000Z

179

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

180

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 "naturally radioactive metallic" 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

The potential human health effect(s) of the metal uranium in the environment. Report on the known human health effects associated with the exposure to the metal uranium  

SciTech Connect

Concern over the levels of the metal uranium in the environment as a result of industrial activities has been expressed by several Federal and State agencies. This concern is associated with potential human health effects of this metal on kidney function and bone formation. Although limits for the Metal uranium in the environment remain to be set, the Environmental Protection Agency (EPA) is currently in the process of establishing guidance limits for this metal in water and soil. These limits will be established for both the metal and the associated radioactivity. The suggested limits currently being considered for water and soil are, 20 pCi/liter and 10 pCi/gram wet weight, respectively. For naturally occurring uranium EPA assumes that 1 ug of uranium metal equals 0.67 pCi at equilibrium (i.e. at equilibrium the mass ratio of {sup 234}uranium to {sup 238}uranium is small but their activities are equal). Thus the limits for water and soil on weight basis for the uranium metal would be 30 ug/liter and 15 ug/gram wet weight, respectively. These limits are being established based on the potential increase in cancer death in populations that exceed this limit. Since there does not appear to be a significant correlation between cancer deaths and.uranium metal exposure (see discussion below), these limits will probably be established based on the known association between radionuclides exposure and cancer deaths. The exposure limits for other health effects such as kidney damage and retardation in bone formation apparently are not being considered by EPA.

1990-12-31T23:59:59.000Z

182

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.

183

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

184

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

185

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

186

Searching, naturally  

Science Conference Proceedings (OSTI)

Keywords: artificial intelligence, computational linguistics, information retrieval, knowledge representation, natural language processing, text processing

Eileen E. Allen

1998-06-01T23:59:59.000Z

187

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...

188

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...

189

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.

190

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.

191

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...

192

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

193

'^^ 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

194

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...

195

Natural Resources in China Water resources  

E-Print Network (OSTI)

. Large reserves of coal, but natural gas and oil are becoming scarce. Import approximately the same, petroleum, natural gas, uranium, etc. Metallic mineral resources include iron, copper, tungsten, aluminum in the production of petrochemicals Materials produced from natural gas or crude oil, such as plastics

Pan, Feifei

196

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

197

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

198

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

199

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

200

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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.

202

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

203

Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

NONE

1997-12-01T23:59:59.000Z

204

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

205

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

206

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

207

Health Physics Society Specialists in Radiation Safety Consumer Products Containing Radioactive Materials  

E-Print Network (OSTI)

Everything we encounter in our daily lives contains some radioactive material, some naturally occurring and some man-made: the air we breathe, the water we drink, the food we eat, the ground we walk upon, and the consumer products we purchase and use. Although many might be familiar with the use of radiation to diagnose disease and treat cancer, some people, when they hear the terms radioactive and radiation, might recall images of mushroom clouds or monster mutants that inhabit the world of science fiction movies and comic books. Unfortunately, those false images can cause inordinate fear that is not justified regarding low levels of radioactive material. Many consumer items containing naturally occurring radioactivity can be safely used. This fact sheet describes a photo courtesy of Ray Johnson few of the more commonly encountered and familiar consumer products. Included are the items that can contain sufficient radioactive material to be distinguished from the general environmental background radiation with a simple handheld radiation survey meter. Smoke Detectors Most residential smoke detectors contain a low-activity

unknown authors

2010-01-01T23:59:59.000Z

208

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

209

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...

210

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,...

211

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...

212

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.

213

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...

214

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...

215

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)...

216

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...

217

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...

218

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...

219

Oil, Gas, and Metallic Minerals (Iowa)  

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

Operators of oil, gas, and metallic mineral exploration and production operations are required to obtain a drilling permit from the Iowa Department of Natural Resources and file specific forms with...

220

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

222

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

223

Radiological surveys of properties contaminated by residual radioactive materials from uranium processing sites  

Science Conference Proceedings (OSTI)

This report examines methods for determining the extent and nature of contamination on properties contaminated by residual radioactive materials from uranium processing sites. Methods are also examined for verifying the success of remedial actions in removing the residual radioactive materials. Using literature review and practical experiences from the Edgemont, South Dakota survey program a critical review is made of sampling programs, instrumentation, analytical procedures, data reporting format, and statistical analyses of data. Protocols are recommended for measuring indoor and outdoor gamma-ray exposure rates, surface and subsurface Radium-226 concentrations in soil, and radon daughter concentrations.

Young, J.A.; Jackson, P.O.; Thomas, V.W.

1983-06-01T23:59:59.000Z

224

Identifying potential repositories for radioactive waste: multiple criteria decision analysis and critical infrastructure systems  

E-Print Network (OSTI)

An approach for the analysis and management of multiple criteria critical infrastructure problems is put forth. Nuclear waste management involves complex tradeoffs under uncertainty. Among all waste either generated by nature or human activities, radioactive nuclear waste is the most toxic to human health and difficult to manage: it is known that some nuclear waste material will be radioactive and potentially dangerous for hundreds of thousands of years. This paper discusses the use of multiple criteria decision analysis techniques such as the analytic hierarchy process for recommending sites to be considered as potential repositories for nuclear waste.

Kouichi Taji; Jason K. Levy; Jens Hartmann; Michelle L. Bell; Richard M. Anderson; Benjamin F. Hobbs; Tom Feglar

2005-01-01T23:59:59.000Z

225

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

226

Natural Gas  

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

The Energy Department supports research and policy options to ensure environmentally sustainable domestic and global supplies of oil and natural gas.

227

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

228

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...

229

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...

230

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

231

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

232

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

233

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:...

234

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

235

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

236

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

237

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

238

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

239

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

240

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

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

THE RADIOACTIVITY OF A NUMBER OF THE HIGHER ALGAE IN THE REGION OF THEODOSIA  

SciTech Connect

Samples of algae were ashed, and the radioactivity in the ash was determined by counting on a MST-17 end-window counter. A potassium standard was used to convert relative activities to absolute values. The potassium in the ash was determined quantitatively by the cobalt-nitrite method. It was found that the radioactivity in Cystoseira barbata significantly exceeded the natural activity due to potassium. Aluminum absorption studies on the ash of this algae indicated the existence of Sr/sup 90/-Y/sup 90/ in the ash. A sample of Cystoseira barbata gathered in 1953 was secured from a local museum and analyzed. It showed only the presence of K/sup 40/. Other samples of Cystoseira barbata from the Sevastopol Biological Station which were gathered in 1939 and 1949 indicated the absence of fission products in the ash. The radioactivity in the ash of the other algae present was due to the presence of K/sup 40/. (TTT)

Mironov, O.G.

1961-05-21T23:59:59.000Z

242

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

243

RADIOACTIVE FALLOUT FROM NUCLEAR EXPLOSIONS  

SciTech Connect

A nontechnical description of the mechanisms of local and world-wide fall-out from nuclear explosions is given. The relative importance of local fall-out in a nuclear war is discussed. The effects upon man of world-wide fall-out from past nuclear testing is discussed. It is pointed out that doses to man frcm testing are quite small when compared to the natural radiation background. (auth)

Parker, E.N.

1960-03-23T23:59:59.000Z

244

Experiments with radioactive samples at the Advanced Photon Source.  

SciTech Connect

The Advanced Photon Source (APS) at Argonne National Laboratory is a national synchrotron-radiation light source research facility. The 7 GeV electron Storage Ring is currently delivering intense high brilliance x-ray beams to a total of 34 beamlines with over 120 experiment stations to members of the international scientific community to carry out forefront basic and applied research in several scientific disciplines. Researchers come to the APS either as members of Collaborative Access Teams (CATs) or as Independent Investigators (IIs). Collaborative Access Teams comprise large number of investigators from universities, industry, and research laboratories with common research objectives. These teams are responsible for the design, construction, finding, and operation of beamlines. They are the owners of their experimental enclosures (''hutches'') designed and built to meet their specific research needs. Fig. 1 gives a plan view of the location of the Collaborative Access Teams by Sector and Discipline. In the past two years, over 2000 individual experiments were conducted at the APS facility. Of these, about 60 experiments involved the use of radioactive samples, which is less than 3% of the total. However, there is an increase in demand for experiment stations to accommodate the use of radioactive samples in different physical forms embedded in various matrices with activity levels ranging from trace amounts of naturally occurring radionuclides to MBq (mCi) quantities including transuranics. This paper discusses in some detail the steps in the safety review process for experiments involving radioactive samples and how ALARA philosophy is invoked at each step and implemented.

Veluri, V. R.; Justus, A.; Glagola, B.; Rauchas, A.; Vacca, J.

2000-11-01T23:59:59.000Z

245

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

246

Natural gas  

E-Print Network (OSTI)

www.eia.gov Over time the electricity mix gradually shifts to lower-carbon options, led by growth in natural gas and renewable generation U.S. electricity net generation trillion kilowatthours 6

Adam Sieminski Administrator; Adam Sieminski Usnic; Adam Sieminski Usnic

2013-01-01T23:59:59.000Z

247

Natural Gas  

U.S. Energy Information Administration (EIA)

Natural Gas. Under the baseline winter weather scenario, EIA expects end-of-October working gas inventories will total 3,830 billion cubic feet (Bcf) and end March ...

248

Natural Energy  

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

originate? I need to give the intitial natural source of this energy. Replies: The energy source for most known organisms is the sun. Some organisms, such as deep-sea vent fauna...

249

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

250

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

251

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...

252

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

253

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

254

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

255

Heat pipe cooling system for underground, radioactive waste storage tanks  

SciTech Connect

An array of 37 heat pipes inserted through the central hole at the top of a radioactive waste storage tank will remove 100,000 Btu/h with a heat sink of 70/sup 0/F atmospheric air. Heat transfer inside the tank to the heat pipe is by natural convection. Heat rejection to outside air utilizes a blower to force air past the heat pipe condenser. The heat pipe evaporator section is axially finned, and is constructed of stainless steel. The working fluid is ammonia. The finned pipes are individually shrouded and extend 35 ft down into the tank air space. The hot tank air enters the shroud at the top of the tank and flows downward as it is cooled, with the resulting increased density furnishing the pressure difference for circulation. The cooled air discharges at the center of the tank above the sludge surface, flows radially outward, and picks up heat from the radioactive sludge. At the tank wall the heated air rises and then flows inward to comple the cycle.

Cooper, K.C.; Prenger, F.C.

1980-02-01T23:59:59.000Z

256

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

257

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

258

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).

259

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

260

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,"

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

262

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

263

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 -

264

Natural System  

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

Natural System Natural System Evaluation and Tool Development - FY11 Progress Report Prepared for U.S. Department of Energy Used Fuel Disposition Program Yifeng Wang (SNL) Michael Simpson (INL) Scott Painter (LANL) Hui-Hai Liu (LBNL) Annie B. Kersting (LLNL) July 15, 2011 FCRD-USED-2011-000223 UFD Natural System Evaluation - FY11 Year-End Report July 15, 2011 2 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe

265

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

266

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.

267

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

268

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

269

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

270

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

271

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

272

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

273

Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors  

Science Conference Proceedings (OSTI)

Sorption of cesium and strontium on kaolinite powders was investigated as a means to minimize the emissions of these metals during certain high temperature processes currently being developed to isolate and dispose of radiological and mixed wastes. In this work, non-radioactive aqueous cesium acetate or strontium acetate was atomized down the center of a natural gas flame supported on a variable-swirl burner in a refractory-lined laboratory-scale combustion facility. Kaolinite powder was injected at a post-flame location in the combustor. Cesium readily vaporizes in the high temperature regions of the combustor, but was reactively scavenged onto dispersed kaolinite. Global sorption mechanisms of cesium vapor on kaolinite were quantified, and are related to those available in the literature for sodium and lead. Both metal adsorption and substrate deactivation steps are important, and so there is an optimum temperature, between 1400 and 1500 K, at which maximum sorption occurs. The presence of chlorine inhibits cesium sorption. In contrast to cesium, and in the absence of chlorine, strontium was only partially vaporized and was, therefore, only partially scavengeable. The strontium data did not allow quantification of global kinetic mechanisms of interaction, although equilibrium arguments provided insight into the effects of chlorine on strontium sorption. These results have implications for the use of sorbents to control cesium and strontium emissions during high temperature waste processing including incineration and vitrification.

William Linak

2004-12-16T23:59:59.000Z

274

Lessons Learned from Radioactive Waste Storage and Disposal Facilities  

Science Conference Proceedings (OSTI)

The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. This paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed: commercial LLW disposal facilities; uranium mill tailings disposal facilities; and reprocessing waste storage and disposal facilities. The observations developed from the monitoring and maintenance of waste disposal and storage facilities provide valuable lessons learned for the design and modeling of future waste disposal facilities and the decommissioning of complex sites.

Esh, David W.; Bradford, Anna H. [U.S. Nuclear Regulatory Commission, Two White Flint North, MS T7J8, 11545 Rockville Pike, Rockville, MD 20852 (United States)

2008-01-15T23:59:59.000Z

275

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

134,294 32,451 0.37 0 0.00 32 1.09 43,764 0.83 10,456 0.38 39,786 1.26 126,488 0.63 C o n n e c t i c u t Connecticut 54. Summary Statistics for Natural Gas Connecticut, 1992-1996...

276

Natural Gas  

Annual Energy Outlook 2012 (EIA)

3.91 119,251 0.60 229 7.81 374,824 7.15 2,867 0.10 189,966 6.01 915,035 4.57 O h i o Ohio 83. Summary Statistics for Natural Gas Ohio, 1992-1996 Table 1992 1993 1994 1995 1996...

277

Natural games  

E-Print Network (OSTI)

Behavior in the context of game theory is described as a natural process that follows the 2nd law of thermodynamics. The rate of entropy increase as the payoff function is derived from statistical physics of open systems. The thermodynamic formalism relates everything in terms of energy and describes various ways to consume free energy. This allows us to associate game theoretical models of behavior to physical reality. Ultimately behavior is viewed as a physical process where flows of energy naturally select ways to consume free energy as soon as possible. This natural process is, according to the profound thermodynamic principle, equivalent to entropy increase in the least time. However, the physical portrayal of behavior does not imply determinism. On the contrary, evolutionary equation for open systems reveals that when there are three or more degrees of freedom for behavior, the course of a game is inherently unpredictable in detail because each move affects motives of moves in the future. Eventually, when no moves are found to consume more free energy, the extensive-form game has arrived at a solution concept that satisfies the minimax theorem. The equilibrium is Lyapunov-stable against variation in behavior within strategies but will be perturbed by a new strategy that will draw even more surrounding resources to the game. Entropy as the payoff function also clarifies motives of collaboration and subjective nature of decision making.

Jani Anttila; Arto Annila

2011-03-05T23:59:59.000Z

278

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

0 0.00 53 1.81 147,893 2.82 7,303 0.27 93,816 2.97 398,581 1.99 W i s c o n s i n Wisconsin 97. Summary Statistics for Natural Gas Wisconsin, 1992-1996 Table 1992 1993 1994...

279

Natural Gas  

Annual Energy Outlook 2012 (EIA)

10,799 1,953 0.02 0 0.00 0 0.00 2,523 0.05 24 0.00 2,825 0.09 7,325 0.04 V e r m o n t Vermont 93. Summary Statistics for Natural Gas Vermont, 1992-1996 Table 1992 1993 1994 1995...

280

Natural Gas  

Annual Energy Outlook 2012 (EIA)

845,998 243,499 2.75 135,000 0.68 35 1.19 278,606 5.32 7,239 0.26 154,642 4.90 684,022 3.42 P e n n s y l v a n i a Pennsylvania 86. Summary Statistics for Natural Gas...

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

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

282

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.

283

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

284

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

285

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

286

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

287

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

288

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

289

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

290

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

291

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

292

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

293

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 Falls, ID)

1976-01-01T23:59:59.000Z

294

Extracting metals directly from metal oxides  

DOE Patents (OSTI)

A method of extracting metals directly from metal oxides by exposing the oxide to a supercritical fluid solvent containing a chelating agent is described. Preferably, the metal is an actinide or a lanthanide. More preferably, the metal is uranium, thorium or plutonium. The chelating agent forms chelates that are soluble in the supercritical fluid, thereby allowing direct removal of the metal from the metal oxide. In preferred embodiments, the extraction solvent is supercritical carbon dioxide and the chelating agent is selected from the group consisting of .beta.-diketones, halogenated .beta.-diketones, phosphinic acids, halogenated phosphinic acids, carboxylic acids, halogenated carboxylic acids, and mixtures thereof. In especially preferred embodiments, at least one of the chelating agents is fluorinated. The method provides an environmentally benign process for removing metals from metal oxides without using acids or biologically harmful solvents. The chelate and supercritical fluid can be regenerated, and the metal recovered, to provide an economic, efficient process.

Wai, Chien M. (Moscow, ID); Smart, Neil G. (Moscow, ID); Phelps, Cindy (Moscow, ID)

1997-01-01T23:59:59.000Z

295

Extracting metals directly from metal oxides  

DOE Patents (OSTI)

A method of extracting metals directly from metal oxides by exposing the oxide to a supercritical fluid solvent containing a chelating agent is described. Preferably, the metal is an actinide or a lanthanide. More preferably, the metal is uranium, thorium or plutonium. The chelating agent forms chelates that are soluble in the supercritical fluid, thereby allowing direct removal of the metal from the metal oxide. In preferred embodiments, the extraction solvent is supercritical carbon dioxide and the chelating agent is selected from the group consisting of {beta}-diketones, halogenated {beta}-diketones, phosphinic acids, halogenated phosphinic acids, carboxylic acids, halogenated carboxylic acids, and mixtures thereof. In especially preferred embodiments, at least one of the chelating agents is fluorinated. The method provides an environmentally benign process for removing metals from metal oxides without using acids or biologically harmful solvents. The chelate and supercritical fluid can be regenerated, and the metal recovered, to provide an economic, efficient process. 4 figs.

Wai, C.M.; Smart, N.G.; Phelps, C.

1997-02-25T23:59:59.000Z

296

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

297

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

298

Transporting & Shipping Hazardous Materials at LBNL: Radioactive Materials  

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

Radioactive Materials Radioactive Materials Refer to transportation guidelines in the applicable Radioactive Work Authorization (RWA). Contact the Radiation Protection Group (x7652) if transportation assistance is needed or if radioactive materials need to be shipped. Refer to RPG's Zone sheet to identifying the RCT or HP for your building: https://ehswprod.lbl.gov/rpg/who_to_call.shtml Need radioactive material shipped from LBNL? Please complete the request for shipment form online, print, sign, and forward to your building assigned RPG support person: RPG Transportation - Request for Shipment Form: http://www.lbl.gov/ehs/rpg/assets/docs/Transportation4.pdf Receiving radioactive material at LBNL? If receiving radioactive material at LBNL; radioactive material should be sent to the following address:

299

RadTrac: Portable and Compact Tracking Radioactive Materials  

Hot cell exits where radioactive materials are used, or at nonproliferation sites Defense companies and airport security equipment manufacturers

300

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

,366 ,366 95,493 1.08 0 0.00 1 0.03 29,406 0.56 1,206 0.04 20,328 0.64 146,434 0.73 - Natural Gas 1996 Million Percent of Million Percent of Cu. Feet National Total Cu. Feet National Total Net Interstate Movements: Industrial: Marketed Production: Vehicle Fuel: Deliveries to Consumers: Electric Residential: Utilities: Commercial: Total: South Carolina South Carolina 88. Summary Statistics for Natural Gas South Carolina, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ...........................................

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

0,216 0,216 50,022 0.56 135 0.00 49 1.67 85,533 1.63 8,455 0.31 45,842 1.45 189,901 0.95 - Natural Gas 1996 Million Percent of Million Percent of Cu. Feet National Total Cu. Feet National Total Net Interstate Movements: Industrial: Marketed Production: Vehicle Fuel: Deliveries to Consumers: Electric Residential: Utilities: Commercial: Total: M a r y l a n d Maryland 68. Summary Statistics for Natural Gas Maryland, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... NA NA NA NA NA Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 9 7 7 7 8 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 33 28 26 22 135 From Oil Wells ...........................................

302

METAL MEDIA FILTERS, AG-1 SECTION FI  

Science Conference Proceedings (OSTI)

One application of metal media filters is in various nuclear air cleaning processes including applications for protecting workers, the public and the environment from hazardous and radioactive particles. To support this application the development of the ASME AG-1 FI Standard on Metal Media has been under way for more than ten years. Development of the proposed section has required resolving several difficult issues associated with operating conditions (media velocity, pressure drop, etc.), qualification testing, and quality acceptance testing. Performance characteristics of metal media are dramatically different than the glass fiber media with respect to parameters like differential pressures, operating temperatures, media strength, etc. These differences make existing data for a glass fiber media inadequate for qualifying a metal media filter for AG-1. In the past much work has been conducted on metal media filters at facilities such as Lawrence Livermore National Laboratory (LLNL) and Savannah River National Laboratory (SRNL) to qualify the media as High Efficiency Particulate Air (HEPA) Filters. Particle retention testing has been conducted at Oak Ridge Filter Test Facility and at Air Techniques International (ATI) to prove that the metal media meets or exceeds the 99.97% particle retention required for a HEPA Filter. Even with his testing, data was lacking to complete an AG-1 FI Standard on metal media. With funding secured by Mississippi State University (MSU) from National Nuclear Security Administration (NNSA), a research test stand is being designed and fabricated at MSU's Institute for Clean Energy Technology (ICET) Facility to obtain qualification data on metal media. This in turn will support required data needed for the FI Standard. The paper will discuss in detail how the test stand at MSU will obtain the necessary data to complete the FI Standard.

Adamson, D.

2012-05-23T23:59:59.000Z

303

Uranium Metal: Potential for Discovering Commercial Uses  

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

Uranium Metal Uranium Metal Potential for Discovering Commercial Uses Steven M. Baker, Ph.D. Knoxville Tn 5 August 1998 Summary Uranium Metal is a Valuable Resource 3 Large Inventory of "Depleted Uranium" 3 Need Commercial Uses for Inventory  Avoid Disposal Cost  Real Added Value to Society 3 Uranium Metal Has Valuable Properties  Density  Strength 3 Market will Come if Story is Told Background The Nature of Uranium Background 3 Natural Uranium: 99.3% U238; 0.7% U 235 3 U235 Fissile  Nuclear Weapons  Nuclear Reactors 3 U238 Fertile  Neutron Irradiation of U238 Produces Pu239  Neutrons Come From U235 Fission  Pu239 is Fissile (Weapons, Reactors, etc.) Post World War II Legacy Background 3 "Enriched" Uranium Product  Weapons Program 

304

Laboratory scale vitrification of low-level radioactive nitrate salts and soils from the Idaho National Engineering Laboratory  

SciTech Connect

INEL has radiologically contaminated nitrate salt and soil waste stored above and below ground in Pad A and the Acid Pit at the Radioactive Waste Management Complex. Pad A contain uranium and transuranic contaminated potassium and sodium nitrate salts generated from dewatered waste solutions at the Rocky Flats Plant. The Acid Pit was used to dispose of liquids containing waste mineral acids, uranium, nitrate, chlorinated solvents, and some mercury. Ex situ vitrification is a high temperature destruction of nitrates and organics and immobilizes hazardous and radioactive metals. Laboratory scale melting of actual radionuclides containing INEL Pad A nitrate salts and Acid Pit soils was performed. The salt/soil/additive ratios were varied to determine the range of glass compositions (resulted from melting different wastes); maximize mass and volume reduction, durability, and immobilization of hazardous and radioactive metals; and minimize viscosity and offgas generation for wastes prevalent at INEL and other DOE sites. Some mixtures were spiked with additional hazardous and radioactive metals. Representative glasses were leach tested and showed none. Samples spiked with transuranic showed low nuclide leaching. Wasteforms were two to three times bulk densities of the salt and soil. Thermally co-processing soils and salts is an effective remediation method for destroying nitrate salts while stabilizing the radiological and hazardous metals they contain. The measured durability of these low-level waste glasses approached those of high-level waste glasses. Lab scale vitrification of actual INEL contaminated salts and soils was performed at General Atomics Laboratory as part of the INEL Waste Technology Development and Environmental Restoration within the Buried Waste Integrated Demonstration Program.

Shaw, P. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Anderson, B. [General Atomics, San Diego, CA (United States). NRT Div.; Davis, D. [Envitco Inc., Toledo, OH (United States)

1993-07-01T23:59:59.000Z

305

Decontamination of metals using chemical etching  

DOE Patents (OSTI)

The invention relates to chemical etching process for reclaiming contaminated equipment wherein a reduction-oxidation system is included in a solution of nitric acid to contact the metal to be decontaminated and effect reduction of the reduction-oxidation system, and includes disposing a pair of electrodes in the reduced solution to permit passage of an electrical current between said electrodes and effect oxidation of the reduction-oxidation system to thereby regenerate the solution and provide decontaminated equipment that is essentially radioactive contamination-free.

Lerch, Ronald E. (Kennewick, WA); Partridge, Jerry A. (Richland, WA)

1980-01-01T23:59:59.000Z

306

Dissolution Studies of Si Metal in Liquid Al under Different Forced ...  

Science Conference Proceedings (OSTI)

Presentation Title, Dissolution Studies of Si Metal in Liquid Al under Different Forced ... studies of Silicon metal in liquid Aluminum will be reported under natural and ... conditions of two-phase flow, utilizing Nitrogen gas, in liquid Aluminum will...

307

Nonhazardous solvent composition and method for cleaning metal surfaces  

DOE Patents (OSTI)

A solvent composition for displacing greasy and oily contaminants as well as water and/or aqueous residue from metallic surfaces, especially surfaces of radioactive materials so that such surfaces can be wiped clean of the displaced contaminants, water and/or aqueous residue. The solvent composition consists essentially of a blend of nonpolar aliphatic hydrocarbon solvent having a minimum flash point of about 140 F and 2 to 25 volume percent of a polar solvent having a flash point sufficiently high so as to provide the solvent composition with a minimum flash point of at least 140 F. The solvent composition is nonhazardous so that when it is used to clean the surfaces of radioactive materials the waste in the form of paper or cloth wipes, lab coats and the like used in the cleaning operation is not considered to be mixed waste composed of a hazardous solvent and a radioactive material.

Googin, J.M.; Simandl, R.F.; Thompson, L.M.

1993-05-04T23:59:59.000Z

308

Effects of metal cations present naturally in coal on the fate of coal-bound nitrogen in the fixed-bed pyrolysis of 25 coals with different ranks: correlation between inherent Fe cations and N{sub 2} formation from low-rank coals  

Science Conference Proceedings (OSTI)

The fate of coal-N in the fixed-bed pyrolysis of 25 coals with 62-81 wt % (daf) C has been studied with a quartz reactor at 1000 C under ambient pressure to examine the effects of metal cations present naturally in these coals on the partitioning of coal-N into N{sub 2}, NH{sub 3}, HCN, tar-N, and char-N. Nitrogen mass balances for all runs fall within the reasonable range of 100 {+-} 5%, and N{sub 2} is the predominant product for all of the coals. As the N{sub 2} yield increases, the sum of NH{sub 3}, HCN, and tar-N is unchanged significantly, whereas the char-N yield decreases almost linearly, showing that most of N{sub 2} originates from char-N. When eight kinds of inherent metals, such as Na, Mg, Al, Si, K, Ca, Fe, and Ti, are determined by the conventional method and related with the N{sub 2} yield, there exists a strong, direct correlation between the Fe content and N{sub 2} formation for low-rank coals with less than 75 wt % (daf) C. Transmission electron microscopy coupled with an energy-dispersive analysis of X-rays (TEM-EDAX) measurements after pyrolysis at 1000{sup o}C of a German brown coal, which provides the highest N{sub 2} yield of about 60%, reveal the existence of lamella structures because of graphitized carbon as well as nanoscale Fe particles with different sizes and shapes. The mechanism for conversion reactions of char-N to N{sub 2} is discussed in terms of the catalysis by nanoparticles of metallic Fe formed from inherent Fe cations. 34 refs., 18 figs., 1 tab.

Yasuo Ohtsuka; Zhiheng Wu [Tohoku University, Sendai (Japan). Research Center of Sustainable Materials Engineering

2009-09-15T23:59:59.000Z

309

Metallic Glass II  

Science Conference Proceedings (OSTI)

Aug 8, 2013 ... Application of Metallic Glass for High Performance Si Solar Cell: ... of the metallic glasses during heating is dependent on the thermal stability of...

310

Light Metals 2010  

Science Conference Proceedings (OSTI)

Feb 1, 2010 ... Softcover book: Light Metals 2008 Volume 2: Aluminum Reduction. Hardcover book and CD-ROM: Light Metals 2009...

311

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.

312

Bulk Metallic Glasses XI  

Science Conference Proceedings (OSTI)

Jul 15, 2013 ... A Bulk Metallic Glass with Record-breaking Damage Tolerance ... Oxidation on the Surface Characteristics of Zr-based Bulk Metallic Glasses.

313

Principal Metals Online  

Science Conference Proceedings (OSTI)

Topic Title: WEB RESOURCE: Principal Metals Online Topic Summary: Principal Metals inventory database. Created On: 2/9/2007 5:41 AM, Topic View:.

314

Refractory Metals Committee  

Science Conference Proceedings (OSTI)

The Refractory Metals Committee is part of the Structural Materials Division. Our Mission: Includes all technical aspects of the science of refractory metals and...

315

Method of removal of heavy metal from molten salt in IFR fuel pyroprocessing  

DOE Patents (OSTI)

An electrochemical method of separating heavy metal values from a radioactive molten salt including Li halide at temperatures of about 500{degree}C. The method comprises positioning a solid Li-Cd alloy anode in the molten salt containing the heavy metal values, positioning a Cd-containing cathode or a solid cathode positioned above a catch crucible in the molten salt to recover the heavy metal values, establishing a voltage drop between the anode and the cathode to deposit material at the cathode to reduce the concentration of heavy metals in the salt, and controlling the deposition rate at the cathode by controlling the current between the anode and cathode.

Gay, E.C.

1993-12-23T23:59:59.000Z

316

Method of removal of heavy metal from molten salt in IFR fuel pyroprocessing  

DOE Patents (OSTI)

An electrochemical method of separating heavy metal values from a radioactive molten salt including Li halide at temperatures of about 500.degree. C. The method comprises positioning a solid Li--Cd alloy anode in the molten salt containing the heavy metal values, positioning a Cd-containing cathode or a solid cathode positioned above a catch crucible in the molten salt to recover the heavy metal values, establishing a voltage drop between the anode and the cathode to deposit material at the cathode to reduce the concentration of heavy metals in the salt, and controlling the deposition rate at the cathode by controlling the current between the anode and cathode.

Gay, Eddie C. (Park Forest, IL)

1995-01-01T23:59:59.000Z

317

Natural networks  

E-Print Network (OSTI)

Scale-free and non-computable characteristics of natural networks are found to result from the least-time dispersal of energy. To consider a network as a thermodynamic system is motivated since ultimately everything that exists can be expressed in terms of energy. According to the variational principle, the network will grow and restructure when flows of energy diminish energy differences between nodes as well as relative to nodes in surrounding systems. The natural process will yield scale-free characteristics because the nodes that contribute to the least-time consumption of free energy preferably attach to each other. Network evolution is a path-dependent and non-deterministic process when there are two or more paths to consume a common source of energy. Although evolutionary courses of these non-Hamiltonian systems cannot be predicted, many mathematical functions, models and measures that characterize networks can be recognized as appropriate approximations of the thermodynamic equation of motion that has been derived from statistical physics of open systems.

Tuomo Hartonen; Arto Annila

2011-06-21T23:59:59.000Z

318

Utilizing Nature's Designs for Solar Energy Conversion  

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

Nature's Designs for Solar Energy Conversion Nature's Designs for Solar Energy Conversion Create new materials that: capture, convert, store sunlight Learn from Nature... ...build with chemistry ANL Photosynthesis Group Fundamental Studies  Solar energy conversion in natural and artificial photosynthesis Resolve mechanisms, design principles  Unique capabilities Time-resolved, multi-frequency EPR Time-resolved synchrotron X-ray Ultrafast spectroscopy Multi-molecular: Artificial systems for H 2 photocatalysis  Limitations:  Large solvent, molecular dependencies  Diffusion  Lifetimes  Uncontrolled back-reactions  Most PS contain noble metals  Organic solvent/high proton

319

Retrieval Of Final Stored Radioactive Waste Resumes  

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

18, 2012 18, 2012 Media Contact: Danielle Miller, DOE-Idaho Operations, 208-526-5709, millerdc@id.doe.gov Rick Dale, Idaho Treatment Group, 208-557-6552, rick.dale@amwtp.inl.gov Retrieval Of Final Stored Radioactive Waste Resumes IDAHO FALLS, ID- Operations to retrieve the estimated 6,900 cubic meters of stored transuranic waste remaining at the Idaho site began this week at the U.S. Department of Energy�s Advanced Mixed Waste Treatment Project. Waste retrieval resumes at the Advanced Mixed Waste Treatment Project. The resumption of work comes after a nearly two-year stoppage of retrieval operations �A significant investment has been made in terms of time and dollars that will allow employees to safely retrieve the final radioactive waste that has been stored aboveground at the Idaho site for more than four

320

ScienceDirect JOURNAL OF ENVIRONMENTAL RADIOACTIVITY  

Office of Legacy Management (LM)

ontine at wtYw.sciencedlrect.com ontine at wtYw.sciencedlrect.com ^-- 9 e* + - . , * * ScienceDirect JOURNAL OF ENVIRONMENTAL RADIOACTIVITY Journal o f Environmental Radioactivity 91 (2006) 27-40 www.elsevier.co~nAocate/jenvrad Radionuclides in marine macroalgae from Amchitka and Kiska Islands in the Aleutians: establishing a baseline for future biomonitoring Joanna Burger Michael Gochfeld C-d, David S . Kosson b7e, Charles W. Powers b-d*e7 Stephen Jewett b*f, Barry Friedlander b7d, Heloise Chenelot b=f7 Conrad D. Volz b-8, Christian Jeitner a-b Division of Life Sciences, Rutgers University, 6 0 4 Allison R o a d . Piscataway, N.I 0 8 8 5 4 - 8 0 8 2 , USA Consortium for Risk Evaluation with Stakeholder Participation (CRESP), Piscataway. N.I 0 8 8 5 4 . USA Environmental and Occupational Health Sciences Institute (EOHSZ), Piscataway, NJ 0

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

DOE - Safety of Radioactive Material Transportation  

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

How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Packagings are used to safely transport radioactive materials across the United States in over 1.6 million shipments per year. [Weiner et. al., 1991, Risk Analysis, Vol. 11, No. 4, p. 663] Most shipments are destined for hospitals and medical facilities. Other destinations include industrial, research and manufacturing plants, nuclear power plants and national defense facilities. The last comprehensive survey showed that less than 1 percent of these shipments involve high-level radioactive material. [Javitz et. al., 1985, SAND84-7174, Tables 4 and 8] The types of materials transported include: Surface Contaminated Object (SCO) Low Specific Activity (LSA) materials, Low-Level Waste (LLW),

322

1969 AUDIT OF SRP RADIOACTIVE WASTE  

Office of Scientific and Technical Information (OSTI)

969 AUDIT OF SRP RADIOACTIVE WASTE 969 AUDIT OF SRP RADIOACTIVE WASTE bY C . Ashley A p r i l 1970 Radiological Sciences Division Savannah River Laboratory E. 1. du Pont de Nemours & Co. Aiken, South Carolina 29801 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best avaiiable original document. . . . CONTENTS Page I n t r o d u c t i o n . . . . . . . . . . . . . . . . . . . . . . . . 5 Summary . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Releases t o t h e Atmosphere . . . . . . . . . . . . . . . . . 6 S e p a r a t i o n s Areas . . . . . . . . . . . . . . . . . . . . 6 TNX and Building 773-A . . . . . . . . . . . . . . . . . 8 Reactor Areas . . . . . . . . . . . . . . . . . . . . . . 7 Releases t o E f f l u e n t Streams . . . . . . . . . . . . . . . . 8 S e p a r a t i o n s Areas . . . . . . . . . . . . . . . . . . . . 8 DArea . . . . . . . . . . . . . . . . . . . . . . . . . 8 R e a c t o r A r e a s . . . . . . . . . . . . . . . . . . . . . . 9

323

Qualifying radioactive waste forms for geologic disposal  

SciTech Connect

We have developed a phased strategy that defines specific program-management activities and critical documentation for producing radioactive waste forms, from pyrochemical processing of spent nuclear fuel, that will be acceptable for geologic disposal by the US Department of Energy. The documentation of these waste forms begins with the decision to develop the pyroprocessing technology for spent fuel conditioning and ends with production of the last waste form for disposal. The need for this strategy is underscored by the fact that existing written guidance for establishing the acceptability for disposal of radioactive waste is largely limited to borosilicate glass forms generated from the treatment of aqueous reprocessing wastes. The existing guidance documents do not provide specific requirements and criteria for nonstandard waste forms such as those generated from pyrochemical processing operations.

Jardine, L.J. [Lawrence Livermore National Lab., CA (United States); Laidler, J.J.; McPheeters, C.C. [Argonne National Lab., IL (United States)

1994-09-01T23:59:59.000Z

324

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

325

RADIOACTIVITY IN RAIN WATER IN BANGKOK  

SciTech Connect

In order to check the effect of nuclear explosions on the atmosphere over Bangkok, rain water was evaporated and the radioactivity of the residue obtained was counted by a G. M. counter. The result shows that the radioactivity in the rain water began to rise from the normal level since 26 September 1961, reached the maximum on 10 November 1961, and then slowly declined. Because the level of radiation remained above that of the Maximum Permissible Concentration (MPC) for only a short time, it did not constitute a health hazard. Analysis of the residue of rain water indicates that the increase in radiation is caused by the fall-out from the Russian tests of nuclear weapons in the air from September to October 1961. (auth)

Sundara-vicharana, Y.; Bhodigen, S.; Hayodom, V.

1961-12-01T23:59:59.000Z

326

Solar Powered Radioactive Air Monitoring Stations  

SciTech Connect

Environmental monitoring of ambient air for radioactive material is required as stipulated in the PNNL Site radioactive air license. Sampling ambient air at identified preferred locations could not be initially accomplished because utilities were not readily available. Therefore, solar powered environmental monitoring systems were considered as a possible option. PNNL purchased two 24-V DC solar powered environmental monitoring systems which consisted of solar panels, battery banks, and sampling units. During an approximate four month performance evaluation period, the solar stations operated satisfactorily at an on-site test location. They were subsequently relocated to their preferred locations in June 2012 where they continue to function adequately under the conditions found in Richland, Washington.

Barnett, J. M.; Bisping, Lynn E.; Gervais, Todd L.

2013-10-30T23:59:59.000Z

327

Handbook of high-level radioactive waste transportation  

Science Conference Proceedings (OSTI)

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government`s system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government`s program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project.

Sattler, L.R.

1992-10-01T23:59:59.000Z

328

Office of Civilian Radioactive Waste Management  

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

RW-0583 RW-0583 QA:N/A Office of Civilian Radioactive Waste Management EVALUATION OF TECHNICAL IMPACT ON THE YUCCA MOUNTAIN PROJECT TECHNICAL BASIS RESULTING FROM ISSUES RAISED BY EMAILS OF FORMER PROJECT PARTICIPANTS February 2006 This page intentionally left blank. Table of Contents Executive Summary .............................................................................................................v 1. Introduction..............................................................................................................1 1.1 Background ....................................................................................................1 1.2 Role of the USGS in Yucca Mountain Work.................................................2

329

Radioactive Materials Transportation and Incident Response  

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

FEMA 358, 05/10 FEMA 358, 05/10 Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program U.S. Department of Energy TRANSPORTATION AND INCIDENT RESPONSE Q&A About Incident Response Q Q Law Enforcement ____________________________________ Fire ___________________________________________ Medical ____________________________________________ State Radiological Assistance ___________________________ Local Government Official ______________________________ Local Emergency Management Agency ___________________ State Emergency Management Agency ___________________ HAZMAT Team ______________________________________ Water Pollution Control ________________________________ CHEMTEL (Toll-free US & Canada) 1-800-255-3924 _________ CHEMTREC (Toll-free US & Canada) 1-800-424-9300 _______

330

SRP radioactive waste releases. Startup through 1959  

SciTech Connect

This report summarizes and documents radioactive waste released to the environs of the Savannah River Plant from startup through 1959. During this period, the quantity of beta-emitting radioisotopes released was determined by a total or ``gross`` analysis. However, advanced instrumentation and technology now permit an economical determination of most individual radionuclides. Therefore, future waste audit reports, beginning with January 1960, will record the quantity of specific radioisotopes released rather than gross amounts.

Ashley, C.

1960-09-01T23:59:59.000Z

331

Radioactive Colloid Removal by Optimizing Chemical Parameters  

Science Conference Proceedings (OSTI)

Engineering and operational differences between nuclear power plants cause large differences in the composition of liquid radioactive waste (LRW) streams. These differences effectively negate any standardized procedure for treatment of these streams before discharge to the environment. This report describes a method EPRI developed to characterize LRW streams and recommend optimum treatment strategies. The report illustrates the concept, demonstrates the application of the methodology, and provides a fram...

2003-04-22T23:59:59.000Z

332

Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) |  

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

Southwestern Low-Level Radioactive Waste Disposal Compact (South Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) < Back Eligibility Utility Investor-Owned Utility Industrial Construction Municipal/Public Utility Rural Electric Cooperative Fuel Distributor Program Info State South Dakota Program Type Siting and Permitting Provider Southwestern Low-Level Radioactive Waste Commission This legislation authorizes the state's entrance into the Southwestern Low-Level Radioactive Waste Disposal Compact, which provides for the cooperative management of low-level radioactive waste. The Compact is administered by a commission, which can regulate and impose fees on in-state radioactive waste generators. The states of Arizona, California,

333

Experiment Hazard Class 8.1 - Radioactive Materials/Samples  

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

1 - Radioactive Materials 1 - Radioactive Materials Applicability This hazard classification applies to all experiments involving radioactive materials as samples. The requirements of this hazard class also apply to sealed radioactive sources that are used as a sample (i.e. a target for x-ray radiation). Other hazard classifications and their associated hazard controls may also apply to experiments in this hazard class. The current requirements can be found in the APS Policy for Conducting Radioactive Sample Experiments in APS Experiment Enclosures. NOTE: The APS must be notified of shipment of any radioactive materials to the site well in advance of the proposed experiment. All radioactive materials must arrive through Argonne Receiving in Building 46 and the Argonne Materials Control & Accountability group (MC&A). Please contact

334

Radioactive Material Use at the EMSL Radiochemistry Annex  

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

Material Use at the EMSL Radiochemistry Annex Material Use at the EMSL Radiochemistry Annex The EMSL Radiochemistry Annex, located in the 3410 Material Science and Technology Building, is authorized to work with small to moderate amounts of radioactive material. In order to work within 3410 facility radiological limits, potential users must provide detailed information about the type and quantity of radioactive material, the form and packaging of the material and the type of work that will be performed at the EMSL Radiochemistry Annex. Radioactive material includes both purchased radioactive material and samples that contain concentrations of radioactive material in excess of normal background levels. Please realize that some samples that may not be considered to be radioactive material at your institution will be managed as radioactive material at

335

Low-Level Radioactive Waste Disposal Act (Pennsylvania) | Department of  

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

Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) < Back Eligibility Utility Commercial Investor-Owned Utility State/Provincial Govt Municipal/Public Utility Local Government Rural Electric Cooperative Transportation Program Info State Pennsylvania Program Type Environmental Regulations Provider Pennsylvania Department of Environmental Protection This act provides a comprehensive strategy for the siting of commercial low-level waste compactors and other waste management facilities, and to ensure the proper transportation, disposal and storage of low-level radioactive waste. Commercial incineration of radioactive wastes is prohibited. Licenses are required for low-level radioactive waste disposal facilities not licensed to accept low-level radioactive waste. Disposal at

336

Trending: Metal Oxo Bonds  

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

Trending: Metal Oxo Bonds Trending: Metal Oxo Bonds Trending: Metal Oxo Bonds Print Wednesday, 29 May 2013 00:00 Metal oxides are important for scientific and technical applications in a variety of disciplines, including materials science, chemistry, and biology. Highly covalent metal-oxygen multiple bonds (metal oxos) are the building blocks of metal oxides and have a bearing on the oxide's desirable chemical, magnetic, electronic, and thermal properties. The lack of a more sophisticated grasp of bonding in metal oxides constitutes a roadblock to innovation in a wide variety of important emergent technologies, including industrial catalysis, biomimetic transformations, and artificial photosynthesis. To address this problem, a research team from four national laboratories, three Department of Energy synchrotron user facilities, and the University of Washington has applied spectroscopic and computational analyses to a number of metal oxides, quantifying trends in metal oxo bonding for groups of metals across the periodic table.

337

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

338

Future radioactive liquid waste streams study  

SciTech Connect

This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL.

Rey, A.S.

1993-11-01T23:59:59.000Z

339

Geological problems in radioactive waste isolation  

SciTech Connect

The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

Witherspoon, P.A. (ed.)

1991-01-01T23:59:59.000Z

340

Radioactive iodine therapy in cats with hyperthyroidism  

SciTech Connect

Eleven cats with hyperthyroidism were treated with radioactive iodine (/sup 131/I). Previous unsuccessful treatments for hyperthyroidism included hemithyroidectomy (2 cats) and an antithyroid drug (7 cats). Two cats had no prior treatment. Thyroid scans, using technetium 99m, showed enlargement and increased radionuclide accumulation in 1 thyroid lobe in 5 cats and in both lobes in 6 cats. Serum thyroxine concentrations were high and ranged from 4.7 to 18 micrograms/dl. Radioactive iodine tracer studies were used to determine peak radioactive iodine uptake (RAIU) and effective and biological half-lives. Activity of /sup 131/I administered was calculated from peak RAIU, effective half-life, and estimated thyroid gland weight. Activity of /sup 131/I administered ranged from 1.0 to 5.9 mCi. The treatment goal was to deliver 20,000 rad to hyperactive thyroid tissue. However, retrospective calculations based on peak RAIU and effective half-life obtained during the treatment period showed that radiation doses actually ranged from 7,100 to 64,900 rad. Complete ablation of the hyperfunctioning thyroid tissue and a return to euthyroidism were seen in 7 cats. Partial responses were seen in 2 cats, and 2 cats became hypothyroid. It was concluded that /sup 131/I ablation of thyroid tumors was a reasonable alternative in the treatment of hyperthyroidism in cats. The optimal method of dosimetry remains to be determined.

Turrel, J.M.; Feldman, E.C.; Hays, M.; Hornof, W.J.

1984-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

Radioactive effluent reduction from 200 Area facilities  

SciTech Connect

Results are reported from a comprehensive study of radioactive wastes discharged to the environment in the 200 Area (chemical processing area) of the Hanford Reservation. Guides for the emission of gaseous waste were being met for the discharge of /sup 131/I, /sup 90/Sr, mixed fission products, and /sup 239/Pu. Treat ment systems for reduction of NO/sub 2/ from several stacks were proposed, and a prototype system for the removal of UOs from stack gases was developed and tested. Significant reductions of radioactivity in soil were achieved during a three to four year period by changes in operating procedures and minor expenditure of funds for process and equipment improvements. Emphasis was placed on the treatment of liquid wastes for the removal of /sup 137/Cs, /sup 90/Sr, and /sup 239/P u, from those streams prior to discharge to the environs. Improved methods for the monitoring and cycling of radioactive wastes, cooling waters, and steam condensates from process vessels were also developed. (CH)

Hanson, G.L.

1971-01-29T23:59:59.000Z

342

Geological problems in radioactive waste isolation  

SciTech Connect

The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

Witherspoon, P.A. (ed.)

1991-01-01T23:59:59.000Z

343

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

344

Mitigation of Memory Effects in Beta Scintillation Cells for Radioactive Gas Detection  

Science Conference Proceedings (OSTI)

The Automated Radioxenon Sampler/Analyzer (ARSA) developed at PNNL measures the relative concentrations of xenon isotopes using a ?-? coincidence system. Previous tests of the ARSA system have shown that latent radioactivity remains in the plastic cells after evacuation of the gases, leading to a memory effect in which the background count rate is dependent on the sample history. The increased background results in lower detection sensitivity. Two possible solutions to the memory effect are explored in this work: depositing a thin layer of metal on the plastic cell (metallization), and using an inorganic scintillating cell composed of yttrium aluminum perovskite (YAP). In both cases, the presence of inorganic material at the surface is intended to inhibit the diffusion of gases into the cell walls.

Seifert, Carolyn E.; McIntyre, Justin I.; Antolick, Kathryn C.; Carman, April J.; Cooper, Matthew W.; Hayes, James C.; Heimbigner, Tom R.; Hubbard, C. W.; Litke, Kevin E.; Ripplinger, Mike D.; Suarez, Reynold

2005-08-31T23:59:59.000Z

345

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01T23:59:59.000Z

346

Isolation of Metals from Liquid Wastes: Reactive in Turbulent Thermal Reactors  

SciTech Connect

A Generic Technology for treatment of DOE Metal-Bearing Liquid Waste The DOE metal-bearing liquid waste inventory is large and diverse, both with respect to the metals (heavy metals, transuranics, radionuclides) themselves, and the nature of the other species (annions, organics, etc.) present. Separation and concentration of metals is of interest from the standpoint of reducing the volume of waste that will require special treatment or isolation, as well as, potentially, from the standpoint of returning some materials to commerce by recycling. The variety of metal-bearing liquid waste in the DOE complex is so great that it is unlikely that any one process (or class of processes) will be suitable for all material. However, processes capable of dealing with a wide variety of wastes will have major advantages in terms of process development, capital, and operating costs, as well as in environmental and safety permitting. Moreover, to the extent that a process operates well with a variety of metal-bearing liquid feedwastes, its performance is likely to be relatively robust with respect to the inevitable composition variations in each waste feed. One such class of processes involves high-temperature treatment of atomized liquid waste to promote reactive capture of volatile metallic species on collectible particulate substrates injected downstream of a flame zone. Compared to low-temperature processes that remove metals from the original liquid phase by extraction, precipitation, ion exchange, etc., some of the attractive features of high-temperature reactive scavenging are: The organic constituents of some metal-bearing liquid wastes (in particular, some low-level mixed wastes) must be treated thermally in order to meet the requirements of the Resource Conservation and Recovery Act (RCRA) and Toxic Substances Control Act (TSCA), and the laws of various states. No species need be added to an already complex liquid system. This is especially important in light of the fact that DOE has already experienced problems with organic complexants added to precipitate radionuclides. For example, the Defense Nuclear Facilities Safety Board has expressed, in a formal Recommendation to the Secretary of Energy, its concern about the evolution of benzene vapor in concentrations greater then the lower flammability limit from tanks to which sodium tetraphenylborate has been added to precipitate 137Cs in the ''In-Tank Precipitation'' (ITP) process at the Savannah River Site. Other species added to the waste in the ITP process are sodium titanate (to adsorb 90Sr and Pu), and oxalic acid. Avoiding addition of organics to radioactive waste has the additional advantage that is likely to significantly reduce the rate of radiolytic and radiolytically-induced hydrogen generation (c.f. Meisel et al., [1993]), in which it is shown that removal of organics reduces the rate of hydrogen generation in simulated waste from Hanford tank 241-SY-101 by over 70%. Organic species already present are destroyed with very high efficiency. This attribute is especially attractive with respect to high-level tank waste at the Hanford Site, in which large amounts of citrate, glyoxylate, EDTA (ethylenediaminetetraacetic acid), and HEDTA [N-(2- hydroxyethyl)-ethylenediaminetriacetic acid] were added to precipitate radionuclides. These organic species are important in the thermal and radiolytic generation of methane, hydrogen, and nitrous oxide, flammable mixtures of which are episodically vented from 25 tanks on Hanford's Flammable Gas Watch List [Hopkins, 1994]. The same basic approach can be used to treat a broad range of liquid wastes, in each case concentrating the metals (regardless of liquid-phase oxidation state or association with chelators or absorbents) using a collectible sorbent, and destroying any organic species present. In common with the Army's approach (see section 2.2) to the thermal destruction of a 10 range of chemical warfare agents (GB, VX, and two blister agents), this may drastically simplify process and plant design and

Wendt, Jost O.L.

2001-09-30T23:59:59.000Z

347

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

21,547 21,547 4,916 0.06 0 0.00 0 0.00 7,012 0.13 3 0.00 7,099 0.22 19,031 0.10 N e w H a m p s h i r e New Hampshire 77. Summary Statistics for Natural Gas New Hampshire, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation..........................

348

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

139,881 139,881 26,979 0.30 463 0.00 115 3.92 27,709 0.53 19,248 0.70 28,987 0.92 103,037 0.52 A r i z o n a Arizona 50. Summary Statistics for Natural Gas Arizona, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... NA NA NA NA NA Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 6 6 6 7 7 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 721 508 711 470 417 From Oil Wells ........................................... 72 110 48 88 47 Total.............................................................. 794 618 759 558 464 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease

349

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

Middle Middle Atlantic Middle Atlantic 37. Summary Statistics for Natural Gas Middle Atlantic, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 1,857 1,981 2,042 1,679 1,928 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 36,906 36,857 26,180 37,159 38,000 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 161,372 152,717 140,444 128,677 152,494 From Oil Wells ........................................... 824 610 539 723 641 Total.............................................................. 162,196 153,327 140,982 129,400 153,134 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed

350

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

386,690 386,690 102,471 1.16 0 0.00 43 1.47 142,319 2.72 5,301 0.19 98,537 3.12 348,671 1.74 M i n n e s o t a Minnesota 71. Summary Statistics for Natural Gas Minnesota, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation..........................

351

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

1,108,583 1,108,583 322,275 3.63 298 0.00 32 1.09 538,749 10.28 25,863 0.95 218,054 6.90 1,104,972 5.52 I l l i n o i s Illinois 61. Summary Statistics for Natural Gas Illinois, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... NA NA NA NA NA Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 382 385 390 372 370 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 337 330 323 325 289 From Oil Wells ........................................... 10 10 10 10 9 Total.............................................................. 347 340 333 335 298 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ...............

352

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

286,485 286,485 71,533 0.81 25 0.00 31 1.06 137,225 2.62 5,223 0.19 72,802 2.31 286,814 1.43 M i s s o u r i Missouri 73. Summary Statistics for Natural Gas Missouri, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... NA NA NA NA NA Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 5 8 12 15 24 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 27 14 8 16 25 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 27 14 8 16 25 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation..........................

353

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

411,951 411,951 100,015 1.13 0 0.00 5 0.17 114,365 2.18 45,037 1.65 96,187 3.05 355,609 1.78 Massachusetts Massachusetts 69. Summary Statistics for Natural Gas Massachusetts, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation..........................

354

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

226,798 226,798 104,124 1.17 0 0.00 0 0.00 58,812 1.12 2,381 0.09 40,467 1.28 205,783 1.03 North Carolina North Carolina 81. Summary Statistics for Natural Gas North Carolina, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation..........................

355

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

68,747 68,747 34,577 0.39 0 0.00 34 1.16 14,941 0.29 0 0.00 11,506 0.36 61,058 0.31 I d a h o Idaho 60. Summary Statistics for Natural Gas Idaho, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation.......................... 0 0 0 0 0 Vented

356

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

0 0 0 0.00 0 0.00 0 0.00 540 0.01 0 0.00 2,132 0.07 2,672 0.01 H a w a i i Hawaii 59. Summary Statistics for Natural Gas Hawaii, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation.......................... 0 0 0 0 0 Vented and Flared

357

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

483,052 483,052 136,722 1.54 6,006 0.03 88 3.00 16,293 0.31 283,557 10.38 41,810 1.32 478,471 2.39 F l o r i d a Florida 57. Summary Statistics for Natural Gas Florida, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 47 50 98 92 96 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 7,584 8,011 8,468 7,133 6,706 Total.............................................................. 7,584 8,011 8,468 7,133 6,706 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ...............

358

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

291,898 291,898 113,995 1.29 0 0.00 4 0.14 88,078 1.68 3,491 0.13 54,571 1.73 260,140 1.30 I o w a Iowa 63. Summary Statistics for Natural Gas Iowa, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation.......................... 0 0 0

359

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

Vehicle Fuel: Vehicle Fuel: Deliveries to Consumers: Electric Residential: Utilities: Commercial: Total: New England New England 36. Summary Statistics for Natural Gas New England, 1992-1996 Table 691,089 167,354 1.89 0 0.00 40 1.36 187,469 3.58 80,592 2.95 160,761 5.09 596,215 2.98 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................

360

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

29,693 29,693 0 0.00 0 0.00 6 0.20 17,290 0.33 0 0.00 16,347 0.52 33,644 0.17 District of Columbia District of Columbia 56. Summary Statistics for Natural Gas District of Columbia, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation..........................

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

42,980 42,980 14,164 0.16 0 0.00 1 0.03 9,791 0.19 23,370 0.86 6,694 0.21 54,020 0.27 D e l a w a r e Delaware 55. Summary Statistics for Natural Gas Delaware, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 0 0 0 0 0 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 0 0 0 0 0 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 0 0 0 0 0 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 0 0 0 0 0 Repressuring ................................................ 0 0 0 0 0 Nonhydrocarbon Gases Removed ............... 0 0 0 0 0 Wet After Lease Separation..........................

362

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

-49,536 -49,536 7,911 0.09 49,674 0.25 15 0.51 12,591 0.24 3 0.00 12,150 0.38 32,670 0.16 North Dakota North Dakota 82. Summary Statistics for Natural Gas North Dakota, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 496 525 507 463 462 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 104 101 104 99 108 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 12,461 18,892 19,592 16,914 16,810 From Oil Wells ........................................... 47,518 46,059 43,640 39,760 38,906 Total.............................................................. 59,979 64,951 63,232 56,674 55,716 Repressuring ................................................

363

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

364

Some safety considerations for steam coolant with liquid metal breeders  

Science Conference Proceedings (OSTI)

Test results indicate the risk and quantity of hydrogen generation, aerosol characterization and release rates, radioactive species behavior, and potential attack on blanket candidate metals for postulated fusion reactor accident conditions when steam may be used near lithium breeder material. These results can be used to evaluate specific reactor safety concerns and to develop computer code models to predict consequences of postulated accidents involving steam and lithium.

Jeppson, D.W.

1989-03-01T23:59:59.000Z

365

Safety considerations for steam coolant with liquid metal breeders  

Science Conference Proceedings (OSTI)

Test results indicate the rate and quantity of hydrogen generation, aerosol characterization and release rates, radioactive species behavior, and potential attack on blanket candidate metals for postulated fusion reactor accident conditions when steam may be used near lithium breeder material. These results can be used to evaluate specific reactor safety concerns and to develop computer code models to predict consequences of postulated accidents involving steam and lithium. 7 figs., 4 tabs.

Jeppson, D.W.

1988-10-01T23:59:59.000Z

366

Some safety considerations for steam coolant with liquid metal breeders  

Science Conference Proceedings (OSTI)

Test results indicate the rate and quantity of hydrogen generation, aerosol characterization and release rates, radioactive species behavior, and potential attack on blanket candidate metals for postulated fusion reactor accident conditions when steam may be used near lithium breeder material. These results can be used to evaluate specific reactor safety concerns and to develop computer code models to predict consequences of postulated accidents involving steam and lithium. 7 figs., 4 tabs.

Jeppson, D.W.

1988-10-01T23:59:59.000Z

367

Apparatus for injection casting metallic nuclear energy fuel rods  

DOE Patents (OSTI)

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 consumable with the fuel rod, and in another embodiment, part of the mold can be re-used. Several molds can be arranged together in a cascaded manner, if desired, or several long cavities can be integrated in a monolithic multiple cavity re-usable mold.

Seidel, Bobby R. (Idaho Falls, ID); Tracy, Donald B. (Firth, ID); Griffiths, Vernon (Butte, MT)

1991-01-01T23:59:59.000Z

368

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

369

Iron phosphate compositions for containment of hazardous metal waste  

DOE Patents (OSTI)

An improved iron phosphate waste form for the vitrification, containment and long-term disposition of hazardous metal waste such as radioactive nuclear waste is provided. The waste form comprises a rigid iron phosphate matrix resulting from the cooling of a melt formed by heating a batch mixture comprising the metal waste and a matrix-forming component. The waste form comprises from about 30 to about 70 weight percent P{sub 2}O{sub 5} and from about 25 to about 50 weight percent iron oxide and has metals present in the metal waste chemically dissolved therein. The concentration of iron oxide in the waste form along with a high proportion of the iron in the waste form being present as Fe{sup 3+} provide a waste form exhibiting improved chemical resistance to corrosive attack. A method for preparing the improved iron phosphate waste forms is also provided. 21 figs.

Day, D.E.

1998-05-12T23:59:59.000Z

370

DOE - Office of Legacy Management -- Titanium Metals Corp Div of NLO - NV  

Office of Legacy Management (LM)

Titanium Metals Corp Div of NLO - Titanium Metals Corp Div of NLO - NV 07 FUSRAP Considered Sites Site: TITANIUM METALS CORP., DIV. OF NLO (NV.07 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Henderson , Nevada NV.07-1 Evaluation Year: 1994 NV.07-1 Site Operations: Experimental work on electrolyzing uranium contaminated magnesium fluoride. NV.07-2 Site Disposition: Eliminated - Potential for contamination considered remote NV.07-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium NV.07-2 Radiological Survey(s): None Indicated Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to TITANIUM METALS CORP., DIV. OF NLO NV.07-1 - DOE Memorandum; Williams to the File; Elimination of the

371

Precious Metals Conversion Information  

Science Conference Proceedings (OSTI)

Precious Metals Conversion Information. The Office of Weights and Measures (OWM) has prepared a Conversion Factors ...

2012-11-21T23:59:59.000Z

372

Corrosion of valve metals  

DOE Green Energy (OSTI)

A general survey related to the corrosion of valve metals or film-forming metals. The way these metals corrode with some general examples is described. Valve metals form relatively perfect oxide films with little breakdown or leakage when anodized. (FS)

Draley, J.E.

1976-01-01T23:59:59.000Z

373

METAL PRODUCTION AND CASTING  

DOE Patents (OSTI)

This patent covers a method and apparatus for collecting the molten metal produced by high temperature metal salt reduction. It consists essentially of subjecting the reaction vessel to centrifugal force in order to force the liberatcd molten metal into a coherent molten mass, and allowing it to solidify there. The apparatus is particularly suitable for use with small quantities of rare metals.

Magel, T.T.

1958-03-01T23:59:59.000Z

374

Ceramic to metal seal  

DOE Patents (OSTI)

Providing a high strength, hermetic ceramic to metal seal by essentially heating a wire-like metal gasket and a ceramic member, which have been chemically cleaned, while simultaneously deforming from about 50 to 95 percent the metal gasket against the ceramic member at a temperature of about 30 to 75 percent of the melting temperature of the metal gasket.

Snow, Gary S. (Albuquerque, NM); Wilcox, Paul D. (Albuquerque, NM)

1976-01-01T23:59:59.000Z

375

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

376

DOE - Safety of Radioactive Material Transportation  

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

Who uses them? Who makes rules? What are the requirements? Safety Record Spent fuel casks are constructed with thick walls of various metals. This cask is approximately 18-feet...

377

Trending: Metal Oxo Bonds  

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

Trending: Metal Oxo Bonds Print Trending: Metal Oxo Bonds Print Metal oxides are important for scientific and technical applications in a variety of disciplines, including materials science, chemistry, and biology. Highly covalent metal-oxygen multiple bonds (metal oxos) are the building blocks of metal oxides and have a bearing on the oxide's desirable chemical, magnetic, electronic, and thermal properties. The lack of a more sophisticated grasp of bonding in metal oxides constitutes a roadblock to innovation in a wide variety of important emergent technologies, including industrial catalysis, biomimetic transformations, and artificial photosynthesis. To address this problem, a research team from four national laboratories, three Department of Energy synchrotron user facilities, and the University of Washington has applied spectroscopic and computational analyses to a number of metal oxides, quantifying trends in metal oxo bonding for groups of metals across the periodic table.

378

Trending: Metal Oxo Bonds  

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

Trending: Metal Oxo Bonds Print Trending: Metal Oxo Bonds Print Metal oxides are important for scientific and technical applications in a variety of disciplines, including materials science, chemistry, and biology. Highly covalent metal-oxygen multiple bonds (metal oxos) are the building blocks of metal oxides and have a bearing on the oxide's desirable chemical, magnetic, electronic, and thermal properties. The lack of a more sophisticated grasp of bonding in metal oxides constitutes a roadblock to innovation in a wide variety of important emergent technologies, including industrial catalysis, biomimetic transformations, and artificial photosynthesis. To address this problem, a research team from four national laboratories, three Department of Energy synchrotron user facilities, and the University of Washington has applied spectroscopic and computational analyses to a number of metal oxides, quantifying trends in metal oxo bonding for groups of metals across the periodic table.

379

Trending: Metal Oxo Bonds  

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

Trending: Metal Oxo Bonds Print Trending: Metal Oxo Bonds Print Metal oxides are important for scientific and technical applications in a variety of disciplines, including materials science, chemistry, and biology. Highly covalent metal-oxygen multiple bonds (metal oxos) are the building blocks of metal oxides and have a bearing on the oxide's desirable chemical, magnetic, electronic, and thermal properties. The lack of a more sophisticated grasp of bonding in metal oxides constitutes a roadblock to innovation in a wide variety of important emergent technologies, including industrial catalysis, biomimetic transformations, and artificial photosynthesis. To address this problem, a research team from four national laboratories, three Department of Energy synchrotron user facilities, and the University of Washington has applied spectroscopic and computational analyses to a number of metal oxides, quantifying trends in metal oxo bonding for groups of metals across the periodic table.

380

Trending: Metal Oxo Bonds  

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

Trending: Metal Oxo Bonds Print Trending: Metal Oxo Bonds Print Metal oxides are important for scientific and technical applications in a variety of disciplines, including materials science, chemistry, and biology. Highly covalent metal-oxygen multiple bonds (metal oxos) are the building blocks of metal oxides and have a bearing on the oxide's desirable chemical, magnetic, electronic, and thermal properties. The lack of a more sophisticated grasp of bonding in metal oxides constitutes a roadblock to innovation in a wide variety of important emergent technologies, including industrial catalysis, biomimetic transformations, and artificial photosynthesis. To address this problem, a research team from four national laboratories, three Department of Energy synchrotron user facilities, and the University of Washington has applied spectroscopic and computational analyses to a number of metal oxides, quantifying trends in metal oxo bonding for groups of metals across the periodic table.

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

NATURAL RESOURCES ASSESSMENT  

DOE Green Energy (OSTI)

The purpose of this report is to summarize the scientific work that was performed to evaluate and assess the occurrence and economic potential of natural resources within the geologic setting of the Yucca Mountain area. The extent of the regional areas of investigation for each commodity differs and those areas are described in more detail in the major subsections of this report. Natural resource assessments have focused on an area defined as the ''conceptual controlled area'' because of the requirements contained in the U.S. Nuclear Regulatory Commission Regulation, 10 CFR Part 60, to define long-term boundaries for potential radionuclide releases. New requirements (proposed 10 CFR Part 63 [Dyer 1999]) have obviated the need for defining such an area. However, for the purposes of this report, the area being discussed, in most cases, is the previously defined ''conceptual controlled area'', now renamed the ''natural resources site study area'' for this report (shown on Figure 1). Resource potential can be difficult to assess because it is dependent upon many factors, including economics (demand, supply, cost), the potential discovery of new uses for resources, or the potential discovery of synthetics to replace natural resource use. The evaluations summarized are based on present-day use and economic potential of the resources. The objective of this report is to summarize the existing reports and information for the Yucca Mountain area on: (1) Metallic mineral and mined energy resources (such as gold, silver, etc., including uranium); (2) Industrial rocks and minerals (such as sand, gravel, building stone, etc.); (3) Hydrocarbons (including oil, natural gas, tar sands, oil shales, and coal); and (4) Geothermal resources. Groundwater is present at the Yucca Mountain site at depths ranging from 500 to 750 m (about 1,600 to 2,500 ft) below the ground surface. Groundwater resources are not discussed in this report, but are planned to be included in the hydrology section of future revisions of the ''Yucca Mountain Site Description'' (CRWMS M&O 2000c).

D.F. Fenster

2000-12-11T23:59:59.000Z

382

Novel Solvent for the Simultaneous recovery of Radioactive Nuclides from Liquid Radioactive Wastes  

DOE Patents (OSTI)

The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

Romanovskiy, Valeriy Nicholiavich; Smirnov, Lgor V.; Babain, Vasiliy A.; Todd, Terry A.; Brewer, Ken N.

1999-10-07T23:59:59.000Z

383

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

1,554,530 1,554,530 311,229 3.51 3,094,431 15.67 442 15.08 299,923 5.72 105,479 3.86 210,381 6.66 927,454 4.64 Mountain Mountain 43. Summary Statistics for Natural Gas Mountain, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 38,711 38,987 37,366 39,275 38,944 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 30,965 34,975 38,539 38,775 41,236 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 2,352,729 2,723,393 3,046,159 3,131,205 3,166,689 From Oil Wells ........................................... 677,771 535,884 472,397 503,986 505,903 Total.............................................................. 3,030,499 3,259,277 3,518,556

384

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

1,592,465 1,592,465 716,648 8.08 239,415 1.21 182 6.21 457,792 8.73 334,123 12.23 320,153 10.14 1,828,898 9.14 South Atlantic South Atlantic 40. Summary Statistics for Natural Gas South Atlantic, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 3,307 3,811 4,496 4,427 4,729 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 39,412 35,149 41,307 37,822 36,827 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 206,766 208,892 234,058 236,072 233,409 From Oil Wells ........................................... 7,584 8,011 8,468 7,133 6,706 Total.............................................................. 214,349 216,903 242,526 243,204 240,115

385

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

1,999,161 1,999,161 895,529 10.10 287,933 1.46 1,402 47.82 569,235 10.86 338,640 12.39 308,804 9.78 2,113,610 10.57 Pacific Contiguous Pacific Contiguous 44. Summary Statistics for Natural Gas Pacific Contiguous, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 3,896 3,781 3,572 3,508 2,082 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 1,142 1,110 1,280 1,014 996 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 156,635 124,207 117,725 96,329 88,173 From Oil Wells ........................................... 294,800 285,162 282,227 289,430 313,581 Total.............................................................. 451,435 409,370

386

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

-122,394 -122,394 49,997 0.56 178,984 0.91 5 0.17 37,390 0.71 205 0.01 28,025 0.89 115,622 0.58 West Virginia West Virginia 96. Summary Statistics for Natural Gas West Virginia, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 2,356 2,439 2,565 2,499 2,703 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 38,250 33,716 39,830 36,144 35,148 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... E 182,000 171,024 183,773 186,231 178,984 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. E 182,000 171,024 183,773 186,231 178,984 Repressuring ................................................

387

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

73,669 73,669 141,300 1.59 221,822 1.12 3 0.10 46,289 0.88 33,988 1.24 31,006 0.98 252,585 1.26 A r k a n s a s Arkansas 51. Summary Statistics for Natural Gas Arkansas, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 1,750 1,552 1,607 1,563 1,470 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 3,500 3,500 3,500 3,988 4,020 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 171,543 166,273 161,967 161,390 182,895 From Oil Wells ........................................... 39,364 38,279 33,446 33,979 41,551 Total.............................................................. 210,906 204,552 195,413 195,369 224,446 Repressuring ................................................

388

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

-1,080,240 -1,080,240 201,024 2.27 1,734,887 8.78 133 4.54 76,629 1.46 136,436 4.99 46,152 1.46 460,373 2.30 O k l a h o m a Oklahoma 84. Summary Statistics for Natural Gas Oklahoma, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 13,926 13,289 13,487 13,438 13,074 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 28,902 29,118 29,121 29,733 29,733 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 1,674,405 1,732,997 1,626,858 1,521,857 1,467,695 From Oil Wells ........................................... 342,950 316,945 308,006 289,877 267,192 Total.............................................................. 2,017,356 2,049,942 1,934,864

389

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

7,038,115 7,038,115 3,528,911 39.78 13,646,477 69.09 183 6.24 408,861 7.80 1,461,718 53.49 281,452 8.91 5,681,125 28.40 West South Central West South Central 42. Summary Statistics for Natural Gas West South Central, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 87,198 84,777 88,034 88,734 62,357 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 92,212 95,288 94,233 102,525 102,864 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 11,599,913 11,749,649 11,959,444 11,824,788 12,116,665 From Oil Wells ........................................... 2,313,831 2,368,395 2,308,634 2,217,752 2,151,247 Total..............................................................

390

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

77,379 77,379 94,481 1.07 81,435 0.41 8 0.27 70,232 1.34 1,836 0.07 40,972 1.30 207,529 1.04 K e n t u c k y Kentucky 65. Summary Statistics for Natural Gas Kentucky, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 1,084 1,003 969 1,044 983 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 12,483 12,836 13,036 13,311 13,501 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 79,690 86,966 73,081 74,754 81,435 From Oil Wells ........................................... 0 0 0 0 0 Total.............................................................. 79,690 86,966 73,081 74,754 81,435 Repressuring ................................................

391

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

-67,648 -67,648 75,616 0.85 480,828 2.43 0 0.00 16,720 0.32 31,767 1.16 29,447 0.93 153,549 0.77 Pacific Noncontiguous Pacific Noncontiguous 45. Summary Statistics for Natural Gas Pacific Noncontiguous, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 9,638 9,907 9,733 9,497 9,294 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 112 113 104 100 102 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 198,603 190,139 180,639 179,470 183,747 From Oil Wells ........................................... 2,427,110 2,588,202 2,905,261 3,190,433 3,189,837 Total.............................................................. 2,625,713 2,778,341

392

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

-310,913 -310,913 110,294 1.24 712,796 3.61 2 0.07 85,376 1.63 22,607 0.83 57,229 1.81 275,508 1.38 K a n s a s Kansas 64. Summary Statistics for Natural Gas Kansas, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 9,681 9,348 9,156 8,571 7,694 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 18,400 19,472 19,365 22,020 21,388 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 580,572 605,578 628,900 636,582 629,755 From Oil Wells ........................................... 79,169 82,579 85,759 86,807 85,876 Total.............................................................. 659,741 688,157 714,659 723,389 715,631 Repressuring ................................................

393

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

819,046 819,046 347,043 3.91 245,740 1.24 40 1.36 399,522 7.62 32,559 1.19 201,390 6.38 980,555 4.90 M i c h i g a n Michigan 70. Summary Statistics for Natural Gas Michigan, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 1,223 1,160 1,323 1,294 2,061 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 3,257 5,500 6,000 5,258 5,826 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 120,287 126,179 136,989 146,320 201,123 From Oil Wells ........................................... 80,192 84,119 91,332 97,547 50,281 Total.............................................................. 200,479 210,299 228,321 243,867 251,404 Repressuring ................................................

394

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

W W y o m i n g -775,410 50,253 0.57 666,036 3.37 14 0.48 13,534 0.26 87 0.00 9,721 0.31 73,609 0.37 Wyoming 98. Summary Statistics for Natural Gas Wyoming, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 10,826 10,933 10,879 12,166 12,320 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 3,111 3,615 3,942 4,196 4,510 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 751,693 880,596 949,343 988,671 981,115 From Oil Wells ........................................... 285,125 142,006 121,519 111,442 109,434 Total.............................................................. 1,036,817 1,022,602 1,070,862 1,100,113 1,090,549 Repressuring

395

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

-67,648 -67,648 75,616 0.85 480,828 2.43 0 0.00 16,179 0.31 31,767 1.16 27,315 0.86 150,877 0.75 A l a s k a Alaska 49. Summary Statistics for Natural Gas Alaska, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 9,638 9,907 9,733 9,497 9,294 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 112 113 104 100 102 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 198,603 190,139 180,639 179,470 183,747 From Oil Wells ........................................... 2,427,110 2,588,202 2,905,261 3,190,433 3,189,837 Total.............................................................. 2,625,713 2,778,341 3,085,900 3,369,904 3,373,584 Repressuring

396

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

628,189 628,189 449,511 5.07 765,699 3.88 100 3.41 528,662 10.09 39,700 1.45 347,721 11.01 1,365,694 6.83 West North Central West North Central 39. Summary Statistics for Natural Gas West North Central, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 10,177 9,873 9,663 9,034 8,156 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 18,569 19,687 19,623 22,277 21,669 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 594,551 626,728 651,594 655,917 648,822 From Oil Wells ........................................... 133,335 135,565 136,468 134,776 133,390 Total.............................................................. 727,886 762,293

397

Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

1,048,760 1,048,760 322,661 3.64 18,131 0.09 54 1.84 403,264 7.69 142,688 5.22 253,075 8.01 1,121,742 5.61 N e w Y o r k New York 80. Summary Statistics for Natural Gas New York, 1992-1996 Table 1992 1993 1994 1995 1996 Reserves (billion cubic feet) Estimated Proved Reserves (dry) as of December 31 ....................................... 329 264 242 197 232 Number of Gas and Gas Condensate Wells Producing at End of Year.............................. 5,906 5,757 5,884 6,134 6,208 Production (million cubic feet) Gross Withdrawals From Gas Wells ......................................... 22,697 20,587 19,937 17,677 17,494 From Oil Wells ........................................... 824 610 539 723 641 Total.............................................................. 23,521 21,197 20,476 18,400 18,134 Repressuring ................................................

398

Enabling Sustainability through the Physics of Metals & Materials ...  

Science Conference Proceedings (OSTI)

Mar 6, 2013 ... Heavy metals in natural water, industrial water and wastewaters are a worldwide ... complexes is released as HCN gas under strength acidic conditions ... Northern Regions of Russia as Alternative Sources of Pure Water for...

399

Influence of Metal Ions on the Synthesis of Silver Nanoparticles  

Science Conference Proceedings (OSTI)

Adsorption of Lead and Cadmium onto Natural and Modified Diatomite ... Mechanical Properties of 5083 Aluminium Welds after Manual and Automatic Pulsed Gas Metal Arc Welding Using ... Tool Failure Criteria while Drilling Titanium Alloys.

400

The natural and industrial cycling of indium in the environment  

E-Print Network (OSTI)

Indium is an important metal whose production is increasing dramatically due to new uses in the rapidly growing electronics, photovoltaic, and LED industries. Little is known, however, about the natural or industrial cycling ...

White, Sarah Jane O'Connell

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

Liquid absorbent solutions for separating nitrogen from natural gas  

DOE Patents (OSTI)

Nitrogen-absorbing and -desorbing compositions, novel ligands and transition metal complexes, and methods of using the same, which are useful for the selective separation of nitrogen from other gases, especially natural gas.

Friesen, Dwayne T. (Bend, OR); Babcock, Walter C. (Bend, OR); Edlund, David J. (Redmond, OR); Lyon, David K. (Bend, OR); Miller, Warren K. (Bend, OR)

2000-01-01T23:59:59.000Z

402

INEL metal recycle annual report, FY-94  

SciTech Connect

In 1992, the mission of the Idaho Chemical Processing Plant was changed from reprocessing of spent nuclear fuels to development of technologies for conditioning of spent nuclear fuels and other high-level wastes for disposal in a geologic repository. In addition, the Department of Energy (DOE) directed Idaho National Engineering Laboratory (INEL) to develop a program plan addressing the management of radioactive contaminated scrap metal (RSM) within the DOE complex. Based on discussions with the EM-30 organization, the INEL Metal Recycle program plan was developed to address all issues of RSM management. Major options considered for RSM management were engineered interim storage, land disposal as low-level waste, and beneficial reuse/recycle. From its inception, the Metal Recycle program has emphasized avoidance of storage and disposal costs through beneficial reuse of RSM. The Metal Recycle program plan includes three major activities: Site-by-site inventory of RSM resources; validation of technologies for conversion of RSM to usable products; and identification of parties prepared to participate in development of a RSM recycle business.

Bechtold, T.E. [ed.

1994-09-01T23:59:59.000Z

403

Derivation of guidelines for uranium residual radioactive material in soil at the New Brunswick Site, Middlesex County, New Jersey  

SciTech Connect

Residual radioactive material guidelines for uranium in soil were derived for the New Brunswick Site, located in Middlesex County, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program of the US Department of Energy (DOE). Residual radioactive material guidelines for individual radionuclides of concern and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the New Brunswick Site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines. The guidelines derived in this report are intended to apply to the remediation of these remaining residual radioactive materials at the site. The primary radionuclides of concern in these remaining materials are expected to be radium-226 and, to a lesser extent, natural uranium and thorium. The DOE has established generic cleanup guidelines for radium and thorium in soil; however, cleanup guidelines for other radionuclides must be derived on a site-specific basis.

Dunning, D.; Kamboj, S.; Nimmagadda, M.; Yu, C. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1996-02-01T23:59:59.000Z

404

CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER  

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

CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT This Fiscal Year 2008 Civilian Radioactive Waste Management Fee Adequacy Letter Report presents an evaluation of the adequacy of the one mill per kilowatt-hour fee paid by commercial nuclear power generators for the permanent disposal of their spent nuclear fuel by the Government. This evaluation recommends no fee change. CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT More Documents & Publications FY 2007 Fee Adequacy, Pub 2008 Fiscal Year 2007 Civilian Radioactive Waste Management Fee Adequacy Assessment Report January 16, 2013 Secretarial Determination of the Adequacy of the Nuclear

405

Upgrading the Radioactive Waste Management Infrastructure in Azerbaijan  

Science Conference Proceedings (OSTI)

Radionuclide uses in Azerbaijan are limited to peaceful applications in the industry, medicine, agriculture and research. The Baku Radioactive Waste Site (BRWS) 'IZOTOP' is the State agency for radioactive waste management and radioactive materials transport. The radioactive waste processing, storage and disposal facility is operated by IZOTOP since 1963 being significantly upgraded from 1998 to be brought into line with international requirements. The BRWS 'IZOTOP' is currently equipped with state-of-art devices and equipment contributing to the upgrade the radioactive waste management infrastructure in Azerbaijan in line with current internationally accepted practices. The IAEA supports Azerbaijan specialists in preparing syllabus and methodological materials for the Training Centre that is currently being organized on the base of the Azerbaijan BRWS 'IZOTOPE' for education of specialists in the area of safety management of radioactive waste: collection, sorting, processing, conditioning, storage and transportation. (authors)

Huseynov, A. [Baku Radioactive Waste Site IZOTOP, Baku (Azerbaijan); Batyukhnova, O. [State Unitary Enterprise Scientific and Industrial Association Radon, Moscow (Russian Federation); Ojovan, M. [Sheffield Univ., Immobilisation Science Lab. (United Kingdom); Rowat, J. [International Atomic Energy Agency, Dept. of Nuclear Safety and Security, Vienna (Austria)

2007-07-01T23:59:59.000Z

406

Low Level Radioactive Waste Authority (Michigan) | Department of Energy  

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

Low Level Radioactive Waste Authority (Michigan) Low Level Radioactive Waste Authority (Michigan) Low Level Radioactive Waste Authority (Michigan) < Back Eligibility Utility Fed. Government Investor-Owned Utility Municipal/Public Utility Program Info State Michigan Program Type Safety and Operational Guidelines Provider Department of Environmental Quality Federal laws passed in 1980 and 1985 made each state responsible for the low-level radioactive waste produced within its borders. Act 204 of 1987 created the Low-Level Radioactive Waste Authority (LLRWA) to fulfill state responsibilities under federal law for managing and assuring disposal capacity for the low-level radioactive waste produced in Michigan. The LLRWA began a facility siting process in 1989 under the statutory limits of Act 204. The LLRWA eventually determined that it was impossible to find a

407

Radioactive Mineral Occurences in Nevada | Open Energy Information  

Open Energy Info (EERE)

Radioactive Mineral Occurences in Nevada Radioactive Mineral Occurences in Nevada Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: Radioactive Mineral Occurences in Nevada Abstract Abstract unavailable. Author Larry J. Garside Organization Nevada Bureau of Mines and Geology Published Nevada Bureau of Mines and Geology, 1973 Report Number Open File Report 94-2 DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Radioactive Mineral Occurences in Nevada Citation Larry J. Garside (Nevada Bureau of Mines and Geology). 1973. Radioactive Mineral Occurences in Nevada. Reno, NV: Nevada Bureau of Mines and Geology. Report No.: Open File Report 94-2. Retrieved from "http://en.openei.org/w/index.php?title=Radioactive_Mineral_Occurences_in_Nevada&oldid=690513"

408

SRNL - Natural Attenuation Monitor  

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

Natural Attenuation Monitor covers Natural Attenuation Monitor Published by the US DOE Monitored Natural Attenuation and Enhanced Attenuation for Chlorinated Solvents Technology...

409

Unconventional Natural Gas  

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

Natural Gas Unconventional Natural Gas Los Alamos scientists are committed to the efficient and environmentally-safe development of major U.S. natural gas and oil resources....

410

,"Texas Natural Gas Summary"  

U.S. Energy Information Administration (EIA) Indexed Site

Natural Gas Wellhead Price (Dollars per Thousand Cubic Feet)","Texas Natural Gas Imports Price (Dollars per Thousand Cubic Feet)","Price of Texas Natural Gas Exports...

411

,"Mississippi Natural Gas Summary"  

U.S. Energy Information Administration (EIA) Indexed Site

Natural Gas Wellhead Price (Dollars per Thousand Cubic Feet)","Mississippi Natural Gas Imports Price All Countries (Dollars per Thousand Cubic Feet)","Mississippi Natural Gas...

412

,"Montana Natural Gas Summary"  

U.S. Energy Information Administration (EIA) Indexed Site

Natural Gas Wellhead Price (Dollars per Thousand Cubic Feet)","Montana Natural Gas Imports Price (Dollars per Thousand Cubic Feet)","Price of Montana Natural Gas Exports...

413

,"Michigan Natural Gas Summary"  

U.S. Energy Information Administration (EIA) Indexed Site

Natural Gas Wellhead Price (Dollars per Thousand Cubic Feet)","Michigan Natural Gas Imports Price (Dollars per Thousand Cubic Feet)","Price of Michigan Natural Gas Exports...

414

RW - Radioactive Waste - Energy Conservation Plan  

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

Unconsciously Unconsciously Negative Behaviors Consciously Negative Behaviors Consciously Positive Behaviors Unconsciously Positive Behaviors Education Motivation Repetition Permanent Change Figure 1 - The Phases of Behavior Change Office of Civilian Radioactive Waste Management (OCRWM) Energy Conservation Plan Summary: Development and implementation of this plan is being treated as a project. This serves two purposes. First, it increases familiarity with the precepts of project management and DOE Order 413. Secondly, project management provides a great structure for organizing and implementing the activities that will facilitate energy savings through behavioral changes. A project structure also helps define how the effort will begin and what constitutes success at the

415

Midwestern Radioactive Materials Transportation Committee Agenda  

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

Council of State Governments Council of State Governments Midwestern Radioactive Materials Transportation Committee May 15, 2012 Knoxville, Tennessee Revised Agenda 9 - 9:45 am Welcome, Introductions, and Committee Reports Report from co-chairs Tim Runyon (Illinois) Project update Lisa Janairo, CSG Midwest Work group reports Integrated Spent Fuel Management Work Group Teri Engelhart (Wisconsin) NTSF-related reports Planning Committee Tim Runyon (Illinois) Communications Ad Hoc Working Group Jane Beetem (Missouri) WIPP Security Communications Protocol Major Lance Evans (Iowa) Ad Hoc Working Group Information and Communications Work Group Lisa Janairo 9:45 - 10:45 am Committee Discussion Blue Ribbon Commission final report: state reactions, next steps

416

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

417

Corrosion resistant storage container for radioactive material  

DOE Patents (OSTI)

A corrosion resistant long-term storage container for isolating high-level radioactive waste material in a repository is claimed. The container is formed of a plurality of sealed corrosion resistant canisters of different relative sizes, with the smaller canisters housed within the larger canisters, and with spacer means disposed between juxtaposed pairs of canisters to maintain a predetermined spacing between each of the canisters. The combination of the plural surfaces of the canisters and the associated spacer means is effective to make the container capable of resisting corrosion, and thereby of preventing waste material from leaking from the innermost canister into the ambient atmosphere.

Schweitzer, D.G.; Davis, M.S.

1984-08-30T23:59:59.000Z

418

BIOLOGICAL DECOMPOSITION OF RADIOACTIVE LAUNDRY WASTE  

SciTech Connect

A series of tests was conducted on a laundry waste containing radtoactive materials, using an activated sludge process, to determine whether the organic materials which would interfere with a process of flocculation and adsorption could be removed along with a substantial quantity of the radioactive material. A trickling filter was used to treat the waste over a long period of time. The filter removed nearly all of the activity and most of the organic compounds. However, sufficient residual activity remained in the effluent to require either two-stage operation or final processing by flocculation and adsorption. Recirculation was beneficial. A supplementary bacteria feed of ammonium nitrate was necessary. (auth)

Wiederhold, E.W.

1954-03-10T23:59:59.000Z

419

RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS  

SciTech Connect

Radioactive material packages are withdrawn from use for various reasons; loss of mission, decertification, damage, replacement, etc. While the packages themselves may be decertified, various components may still be able to perform to their required standards and find useful service. The Packaging Technology and Pressurized Systems group of the Savannah River National Laboratory has been reducing the cost of producing new Type B Packagings by reclaiming, refurbishing, and returning to service the containment vessels from older decertified packagings. The program and its benefits are presented.

Abramczyk, G.; Nathan, S.; Loftin, B.; Bellamy, S.

2011-06-06T23:59:59.000Z

420

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect

The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations & Development (PO&D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage.

McCarthy, T.L.

1995-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

Particle beam generator using a radioactive source  

DOE Patents (OSTI)

The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

Underwood, D.G.

1991-12-31T23:59:59.000Z

422

ORNL Radioactive Beams for Stellar Explosion Studies  

Science Conference Proceedings (OSTI)

At ORNL, we are using unique radioactive beams to measure scattering, transfer, and capture reactions to help understand exploding stars such as novae, supernovae, and X-ray bursts. Recent results have been obtained with beams of {sup 26}Al, {sup 17}F, and {sup 130,132}Sn, utilizing gas targets, silicon strip detectors, and recoil separators. More exciting work is planned at the future FRIB facility. We are also using synergistic nuclear data evaluations and the Computational Infrastructure for Nuclear Astrophysics to investigate the astrophysical impact of our measurements.

Smith, Michael S. [Physics Division, Oak Ridge National Lab, Oak Ridge, Tennessee, 37831-6354 (United States)

2010-08-12T23:59:59.000Z

423

Particle beam generator using a radioactive source  

DOE Patents (OSTI)

The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

Underwood, D.G.

1993-03-30T23:59:59.000Z

424

THE DESIGN OF A RADIOACTIVITY CONTAMINATION METER  

SciTech Connect

A description is given of the design and performance of a portable instrument for measurement of radiation from small quantities of radioactive contamination. The device weighs 4 lb 2 oz, operates on a single flashlight battery for 200 hr, and operates at low temperatures with the proper battery. The most novel feature is a clockworkdriven chopper for a-c. The circuit includes cold cathode tubes and a halogen-quenched G-M tube. Reliability was emphasized in the design. (T.R.H.)

Goulding, F.S.

1954-04-27T23:59:59.000Z

425

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

426

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

427

The Enrichment of Intergalactic Medium With Adiabatic Feedback I: Metal Cooling and Metal Diffusion  

E-Print Network (OSTI)

A study of IGM metal enrichment using a series of SPH simulations is presented, employing metal cooling and the turbulent diffusion of metals and thermal energy. Stellar feedback naturally drives winds in the simulations reproducing both the observed star formation history (SFH) and the universal neutral hydrogen fraction. This challenges assumptions that wind recipes are necessary for correct SFH. The mass and metal evolution in stars and various gas phases was investigated. At z=0, 40 % of the baryons are in the warm-hot intergalactic medium (WHIM), but most metals (82 %) are in stars. At higher z the most metals were in the IGM was higher due to more efficient winds. This indicates that IGM metals primarily reside in the WHIM throughout cosmic history (unlike momentum driven wind model). The WHIM metallicity is 0.01-0.1 solar with a slight decrease at lower z. The metallicity evolution is consistent with observations. Galactic winds most efficiently enrich the IGM for intermediate mass galaxies ($10^{10}$M...

Shen, Sijing; Stinson, Gregory

2009-01-01T23:59:59.000Z

428

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

429

South Carolina Radioactive Waste Transportation and Disposal Act (South Carolina)  

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

The Department of Health and Environmental Control is responsible for regulating the transportation of radioactive waste, with some exceptions, into or within the state for storage, disposal, or...

430

Appalachian States Low-Level Radioactive Waste Compact (Maryland)  

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

This legislation authorizes Maryland's entrance into the Appalachian States Low-Level Radioactive Waste Compact, which seeks to promote interstate cooperation for the proper management and disposal...

431

Portsmouth Site Delivers First Radioactive Waste Shipment to...  

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

Eckert, Anthony Howard and Chris Ashley. These drums containing radioactive waste from uranium enrichment operations were included in the Portsmouth site's first shipment to...

432

Cyclotrons to Make Neutrons & Radioactive Targets for SBSS at...  

Office of Science (SC) Website

to Make Neutrons & Radioactive Targets for SBSS at LBNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications...

433

EA-0981: Solid Waste Retrieval Complex, Enhanced Radioactive...  

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

Waste Retrieval Complex, Enhanced Radioactive and Mixed Waste Storage Facility, Infrastructure Upgrades, and Central Waste Support Complex, Hanford Site, Richland, Washington...

434

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

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

environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result...

435

Applying Risk Communication to the Transportation of Radioactive...  

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

to the Transportation of Radioactive Materials More Documents & Publications Status and Future of TRANSCOM Department of Energy Office of Science Transportation Overview NTSF...

436

Sandia technology used to remove radioactive material at Fukushima...  

National Nuclear Security Administration (NNSA)

technology used to remove radioactive material at Fukushima | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

437

UNITED STATES DEPARTMENT OF ENERGY OFFICE OF CIVILIAN RADIOACTIVE...  

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

UNITED STATES DEPARTMENT OF ENERGY OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT Annual Financial Report Years Ended September 30, 2009 and 2008 UNITED STATES DEPARTMENT OF...

438

DOE O 435.1 Chg 1, Radioactive Waste Management  

Directives, Delegations, and Requirements

The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public ...

1999-07-09T23:59:59.000Z

439

Photo of the Week: What Do Airborne Radioactive Particles Taste...  

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

1:40pm Addthis At Sandia National Laboratories, researchers have developed pods that can survey and "taste" radioactive particles without exposing a human crew to nuclear hazards....

440

Aerial survey finds no increase in radioactivity for Los Alamos...  

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

Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Aerial survey finds no increase in radioactivity ... Aerial survey finds no increase in...

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

Metal-Air Batteries  

Science Conference Proceedings (OSTI)

Metal-air batteries have much higher specific energies than most currently available primary and rechargeable batteries. Recent advances in electrode materials and electrolytes, as well as new designs on metal-air batteries, have attracted intensive effort in recent years, especially in the development of lithium-air batteries. The general principle in metal-air batteries will be reviewed in this chapter. The materials, preparation methods, and performances of metal-air batteries will be discussed. Two main metal-air batteries, Zn-air and Li-air batteries will be discussed in detail. Other type of metal-air batteries will also be described.

Zhang, Jiguang; Bruce, Peter G.; Zhang, Gregory

2011-08-01T23:59:59.000Z

442

Alkali metal nitrate purification  

DOE Patents (OSTI)

A process is disclosed for removing contaminants from impure alkali metal nitrates containing them. The process comprises heating the impure alkali metal nitrates in solution form or molten form at a temperature and for a time sufficient to effect precipitation of solid impurities and separating the solid impurities from the resulting purified alkali metal nitrates. The resulting purified alkali metal nitrates in solution form may be heated to evaporate water therefrom to produce purified molten alkali metal nitrates suitable for use as a heat transfer medium. If desired, the purified molten form may be granulated and cooled to form discrete solid particles of purified alkali metal nitrates.

Fiorucci, Louis C. (Hamden, CT); Morgan, Michael J. (Guilford, CT)

1986-02-04T23:59:59.000Z

443

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

444

Natural Gas Vehicles  

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

Natural gas vehicles (NGVs) are either fueled exclusively with compressed natural gas or liquefied natural gas (dedicated NGVs) or are capable of natural gas and gasoline fueling (bi-fuel NGVs).

445

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

446

Bulk Metallic Glasses X  

Science Conference Proceedings (OSTI)

Jul 31, 2012 ... Aerospace and Spacecraft Applications for Bulk Metallic Glasses and Matrix Composites Air Oxidation of a Binary Cu64.5Zr35.5 Bulk Metallic...

447

Bulk Metallic Glasses VII  

Science Conference Proceedings (OSTI)

Sponsorship, The Minerals, Metals and Materials Society ... Air-Oxidation of a ( Zr55Cu30Al10Ni5)98Er2 Bulk Metallic Glass at 350-500oc Anelastic...

448

Metal phthalocyanine catalysts  

DOE Patents (OSTI)

As a new composition of matter, alkali metal or ammonium or tetraalkylammonium diazidoperfluorophthalocyanatoferrate. Other embodiments of the invention comprise compositions wherein the metal of the coordination complex is cobalt, manganese and chromium.

Ellis, Jr., Paul E. (Downingtown, PA); Lyons, James E. (Wallingford, PA)

1994-01-01T23:59:59.000Z

449

Metal phthalocyanine catalysts  

DOE Patents (OSTI)

A new composition of matter is described which is an alkali metal or ammonium or tetraalkylammonium diazidoperfluorophthalocyanatoferrate. Other embodiments of the invention comprise compositions wherein the metal of the coordination complex is cobalt, manganese and chromium.

Ellis, P.E. Jr.; Lyons, J.E.

1994-10-11T23:59:59.000Z

450

Precision metal rulers  

Science Conference Proceedings (OSTI)

... precision metal rulers. Our customers include state bureaus of Weights and Measures and departments of Agriculture. We also ...

2011-10-28T23:59:59.000Z

451

Fasteners & Metals Program  

Science Conference Proceedings (OSTI)

Directory of Accredited Laboratories. Fasteners & Metals Program. The Fastener Quality Act (FQA), Public Law 101-592, was ...

2013-11-08T23:59:59.000Z

452

TMS Light Metals Publication  

Science Conference Proceedings (OSTI)

The following instructions should be used when submitting a manuscript for any TMS Light Metals proceedings volume. INTRODUCTION. Orientation to...

453

Refractory Metals 2011  

Science Conference Proceedings (OSTI)

Aug 2, 2010 ... TMS Structural Materials Division TMS: Refractory Metals Committee. Organizer( s), Omer Dogan, DOE National Energy Technology Laboratory

454

INEEL Radioactive Liquid Waste Reduction Program  

SciTech Connect

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of EnergyIdaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most promising alternatives were compared by applying weighting factors to each based on how well the alternative met the established criteria. From this information, an overall ranking of the various alternatives was obtained and a path forward recommended.

Tripp, Julia Lynn; Archibald, Kip Ernest; Argyle, Mark Don; Demmer, Ricky Lynn; Miller, Rose Anna; Lauerhass, Lance

1999-03-01T23:59:59.000Z

455

INEEL Radioactive Liquid Waste Reduction Program  

SciTech Connect

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy ? Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most promising alternatives were compared by applying weighting factors to each based on how well the alternative met the established criteria. From this information, an overall ranking of the various alternatives was obtained and a path forward recommended.

C. B. Millet; J. L. Tripp; K. E. Archibald; L. Lauerhauss; M. D. Argyle; R. L. Demmer

1999-02-01T23:59:59.000Z

456

PRODUCTION OF METALS  

DOE Patents (OSTI)

A process is described producing metallic thorium, titanium, zirconium, or hafnium from the fluoride. In the process, the fluoride is reduced with alkali or alkaline earth metal and a booster compound (e.g. iodine or a decomposable oxysalt) in a sealed bomb at superatmospheric pressure and a temperature above the melting point of the metal to be produced.

Spedding, F.H.; Wilhelm, H.A.; Keller, W.H.

1961-09-19T23:59:59.000Z

457

Durable metallized polymer mirror  

DOE Patents (OSTI)

A metallized polymer mirror construction is disclosed having improved durability against delamination and tunneling, comprising: an outer layer of polymeric material; a metal oxide layer underlying the outer layer of polymeric material; a silver reflective layer underneath the metal oxide layer; and a layer of adhesive attaching the silver layer to a substrate. 6 figs.

Schissel, P.O.; Kennedy, C.E.; Jorgensen, G.J.; Shinton, Y.D.; Goggin, R.M.

1994-11-01T23:59:59.000Z

458

Discovery of underground argon with low level of radioactive 39Ar and possible applications to WIMP dark matter detectors  

E-Print Network (OSTI)

We report on the first measurement of 39Ar in argon from underground natural gas reservoirs. The gas stored in the US National Helium Reserve was found to contain a low level of 39Ar. The ratio of 39Ar to stable argon was found to be important backgrounds in argon detectors for WIMP dark matter searches. The findings reported demonstrate the possibility of constructing large multi-ton argon detectors with low radioactivity suitable for WIMP dark matter searches.

Galbiati, C

2007-01-01T23:59:59.000Z

459

Discovery of underground argon with low level of radioactive 39Ar and possible applications to WIMP dark matter detectors  

E-Print Network (OSTI)

We report on the first measurement of 39Ar in argon from underground natural gas reservoirs. The gas stored in the US National Helium Reserve was found to contain a low level of 39Ar. The ratio of 39Ar to stable argon was found to be important backgrounds in argon detectors for WIMP dark matter searches. The findings reported demonstrate the possibility of constructing large multi-ton argon detectors with low radioactivity suitable for WIMP dark matter searches.

C. Galbiati; R. Purtschert

2007-12-03T23:59:59.000Z

460

Fluorescent Functionalized Mesoporous Silica for Radioactive Material Extraction  

Science Conference Proceedings (OSTI)

Mesoporous silica with covalently bound salicylic acid molecules incorporated in the structure was synthesized with a one-pot, co-condensation reaction at room temperature. The as-synthesized material has a large surface area, uniform particle size, and an ordered pore structure as determined by characterization with transmission electron microscopy, thermal gravimetric analysis, and infrared spectra, etc. Using the strong fluorescence and metal coordination capability of salicylic acid, functionalized mesoporous silica (FMS) was developed to track and extract radionuclide contaminants, such as uranyl [U(VI)] ions encountered in subsurface environments. Adsorption measurements showed a strong affinity of the FMS toward U(VI) with a Kd value of 105 mL/g, which is four orders of magnitude higher than the adsorption of U(VI) onto most of the sediments in natural environments. The new materials have a potential for synergistic environmental monitoring and remediation of the radionuclide U(VI) from contaminated subsurface environments.

Li, Juan; Zhu, Kake; Shang, Jianying; Wang, Donghai; Nie, Zimin; Guo, Ruisong; Liu, Chongxuan; Wang, Zheming; Li, Xiaolin; Liu, Jun

2012-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "naturally radioactive metallic" 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

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Video User' s Guide Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL 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

462

Radioactive Effluents from Nuclear Power Plants Annual Report 2008  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

463

Radioactive Effluents from Nuclear Power Plants Annual Report 2007  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

464

Die ^ o o \\3,S* Environmental Radioactivity in  

E-Print Network (OSTI)

. Measurements of fallout radioactivity in the Faroes in 1980 are presented. Strontium-90 (and 137cs in most DATA, FAROE ISLANDS, FISHES, FOOD, FOOD CHAINS, GLOBAL FALLOUT, GRAPHS, MILK, PLANTS, RADIOACTIVITY (P > 99.9%) #12;1. INTRODUCTION 1.1. The fallout programme for t-he Faroes, which was initiated

465