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1

Naturally Occurring Radioactive Materials (NORM)  

SciTech Connect

This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training).

Gray, P. [ed.

1997-02-01T23:59:59.000Z

2

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

3

Issues of natural radioactivity in phosphates  

SciTech Connect

The fertilization of phosphorus (P) fertilizers is essential in agricultural production, but phosphates contain in dependence on their origin different amounts of trace elements. The problem of cadmium (Cd) loads and other heavy metals is well known. However, only a limited number of investigations examined the contamination of phosphates with the two heaviest metals, uranium (U) and thorium (Th), which are radioactive. Also potassium (K) is lightly radioactive. Measurements are done n the radioactivity content of phosphates, P fertilizers and soils. The radiation doses to workers and public as well as possible contamination of soils from phosphate rock or fertilizer caused by these elements or their daughter products is of interest with regard to radiation protection. The use of P fertilizers is necessary for a sustainable agriculture, but it involves radioactive contamination of soils. The consequences of the use of P fertilizers is discussed, also with regard to existing and proposed legislation. 11 refs., 2 figs., 7 tabs.

Schnug, E.; Haneklaus, S. [Institute of Plant Nutrition and Soil Science, Braunschweig (Germany); Schnier, C. [GKSS-Research Centre, Geesthacht (Germany); Scholten, L.C. [KEMA, Arnhem (Netherlands)

1996-12-31T23:59:59.000Z

4

Properties of Natural Radiation and Radioactivity  

SciTech Connect

Ubiquitous natural sources of radiation and radioactive material (naturally occurring radioactive material, NORM) have exposed humans throughout history. To these natural sources have been added technologically-enhanced naturally occurring radioactive material (TENORM) sources and human-made (anthropogenic) sources. This chapter describes the ubiquitous radiation sources that we call background, including primordial radionuclides such as 40K, 87Rb, the 232Th series, the 238U series, and the 235U series; cosmogenic radionuclides such as 3H and 14C; anthropogenic radionuclides such as 3H, 14C, 137Cs, 90Sr, and 129I; radiation from space; and radiation from technologically-enhanced concentrations of natural radionuclides, particularly the short-lived decay products of 222Rn ("radon") and 220Rn ("thoron") in indoor air. These sources produce radiation doses to people principally via external irradiation or internal irradiation following intakes by inhalation or ingestion. The effective doses from each are given, with a total of 3.11 mSv y-1 (311 mrem y-1) to the average US resident. Over 2.5 million US residents receive over 20 mSv y-1 (2 rem y-1), primarily due to indoor radon. Exposure to radiation from NORM and TENORM produces the largest fraction of ubiquitous background exposure to US residents, on the order of 2.78 mSv (278 mrem) or about 89%. This is roughly 45% of the average annual effective dose to a US resident of 6.2 mSv y-1 (620 mrem y-1) that includes medical (48%), consumer products and air travel (2%), and occupational and industrial (0.1%). Much of this chapter is based on National Council on Radiation Protection and Measurements (NCRP) Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," for which the author chaired the subcommittee that wrote Chapter 3 on "Ubiquitous Background Radiation."

Strom, Daniel J.

2009-07-13T23:59:59.000Z

5

Measurement of natural radioactivity from soil samples of Sind, Pakistan  

Science Journals Connector (OSTI)

......Gnbold G., Ganhimeg G. Natural Radioactivity of Some Mongolian Building Materials (2000) National University of Mongolia. INIS Electronic Form No. E16-20002-46. 14 Baeza A. , Del-Rio M., Miro C. Natural radioactivity in soils of the Province......

S. A. Mujahid; S. Hussain

2011-06-01T23:59:59.000Z

6

Natural radioactivity in soil in the Baluchistan province of Pakistan  

Science Journals Connector (OSTI)

......Gnbold G., Ganhimeg G. Natural radioactivity of some Mongolian building materials. (2000) National University of Mongolia, INIS Electronic Form No. E16-20002-46. 17 Baeza A. , Del-Rio M., Miro C. Natural radioactivity in soils of the Province......

S. A. Mujahid; S. Hussain

2010-08-01T23:59:59.000Z

7

Uranium Compounds and Other Natural Radioactivities  

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

radioactive materials and global fallout as it exists in the environment (such as from testing of nuclear explosive devices.) However, any action that has been taken to separate...

8

Naturally Occurring Radioactive Materials in Cargo at US Borders  

SciTech Connect

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

9

Natural Airborne Radioactivity at Kjeller, Norway  

Science Journals Connector (OSTI)

... During the last four months of 1957, radon concentrations have varied between about 30 and 1,100 X 10~18 c./cm. ... inversion and low temperature. In order to explain this effect, we suggest that considerable radon exhalation may be trapped in the cooled air which tends to follow the natural water ...

S. H. SMALL; A. LILLEGRAVEN; P. B. STOREB

1958-04-26T23:59:59.000Z

10

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

11

On the Radio-activity of Natural Gas  

Science Journals Connector (OSTI)

... Physical Science Series, an account is given of some experiments with a highly radio-active gas obtained from crude petroleum. In this investigation it was found that air drawn through ... emanation from radium. The present writer has extended this investigation to an examination of the natural ...

J. C. MCLENNAN

1904-06-16T23:59:59.000Z

12

Natural radioactivity measurements in rock samples of Cuihua Mountain National Geological Park, China  

Science Journals Connector (OSTI)

......samples were stored in gas-tight, radon impermeable...concentrations of the natural radionuclides 226Ra...radiation hazard indices from natural radioactivity of some...radioactive samples from Cyprus characteristic geological...Matiullah, Kenawy M. A. Natural radioactivity in marble......

Xinwei Lu; Xiaolan Zhang

2008-01-01T23:59:59.000Z

13

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

14

Hydrogen production during processing of radioactive sludge containing noble metals  

SciTech Connect

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

15

Hydrogen production during processing of radioactive sludge containing noble metals  

SciTech Connect

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

16

Natural radioactivity measurements in rock samples of Cuihua Mountain National Geological Park, China  

Science Journals Connector (OSTI)

......Holm E. The natural radioactivity in phosphate deposits from Sudan. Sci. Total Environ (1995) 162:173-178. 17 Sesana L...24 El-Arabi A. M . Natural radioactivity in sand used in thermal therapy at the Red Sea Coast. J. Environ. Radioact (2005......

Xinwei Lu; Xiaolan Zhang

2008-01-01T23:59:59.000Z

17

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

Science Journals Connector (OSTI)

In Canada nuclear and radiological regulatory responsibilities are shared between the provinces/territories and the federal government. The Canadian Nuclear Safety Commission (CNSC) regulates nuclear fuel cycle materials and man?made radionuclides under the Nuclear Safety and Control Act (2000). The provinces and territories regulate NORM arising from industrial activities not involving the nuclear fuel cycle materials. Present guidelineCanadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM)was published in 2000 in order to bring uniformity to the management of NORM?related procedures to provide adequate radiation protection for workers and the general public. The basic premise of these guidelines is that the NORM?related activities should not be posing any greater hazard than those activities regulated under the Nuclear Safety and Control Act; these concepts are described in this paper.

Anar S. Baweja; Bliss L. Tracy

2008-01-01T23:59:59.000Z

18

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

SciTech Connect

In Canada, nuclear and radiological regulatory responsibilities are shared between the provinces/territories and the federal government. The Canadian Nuclear Safety Commission (CNSC) regulates nuclear fuel cycle materials and man-made radionuclides under the Nuclear Safety and Control Act (2000). The provinces and territories regulate NORM arising from industrial activities, not involving the nuclear fuel cycle materials. Present guideline--Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM)--was published in 2000 in order to bring uniformity to the management of NORM-related procedures to provide adequate radiation protection for workers and the general public. The basic premise of these guidelines is that the NORM-related activities should not be posing any greater hazard than those activities regulated under the Nuclear Safety and Control Act; these concepts are described in this paper.

Baweja, Anar S.; Tracy, Bliss L. [Radiation Protection Bureau, Health Canada, Ottawa, Ontario (Canada)

2008-08-07T23:59:59.000Z

19

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...

Demarchos, Andronikos Stavros

2012-06-07T23:59:59.000Z

20

The fate and behaviour of enhanced natural radioactivity with respect to environmental protection  

SciTech Connect

In contrast to the monitoring and prevention of occupational radiation risk caused by enhanced natural radioactivity, relatively little attention has been paid to the environmental impact associated with residues containing enhanced activity concentration of naturally occurring radionuclides. Such materials are often deposited directly into the environment, a practice which is strictly forbidden in the management of other types of radioactive waste. In view of the new trends in radiation protection, the need to consider the occurrence of anthropogenically enhanced natural radioactivity as a particular unique case of environmental hazard is quite apparent. Residues containing high activity concentrations of some natural radionuclides differ from radioactive materials arising from the nuclear industry. In addition, the radiation risk is usually combined with the risk caused by other pollutants. As such and to date, there are no precise regulations regarding this matter and moreover, the non-nuclear industry is often not aware of potential environmental problems caused by natural radioactivity. This article discusses aspects of environmental radiation risks caused by anthropogenically enhanced natural radioactivity stored at unauthorised sites. Difficulties and inconclusiveness in the application of recommendations and models for radiation risk assessment are explored. General terms such as 'environmental effects' and the basic parameters necessary to carry out consistent and comparable Environmental Risk Assessment (ERA) have been developed and defined. - Highlights: Black-Right-Pointing-Pointer Features of environmental impact caused by residues containing high activity concentration of natural radionuclides Black-Right-Pointing-Pointer Definition of an effect of radiation on an ecosystem and novel method for its assessment Black-Right-Pointing-Pointer Radiation protection regulation inconclusiveness in the aspects of enhanced natural radioactivity.

Michalik, B., E-mail: b.michalik@gig.eu [Laboratory of Radiometry, Central Mining Institute (GIG), Plac Gwarkow 1, 40-166 Katowice (Poland); Brown, J., E-mail: Justin.Brown@nrpa.no [Norwegian Radiation Protection Authority (NRPA), Grini naeringspark 13, 1361 Osteras Norway (Norway); Krajewski, P., E-mail: krajewski@clor.waw.pl [Central Laboratory for Radiological Protection (CLOR), ul. Konwaliowa 7, 03-194 Warszawa Poland (Poland)

2013-01-15T23:59:59.000Z

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.


21

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

SciTech Connect

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

22

Use of Long-Lived Natural Radioactivity as an Atmospheric Tracer  

Science Journals Connector (OSTI)

... group of radioactive isotopes for this purpose would be the longer-lived, daughter products of radon radium-D, -E and -F which are naturally present in the atmosphere as ... -F which are naturally present in the atmosphere as a result of the leakage of radon from soils and rocks on the Earth's surface.

W. M. BURTON; N. G. STEWART

1960-05-21T23:59:59.000Z

23

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

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

natural sources The study was subsequently peer reviewed externally by scientists at Colorado State University and internally within the Lab. December 10, 2008 Los Alamos National...

24

RADIOACTIVE MATERIAL SHIPPING PACKAGINGS AND METAL TO METAL SEALS FOUND IN THE CLOSURES OF CONTAINMENT VESSELS INCORPORATING CONE SEAL CLOSURES  

SciTech Connect

The containment vessels for the Model 9975 radioactive material shipping packaging employ a cone-seal closure. The possibility of a metal-to-metal seal forming between the mating conical surfaces, independent of the elastomer seals, has been raised. It was postulated that such an occurrence would compromise the containment vessel hydrostatic and leakage tests. The possibility of formation of such a seal has been investigated by testing and by structural and statistical analyses. The results of the testing and the statistical analysis demonstrate and procedural changes ensure that hydrostatic proof and annual leakage testing can be accomplished to the appropriate standards.

Loftin, B; Glenn Abramczyk, G; Allen Smith, A

2007-06-06T23:59:59.000Z

25

Natural radioactivity and external gamma radiation exposure at the coastal Red Sea in Egypt  

Science Journals Connector (OSTI)

......0.5 - 151 39 1.08 0.27 - (25) Sudan 29.6 6.02 158.4 4.09...Natural radioactivity in sand used in thermal therapy at the Red Sea Coast. J. Environ...in the Red Sea coastal environment of Sudan. Mar. Pollut. Bull. (1998) 36......

S. Harb

2008-07-01T23:59:59.000Z

26

The application of metal cutting technologies in tasks performed in radioactive environments  

SciTech Connect

The design and use of equipment to perform work in radioactive environments is uniquely challenging. Some tasks require that the equipment be operated by a person wearing a plastic suit or full face respirator and donning several pairs of rubber gloves. Other applications may require that the equipment be remotely controlled. Other important, design considerations include material compatibility, mixed waste issues, tolerance to ionizing radiation, size constraints and weight capacities. As always, there is the ``We need it ASAP`` design criteria. This paper describes four applications where different types of metal cutting technologies were used to successfully perform tasks in radioactive environments. The technologies include a plasma cutting torch, a grinder with an abrasive disk, a hydraulic shear, and a high pressure abrasive water jet cutter.

Fogle, R.F.; Younkins, R.M.

1997-05-01T23:59:59.000Z

27

Measurement of natural radioactivity and assessment of associated radiation hazards in soil around Baoji second coal-fired thermal power plant, China  

Science Journals Connector (OSTI)

......10001 g) were sealed in gas-tight, radon-impermeable...concentrations of the natural radionuclides 226Ra...Comparative study of natural radioactivity levels...radioactive samples from Cyprus characteristic geological...Mechanisms of enrichment of natural radioactivity along the......

Xinwei Lu; Xiaoxue Li; Pujun Yun; Dacheng Luo; Lijun Wang; Chunhui Ren; Cancan Chen

2012-01-01T23:59:59.000Z

28

Assessment of natural and anthropogenic radioactivity levels in soils, rocks and water in the vicinity of Chirano Gold Mine in Ghana  

Science Journals Connector (OSTI)

......gamma-ray exposure from natural radioactivity concentrations...drinking water containing natural radioactivity due to...inhalation of airborne radon gas for the area where both...concentrations in surface soils in Cyprus. J. Environ. Radioact...UNSCEAR. Exposures from natural sources of radiation......

A. Faanu; H. Lawluvi; D. O. Kpeglo; E. O. Darko; G. Emi-Reynolds; A. R. Awudu; O. K. Adukpo; C. Kansaana; I. D. Ali; B. Agyeman; L. Agyeman; R. Kpodzro

2014-01-01T23:59:59.000Z

29

Background in the context of land contaminated with naturally occurring radioactive material  

Science Journals Connector (OSTI)

The financial implications of choosing a particular threshold for clearance of radioactively contaminated land are substantial, particularly when one considers the volume of naturally occurring radioactive material (NORM) created each year by the production and combustion of fossil fuels and the exploitation of industrial minerals. Inevitably, a compromise needs to be reached between the level of environmental protection sought and the finite resources available for remediation. In the case of natural series radionuclides, any anthropogenic input is always superimposed on the inventory already present in the soil; this 'background' inventory is conventionally disregarded when assessing remediation targets. Unfortunately, the term is not well defined and the concept of 'background dose' is open to alternative interpretations. In this paper, we address the issue of natural background from a geochemical rather than from a solely radiological perspective, illustrating this with an example from the china clay industry. We propose a simple procedure for decision making based on activity concentrations of primordial radionuclides and their progeny. Subsequent calculations of dose need to take into account the mineralogical and chemical characteristics of the contamination, which in the case of NORM are invariably reflected in uranium series disequilibrium.

D Read; G D Read; M C Thorne

2013-01-01T23:59:59.000Z

30

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 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

31

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

32

Natural radioactivity in various water samples and radiation dose estimations in Bolu province, Turkey  

Science Journals Connector (OSTI)

Abstract The level of natural radioactivity for Bolu province of north-western Turkey was assessed in this study. There is no information about radioactivity measurement reported in water samples in the Bolu province so far. For this reason, gross ? and ? activities of 55 different water samples collected from tap, spring, mineral, river and lake waters in Bolu were determined. The mean activity concentrations were 68.11mBqL?1, 169.44mBqL?1 for gross ? and ? in tap water. For all samples the gross ? activity is always higher than the gross ? activity. All value of the gross ? were lower than the limit value of 500mBqL?1 while two spring and one mineral water samples were found to have gross ? activity concentrations of greater than 1000mBqL?1. The associated age-dependent dose from all water ingestion in Bolu was estimated. The total dose for adults had an average value exceeds the WHO recommended limit value. The risk levels from the direct ingestion of the natural radionuclides in tap and mineral water in Bolu were determinated. The mean 210Po and 228Ra risk the value of tap and mineral waters slightly exceeds what some consider on acceptable risk of 10?4 or less.

F. Korkmaz Gorur; H. Camgoz

2014-01-01T23:59:59.000Z

33

Performance of Liquid Metals in Natural Circulation Cooled Nuclear Reactors  

SciTech Connect

The inherent safety capability of natural circulation makes reactor design more reliable. Additionally, the construction and operation of a nuclear power plant with natural circulation in the primary cooling circuit is an interesting alternative for nuclear plant designers, due to their lower operational and investment costs obtained by simplifying systems and controls. This paper deals with the feasibility of application of natural circulation in the primary cooling circuit of a liquid metal fast reactor. The methodology employed is a non-dimensional analysis, which describes the relationship between the physical properties and system variables. The performance criterion is bounded by a safety argument, referring to the maximum cladding temperature allowed during operation. The study considers several coolants, which can play a part in reactor cooling systems, such as lead, lead-bismuth and sodium. Bismuth and gallium are included in this analysis, in order to extend the range of properties for reference purposes. The results present a characterization of natural circulation flow in a reactor and compare the cooling capabilities from different liquid metals coolants. (authors)

Ceballos, Carlos; Lathouwers, Danny; Verkooijen, Adrian [Interfacultair Reactor Instituut, Technische Universiteit Delft, Mekelweg 15, Delft (Netherlands)

2004-07-01T23:59:59.000Z

34

Natural radioactive nuclides and chemical components in the groundwater of Beni Suef  

Science Journals Connector (OSTI)

Measurements of natural radioactivity in drinking water have been performed in many parts of the world, mostly for assessment of the doses and risk resulting from consuming water. A study of the radionuclide and chemical components in groundwater from Beni Suef Governate, Egypt has been carried out. Fifty water samples were analysed by ?-ray spectroscopy to determine the 226Ra, 232Th and 40K concentrations; major elements, pH, alkalinity and conductivity were also measured. The activity concentration values ranged from 0.008 to 0.040Bql?1 for 226Ra, from 0.003 to 0.019Bql?1 for 232Th and from 0.025 to 0.344Bql?1 for 40K. The annual ingestion of these radionuclides, using local consumption rates (averaged over the whole population) of 1.5ld?1, was estimated to be 8.59, 4.86 and 83.47Bqy?1 for 226Ra, 232Th and 40K, respectively. The estimated effective doses from drinking water were found to be 2.4Svy?1 (226Ra), 1.1Svy?1 (232Th) and 0.5Svy?1 (40K). The contribution of these radionuclides to the committed effective dose from a year's consumption of drinking water is therefore estimated to be only 4% of the WHO value (0.1mSvy?1). The moderate pH value is the most important parameter, and there was no observed correlation between natural radioactivity and electrical conductivity or concentrations of major ions.

F A Khalil; Rafat M Amin; M A K El Fayoumi

2009-01-01T23:59:59.000Z

35

Interactions between radioactively labeled colloids and natural particles: Evidence for colloidal pumping  

SciTech Connect

It has been hypothesized that colloidal forms of trace metals can be reactive intermediaries in the scavenging processes leading to the removal of their particulate forms. A series of radiotracer experiments using natural colloidal organic matter from Galveston Bay, USA were carried out in order to test this hypothesis. Suspended particle uptake of originally colloidally bound trace metals occurred in a matter of hours to days in estuarine waters. After ten days, the majority ( >50%) of the colloidal trace metals had been transferred into the particulate phase ({ge} 0.45{mu}m), except for {sup 65}Zn. Two distinctively different temporal regions of removal of colloidal trace metals were identified: a faster reaction during the first four hours, followed by a slower reaction after approximately one day. In a separate river water-seawater mixing experiment, the solid/solution partitioning of the radiotracers was investigated in the absence of suspended matter. About 30% of most of the elements, except Ag and Fe ({approximately}60%), were associated with a newly formed particulate phase after eight days. There were two major trends: (1) the particulate fraction of {sup 59}Fe and {sup 110}Ag increased while the colloidal fraction decreased, suggesting a colloidal pumping mechanism. (2) The particulate fraction of {sup 54}Mn, {sup 133}Ba, {sup 65}Zn, {sup 109}Cd, {sup 113}Sn, and {sup 60}Co increased while the LMW({le}1 kDa) fraction decreased, suggesting a direct uptake into the particulate fraction with less involvement of a transitory colloidal phase. The results from these experiments suggested two different pathways for colloidal tracer uptake by particles: (1) colloidal pumping of a major component (e.g., biopolymer) of the colloidal pool and (2) coagulation of trace components (e.g., phytochelatins) with varying affinities for different trace metals. 39 refs., 8 figs., 3 tabs.

Wen, L.S.; Santschi, P.H.; Tang, D. [Texas A & M Univ., Galveston, TX (United States)] [Texas A & M Univ., Galveston, TX (United States)

1997-07-01T23:59:59.000Z

36

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

37

An overview of naturally occurring radioactive materials (NORM) in the petroleum industry  

SciTech Connect

Oil and gas extraction and processing operations sometimes accumulate naturally occurring radioactive materials (NORM) at concentrations above normal in by-product waste streams. Results from NORM surveys indicate that radionuclide concentrations can be quite variable, ranging from undetectable to extremely high levels. To date, efforts to characterize the geographic distribution of NORM have been limited by poor statistical representation. In addition, the fate of NORM in the environment has not been fully defined, and few human health risk assessment have been conducted. Both the petroleum industry and regulators are becoming increasingly concerned about the presence of NORM. At present, most existing federal environmental regulations do not address oil and gas NORM, and only a few states have developed regulatory programs. Available data suggest that the occurrence of NORM (and associated health risks) is significant enough to warrant increased regulatory control. However, before these regulations can be developed, additional research is needed to (1) better characterize the occurrence and distribution of NORM throughout the industry, (2) quantify hazards posed by NORM to industry workers and the general public, and (3) develop effective waste treatment and minimization technologies that will lower the risk associated with NORM and reduce disposal costs.

Smith, K.P.

1992-12-01T23:59:59.000Z

38

Naturally occurring heavy radioactive elements in the geothermal microcosm of the Los Azufres (Mexico) volcanic complex  

Science Journals Connector (OSTI)

Abstract The Los Azufres geothermal complex of central Mexico is characterized by fumaroles and boiling hot-springs. The fumaroles form habitats for extremophilic mosses and ferns. Physico-chemical measurements of two relatively pristine fumarolic microcosms point to their resemblance with the paleo-environment of earth during the Ordovician and Devonian periods. These geothermal habitats were analysed for the distribution of elemental mass fractions in the rhizospheric soil (RS), the native volcanic substrate (VS) and the sediments (S), using the new high-sensitivity technique of polarized x-ray energy dispersive fluorescence spectrometry (PEDXRF) as well as instrumental neutron activation analysis (INAA) for selected elements. This work presents the results for the naturally occurring heavy radioactive elements (NOHRE) Bi, Th and U but principally the latter two. For the RS, the density was found to be the least and the total organic matter content the most. Bi was found to be negligibly present in all substrate types. The average Th and U mass fractions in the RS were higher than in the VS and about equal to their average mass fractions in the S. The VS mass fraction of Th was higher, and of U lower, than the mass fractions in the earth's crust. In fact for the fumaroles of one site, the average RS mass fractions of these elements were higher than the averaged values for S (without considering the statistical dispersion). The immobilization of the NOHRE in the RS is brought about by the bio-geochemical processes specific to these extremophiles. Its effectiveness is such that despite the small masses of these plants, it compares with, or may sometimes exceed, the immobilization of the NOHRE in the S by the abiotic and aggressive chemical action of the hot-springs. These results indicate that the fumarolic plants are able to transform the volcanic substrate to soil and to affect the NOHRE mass fractions even though these elements are not plant nutrients. Mirrored back to the paleo times when such plant types were ubiquitous, it would mean that the first plants contributed significantly to pedogenesis and the biogeochemical recycling of even the heaviest and radioactive elements. Such plants may potentially be useful for the phytostabilisation of soil moderately contaminated by the NOHRE. Furthermore where applicable, geochronology may require taking into account the influence of the early plants on the NOHRE distributions.

W.A. Abuhani; N. Dasgupta-Schubert; L.M. Villaseor; D. Garca Avila; L. Surez; C. Johnston; S.E. Borjas; S.A. Alexander; S. Landsberger; M.C. Surez

2015-01-01T23:59:59.000Z

39

Comparison of costs for solidification of high-level radioactive waste solutions: glass monoliths vs metal matrices  

SciTech Connect

A comparative economic analysis was made of four solidification processes for liquid high-level radioactive waste. Two processes produced borosilicate glass monoliths and two others produced metal matrix composites of lead and borosilicate glass beads and lead and supercalcine pellets. Within the uncertainties of the cost (1979 dollars) estimates, the cost of the four processes was about the same, with the major cost component being the cost of the primary building structure. Equipment costs and operating and maintenance costs formed only a small portion of the building structure costs for all processes.

Jardine, L.J.; Carlton, R.E.; Steindler, M.J.

1981-05-01T23:59:59.000Z

40

Public exposure to hazards associated with natural radioactivity in open-pit mining in Ghana  

Science Journals Connector (OSTI)

......and Waste Safety in Mining and Mineral Procession...on the Kubi Forest Mining Project. Environmental...Anglogold Ashanti. Review of Operations. Annual...Community Development Plan, Iduapriem and Teberebe...International Basic Safety Standards (BSS) for protection...radioactivity in open-pit mining in Ghana. | The......

E. O. Darko; A. Faanu; A. R. Awudu; G. Emi-Reynolds; J. Yeboah; O. C. Oppon; E. H. K. Akaho

2010-01-01T23:59:59.000Z

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.


41

Radioactive Dust from Nuclear Detonations  

Science Journals Connector (OSTI)

...than the dose received from natural radioactivity in a period of...radioactive particles. The natural radioactivity of the atmosphere...curies/liter. This radioactive gas is present in equilibrium with...With an approximation of the natural radiation dose to the lung as...

Merril Eisenbud; John H. Harley

1953-02-13T23:59:59.000Z

42

ENVIRONMENTAL IMPACT OF HEAVY METAL POLLUTION IN NATURAL AQUATIC SYSTEMS  

E-Print Network (OSTI)

He who taught the use of the pen, Taught man that which he knew not" The distribution of heavy metals between soil and soil solutions is a key issue in evaluating the environmental impact of long term applications of heavy metals to land. Contamination of soils by heavy metals has been reported by many workers. Metal adsorption is affected by many factors, including soil pH, clay mineralogy, abundance of oxides and organic matter, soil composition and solution ionic strength. The pH is one of the many factors affecting mobility of heavy metals in soils and it is likely to be the most easily managed and the most significant. To provide the appropriate level of protection for aquatic life and other uses of the resource, it is important to be able to predict the environmental distribution of important metals on spatial and temporal scales and to do so with particular emphasis on the water column concentrations. Regulatory levels reflected in water quality criteria or standards are based on

Muhammad Rehan Tayab

43

Radioactive Waste Radioactive Waste  

E-Print Network (OSTI)

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

44

Natural radioactivity of 226Ra and 228Ra in thermal and mineral waters in Croatia  

Science Journals Connector (OSTI)

......and Occupational Health, Radiation Protection...the elements of the uranium and thorium natural...Croatia, with many health resorts based on...detector (partially depleted PIPS detector: active...other elements of the uranium and thorium natural...ingested U and Ra. Health Phys (1985) 48......

Tomislav Bituh; Gordana Marovic; Branko Petrinec; Jasminka Sencar; Iva Franulovic

2009-01-01T23:59:59.000Z

45

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. 9 figs.

Kochen, R.L.; Navratil, J.D.

1997-01-21T23:59:59.000Z

46

Natural radioactivity measurements and dose calculations to the public: Case of the uranium-bearing region of Poli in Cameroon  

Science Journals Connector (OSTI)

The objective of this work is to carry out a baseline study of the uranium-bearing region of Poli in which lies the uranium deposit of Kitongo, prior to its impending exploitation. This study required sampling soil, water and foodstuffs representative of the radioactivity exposure and food consumption patterns of the population of Poli. After sampling and radioactivity measurements were taken, our results indicated that the activities of natural series in soil and water samples are low. However, high levels of 210Po and 210Pb in foodstuffs (vegetables) were discovered and elevated activities of 40K were observed in some soil samples. All components of the total dose were assessed and lead to an average value of 5.2mSv/year, slightly higher than the average worldwide value of 2.4mSv/year. Most of this dose is attributable to the ingestion dose caused by the high levels of 210Po and 210Pb contained in vegetables, food items which constitute an important part of the diet in Northern Cameroon. Consequently, bringing uranium ore from underground to the surface might lead to an increased dose for the population of Poli through a higher deposition of 222Rn decay products on leafy vegetables.

Sadou; Franois O. Bochud; Sbastien Baechler; Kwato Njock Mose; Ngachin Merlin; Pascal Froidevaux

2011-01-01T23:59:59.000Z

47

Results of the European Commission Marina II Study Part IIeffects of discharges of naturally occurring radioactive material  

Science Journals Connector (OSTI)

Enhanced levels of naturally occurring radioactive materials (NORM) are produced through various industrial operations and may lead to discharges to the marine environment. A recent study, called MARINA II, carried out for the European Commission considered discharges of radionuclides from the NORM industries to north European marine waters and their consequences. There are two main sources that were considered in the study. The use of phosphogypsum during the production of phosphoric acid by the fertiliser industry and the pumping of oil and gas from the continental shelf in the North Sea which produces large quantities of water contaminated with enhanced levels of naturally occurring radionuclides. Discharges of alpha emitting radionuclides from these two industries have contributed significantly to the total input of alpha emitters to north European waters over the period 19812000 (data were not available prior to 1981). Discharges due to the use of phosphogypsum have declined since the early 1990s and are now very low. Discharges from the oil and gas industries stabilised in the second half of the 1990s and are now the major contributor to alpha discharges to the region. As most European countries do not report discharges of radioactivity with the water produced during extraction, there is considerable uncertainty in the discharges used in the study. The impact of the discharges has been estimated both in terms of the effect on non-human biota and the radiological impact for people. In the 1980s the radiation dose rates to marine biota in the region around a phosphate plant on the north-west coast of England were as high due to the discharges from the phosphate plant as those near to the Sellafield reprocessing plant due to its discharges. In recent years the additional dose to marine biota in this region due to the past NORM discharges is of the same order of magnitude as the natural background. The collective dose rate was estimated to determine the radiological impact on people. The peak collective dose rate from the NORM industries occurred in 1984 and was just over 600 manSv y?1. The collective dose rate fell with time as discharges from the phosphate industry reduced and was estimated as under 200 manSv y?1 in 2000.

M. Betti; L. Aldave de las Heras; A. Janssens; E. Henrich; G. Hunter; M. Gerchikov; M. Dutton; A.W. van Weers; S. Nielsen; J. Simmonds; A. Bexon; T. Sazykina

2004-01-01T23:59:59.000Z

48

Towards a more quantitative understanding of the complex interactions between natural organic matter, heavy metals, and goethite.  

E-Print Network (OSTI)

??Dissolved natural organic matter (NOM) and heavy metals are ubiquitous in aqueous and terrestrial systems. Adsorption processes involving mineral surfaces largely control the fate, transport, (more)

Arthurs, Leilani

2008-01-01T23:59:59.000Z

49

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

SciTech Connect

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

Natural radioactivity and radiation exposure at the Minjingu phosphate mine in Tanzania  

Science Journals Connector (OSTI)

In this paper the results of studies on activity and ambient radiation background around the Minjingu phosphate mine in Tanzania are presented. The outdoor dose rate in air and the activity levels of samples from and outside the mine were determined by thermoluminiscent dosimeters and a gamma spectrometer system with a Hyper Pure germanium detector system respectively. The determination of activity was made for the 226 Ra, 228 Ra, 228 Th and 40 K radionuclides. High concentrations of radium-226 were observed in phosphate rock (5760107 Bq kg-1 ), waste rock (425098 Bq kg-1 ), wild leaf vegetation (65011 Bq kg-1 ), edible leaf vegetation (3939 Bq kg-1 ), surface water (4.70.4 mBq l-1 ) and chicken feed (40.1 Bq kg-1 ) relative to selected control sites. These findings suggest a radiation health risk particularly when the samples are ingested, because the internal exposure may give rise to an effective dose exceeding 20 mSv which is the annual limit of intake of natural radionuclides recommended by the ICRP. On the other hand, the radiation dose from ambient air over five years at the phosphate mine ranges from 1375 to 1475 nGy h-1 with an average of 1415 nGy h-1 . The average is about 28 times that of the global average background radiation from terrestrial sources, and about 12 times the allowed average dose limit for public exposure over five consecutive years. Future investigations on the occupancy factor, external dose rate and radon and radon progeny exposure in drinking water, buildings and activity content in the locally grown foodstuffs are proposed, for the realistic quantification of the overall exposure of workers and public at Minjingu, and remedial measures for future radiation safety.

Firmi P Banzi; Leonard D Kifanga; Felician M Bundala

2000-01-01T23:59:59.000Z

51

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

SciTech Connect

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

52

Determination of the natural radioactivity levels in north west of Dukhan, Qatar using high-resolution gamma-ray spectrometry  

Science Journals Connector (OSTI)

This study is aimed at the determination of the activity concentrations of naturally occuring and technologically enhanced levels of radiation in 34 representative soil samples that have been collected from an inshore oil field area which was found to have, in a previous study, the highest observed value of 226Ra concentration among 129 soil samples. The activity concentrations of 238U and 226Ra have been inferred from gamma-ray transitions associated with their decay progenies and measured using a hyper-pure germanium detector. Details of the sample preparation and the gamma-ray spectroscopic analysis techniques are presented, together with the values of the activity concentrations associated with the naturally occuring radionuclide chains for all the samples collected from NW Dukhan. Discrete-line, gamma-ray energy transitions from spectral lines ranging in energy from ?100keV up to 2.6MeV have been associated with characteristic decays of the various decay products within the 235.8U and 232Th radioactive decay chains. These data have been analyzed, under the assumption of secular equilibrium for the U and Th decay chains. Details of the sample preparation and the gamma-ray spectroscopic analysis techniques are presented. The weighted mean value of the activity concentrations of 226Ra in one of the samples was found to be around a factor of 2 higher than the values obtained in the previous study and approximately a factor of 10 higher than the accepted worldwide average value of 35Bq/kg. The weighted mean values of the activity concentrations of 232Th and 40K were also deduced and found to be within the worldwide average values of 30 and 400Bq/kg, respectively. Our previous study reported a value of 201.91.5Stat.13Syst.Bq/kg for 226Ra in one sample and further investigation in the current work determined a measured value for 226Ra of 342.001.9Stat.25Syst.Bq/kg in a sample taken from the same locality. This is significantly higher than all the other investigated soil samples in the current and previous works. Notably, the Th levels in the same sample are within the worldwide average expectations, implying that the increased 226Ra concentration arises from TENORM processes.

Huda Al-Sulaiti; Tabassum Nasir; K.S. Al Mugren; N. Alkhomashi; N. Al-Dahan; M. Al-Dosari; D.A. Bradley; S. Bukhari; M. Matthews; P.H. Regan; T. Santawamaitre; D. Malain; A. Habib

2012-01-01T23:59:59.000Z

53

Natural Convection Heat Transfer in a Rectangular Liquid Metal Pool With Bottom Heating and Top Cooling  

SciTech Connect

An experimental study is performed to investigate the natural convection heat transfer characteristics with subcooled coolant to create engineering database for basic applications in a lead alloy cooled reactor. Tests are performed in the ALTOS (Applied Liquid-metal Thermal Operation Study) apparatus as part of MITHOS (Metal Integrated Thermo Hydrodynamic Operation System). A relationship is determined between the Nusselt number Nu and the Rayleigh number Ra in the liquid metal rectangular pool. Results are compared with correlations and experimental data in the literature. Given the similar Ra condition, the present test results for Nu of the liquid metal pool with top subcooling are found to be similar to those predicted by the existing correlations or experiments. The current test results are utilized to develop natural convection heat transfer correlations applicable to low Prandtl number Pr fluids that are heated from below and cooled by the external coolant above. Results from this study are slated to be used in designing BORIS (Battery Optimized Reactor Integral System), a small lead cooled modular fast reactor for deployment at remote sites cycled with MOBIS (Modular Optimized Brayton Integral System) for electricity generation, tied with NAVIS (Naval Application Vessel Integral System) for ship propulsion, joined with THAIS (Thermochemical Hydrogen Acquisition Integral System) for hydrogen production, and coupled with DORIS (Desalination Optimized Reactor Integral System) for seawater desalination. Tests are performed with Wood's metal (Pb-Bi-Sn-Cd) filling a rectangular pool whose lower surface is heated and upper surface cooled by forced convection of water. The test section is 20 cm long, 11.3 cm high and 15 cm wide. The simulant has a melting temperature of 78 deg. C. The constant temperature and heat flux condition was realized for the bottom heating once the steady state had been met. The test parameters include the heated bottom surface temperature of the liquid metal pool, the input power to the bottom surface of the section, and the coolant temperature. (authors)

Lee, Il S.; Yu, Yong H.; Son, Hyoung M.; Hwang, Jin S.; Suh, Kune Y. [Seoul National University, 599 Gwanangno, Gwanak-gu, Seoul, 151-742 (Korea, Republic of)

2006-07-01T23:59:59.000Z

54

Metrological Determination of Natural Radioactive Isotopes {sup 226}Ra, {sup 228}Ra and {sup 210}Pb by Means of Ge Detector  

SciTech Connect

A metrological method to determine the activity per mass unity (activity concentration) of {sup 226}Ra and {sup 210}Pb ({sup 238}U decay series) and {sup 228}Ra ({sup 232}Th series) by gamma-ray spectrometers based on hyper-pure coaxial germanium detector was developed. In the soil the {sup 22}Ra (half-life = 1600 years) exhibits the same level of radioactivity as {sup 238}U (half-life 4.5x10{sup 9} years) because of a natural phenomenon called secular equilibrium. {sup 226}Ra decays into {sup 222}Rn (half-life = 3.8 days), a radioactive inert gas. After several days, the {sup 222}Rn naturally decays to {sup 218}Po (half-life = 3 minutes), where finally {sup 210}Pb (half-life = 22 years) is produced. The metrological capability of high-resolution gamma-ray spectrometry for naturally occurring radionuclides at environmental levels is showed, with emphasis on the use of 2 mL standard sources volume in a glass ampoule. Source preparation and calibration procedures are described. Radionuclide standards in an activity range of 10 to 250 Bq/g were produced which can be applied in a variety of environmental sample analysis (water, plant material, sediment, etc.). Uncertainties for {sup 226}Ra and {sup 210}Pb around 3% (k = 1) were obtained.

Almeida, Maria Candida M. de; Delgado, Jose U.; Poledna, Roberto; Oliveira, Estela Maria de; Silva, Ronaldo L. da [Laboratorio Nacional de Metrologia das Radiacoes Ionizantes, Instituto de Radioprotecao e Dosimetria, Comissao Nacional de Energia Nuclear(SEMRA/LNMRI/IRD/CNEN) Av. Salvador Allende s/n, Recreio, Rio de Janeiro, CEP 22780-160, RJ (Brazil)

2008-08-07T23:59:59.000Z

55

Measurement of natural radioactivity and dose rate assessment of terrestrial gamma radiation in the soil of southern Punjab, Pakistan  

Science Journals Connector (OSTI)

......terrestrial background radiation mainly due to these...assess the population radiation doses(4-9). However...data are available on naturally occuring and artificial radionulides...order to assess the radiation doses for the general......

I. Fatima; J. H. Zaidi; M. Arif; M. Daud; S. A. Ahmad; S. N. A. Tahir

2008-01-01T23:59:59.000Z

56

Nature and evolution of the fusion boundary in ferritic-austenitic dissimilar weld metals. Part 1 -- Nucleation and growth  

SciTech Connect

A fundamental investigation of fusion boundary microstructure evolution in dissimilar-metal welds (DMWs) between ferritic base metals and a face-centered-cubic (FCC) filler metal was conducted. The objective of the work presented here was to characterize the nature and character of the elevated-temperature fusion boundary to determine the nucleation and growth characteristics of DMWs. Type 409 ferritic stainless steel and 1080 pearlitic steel were utilized as base metal substrates, and Monel (70Ni-30Cu) was used as the filler metal. The Type 409 base metal provided a fully ferritic or body-centered-cubic (BCC) substrate at elevated temperatures and exhibited no on-cooling phase transformations to mask or disguise the original character of the fusion boundary. The 1080 pearlitic steel was selected because it is austenitic at the solidus temperature, providing an austenite substrate at the fusion boundary. The weld microstructure generated with each of the base metals in combination with Monel was fully austenitic. In the Type 409/Monel system, there was no evidence of epitaxial nucleation and growth as normally observed in homogeneous weld metal combinations. The fusion boundary in this system exhibited random grain boundary misorientations between the heat-affected zone (HAZ) and weld metal grains. In the 1080/Monel system, evidence of normal epitaxial growth was observed at the fusion boundary, where solidification and HAZ grain boundaries converged. The fusion boundary morphologies are a result of the crystal structure present along the fusion boundary during the initial stages of solidification. Based on the results of this investigation, a model for heterogeneous nucleation along the fusion boundary is proposed when the base and weld metals exhibit ferritic (BCC) and FCC crystal structures, respectively.

Nelson, T.W.; Lippold, J.C.; Mills, M.J.

1999-10-01T23:59:59.000Z

57

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

58

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

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.

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

60

Researchers at Montana State University and Idaho National Lab have developed a process to effectively and efficiently clean natural and man-made porous material of radioactive contamination. The system eliminates  

E-Print Network (OSTI)

to effectively and efficiently clean natural and man-made porous material of radioactive contamination. The system eliminates the practice of full demolition and removal of contaminated objects and can address contaminated substrate. Thus, building walls (interior or exterior), floors and ceilings can be remediated

Maxwell, Bruce D.

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

Green synthesis of metal/C and metal oxide/C films by using natural membrane as support  

Science Journals Connector (OSTI)

A protocol aiming at making use of the huge amount of naturally existing wastes such as defoliation, pericarp and egg shell for nanostructured composite materials was proposed. In this study, a green synthetic ro...

Cheng-Zhen Wei; Hai-Feng Ma; Feng Gao

2014-06-01T23:59:59.000Z

62

The nature of the metal-insulator transition in silicon germanide quantum wells.  

E-Print Network (OSTI)

??A study of the temperature dependence of the resistivity of gated SiGe quantum well structures has revealed a metal-insulator transition as a function of carrier (more)

Lam, Jennifer Eleanor.

2009-01-01T23:59:59.000Z

63

RADIOACTIVITY 1997 BNL Site Environmental Report 4 -1  

E-Print Network (OSTI)

of a few inches. Naturally occurring radioactive elements such as potassium-40 emit beta radiation. Gamma by materials such as paper and have a range in air of only an inch or so. Naturally occurring radioactive 4.3 Sources of Radiation Radioactivity and radiation are part of the earth's natural environment

64

MARSAME Appendix B B. SOURCES OF BACKGROUND RADIOACTIVITY  

E-Print Network (OSTI)

consideration is given to issues associated with technologically enhanced naturally occurring radioactive reports on Exposure of the Population in the United States and Canada from Natural Background Radiation.1 Terrestrial Radioactivity The naturally occurring forms of radioactive elements incorporated into the Earth

65

Measurement of natural radioactivity and radon exhalation rate in fly ash samples from a thermal power plant and estimation of radiation doses  

Science Journals Connector (OSTI)

Fly ash produced by coal-burning in thermal power station has become a subject of world wide interest in recent years because of its diverse uses in construction activities and considerable economic and environmental importance. Fly ash is used in the production of bricks, sheets, cement and also in land filling etc. Indian coals used in thermal power plants are found to have high ash contents, resulting in the production of large amount of fly ash. Coal contains radionuclides including uranium (the source of inert gas radon), Th and K. Thus coal combustion results in enhanced concentration of natural radionuclides 226Ra, 232Th and 40K. Since these radionuclides concentration in fly ash plays an important role in health physics it is important to measure radionuclides concentration in fly ash. In the present work enhanced radioactivity and radon exhalation rate from fly ash samples collected from a thermal power plant of NTPC (National Thermal Power Corporation), Dadri (U.P.) India, have been measured. A high resolution gamma ray spectroscopic system has been used for the measurement of natural radioactivity (226Ra, 232Th and 40K). Gamma spectrometric measurements were carried out at Inter-University Accelerator Centre, New Delhi using a coaxial n-type \\{HPGe\\} detector (EG&G, ORTEC, Oak Ridge, USA). Activity concentration of 226Ra varies from 81.82.2 to 177.310.0Bqkg?1 with an average value of 118.67.4Bqkg?1 and of 232Th from 111.63.2 to 178.53.9Bqkg?1 with an average value of 147.03.4Bqkg?1. 40K activity was found to be below detection limit in some samples while other samples have shown potassium activity to vary from 365.94.8 to 495.96.2Bqkg?1 with an average value of 352.04.5Bqkg?1. Surface radon exhalation rates (EA) and Mass exhalation rates (EM) in these samples were measured by Sealed can technique using LR-115 type II track detectors. EA is found to vary from 80.19.3 to 242.716.3mBqm?2h?1 with an average value 155.512.8mBqm?2h?1, while EM varies from 3.10.4 to 9.30.6mBqkg?1h?1 with an average value of 6.00.5mBqkg?1h?1. Radium equivalent activity (Raeq), related to the external gamma dose and internal dose due to radon and its daughters range from 283.2 to 422.4Bqkg?1 with an average value of 353.9Bqkg?1. The calculated values of external hazard index (Hex) vary from 0.77 to 1.87 with an average value of 1.03. Most of the samples show the value of Raeq close to the allowed upper limit of 370Bqkg?1 and Hex close to unity respectively except in two samples. Annual effective dose varies from 0.15 to 0.23mSvy?1 with an average value 0.19mSvy?1.

Mamta Gupta; Ajay Kumar Mahur; Rati Varshney; R.G. Sonkawade; K.D. Verma; Rajendra Prasad

2013-01-01T23:59:59.000Z

66

Airborne Observations of Natural Radioactivity  

Science Journals Connector (OSTI)

... al. on cosmic rays; (2) the results of the direct determination of the radon content of free atmosphere at different altitudes made as early as 1928 by Wigand and ... in a series of airplane measurements:

F. B?HOUNEK

1966-03-26T23:59:59.000Z

67

Radionuclides, Heavy Metals, and Polychlorinated Biphenyls in Soils Collected Around the Perimeter of Low-Level Radioactive Waste Disposal Area G during 2006  

SciTech Connect

Twenty-one soil surface samples were collected in March around the perimeter of Area G, the primary disposal facility for low-level radioactive solid waste at Los Alamos National Laboratory (LANL). Three more samples were collected in October around the northwest corner after elevated tritium levels were detected on an AIRNET station located north of pit 38 in May. Also, four soil samples were collected along a transect at various distances (48, 154, 244, and 282 m) from Area G, starting from the northeast corner and extending to the Pueblo de San Ildefonso fence line in a northeasterly direction (this is the main wind direction). Most samples were analyzed for radionuclides ({sup 3}H, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, {sup 234}U, {sup 235}U, and {sup 238}U), inorganic elements (Al, Ba, Be, Ca, Cr, Co, Cu, Fe, Mg, Mn, Ni, K, Na, V, Hg, Zn, Sb, As, Cd, Pb, Se, Ag, and Tl) and polychlorinated biphenyl (PCB) concentrations. As in previous years, the highest levels of {sup 3}H in soils (690 pCi/mL) were detected along the south portion of Area G near the {sup 3}H shafts; whereas, the highest concentrations of {sup 241}Am (1.2 pCi/g dry) and the Pu isotopes (1.9 pCi/g dry for {sup 238}Pu and 5 pCi/g dry for {sup 239,240}Pu) were detected along the northeastern portions near the transuranic waste pads. Concentrations of {sup 3}H in three soil samples and {sup 241}Am and Pu isotopes in one soil sample collected around the northwest corner in October increased over concentrations found in soils collected at the same locations earlier in the year. Almost all of the heavy metals, with the exception of Zn and Sb in one sample each, in soils around the perimeter of Area G were below regional statistical reference levels (mean plus three standard deviations) (RSRLs). Similarly, only one soil sample collected on the west side contained PCB concentrations--67 {micro}g/kg dry of aroclor-1254 and 94 {micro}g/kg dry of aroclor-1260. Radionuclide and inorganic element concentrations in soils collected along a transect from Area G to the Pueblo de San Ildefonso fence line show that most contained concentrations of {sup 241}Am, {sup 238}Pu, and {sup 239,240}Pu above the RSRLs. Overall, all concentrations of radionuclides, heavy metals, and PCBs that were detected above background levels in soils collected around the perimeter of Area G and towards the Pueblo de San Ildefonso boundary were still very low and far below LANL screening levels and regulatory standards.

P. R. Fresquez

2007-02-28T23:59:59.000Z

68

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

SciTech Connect

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

69

Study of integrated metal hydrides heat pump and cascade utilization of liquefied natural gas cold energy recovery system  

Science Journals Connector (OSTI)

The traditional cold energy utilization of the liquefied natural gas system needs a higher temperature heat source to improve exergy efficiency, which barricades the application of the common low quality thermal energy. The adoption of a metal hydride heat pump system powered by low quality energy could provide the necessary high temperature heat and reduce the overall energy consumption. Thus, an LNG cold energy recovery system integrating metal hydride heat pump was proposed, and the exergy analysis method was applied to study the case. The performance of the proposed integration system was evaluated. Moreover, some key factors were also theoretically investigated about their influences on the system performance. According to the results of the analysis, some optimization directions of the integrated system were also pointed out.

Xiangyu Meng; Feifei Bai; Fusheng Yang; Zewei Bao; Zaoxiao Zhang

2010-01-01T23:59:59.000Z

70

(Revised May 25, 2012) Radioactivity  

E-Print Network (OSTI)

(Revised May 25, 2012) Radioactivity GOALS (1) To gain a better understanding of naturally-occurring. (3) To measure the amount of "background radiation" from natural sources. (4) To test whether and man-made radiation sources. (2) To use a Geiger-Mueller tube to detect both beta and gamma radiation

Collins, Gary S.

71

Internal and External Radioactive Backgrounds  

E-Print Network (OSTI)

.6 Table 3.1: Naturally occurring radioactive isotopes [89]. The elemental abundance is the total amount words the signal to noise ratio should be greater than one, S/N > 1. Naturally, the larger S/N is to be distinguished from beta particles or gamma radiation. The big challenge for the Borexino experiment is to deal

72

B-1 2001 SITE ENVIRONMENTAL REPORT APPENDIX B: CONCEPTS OF RADIOACTIVITY  

E-Print Network (OSTI)

such as paper and have a range in air of only an inch or so. Naturally occurring radioactive elements a range in air of several feet. Naturally occurring radioactive elements such as potassium- 40 (K-40) emit: CONCEPTS OF RADIOACTIVITY SOURCES OF RADIATION Radioactivity and radiation are part of the earths natural

Homes, Christopher C.

73

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

74

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.

75

Electronic nature of one-dimensional noble-metal nanowires on the Si(5 5 12) surface  

Science Journals Connector (OSTI)

Ag (Au) adsorption on a highly vicinal Si(5 5 12) surface was reported to form interesting one-dimensional chain structures. The electronic structures of these nanostructures are investigated by angle-resolved photoelectron spectroscopy. Single- and double-row chain structures of Ag formed below and above 0.25 ML, respectively, are found to quench significantly the two characteristic surface states of the clean Si(5 5 12)-21 surface. Only for the Ag single-row chains, is a very weak extra surface state observed at a binding energy of about 0.2 eV without revealing a metallic behavior. This semiconduting nature contrasts with the interpretation of a previous scanning tunneling spectroscopy study. A similar chain structure with double rows of Au exhibits a consistent result with that of the Ag-induced ones.

J. R. Ahn; Y. J. Kim; H. S. Lee; C. C. Hwang; B. S. Kim; H. W. Yeom

2002-10-17T23:59:59.000Z

76

Metal Toxicity  

Science Journals Connector (OSTI)

Problems posed to plants by metal toxicity in the soils of the world are basically of two kinds. The first kind are of natural origin. These arise either as a consequence of the nature of the parent material f...

T. McNeilly

1994-01-01T23:59:59.000Z

77

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

78

Radioactive Fallout in the United States  

Science Journals Connector (OSTI)

...radiopotassium, radium, and other natural sources of radioactivity...Tex. Amarillo, Tex. *Corpus Christi, Tex. *Dallas, Tex...Kr90, which is an inert gas having a half-life of...dispersion of the radioactive gas radon and its daughter...

Merril Eisenbud; John H. Harley

1955-05-13T23:59:59.000Z

79

S9 -Kinetics & Mechanism of Metal Sorption/Release on Natural Materials ADSORPTION MECHANISMS OF PB ON AMORPHOUS SILICA: AN XAS  

E-Print Network (OSTI)

S9 - Kinetics & Mechanism of Metal Sorption/Release on Natural Materials ADSORPTION MECHANISMS the sorption behavior and mechanisms of Pb on amorphous silica using X-ray absorption spectroscopy (XAS t h o d s Pb sorption on silica was studied as a function of pH. The pH range used was pH 3

Sparks, Donald L.

80

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.......

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 Waste Management  

Directives, Delegations, and Requirements

To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

1984-02-06T23:59:59.000Z

82

Radioactive Material Transportation Practices  

Directives, Delegations, and Requirements

Establishes standard transportation practices for Departmental programs to use in planning and executing offsite shipments of radioactive materials including radioactive waste. Does not cancel other directives.

2002-09-23T23:59:59.000Z

83

Estimation of radiation doses associated with natural radioactivity in sand samples of the north western areas of Pakistan using Monte Carlo simulation  

Science Journals Connector (OSTI)

Activity concentrations of naturally occurring radionuclides, i.e., 226Ra, 232Th and 40K, were measured in sand samples of north western areas of Pakistan using gamma-spectrometry. The measured ranges of activity...

Khalid Khan; P. Akhter; S. D. Orfi

2005-08-01T23:59:59.000Z

84

Evidence for viscous flow nature in Zr{sub 60}Al{sub 15}Ni{sub 25} metallic glass subjected to cold rolling  

SciTech Connect

The microstructure changes of Zr{sub 60}Al{sub 15}Ni{sub 25} metallic glass upon cold rolling and their influences on the thermally induced crystallization kinetics are investigated. The results show that atomic redistribution occurs within the localized zones in the glassy matrix, resulting from the softening of the shear modulus, which retards the crystallization behaviors during the subsequent heating. The present work provides direct evidence for the viscous flow nature in a metallic glass subjected to plastic deformation, during which the softened zones act as potential shear transformation zones.

Yan Zhijie [School of Materials Science and Engineering, Taiyuan University of Science and Technology, Taiyuan 030024 (China); IFW Dresden, Institut fuer Komplexe Materialien, Helmholtzstrasse 20, D-01069 Dresden (Germany); Hao Weixin; Hu Yong [School of Materials Science and Engineering, Taiyuan University of Science and Technology, Taiyuan 030024 (China); Song Kaikai; Eckert, Juergen [IFW Dresden, Institut fuer Komplexe Materialien, Helmholtzstrasse 20, D-01069 Dresden (Germany); TU Dresden, Institut fuer Werkstoffwissenschaft, D-01062 Dresden (Germany); Stoica, Mihai; Scudino, Sergio [IFW Dresden, Institut fuer Komplexe Materialien, Helmholtzstrasse 20, D-01069 Dresden (Germany)

2013-07-08T23:59:59.000Z

85

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

86

Conceptual design study on very small long-life gas cooled fast reactor using metallic natural Uranium-Zr as fuel cycle input  

SciTech Connect

A conceptual design study of very small 350 MWth Gas-cooled Fast Reactors with Helium coolant has been performed. In this study Modified CANDLE burn-up scheme was implemented to create small and long life fast reactors with natural Uranium as fuel cycle input. Such system can utilize natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. The core with metallic fuel based was subdivided into 10 regions with the same volume. The fresh Natural Uranium is initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all axial regions. The reactor discharge burn-up is 31.8% HM. From the neutronic point of view, this design is in compliance with good performance.

Monado, Fiber, E-mail: fiber.monado@gmail.com [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung, Indonesia and Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Ariani, Menik [Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Su'ud, Zaki; Waris, Abdul; Basar, Khairul; Permana, Sidik [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung (Indonesia); Aziz, Ferhat [National Nuclear Energy Agency of Indonesia (BATAN) (Indonesia); Sekimoto, Hiroshi [CRINES, Tokyo Institute of Technology, O-okoyama, Meguro-ku, Tokyo 152-8550 (Japan)

2014-02-12T23:59:59.000Z

87

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!

88

Midwestern Radioactive Materials Transportation Committee Agenda...  

Office of Environmental Management (EM)

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

89

A preliminary report on the determination of natural radioactivity levels of the State of Qatar using high-resolution gamma-ray spectrometry  

Science Journals Connector (OSTI)

This study is aimed at the determination of the activity concentrations of naturally occuring and technically enhanced levels of radiation in soil samples collected across the landscape of Qatar. Representative soil samples from various locations across the Qatarian peninsula have been collected and analyzed in order to establish activity concentrations associated with the 235,8U and 232Th natural decay chains and also the long-lived naturally occurring radionuclide 40K. The activity concentrations have been measured using a hyper-pure germanium detector. Details of the sample preparation and the gamma-ray spectroscopic analysis techniques are presented, together with the preliminary values of the activity concentrations associated with the naturally occuring radionuclide chains for six soil samples collected from the Qatarian peninsula. Sample 228, which has been collected from an inshore oil-field area, was observed to have the highest observed value of 226Ra concentration among the six samples. The weighted mean values of the activity concentrations of the radionuclides 238U, 232Th and 40K in one particular sample (sample 228) were, respectively, found to be 213.91.4, 4.550.11 and 111.43.6Bq/kg, which compare with the worldwide weighted mean values in soil samples, 33, 45 and 420Bq/kg, respectively. The deduced activity concentration of 238U in sample 228 in the current work was found to be significantly higher than the worldwide average value and was also significantly higher than the values determined for the five other initial samples discussed here. The mean values of the activity concentration of the 232Th series, 40K and 137Cs in Bq/kg from the six investigated soil samples were found to be 9.41.3, 20422 and 5.85.6, respectively, with the quoted uncertainty referring to the standard deviation among these measurements.

H. Al-Sulaiti; P.H. Regan; D.A. Bradley; D. Malain; T. Santawamaitre; A. Habib; M. Matthews; S. Bukhari; M. Al-Dosari

2010-01-01T23:59:59.000Z

90

GammaSense: Infrastructureless Positioning Using Background Radioactivity  

Science Journals Connector (OSTI)

We introduce the harvesting of natural background radioactivity for positioning. Using a standard Geiger-Mller counter as sensor, we fingerprint the natural levels of gamma radiation with the aim of then roughly pinpointing the position of a client ...

Doina Bucur; Mikkel Baun Kjrgaard

2008-10-01T23:59:59.000Z

91

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

Paris-Sud XI, Université de

92

RADIOACTIVE ELEMENT REMOVAL FROM WATER USING GRAPHENE OXIDE (GO)  

E-Print Network (OSTI)

and may release significant amounts of radioactive material into the environment resulting in the potential for widespread exposure. These industries include mining, phosphate processing, metal ore processing, heavy mineral sand processing, titanium...

Concklin, Joshua Paul

2013-12-19T23:59:59.000Z

93

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...

94

VOLUME 85, NUMBER 9 P H Y S I C A L R E V I E W L E T T E R S 28 AUGUST 2000 Nature, Strength, and Consequences of Indirect Adsorbate Interactions on Metals  

E-Print Network (OSTI)

, and Consequences of Indirect Adsorbate Interactions on Metals A. Bogicevic,1, * S. Ovesson,2 P. Hyldgaard,2 B. I adsorbed on metals affect each other indirectly even over considerable distances. Via systematic density-functional calculations, we establish the nature and strength of such interactions, and explain for what adsorbate systems

Brune, Harald

95

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

96

Distribution of Radioactive Materials in the Absheron Peninsula, Azerbaijan - 13567  

SciTech Connect

The Absheron Peninsula forms the extreme Eastern part of Azerbaijan and juts into the Caspian Sea. The region has a long history of oil and gas exploration, transport, and processing and includes a number of abandoned chemical plants that were used in the separation of iodine from formation waters. As a result of lax environmental standards during the Soviet era, the industrial activity has led to serious contamination from oils residues, heavy metals and naturally occurring radioactive materials (NORM). Radiometric surveys performed over a wide range of the Absheron Peninsula showed generally low NORM concentrations. However, radiation levels two to three orders of magnitude above background levels were detected at two abandoned iodine separation plants near the capital city, Baku. These elevated radiation levels are mainly due to Ra-226 and U-238 with lower contributions from Ra-228 and U-235. (authors)

Vandergraaf, Tjalle T. [Consultant, Pinawa, MB, R0E 1L0 (Canada)] [Consultant, Pinawa, MB, R0E 1L0 (Canada); Mamedov, Gudrat G.; Ramazanov, Mahammadali A.; Badalov, Vatan H. [Baku State University, Baku (Azerbaijan)] [Baku State University, Baku (Azerbaijan); Naghiyev, Jalal A. [Institute of Radiation Problems of ANAS, Baku (Azerbaijan)] [Institute of Radiation Problems of ANAS, Baku (Azerbaijan); Mehdiyeva, Afat A. [National Aerospace Agency of Ministry of Defense Industry, Baku (Azerbaijan)] [National Aerospace Agency of Ministry of Defense Industry, Baku (Azerbaijan)

2013-07-01T23:59:59.000Z

97

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

SciTech Connect

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

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 frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

99

Natural radionuclides in the rocks of the Valle del Cervo Pluton in Piedmont  

Science Journals Connector (OSTI)

......experimental tool in studying natural radioactivity and determining...accurately determine the natural radioactivity in quarries...exhalation rate of radon gas has been determined to...G. and Vecchi, R. Natural Radioactivity and Radon...radioactive samples from Cyprus characteristic geological......

Lucia Sesana; Marco Fumagalli; Mauro Carnevale; Giancarla Polla; Ugo Facchini; Annita Colombo; Annalisa Tunesi; Luisa De Capitani; Rosella Rusconi

2006-06-01T23:59:59.000Z

100

todayELSEVIER CatalysisToday21 (1994) 141-156 Nature of metal catalyst precursors adsorbed onto  

E-Print Network (OSTI)

adsorbed onto oxide supports N. Santhanam, T.A. Conforti, W. Spieker, J.R. Regalbuto* Dept. of Chemical of experimentswere conductedto investigatethe nature of adsorbed catalyst precursor complexes during and after drying. In the first, PdC12- was adsorbed onto a positively charged A1203 surface and (NHa)aPd2+ onto negatively

Regalbuto, John R.

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

Radioactivity in Products Derived from Gypsum in Tanzania  

Science Journals Connector (OSTI)

......Dosimetry Article Radioactivity in Products Derived from Gypsum in Tanzania P. Msaki F.P. Banzi Scientific investigations have long...products suspected to have natural radioactivity radiation risk in Tanzania. In response to the concern expressed by the users of chalk......

P. Msaki; F.P. Banzi

2000-10-01T23:59:59.000Z

102

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).

103

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

104

CHAPTER 4: CONCEPTS OF RADIOACTIVITY 1998 SITE ENVIRONMENTAL REPORT4-1  

E-Print Network (OSTI)

a range in air of only an inch or so. Naturally occurring radioactive elements such as radon emit alpha by materials such as aluminum foil. They have a range in air of a few inches. Naturally occurring radioactive-rays are essen- tially a form of gamma radiation. Figure 4-1. Typical Annual Radiation Doses from Natural and Man

105

Radioactive residues associated with water treatment, use and disposal in Australia.  

E-Print Network (OSTI)

??Water resources are known to contain radioactive materials, either from natural or anthropogenic sources. Treatment, including wastewater treatment, of water for drinking, domestic, agricultural and (more)

Kleinschmidt, Ross Ivan

2011-01-01T23:59:59.000Z

106

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

1999-07-09T23:59:59.000Z

107

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

108

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.

109

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

1999-07-09T23:59:59.000Z

110

International Recycling of LLW Metals  

SciTech Connect

Melting of radioactive scrap metal has been successfully practiced for more than 15 years, with approximately 60,000 tons of steel being processed into beneficial reuse applications. This process has converted radioactive scrap metal at a licensed facility into useful products such as shield blocks, security barriers and shield containers. These products are used within the nuclear industry, such as nuclear power plants, waste disposal facilities and high-energy physics research facilities. Recycling provides the following benefits by comparison with direct disposal: - Preserving metal resources. - Conserving valuable Low Level Waste (LLW) disposal site resources, thereby extending disposal site life. - Reducing the cost of metal products to end users by using materials less expensive than virgin metals. This paper outlines international metal recycling practices implemented at EnergySolutions' Bear Creek Facility in Oak Ridge, Tennessee. (authors)

Eshleman, T.; Jansen, J. [EnergySolutions (United States); Shinya, Sawada [KEK - High Energy Accelerator Research Organization (Japan)

2008-07-01T23:59:59.000Z

111

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

112

Geochemical aspects of radioactive waste disposal  

SciTech Connect

The book addresses various topics related to the geochemistry of waste disposal: natural radioactivity, kinds of radioactive waste, details of possible disposal sites, low-level waste, uranium mill tailing, natural analogs, waste forms, and engineered barriers. Emphasis throughout is on the importance of natural analogs, the behavior of elements resembling those to be put in a waste repository as they occur in natural situations where the temperature, pressure, and movement of ground water are similar to those expected near a repository. The author is convinced that conclusions drawn from the study of analog elements are directly applicable to predictions about radionuclide behavior, and that the observed near-immobility of most of these elements in comparable geologic environments is good evidence that radioactive waste can be disposed of underground with negligible effects on the biosphere. Much of his own research has been in this area, and the best parts of the book are the descriptions of his work on trace elements in the salt minerals at the Waste Isolation Pilot Plant in southeastern New Mexico, on the movement of radionuclides and their daughter elements from the famous Precambrian reactor at Oklahoma in Gabon, and on the distribution of analog elements in rocks near the contacts of igneous intrusions.

Brookins, D.G.

1984-01-01T23:59:59.000Z

113

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

114

C-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX C: CONCEPTS OF RADIOACTIVITY  

E-Print Network (OSTI)

occurring radioactive elements such as radon emit alpha radiation. BETA Beta radiation is composed and Lucite panels. They have a range in air of several feet. Naturally occur- ring radioactive elements and radiation are part of the earth's natural environment. Human beings are exposed to radiation from a variety

115

B-1 2002 SITE ENVIRONMENTAL REPORT APPENDIX B: CONCEPTS OF RADIOACTIVITY  

E-Print Network (OSTI)

such as aluminum foil and Lucite panels. They have a range in air of several feet. Naturally occurring radioactive OF RADIATION Radioactivity and radiation are part of the earths natural environment. Human beings are exposed in the environment, and how they contribute to an individuals radiation dose are provided. Some gen- eral statistical

Homes, Christopher C.

116

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, cancels DOE M 435.1-1 Chg 1.

1999-07-09T23:59:59.000Z

117

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

118

Sealed Radioactive Source Accountability  

Directives, Delegations, and Requirements

This Notice extends DOE N 5400.9, Sealed Radioactive Source Accountability, of 12-24-91, until 12-24-95, unless sooner superseded or rescinded. The contents of DOE N 5400.9 will be updated and incorporated in the revised DOE O 5480.11, Radiation Protection for Occupational Workers.

1994-12-22T23:59:59.000Z

119

Sealed Radioactive Source Accountability  

Directives, Delegations, and Requirements

To establish Department of Energy (DOE) interim policy and to provide guidance for sealed radioactive source accountability. The directive does not cancel any directives. Extended by DOE N 5400.10 to 12-24-93 & Extended by DOE N 5400.12 to 12-24-94.

1991-12-24T23:59:59.000Z

120

Vacuuming radioactive sludge  

SciTech Connect

Vacuuming an estimated 55 cubic yards of radioactive sludge from the floor of Hanford's K East Basin was a complicated process. Workers stood on grates suspended above the 20-foot deep basin and manipulated vacuuming equipment at the end of long poles--using underwater cameras to guide their work.

2006-10-16T23:59:59.000Z

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

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 health and safety and the environment. Cancels DOE O 5820.2A

1999-07-09T23:59:59.000Z

122

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)

123

Radioactive ion detector  

DOE Patents (OSTI)

Apparatus for detecting the presence, in aqueous media, of substances which emit alpha and/or beta radiation and determining the oxidation state of these radioactive substances, that is, whether they are in cationic or anionic form. In one embodiment, a sensor assembly has two elements, one comprised of an ion-exchange material which binds cations and the other comprised of an ion-exchange material which binds anions. Each ion-exchange element is further comprised of a scintillation plastic and a photocurrent generator. When a radioactive substance to which the sensor is exposed binds to either element and emits alpha or beta particles, photons produced in the scintillation plastic illuminate the photocurrent generator of that element. Sensing apparatus senses generator output and thereby indicates whether cationic species or anionic species or both are present and also provides an indication of species quantity. 2 figs.

Bower, K.E.; Weeks, D.R.

1997-08-12T23:59:59.000Z

124

Radioactive ion detector  

DOE Patents (OSTI)

Apparatus for detecting the presence, in aqueous media, of substances which emit alpha and/or beta radiation and determining the oxidation state of these radioactive substances, that is, whether they are in cationic or anionic form. In one embodiment, a sensor assembly has two elements, one comprised of an ion-exchange material which binds cations and the other comprised of an ion-exchange material which binds anions. Each ion-exchange element is further comprised of a scintillation plastic and a photocurrent generator. When a radioactive substance to which the sensor is exposed binds to either element and emits alpha or beta particles, photons produced in the scintillation plastic illuminate the photocurrent generator of that element. Sensing apparatus senses generator output and thereby indicates whether cationic species or anionic species or both are present and also provides an indication of species quantity.

Bower, Kenneth E. (Los Alamos, NM); Weeks, Donald R. (Saratoga, CA)

1997-01-01T23:59:59.000Z

125

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the disposal of radioactive wastes that arise from a great variety of sources, including the nuclear fuel cycle, beneficial uses of isotopes, and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. The spent fuel is accumulating, awaiting the development of a high-level waste repository. It is anticipated that a multi-barrier system involving packaging and geologic media will provide protection of the public over the centuries. The favored method of disposal is in a mined cavity deep underground. In some countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is done by casks and containers designed to withstand severe accidents. Low-level wastes come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2001-01-01T23:59:59.000Z

126

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

127

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

128

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

129

RADIOACTIVE MATERIALS SENSORS  

SciTech Connect

Providing technical means to detect, prevent, and reverse the threat of potential illicit use of radiological or nuclear materials is among the greatest challenges facing contemporary science and technology. In this short article, we provide brief description and overview of the state-of-the-art in sensor development for the detection of radioactive materials, as well as an identification of the technical needs and challenges faced by the detection community. We begin with a discussion of gamma-ray and neutron detectors and spectrometers, followed by a description of imaging sensors, active interrogation, and materials development, before closing with a brief discussion of the unique challenges posed in fielding sensor systems.

Mayo, Robert M.; Stephens, Daniel L.

2009-09-15T23:59:59.000Z

130

Radioactivity levels in some sediment samples from Red Sea and Baltic Sea  

Science Journals Connector (OSTI)

......Natural radioactivity in sand used in thermal therapy at the Red Sea coast. Environ...and surface sediments of the Red Sea, Sudan. Environ. Radioact. (2008) 99:1825-1828...in the Red Sea coastal Environment of Sudan. Marine Pollut. Bull. (1998b) 36......

K. Salahel Din; P. Vesterbacka

2012-01-01T23:59:59.000Z

131

Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &  

E-Print Network (OSTI)

quarterly · Radioactive waste retrieval, storage, disposal · Dosimetry exchange · Leak tests of sealedRadiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material, Chemistry, Physics, Applied Physiology · Radioactive Material ­ Sealed Sources, Unsealed Sources (liquid

Sherrill, David

132

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 RADIOACTIVE WASTE DISPOSAL  

E-Print Network (OSTI)

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 CHAPTER 7 RADIOACTIVE WASTE DISPOSAL PAGE I. Radioactive Waste Disposal ............................................................................................ 7-2 II. Radiation Control Technique #2 Instructions for Preparation of Radioactive Waste

Slatton, Clint

133

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.)

134

Natural radiation environment III. [Lead Abstract  

SciTech Connect

Separate abstracts were prepared for the 52 research papers presented at this symposium in April 1978. The major topics in this volume deal with penetrating radiation measurements, radiation surveys and population exposure, radioactivity in the indoor environment, and technologically enhanced natural radioactivity. (KRM)

Gesell, T.F.; Lowder, W.M. (eds.)

1980-01-01T23:59:59.000Z

135

Radioactive Material Transportation Practices Manual  

Directives, Delegations, and Requirements

This Manual establishes standard transportation practices for the Department of Energy, including National Nuclear Security Administration to use in planning and executing offsite shipments of radioactive materials and waste. The revision reflects ongoing collaboration of DOE and outside organizations on the transportation of radioactive material and waste. Cancels DOE M 460.2-1.

2008-06-04T23:59:59.000Z

136

Adhesion, stability, and bonding at metal/metal-carbide interfaces: Al/WC Donald J. Siegel  

E-Print Network (OSTI)

of adhesion between metals and transition metal carbides/nitrides based on Density Functional Theory(DFT)[14Adhesion, stability, and bonding at metal/metal-carbide interfaces: Al/WC Donald J. Siegel the nature of metal/carbide bonding. Based on the surface and interfacial free energies, we find that both

Adams, James B

137

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

138

Stabilization of Electrocatalytic Metal Nanoparticles at Metal...  

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

Electrocatalytic Metal Nanoparticles at Metal-Metal Oxide-Graphene Triple Junction Points. Stabilization of Electrocatalytic Metal Nanoparticles at Metal-Metal Oxide-Graphene...

139

E-Print Network 3.0 - alpha radioactivity measurement Sample...  

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

SITE ENVIRONMENTAL REPORT4-1 Summary: a range in air of only an inch or so. Naturally occurring radioactive elements such as radon emit alpha... . This is a measure of the rate at...

140

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste 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, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

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.


141

Civilian Radioactive Waste Management System Requirements Document...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management System Requirements Document Civilian Radioactive Waste Management System Requirements Document This document specifies the top-level...

142

Radioactive Waste Management Complex Wide Review | Department...  

Office of Environmental Management (EM)

Radioactive Waste Management Complex Wide Review Radioactive Waste Management Complex Wide Review The main goal of this complex-wide review was to obtain feedback from DOE sites...

143

5 - Fukushima Radioactivity Impact  

Science Journals Connector (OSTI)

Abstract Huge amounts of radioactivity have been released to the environment because of the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident. In order to implement adequate protective actions and to assess the impact of the Fukushima radioactivity on the environment, an environmental monitoring has been conducted by national and local governments, research institutes and universities in Japan and over the world. The environmental monitoring revealed that heavy radioactivity-contaminated areas appeared within about 50 km of the Fukushima Dai-ichi NPP, controlled by land topography as do meteorological factors. The Fukushima-derived radionuclides, in which dominant nuclides were 131I, 134Cs and 137Cs, contaminated food stuffs. The radionuclide levels exceeded the regulation values in a part of food stuffs produced within about 500 km off Fukushima. Based on the comprehensive monitoring data, we describe here levels of the Fukushima-derived radionuclides in terrestrial and marine environments and in food products in Japan and over the globe. Temporal and spatial distributions of Fukushima-derived radionuclides in aerosols revealed the presence of two dominant radionuclide maxima which were observed throughout the Europe with decreasing amplitudes from the North to the South, which were associated with different air masses present in the European air. Modeled forward and backward trajectories indicated a preferential transport of air masses between Fukushima and Europe at 500 hPa (5000 m a. s. l.) air heights. The Lagrangian dispersion modeling showed that the horizontal dispersion in the Europe reached about 4000-km-wide belt, however, the entire world has been labeled with the Fukushima radionuclides, although at very low levels. A typical travel time between Fukushima and Europe has been estimated to be of 1015 days, with an average speed of the plume of 5070 km/h. An average 131I concentration, which was measured over the Europe (?1 mBq/m3), would result in the total amount of dispersed 131I of about 1 PBq. Although this represents a high release rate (almost 1% of the total amount of 131I released from the Fukushima NPP), as it was distributed over a huge area, it has not been of any radiological significance for European citizens. 134Cs and 137Cs were released to the North Pacific Ocean by two major likely pathways, direct discharge from the Fukushima Dai-ichi NPP site and atmospheric deposition off Honshu Islands of Japan, east and northeast of the site. High-density observations of 134Cs and 137Cs in the surface water were carried out by 17 cruises of cargo ships and several research-vessel cruises since March 2011 till March 2012. Main body of radioactive surface plume whose activity exceeded 10 Bq/m3 had been traveling along 40 N, and reached International Date Line on March 2012, 1 year after the accident. A zonal speed of the radioactive plume was estimated to be about 8 cm/s which was consistent with the zonal speed derived by Argo floats and satellite observations at the region. The dispersion of Fukushima-derived 137Cs in surface seawater of the North Pacific Ocean was carried out using an ocean global circulation model. The traveling time from the Fukushima coast to the US west coast was estimated to be 45 years, and the predicted 137Cs levels will reach ?3 Bq/m3, which are by about a factor of three higher than the present global fallout background levels. After 10 years, the 137Cs in the North Pacific Ocean will not be distinguishable over the global fallout background of 1 Bq/m3. The maximum predicted 137Cs activity concentrations in 2012 in the open western North Pacific Ocean will be around 20 Bq/m3, which will be comparable to that observed during the early 1960s after atmospheric nuclear weapons tests. However, after 10 years this concentration will be similar to that from global fallout. The open Pacific Ocean radionuclide concentrations will not pose therefore any radiation risk to the world population from consumption of seafood collected in this region.

Pavel P. Povinec; Katsumi Hirose; Michio Aoyama

2013-01-01T23:59:59.000Z

144

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.

145

Radioactive Kr Isotopes  

Science Journals Connector (OSTI)

A radioactive isotope of 1.1-hour half-life has been produced in krypton by alpha-particle bombardment of Se74, enriched electromagnetically from 0.9 percent to 14.1 percent. Assignment of the isotope is made to Kr77. Aluminum absorption measurements indicate a positron end point of 1.7 Mev. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se74(?,n) reaction is computed as 2.6. The krypton 1.42-day isotope has been produced by an ?,n reaction on electromagnetically enriched Se76. The isotope is located as Kr79 and its half-life confirmed. A positron end point of 1.0 Mev is determined by aluminum absorption measurements. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se76(?,n) reaction is computed to be 50. The cross-section ratio for formation of Kr77 compared to Kr79 by alpha-particle bombardment of selenium is computed as 1.4. The 4.6-hour Kr85 isotope has been produced by a Se(?,n) reaction.

L. L. Woodward; D. A. Mccown; M. L. Pool

1948-10-01T23:59:59.000Z

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

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

148

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)

149

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

150

Storage depot for radioactive material  

DOE Patents (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

151

Evidence for the Existence of a Late-Metal Terminal Sulfido Complex  

E-Print Network (OSTI)

and are active promoters in current hydrotreating catalysts.2 Under- standing the nature of the metal

Jones, William D.

152

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect

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

153

Experiences in the field of radioactive materials seizures in the Czech Republic  

SciTech Connect

In recent years, the amount of radioactive materials seizures (captured radioactive materials) has been rising. It was above all due to newly installed detection facilities that were able to check metallic scrap during its collection in scrap yards or on the entrance to iron-mills, checking municipal waste upon entrance to municipal disposal sites, even incineration plants, or through checking vehicles going through the borders of the Czech Republic. Most cases bore a relationship to secondary raw materials or they were connected to the application of machines and installations made from contaminated metallic materials. However, in accordance to our experience, the number of cases of seizures of materials and devices containing radioactive sources used in the public domain was lower, but not negligible, in the municipal storage yards or incineration plants. Atomic Act No. 18/1997 Coll. will apply to everybody who provides activities leading to exposure, mandatory assurance as high radiation safety as risk of the endangering of life, personal health and environment is as low as reasonably achievable in according to social and economic aspects. Hence, attention on the examination of all cases of the radioactive material seizure based on detection facilities alarm or reasonably grounds suspicion arising from the other information is important. Therefore, a service carried out by group of workers who ensure assessment of captured radioactive materials and eventual retrieval of radioactive sources from the municipal waste has come into existence in the Nuclear Research Institute Rez plc. This service has covered also transport, storage, processing and disposal of found radioactive sources. This service has arisen especially for municipal disposal sites, but later on even other companies took advantage of this service like incineration plants, the State Office for Nuclear Safety, etc. Our experience in the field of ensuring assessment of captured radioactive materials and eventual retrieval of radioactive sources will be presented in the paper. (authors)

Svoboda, Karel; Podlaha, Josef; Sir, David; Mudra, Josef [Nuclear Research Institute Rez plc (Czech Republic)

2007-07-01T23:59:59.000Z

154

Reduction Chemistry of Rare-Earth Metal Complexes: Toward New Reactivity and Properties  

E-Print Network (OSTI)

reactor and was named promethium. Even Nature could onlyrare-earths (except for promethium and europium; ytterbiumeuropium and radioactive promethium) on hand, we synthesized

Huang, Wenliang

2013-01-01T23:59:59.000Z

155

Radioactive Material Use at the EMSL Radiochemistry Annex  

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

The radioactive material must then be placed in inner packages that will prevent radioactive contamination during transportation. Dispersible radioactive material must be...

156

DOE Comments on Radioactive Waste | Department of Energy  

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

on Radioactive Waste DOE Comments on Radioactive Waste 1. Summary Comments on Draft Branch Technical Position on a Performance Assessment Methodology for Low-Level Radioactive...

157

Northeast High-Level Radioactive Waste Transportation Task Force...  

Office of Environmental Management (EM)

Northeast High-Level Radioactive Waste Transportation Task Force Agenda Northeast High-Level Radioactive Waste Transportation Task Force Agenda Northeast High-Level Radioactive...

158

Natural removal of added N-nutrients, reactive phosphorus, crude oil, and heavy metals from the water phase in a simulated water/sediment system  

SciTech Connect

Water/sediment simulation systems were constructed by using an aquarium (0.45 x 0.29 x 0.35 m{sup 3}), filled with suitable amounts of water and sediment collected from three selected locations: Lan Hau Shan (LHS), Tai Hu (TH), and Loong Yu Tao (LYT) of the Zhujiang (Pearl River) Estuary of China in November 1992 at low-tide period. The salinities of the water samples collected form LHS, TH, LYT were found to be 0.2, 4.6, 16.2 g L{sup -1}, respectively. Known amounts of ammonium, nitrate, nitrite, reactive phosphorous, crude oil, arsenate(III), cadmium (II), copper(II), and zinc(II) were added as pollutants into each of the water/sediment simulation systems. The rates of the natural removal of each added pollutant in all water/sediment simulation systems were studied by monitoring their concentrations at various intrevals in the investigation period. Except for Cr(III) and reactive phosphorous in the water/sediment systems of the LHS, TH, and LYT sites, and nitrate in the TH and LYT sites, the concentrations of the added pollutants in the water phase of the studied systems under a flow-condition simulation were reduced to 8% or less of the corresponding added amount on or before the 12th day by natural processes. The rate of self-purification and the estimated assimulative capacity of each added pollutant in all water/sediment simulation systems is discussed. 30 refs., 11 figs., 4 tabs.

Lam-Leung, S.Y.; Cheung, M.T. [Hong Kong Baptist Univ., Kowloon (Hong Kong)] [Hong Kong Baptist Univ., Kowloon (Hong Kong); He, Y.Q. [South China Sea Institute of Oceanology, Guangzhou (China)] [and others] [South China Sea Institute of Oceanology, Guangzhou (China); and others

1996-08-01T23:59:59.000Z

159

Layered metal sulfides: Exceptionally selective agents for radioactive strontium removal  

Science Journals Connector (OSTI)

...07 mmol, 40 mg) in water (20 ml), an excess...washed several times with water, acetone, and...Complex Environmental Remediation Problems , ed Blacklick...removal from contaminated ground water and wastewater...

Manolis J. Manos; Nan Ding; Mercouri G. Kanatzidis

2008-01-01T23:59:59.000Z

160

Four methods for determining the composition of trace radioactive surface contamination of low-radioactivity metal  

E-Print Network (OSTI)

Four methods for determining the composition of low-level uranium- and thorium-chain surface contamination are presented. One method is the observation of Cherenkov light production in water. In two additional methods a position-sensitive proportional counter surrounding the surface is used to make both a measurement of the energy spectrum of alpha particle emissions and also coincidence measurements to derive the thorium-chain content based on the presence of short-lived isotopes in that decay chain. The fourth method is a radiochemical technique in which the surface is eluted with a weak acid, the eluate is concentrated, added to liquid scintillator and assayed by recording beta-alpha coincidences. These methods were used to characterize two `hotspots' on the outer surface of one of the He-3 proportional counters in the Neutral Current Detection array of the Sudbury Neutrino Observatory experiment. The methods have similar sensitivities, of order tens of ng, to both thorium- and uranium-chain contamination.

O'Keeffe, H M; Cleveland, B T; Doucas, G; Gagnon, N; Jelley, N A; Kraus, C; Lawson, I T; Majerus, S; McGee, S R; Myers, A W; Poon, A W P; Rielage, K; Robertson, R G H; Rosten, R C; Stonehill, L C; VanDevender, B A; Van Wechel, T D

2011-01-01T23:59:59.000Z

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.


161

Four methods for determining the composition of trace radioactive surface contamination of low-radioactivity metal  

E-Print Network (OSTI)

Four methods for determining the composition of low-level uranium- and thorium-chain surface contamination are presented. One method is the observation of Cherenkov light production in water. In two additional methods a position-sensitive proportional counter surrounding the surface is used to make both a measurement of the energy spectrum of alpha particle emissions and also coincidence measurements to derive the thorium-chain content based on the presence of short-lived isotopes in that decay chain. The fourth method is a radiochemical technique in which the surface is eluted with a weak acid, the eluate is concentrated, added to liquid scintillator and assayed by recording beta-alpha coincidences. These methods were used to characterize two `hotspots' on the outer surface of one of the He-3 proportional counters in the Neutral Current Detection array of the Sudbury Neutrino Observatory experiment. The methods have similar sensitivities, of order tens of ng, to both thorium- and uranium-chain contamination.

H. M. O'Keeffe; T. H. Burritt; B. T. Cleveland; G. Doucas; N. Gagnon; N. A. Jelley; C. Kraus; I. T. Lawson; S. Majerus; S. R. McGee; A. W. Myers; A. W. P. Poon; K. Rielage; R. G. H. Robertson; R. C. Rosten; L. C. Stonehill; B. A. VanDevender; T. D. Van Wechel

2011-03-29T23:59:59.000Z

162

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

163

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

164

Reporting of Radioactive Sealed Sources  

Directives, Delegations, and Requirements

To establish U.S. Department of Energy requirements for inventory reporting, transaction reporting, verification of reporting, and assign responsibilities for reporting of radioactive sealed sources. DOE N 251.86 extends this notice until 5-6-11. No cancellations. Canceled by DOE O 231.1B

2008-02-27T23:59:59.000Z

165

Chapter 22 - Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses safe disposal of radioactive waste in order to provide safety to workers and the public. Radioactive wastes arise from a great variety of sources, including the nuclear fuel cycle, and from beneficial uses of isotopes and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. In the United States spent fuel is accumulating, awaiting the development of a high-level waste repository. A multi-barrier system involving packaging and geological media will provide protection of the public over the centuries the waste must be isolated. The favored method of disposal is in a mined cavity deep underground. In other countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is by casks and containers designed to withstand severe accidents. Low-level wastes (LLWs) come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Establishment of regional disposal sites by interstate compacts has generally been unsuccessful in the United States. Decontamination of defense sites will be long and costly. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2009-01-01T23:59:59.000Z

166

Radioactive waste at Ward Valley  

Science Journals Connector (OSTI)

...Data Base for 1992: U.S. Spent Fuel and Radioactive Waste Inventories, Projections and Characteristics, publi. DOE/RW-0006, Rev. 8 (U.S. Department of Energy, Washington, DC, 1989), p. 113. 2. T. Taylor, quoted by S. Salesky...

Earl Budin

1995-09-22T23:59:59.000Z

167

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

168

Fusion Reactions Involving Radioactive Beams at GANIL  

Science Journals Connector (OSTI)

......February 2004 research-article Articles Fusion Reactions Involving Radioactive Beams...been used to produce exotic nuclei via fusion evaporation or to study reaction mechanisms...Physics Supplement No. 154, 2004 113 Fusion Reactions Involving Radioactive Beams......

Gilles de France

2004-02-01T23:59:59.000Z

169

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

170

Regulation of naturally occurring radioactive materials in Australia  

Science Journals Connector (OSTI)

......implement those standards. In order to...competency standards, Codes of Practice, Standards and guidance...associated with uranium (and thorium...provision for plans to manage occupational...commissioned a review of operations......

Cameron Jeffries; Riaz Akber; Andrew Johnston; Brad Cassels

2011-07-01T23:59:59.000Z

171

Regulation of naturally occurring radioactive materials in Australia  

Science Journals Connector (OSTI)

......provide an overview of the regulatory approach to managing...been variation in the regulatory approach to implement...makes provision for plans to manage occupational...ARPANSA commissioned a review of operations involving...process to identify when regulatory control is appropriate......

Cameron Jeffries; Riaz Akber; Andrew Johnston; Brad Cassels

2011-07-01T23:59:59.000Z

172

A Study on Natural Radioactivity in Khewra Salt Mines, Pakistan  

Science Journals Connector (OSTI)

......The excess lifetime cancer risk (ELCR) was calculated...salt mines (Excluding Uranium) of some other countries...and Excess Life Time Cancer Risk (%) in the Khewra...than the other non-uranium mines.5) The average...and Excess Life Time Cancer Risk (100%) are calculated......

Muzahir Ali Baloch; Aziz Ahmed Qureshi; Abdul Waheed; Muhammad Ali; Nawab Ali; Muhammad Tufail; Saima Batool; Muhammad Akram; Poonam Iftikhar; Hamza Qayyum; Shahid Manzoor; Hameed Ahmed Khan

2012-05-01T23:59:59.000Z

173

Natural radioactivity of Zambian coal and coal ash  

Science Journals Connector (OSTI)

226Ra and232Th specific activities in coal from Maamba Collieries in Zambia have been...?1..., respectively. These values are nearly two and a half times larger than the world average for coal an...

P. Hayumbu; M. B. Zaman; S. S. Munsanje

1995-11-01T23:59:59.000Z

174

Regulation of naturally occurring radioactive materials in Australia  

Science Journals Connector (OSTI)

......implement those standards. In order to...competency standards, Codes of Practice, Standards and guidance...protection in mining and mineral processing...provision for plans to manage occupational...commissioned a review of operations......

Cameron Jeffries; Riaz Akber; Andrew Johnston; Brad Cassels

2011-07-01T23:59:59.000Z

175

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

176

Metal inks  

DOE Patents (OSTI)

Self-reducing metal inks and systems and methods for producing and using the same are disclosed. In an exemplary embodiment, a method may comprise selecting metal-organic (MO) precursor, selecting a reducing agent, and dissolving the MO precursor and the reducing agent in an organic solvent to produce a metal ink that remains in a liquid phase at room temperature. Metal inks, including self-reducing and fire-through metal inks, are also disclosed, as are various applications of the metal inks.

Ginley, David S; Curtis, Calvin J; Miedaner, Alex; van Hest, Marinus Franciscus Antonius Maria; Kaydanova, Tatiana

2014-02-04T23:59:59.000Z

177

Radioactive Waste Incineration: Status Report  

SciTech Connect

Incineration is generally accepted as a method of reducing the volume of radioactive waste. In some cases, the resulting ash may have high concentrations of materials such as Plutonium or Uranium that are valuable materials for recycling. Incineration can also be effective in treating waste that contains hazardous chemicals as well as radioactive contamination. Despite these advantages, the number of operating incinerators currently in the US currently appears to be small and potentially declining. This paper describes technical, regulatory, economic and political factors that affect the selection of incineration as a preferred method of treating radioactive waste. The history of incinerator use at commercial and DOE facilities is summarized, along with the factors that have affected each of the sectors, thus leading to the current set of active incinerator facilities. In summary: Incineration has had a long history of use in radioactive waste processing due to their ability to reduce the volume of the waste while destroying hazardous chemicals and biological material. However, combinations of technical, regulatory, economic and political factors have constrained the overall use of incineration. In both the Government and Private sectors, the trend is to have a limited number of larger incineration facilities that treat wastes from a multiple sites. Each of these sector is now served by only one or two incinerators. Increased use of incineration is not likely unless there is a change in the factors involved, such as a significant increase in the cost of disposal. Medical wastes with low levels of radioactive contamination are being treated effectively at small, local incineration facilities. No trend is expected in this group. (authors)

Diederich, A.R.; Akins, M.J. [WorleyParsons, Reading, PA (United States)

2008-07-01T23:59:59.000Z

178

Radioactive isotopes in Danish drinking water  

E-Print Network (OSTI)

Radioactive isotopes in Danish drinking water Sven P. Nielsen Risø National Laboratory Working OF INVESTIGATION 11 3 DESCRIPTION OF INVESTIGATION 12 4 RADIOACTIVITY IN DRINKING WATER 13 5 SAMPLING 15 6 27 #12;4 #12;5 Preface This project for investigation of radioactivity in drinking water shall

179

Spills of Radioactive Materials -Emergency Procedures  

E-Print Network (OSTI)

to radioactive waste container. For surface decontamination, use soap and water and cleansers appropriateSpills of Radioactive Materials - Emergency Procedures Procedure: 7.53 Created: 1/16/2014 Version for injured personnel. B. Applicability/scope This policy applies to all facilities where radioactive

Jia, Songtao

180

Laboratory Surveys when Working with Radioactive Materials  

E-Print Network (OSTI)

radioactive materials (RAM) are used or stored, including waste areas. Negative results should be clearlyLaboratory Surveys when Working with Radioactive Materials Procedure: 7.546 Created: 9/25/14 Version: 1.0 Revised: Environmental Health & Safety Page 1 of 6 A. Purpose Radioactive contamination and

Jia, Songtao

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

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

182

Low-level radioactive waste disposal facility closure  

SciTech Connect

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

183

Metal Oxides  

Science Journals Connector (OSTI)

Metal oxides are the class of materials having the widest application in gas sensors. This chapter presents information related to the application of various metal oxides in gas sensors designed on different p...

Ghenadii Korotcenkov

2013-01-01T23:59:59.000Z

184

PERFORMANCE OF A CONTAINMENT VESSEL CLOSURE FOR RADIOACTIVE GAS CONTENTS  

SciTech Connect

This paper presents a summary of the design and testing of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This package is a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The containment vessel closure incorporates features specifically designed for the containment of tritium when subjected to the normal and hypothetical conditions required of Type B radioactive material shipping Packages. The paper discusses functional performance of the containment vessel closure of the BTSP prototype packages and separate testing that evaluated the performance of the metallic C-Rings used in a mock BTSP closure.

Blanton, P.; Eberl, K.

2010-07-09T23:59:59.000Z

185

Silicone metalization  

DOE Patents (OSTI)

A system for providing metal features on silicone comprising providing a silicone layer on a matrix and providing a metal layer on the silicone layer. An electronic apparatus can be produced by the system. The electronic apparatus comprises a silicone body and metal features on the silicone body that provide an electronic device.

Maghribi, Mariam N. (Livermore, CA); Krulevitch, Peter (Pleasanton, CA); Hamilton, Julie (Tracy, CA)

2006-12-05T23:59:59.000Z

186

Radioactive waste treatment technologies and environment  

SciTech Connect

The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented. (authors)

HORVATH, Jan; KRASNY, Dusan [JAVYS, PLc. - Nuclear and Decommisioning Company, PLc. (Slovakia)

2007-07-01T23:59:59.000Z

187

Radiation and Radon from Natural Stone May 7, 2008  

E-Print Network (OSTI)

Radiation and Radon from Natural Stone May 7, 2008 W.J. Llope Rice University, Houston, TX 77005 is "radiation" and the other is "radon." Radioactive elements, by their very nature, seek stability by decaying the outside and cause damage to cells and DNA, potentially causing cancer. Also, naturally occurring Uranium

Llope, William J.

188

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.

Not Available

1990-12-31T23:59:59.000Z

189

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

190

Office of Civilian Radioactive Waste Management | Department...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management February 2006 Evaluation of technical impact on the Yucca Mountain Project technical basis resulting from issues raised by emails of former...

191

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.

192

Annual Transportation Report for Radioactive Waste Shipments...  

National Nuclear Security Administration (NNSA)

ANNUAL TRANSPORTATION REPORT FY 2008 Radioactive Waste Shipments to and from the Nevada Test Site (NTS) February 2009 United States Department of Energy National Nuclear Security...

193

Science with Beams of Radioactive Isotopes  

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

2015 The International Chemical Congress of Pacific Basin Societies Science with Beams of Radioactive Isotopes ( 340) Honolulu, Hawaii, USA December 15-20, 2015 Science...

194

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...

195

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.

196

Radioactive Material Declaration Form Exhibit to the Radioactive Waste Manual (RWM)  

E-Print Network (OSTI)

Radioactive Material Declaration Form Exhibit to the Radioactive Waste Manual (RWM) 12/5/2013 (form Declaration Form Exhibit to the Radioactive Waste Manual (RWM) 12/5/2013 (form date) SLAC-I-760-2A08Z-001 (RWM date) SLAC-I-760-2A08Z-001 (RWM number) Page 1 of 2 RADIOACTIVE MATERIAL DECLARATION FORM For RP use

Wechsler, Risa H.

197

Natural Gas  

Science Journals Connector (OSTI)

30 May 1974 research-article Natural Gas C. P. Coppack This paper reviews the world's existing natural gas reserves and future expectations, together with natural gas consumption in 1972, by main geographic...

1974-01-01T23:59:59.000Z

198

Radioactive material package seal tests  

SciTech Connect

General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.

Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

1990-01-01T23:59:59.000Z

199

Indirect Estimation of Radioactivity in Containerized Cargo  

SciTech Connect

Detecting illicit nuclear and radiological material in containerized cargo challenges the state of the art in detection systems. Current systems are being evaluated and new systems envisioned to address the need for the high probability of detection and extremely low false alarm rates necessary to thwart potential threats and extremely low nuisance and false alarm rates while maintaining necessary to maintain the flow of commerce impacted by the enormous volume of commodities imported in shipping containers. Maintaining flow of commerce also means that primary inspection must be rapid, requiring relatively indirect measurements of cargo from outside the containers. With increasing information content in such indirect measurements, it is natural to ask how the information might be combined to improved detection. Toward this end, we present an approach to estimating isotopic activity of naturally occurring radioactive material in cargo grouped by commodity type, combining container manifest data with radiography and gamma spectroscopy aligned to location along the container. The heart of this approach is our statistical model of gamma counts within peak regions of interest, which captures the effects of background suppression, counting noise, convolution of neighboring cargo contributions, and down-scattered photons to provide physically constrained estimates of counts due to decay of specific radioisotopes in cargo alone. Coupled to that model, we use a mechanistic model of self-attenuated radiation flux to estimate the isotopic activity within cargo, segmented by location within each container, that produces those counts. We demonstrate our approach by applying it to a set of measurements taken at the Port of Seattle in 2006. This approach to synthesizing disparate available data streams and extraction of cargo characteristics holds the potential to improve primary inspection using current detection capabilities and to enable simulation-based evaluation of new candidate detection systems.

Jarman, Kenneth D.; Scherrer, Chad; Smith, Eric L.; Chilton, Lawrence; Anderson, K. K.; Ressler, Jennifer J.; Trease, Lynn L.

2011-01-01T23:59:59.000Z

200

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both radioactive materials  

E-Print Network (OSTI)

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both as noted on the list, you do not have a mixed waste and it may be managed as a normal radioactive waste radioactive waste after initially dating the container, the hold for decay time is extended, but you cannot

Straight, Aaron

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

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

202

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

203

Metal oxide films on metal  

DOE Patents (OSTI)

A structure including a thin film of a conductive alkaline earth metal oxide selected from the group consisting of strontium ruthenium trioxide, calcium ruthenium trioxide, barium ruthenium trioxide, lanthanum-strontium cobalt oxide or mixed alkaline earth ruthenium trioxides thereof upon a thin film of a noble metal such as platinum is provided.

Wu, Xin D. (Los Alamos, NM); Tiwari, Prabhat (Los Alamos, NM)

1995-01-01T23:59:59.000Z

204

Some radioactive-elements in the coastal sediments of the Mediterranean Sea  

Science Journals Connector (OSTI)

......igneous rocks from the mountainous ranges in Sudan and Abyssinia carried down the course...in the Red Sea coastal environment of Sudan. Mar. Pollut. Bull (1998) 36(1...Natural radioactivity in sand used in thermal therapy at the Red Sea Coast. J. Environ......

Mahmoud A. Radi Dar; Abeer A. El-Saharty

2013-03-01T23:59:59.000Z

205

Radioactive Thulium for X-Rays  

Science Journals Connector (OSTI)

Radioactive power from thulium makes Argonne x-ray unit a potential for medical and industrial use ... Active component of the instrument is a tiny particle (one-fifth gram) of thulium-170 which has been made radioactive in a heavy water nuclear reactor at Arco, Idaho. ...

1954-05-03T23:59:59.000Z

206

Cyclotrons for the production of radioactive beams  

SciTech Connect

This paper describes the characteristics and design choices for modern cyclotrons. Cyclotrons can be used in 3 areas in the radioactive beam field: the production of high energy heavy ion beams for use in fragmentation, the spallation of targets with high energy protons, and the acceleration of radioactive beams from low energy to the MeV/u range. 16 refs., 6 figs.

Clark, D.J.

1990-01-01T23:59:59.000Z

207

Natural Gas  

Science Journals Connector (OSTI)

... CHOOSING an awkward moment, Phillips Petroleum Exploration have announced a new find of natural ...naturalgas ...

1967-02-11T23:59:59.000Z

208

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

209

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

210

Apparatus and method for radioactive waste screening  

SciTech Connect

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

211

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.

212

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

213

Neutron-deficient nuclei studied with stable and radioactive beams  

Science Journals Connector (OSTI)

...radioactive nuclei compiled by W. Gelletly Neutron-deficient nuclei studied with stable and radioactive beams Neutron-deficient nuclei close to the proton...proton drip-line|radioactive beams| Neutron-deficient nuclei studied with stable...

1998-01-01T23:59:59.000Z

214

Rev August 2006 Radiation Safety Manual Section 14 Radioactive Waste  

E-Print Network (OSTI)

Rev August 2006 Radiation Safety Manual Section 14 ­ Radioactive Waste Page 14-1 Section 14 Radioactive Waste Contents A. Proper Collection, Disposal, and Packaging and Putrescible Animal Waste.........................14-8 a. Non-Radioactive Animal Waste

Wilcock, William

215

Characterization of Plutonium in Maxey Flats Radioactive Trench Leachates  

Science Journals Connector (OSTI)

...leachates at the Maxey Flats radioactive waste disposal site exists as dissolved...leachates at the Maxey Flats radioactive waste disposal site exists as dissolved...leachates at the Maxey Flats radioactive waste disposal site exists as dissolved...

JESS M. CLEVELAND; TERRY F. REES

1981-06-26T23:59:59.000Z

216

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

217

Natural radionuclide content and radiological hazard associated with usage of quartzite sand samples from OvacikSilifkeMersin open pit as building material in Turkey  

Science Journals Connector (OSTI)

......building materials such as gas concrete and concrete...respectively. CONCLUSIONS The natural radioactivity due to...Xiaolan Z. Measurement of natural radioactivity in sand...concentrations in surface soils in Cyprus samples. J. Environ...Karahan G., Karack Z. Natural and anthropogenic radionuclides......

S. Turhan; A. S. Aykamis; A. M. Kili

2009-09-01T23:59:59.000Z

218

Environmental Security and Radioactive Contaminantion  

Science Journals Connector (OSTI)

The problem of environmental security is connected to changes in the natural environment as a result of increased stress and the incidence and consequences of extreme events. One of the major problems of envir...

Kazimir A. Karimov; R. D. Gainutdinova

2002-01-01T23:59:59.000Z

219

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

220

Synthesis of a Novel Macroporous Silica-Calix[4]arene-Crown Polymeric Composite and Its Adsorption for Alkali Metals and Alkaline-Earth Metals  

Science Journals Connector (OSTI)

They are released to the environment usually from the natural process of radioactivity, nuclear plant accidents, nuclear weapons testing, and leakage from radioactive waste storage facilities and a variety of wastes associated with the reprocessing of nuclear spent fuel (NSF). ... cycle was developed as a part of a collaborative effort between the Khlopin Ra Institute (KRI) and the Idaho National Engineering and Environmental Lab. ...

Anyun Zhang; Qihui Hu; Zhifang Chai

2010-01-19T23:59:59.000Z

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

Dendritic metal nanostructures  

DOE Patents (OSTI)

Dendritic metal nanostructures made using a surfactant structure template, a metal salt, and electron donor species.

Shelnutt, John A. (Tijeras, NM); Song, Yujiang (Albuquerque, NM); Pereira, Eulalia F. (Vila Nova de Gaia, PT); Medforth, Craig J. (Winters, CA)

2010-08-31T23:59:59.000Z

222

Portsmouth Site Delivers First Radioactive Waste Shipment to...  

Office of Environmental Management (EM)

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas...

223

PTS 13.1 Radioactive And Hazardous Material Transportation 4...  

Office of Environmental Management (EM)

PTS 13.1 Radioactive And Hazardous Material Transportation 41300 PTS 13.1 Radioactive And Hazardous Material Transportation 41300 The objective of this surveillance is to...

224

Applying Risk Communication to the Transportation of Radioactive...  

Office of Environmental Management (EM)

Applying Risk Communication to the Transportation of Radioactive Materials Applying Risk Communication to the Transportation of Radioactive Materials Participants should expect to...

225

2010 Annual Planning Summary for Civilian Radioactive Waste Management...  

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

Civilian Radioactive Waste Management (CRWM) 2010 Annual Planning Summary for Civilian Radioactive Waste Management (CRWM) Annual Planning Summaries briefly describe the status of...

226

Lab obtains approval to begin design on new radioactive waste...  

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

New radioactive waste staging facility Lab obtains approval to begin design on new radioactive waste staging facility The 4-acre complex will include multiple staging buildings...

227

Letter to Congress RE: Office of Civilian Radioactive Waste Management...  

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

to Congress RE: Office of Civilian Radioactive Waste Management's Annual Financial Report Letter to Congress RE: Office of Civilian Radioactive Waste Management's Annual Financial...

228

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.

229

Safety and Security Technologies for Radioactive Material Shipments...  

Office of Environmental Management (EM)

Safety and Security Technologies for Radioactive Material Shipments Safety and Security Technologies for Radioactive Material Shipments Safety and Security Technologies for...

230

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

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

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

231

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...

232

Microbial transformation of low-level radioactive waste  

SciTech Connect

Microorganisms play a significant role in the transformation of the radioactive waste and waste forms disposed of at shallow-land burial sites. Microbial degradation products of organic wastes may influence the transport of buried radionuclides by leaching, solubilization, and formation of organoradionuclide complexes. The ability of indigenous microflora of the radioactive waste to degrade the organic compounds under aerobic and anaerobic conditions was examined. Leachate samples were extracted with methylene chloried and analyzed for organic compounds by gas chromatography and mass spectrometry. In general, several of the organic compounds in the leachates were degraded under aerobic conditions. Under anaerobic conditions, the degradation of the organics was very slow, and changes in concentrations of several acidic compounds were observed. Several low-molecular-weight organic acids are formed by breakdown of complex organic materials and are further metabolized by microorganisms; hence these compounds are in a dynamic state, being both synthesized and destroyed. Tributyl phosphate, a compound used in the extraction of metal ions from solutions of reactor products, was not degraded under anaerobic conditions.

Francis, A.J.

1980-06-01T23:59:59.000Z

233

Method for solidification of radioactive and other hazardous waste  

DOE Patents (OSTI)

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

234

Geological problems in radioactive waste isolation - A world wide review  

SciTech Connect

The problem of isolating radioactive wastes from the biosphere presents specialists in the 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. The most widely accepted method of doing this is to seal the radioactive materials in metal canisters that are enclosed by a protective sheath and placed underground in a repository that has been carefully constructed in an appropriate rock formation. 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. Table 1 presents a summary of the various formations under investigation according to the reports submitted for this world wide review. It can be seen that in those countries that are searching for repository sites, granitic and metamorphic rocks are the prevalent rock type under investigation. Six countries have developed underground research facilities that are currently in use. All of these investigations are in saturated systems below the water table, except the United States project, which is in the unsaturated zone of a fractured tuff.

Witherspoon, P.A. [Lawrence Berkeley Lab., CA (United States)

1991-06-01T23:59:59.000Z

235

Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513  

SciTech Connect

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

2013-07-01T23:59:59.000Z

236

Durability of metals from archaeological objects, metal meteorites, and native metals  

SciTech Connect

Metal durability is an important consideration in the multi-barrier nuclear waste storage concept. This study summarizes the ancient metals, the environments, and factors which appear to have contributed to metal longevity. Archaeological and radiochemical dating suggest that human use of metals began in the period 6000 to 7000 BC. Gold is clearly the most durable, but many objects fashioned from silver, copper, bronze, iron, lead, and tin have survived for several thousand years. Dry environments, such as tombs, appear to be optimum for metal preservation, but some metals have survived in shipwrecks for over a thousand years. The metal meteorites are Fe-base alloys with 5 to 60 wt% Ni and minor amounts of Co, I, and S. Some meteoritic masses with ages estimated to be 5,000 to 20,000 years have weathered very little, while other masses from the same meteorites are in advanced stages of weathering. Native metals are natural metallic ores. Approximately five million tonnes were mined from native copper deposits in Michigan. Copper masses from the Michigan deposits were transported by the Pleistocene glaciers. Areas on the copper surfaces which appear to represent glacial abrasion show minimal corrosion. Dry cooling tower technology has demonstrated that in pollution-free moist environments, metals fare better at temperatures above than below the dewpoint. Thus, in moderate temperature regimes, elevated temperatures may be useful rather than detrimental for exposures of metal to air. In liquid environments, relatively complex radiolysis reactions can occur, particularly where multiple species are present. A dry environment largely obviates radiolysis effects.

Johnson, A.B. Jr.; Francis, B.

1980-01-01T23:59:59.000Z

237

Radioactivity evaluation for the KSTAR tokamak  

Science Journals Connector (OSTI)

......Articles Radioactivity evaluation for the KSTAR tokamak Hyunduk Kim 1 Hee-Seock Lee 1 Sukmo Hong 1 Minho...reaction in the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak generates neutrons with a peak yield of 2.51016......

Hyunduk Kim; Hee-Seock Lee; Sukmo Hong; Minho Kim; Chinwha Chung; Changsuk Kim

2005-12-20T23:59:59.000Z

238

Argonne In-Flight Radioactive Ion Separator  

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

In-Flight Radioactive Ion Separator www.phy.anl.govairis B. B. Back, C. Dickerson, C. R. Hoffman, B. P. Kay, B. Mustapha, J. A. Nolen, P. Ostroumov, R. C. Pardo, K. E. Rehm, G....

239

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

240

Accelerated Radioactive Nuclear Beams (Low Energy)  

Science Journals Connector (OSTI)

The possibility of producing and accelerating intense beams of short-lived radioactive heavy ions, both for studies of nuclides themselves and for use as projectiles in reactions of considerable interest to the f...

John M. DAuria

1990-01-01T23:59:59.000Z

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.


241

Radioactivity in man: levels, effects and unknowns  

SciTech Connect

The report discusses the potential for significant human exposure to internal radiation. Sources of radiation considered include background radiation, fallout, reactor accidents, radioactive waste, and occupational exposure to various radioisotopes. (ACR)

Rundo, J.

1980-01-01T23:59:59.000Z

242

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

243

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

244

Radioactivity and X-rays Applications and health effects  

E-Print Network (OSTI)

as the release of radioactivity from reactor accidents and fallout from nuclear explosions in the atmosphereRadioactivity and X-rays Applications and health effects by Thormod Henriksen #12;Preface ­ 7 Chapter 2. What is radioactivity page 8 ­ 27 Chapter 3. Radioactive decay laws page 28 ­ 35

Sahay, Sundeep

245

Sorting and disposal of hazardous laboratory Radioactive waste  

E-Print Network (OSTI)

Sorting and disposal of hazardous laboratory waste Radioactive waste Solid radioactive waste or in a Perspex box. Liquid radioactive waste collect in a screw-cap plastic bottle, ½ or 1 L size. Place bottles in a tray to avoid spill Final disposal of both solid and radioactive waste into the yellow barrel

Maoz, Shahar

246

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

247

Composite metal membrane  

DOE Patents (OSTI)

A composite metal membrane including a first metal layer of Group IVB met or Group VB metals, the first metal layer sandwiched between two layers of an oriented metal of palladium, platinum or alloys thereof is provided together with a process for the recovery of hydrogen from a gaseous mixture including contacting a hydrogen-containing gaseous mixture with a first side of a nonporous composite metal membrane including a first metal of Group IVB metals or Group VB metals, the first metal layer sandwiched between two layers of an oriented metal of palladium, platinum or alloys thereof, and, separating hydrogen from a second side of the nonporous composite metal membrane.

Peachey, Nathaniel M. (Espanola, NM); Dye, Robert C. (Los Alamos, NM); Snow, Ronny C. (Los Alamos, NM); Birdsell, Stephan A. (Los Alamos, NM)

1998-01-01T23:59:59.000Z

248

Composite metal membrane  

DOE Patents (OSTI)

A composite metal membrane including a first metal layer of Group IVB met or Group VB metals, the first metal layer sandwiched between two layers of an oriented metal of palladium, platinum or alloys thereof is provided together with a process for the recovery of hydrogen from a gaseous mixture including contacting a hydrogen-containing gaseous mixture with a first side of a nonporous composite metal membrane including a first metal of Group IVB metals or Group VB metals, the first metal layer sandwiched between two layers of an oriented metal of palladium, platinum or alloys thereof, and, separating hydrogen from a second side of the nonporous composite metal membrane.

Peachey, N.M.; Dye, R.C.; Snow, R.C.; Birdsell, S.A.

1998-04-14T23:59:59.000Z

249

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

250

Measurement of radioactive contaminated wastes  

SciTech Connect

At Los Alamos, a comprehensive program is underway for the development of sensitive, practical, nondestructive assay techniques for the quantification of low-level transuranics in bulk solid wastes. The program encompasses a broad range of techniques, including sophisticated active and passive gamma-ray spectroscopy, passive neutron detection systems, pulsed portable neutron generator interrogation systems, and electron accelerator-based techniques. The techniques can be used with either low-level or high-level beta-gamma wastes in either low-density or high-density matrices. The techniques are quite sensitive (< 10 nCi/g detection) and, in many cases, isotopic specific. Waste packages range in size from small cardboard boxes to large metal or wooden crates. Considerable effort is being expended on waste matrix identification to improve assay accuracy.

Caldwell, J.T.; Close, D.A.; Crane, T.W.

1983-01-01T23:59:59.000Z

251

33. Radioactivity and radiation protection 1 33. RADIOACTIVITY AND RADIATION PROTECTION  

E-Print Network (OSTI)

a conservative estimate for the value of the protection quantity. · Ambient dose equivalent, H(10) (unit: sievert): The dose equivalent at a point in a radiation field that would be produced by the corresponding expanded33. Radioactivity and radiation protection 1 33. RADIOACTIVITY AND RADIATION PROTECTION Revised

252

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

253

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

254

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

255

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

256

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

257

Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216  

SciTech Connect

Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq)] [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)] [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

2013-07-01T23:59:59.000Z

258

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 -

259

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,"

260

DOE - Safety of Radioactive Material Transportation  

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

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

Note: This page contains sample records for the topic "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

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

262

Completion of the Radioactive Materials Packaging Handbook  

SciTech Connect

The Radioactive Materials Packaging Handbook: Design, Operation and Maintenance, which will serve as a replacement for the Cask Designers Guide (Shappert, 1970), has now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for layout and printing; it is scheduled to be printed in late spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that address the design aspects of a package intended for transporting radioactive material in normal commerce; it was prepared under the direction of M. E. Wangler of the US Department of Energy (DOE) and is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators on specific aspects of package design, and the types of analyses that should be considered when designing a package to carry radioactive materials.

Shappert, L.B.

1998-02-01T23:59:59.000Z

263

Enhancement factors for resuspended aerosol radioactivity: Effects of topsoil disturbance  

SciTech Connect

The enhancement factor for airborne radionuclides resuspended by wind is defined as the ratio of the activity density (Bq g{sup {minus}1}) in the aerosol to the activity density in the underlying surface of contaminated soil. Enhancement factors are useful for assessment of worst-case exposure scenarios and transport conditions, and are one of the criteria for setting environmental standards for radioactivity in soil. This paper presents results of experimental studies where resuspension of {sup 239}Pu was measured when air concentrations were equilibrated to the soil surface. Enhancement factors were observed for several types of man-made disturbances (bulldozer-blading, soil raking, vacuum-cleaning) and natural disturbances (springtime thaw, soil-drying, wildfire). For some cases, enhancement factors are compared over range of geographical locations (Bikini Atoll, California, Nevada, and South Carolina). The particle-size distributions of aerosol activity are compared to particle-size distributions of the underlying soil.

Shinn, J.H.

1991-11-01T23:59:59.000Z

264

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

265

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

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

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

268

E-Print Network 3.0 - acid liquid radioactive Sample Search Results  

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

WASHINGTON, D.C. 20460 Summary: radioactive wastes in liquid or solid forms. Oil and gas production, as an example, also results... a radioactive source, plus radioactive...

269

natural gasoline  

Science Journals Connector (OSTI)

natural gasoline, condensate, distillate [Liquid hydrocarbons, generally clear or pale straw-coloured and of high API gravity (above 6o), that are produced with wet gas] ? Gasbenzin n, Gasolin n ...

2014-08-01T23:59:59.000Z

270

Electron transport through a metal-molecule-metal junction  

Science Journals Connector (OSTI)

Molecules of bisthiolterthiophene have been adsorbed on the two facing gold electrodes of a mechanically controllable break junction in order to form metal-molecule(s)-metal junctions. Current-voltage (I-V) characteristics have been recorded at room temperature. Zero bias conductances were measured in the 10100 nS range and different kinds of nonlinear I-V curves with steplike features were reproducibly obtained. Switching between different kinds of I-V curves could be induced by varying the distance between the two metallic electrodes. The experimental results are discussed within the framework of tunneling transport models explicitly taking into account the discrete nature of the electronic spectrum of the molecule.

C. Kergueris; J.-P. Bourgoin; S. Palacin; D. Esteve; C. Urbina; M. Magoga; C. Joachim

1999-05-15T23:59:59.000Z

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

Determination of Dose from the Disposal of Radioactive Waste Related with TENORM using Residual Radioactivity (RESRAD) Monte Carlo Code  

SciTech Connect

The working procedures in the RESRAD for specific evaluations of environmental pollutants are briefly mentioned. The risk of human health associated with Naturally Occurring Radioactive Materials (NORM) who are working in the Malaysian oil and gas industry are analyzed. The sources of NORM and Technologically Enhanced NORM (TENORM) in the oil and gas industry are described. Some measurements for the external and internal effective dose equivalent on the workers will be described. These data are entered into the RESRAD software program and the output reports are taken. Long-term effects of TENORM to the industrial workers are also discussed with graphical illustrations. These results are compared with previous research work within the same field to validate and verify.

Lwin, Maung Tin Moe; Kassim, Hassan Abu; Amin, Yusoff Mohd. [Department of Physics, Faculty of Science, University of Malaya, 50603 Kuala Lampur (Malaysia)

2008-05-20T23:59:59.000Z

273

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

274

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

275

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.

276

Low-level radioactive waste source terms for the 1992 integrated data base  

SciTech Connect

This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF{sub 6}) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and {open_quotes}other{close_quotes}. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF{sub 6} conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992.

Loghry, S L; Kibbey, A H; Godbee, H W; Icenhour, A S; DePaoli, S M

1995-01-01T23:59:59.000Z

277

Physics with energetic radioactive ion beams  

SciTech Connect

Beams of short-lived, unstable nuclei have opened new dimensions in studies of nuclear structure and reactions. Such beams also provide key information on reactions that take place in our sun and other stars. Status and prospects of the physics with energetic radioactive beams are summarized.

Henning, W.F.

1996-12-31T23:59:59.000Z

278

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.)

1984-09-01T23:59:59.000Z

279

Radioactivity: Olympic Games: dirty and decaying?  

Science Journals Connector (OSTI)

Radioactivity: Olympic Games: dirty and decaying? Awards: SciCast rewards the best in scientific short films Conference: Teachers conference is big in Boston Workshop: Experts and teachers mingle in Mexico Awards: Olympiad holds lavish ceremony Cinema: Indiana Jones has a skull full of physics Conference: ESERA announces Turkish delight for 2009 Forthcoming Events

280

Annual radioactive waste tank inspection program: 1995  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1995 to evaluate these vessels and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

McNatt, F.G. Sr.

1996-04-01T23:59:59.000Z

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.


281

International Standards and Units of Radioactivity  

Science Journals Connector (OSTI)

... latter could be measured and their radium contents expressed in grams. For the measurement of radon, grams (or cubic centimetres) of this gas are impracticable as units, and it ... gas are impracticable as units, and it was therefore decided to use as unit of radon the quantity which is in radioactive equilibrium with 1 gm. of radium; it was ...

1947-12-06T23:59:59.000Z

282

Tunable Biopolymers for Heavy Metal Removal Jan Kostal, Ashok Mulchandani, and Wilfred Chen*  

E-Print Network (OSTI)

persistent nature, heavy metal ions are major contributors to pollution of the biosphere.1,2 These metalsTunable Biopolymers for Heavy Metal Removal Jan Kostal, Ashok Mulchandani, and Wilfred Chen synthesized for the removal of heavy metals from dilute waste streams. Protein-protein interaction

Chen, Wilfred

283

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:

284

Retrieval Of Final Stored Radioactive Waste Resumes | Department...  

Office of Environmental Management (EM)

Retrieval Of Final Stored Radioactive Waste Resumes Retrieval Of Final Stored Radioactive Waste Resumes April 18, 2012 - 12:00pm Addthis Media Contacts Danielle Miller, DOE-Idaho...

285

Radioactive waste management and decommissioning of accelerator facilities  

Science Journals Connector (OSTI)

......Austria). EPAC. 2 International Atomic Energy Agency. Management of radioactive waste...Association, October 2008: Buenos Aires, Argentina. Argentina: SAR editor. 5 International Atomic Energy Agency. Classification of radioactive......

Luisa Ulrici; Matteo Magistris

2009-11-01T23:59:59.000Z

286

Depleted uranium: a contemporary controversy for the teaching of radioactivity  

Science Journals Connector (OSTI)

Depleted uranium has been used in recent military conflicts and the media have reported the danger from radioactivity. This context provides a good way to keep students' attention when introducing the subject of radioactivity at GCSE or advanced level.

Mark Whalley

2006-01-01T23:59:59.000Z

287

Application of Field-Flow Fractionation to Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Marcus N. Myers; Kathy A. Graff; J. Calvin Giddings

288

METAL MEDIA FILTERS, AG-1 SECTION FI  

SciTech Connect

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

289

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

290

Film Badge Application Radioactive Material Package Receipt Log  

E-Print Network (OSTI)

;RADIOACTIVE MATERIAL PACKAGE RECEIPT LOG DATE: DELIVERED BY: AUTHORIZED BY: Contamination Check DPM/100 cm2APPENDIX A Film Badge Application Radioactive Material Package Receipt Log Radioactive Material Package Receipt Form (Off-Campus Locations) Radiation / Contamination Survey Form #12;PERSONNEL MONITORING

Slatton, Clint

291

1 INSTRODUCTION In the concept of geological radioactive waste disposal,  

E-Print Network (OSTI)

1 INSTRODUCTION In the concept of geological radioactive waste disposal, argillite is being of the radioactive waste disposal, the host rock will be subjected to various thermo-hydro-mechanical loadings, thermal solicitation comes from the heat emitting from the radioactive waste packages. On one hand

Boyer, Edmond

292

Survey of National Programs for Managing High-Level Radioactive  

E-Print Network (OSTI)

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel-Level Radioactive Waste and Spent Nuclear Fuel A Report to Congress and the Secretary of Energy October 2009 #12 Safety (Germany) Peter De Preter: National Agency for Radioactive Waste and Enriched Fissile Materials

293

Study of gel materials as radioactive 222Rn gas detectors  

Science Journals Connector (OSTI)

......studied as radioactive radon gas detectors. The detection...diffusion of the radioactive gas in the gel material...easy handling and low cost of the gel material...and other radioactive gases. INTRODUCTION The objective...homogeneity of the device production, dimensions, almost......

G. Espinosa; J. I. Golzarri; J. Rickards; R. B. Gammage

2006-09-01T23:59:59.000Z

294

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

295

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 

296

Metal-phosphate binders  

DOE Patents (OSTI)

A metal-phosphate binder is provided. The binder may include an aqueous phosphoric acid solution, a metal-cation donor including a metal other than aluminum, an aluminum-cation donor, and a non-carbohydrate electron donor.

Howe, Beth Ann [Lewistown, IL; Chaps-Cabrera, Jesus Guadalupe [Coahuila, MX

2009-05-12T23:59:59.000Z

297

Gold, Copper, and Platinum Nanoparticles Dispersed on CeOx/TiO2(110) Surfaces: High Water-Gas Shift Activity and the Nature of the Mixed-Metal Oxide at the Nanometer Level  

SciTech Connect

At small coverages of ceria on TiO{sub 2}(110), the CeO{sub x} nanoparticles have an unusual coordination mode. Scanning tunneling microscopy and density-functional calculations point to the presence of Ce{sub 2}O{sub 3} dimers, which form diagonal arrays that have specific orientations of 0, 24, and 42{sup o} with respect to the [1 -1 0] direction of the titania substrate. At high coverages of ceria on TiO{sub 2}(110), the surface exhibits two types of terraces. In one type, the morphology is not very different from that observed at low ceria coverage. However, in the second type of terrace, there is a compact array of ceria particles with structures that do not match the structures of CeO{sub 2}(111) or CeO{sub 2}(110). The titania substrate imposes on the ceria nanoparticles nontypical coordination modes, enhancing their chemical reactivity. This phenomenon leads to a larger dispersion of supported metal nanoparticles (M = Au, Cu, Pt) and makes possible the direct participation of the oxide in catalytic reactions. The M/CeO{sub x}/TiO{sub 2}(110) surfaces display an extremely high catalytic activity for the water-gas shift reaction that follows the sequence Au/CeO{sub x}/TiO{sub 2}(110) < Cu/CeO{sub x}/TiO{sub 2}(110) < Pt/CeO{sub x}/TiO{sub 2}(110). For low coverages of Cu and CeO{sub x}, Cu/CeO{sub x}/TiO{sub 2}(110) is 8-12 times more active than Cu(111) or Cu/ZnO industrial catalysts. In the M/CeO{sub x}/TiO{sub 2}(110) systems, there is a strong coupling of the chemical properties of the admetal and the mixed-metal oxide: The adsorption and dissociation of water probably take place on the oxide, CO adsorbs on the admetal nanoparticles, and all subsequent reaction steps occur at the oxide-admetal interface. The high catalytic activity of the M/CeO{sub x}/TiO{sub 2}(110) surfaces reflects the unique properties of the mixed-metal oxide at the nanometer level.

Park, J.; Graciani, J; Evans, J; Stacchiola, D; Senanayake, S; Barrio, L; Liu, P; Fdez. Sanz, J; Hrbek, J; Rodriguez, J

2010-01-01T23:59:59.000Z

298

Gold, Copper and Platinum Nanoparticles Dispersed on CeOx/TiO2(110) Surfaces: High Water-Gas Shift Activity and the Nature of the Mixed-Metal Oxide at the Nanometer Level  

SciTech Connect

At small coverages of ceria on TiO{sub 2}(110), the CeO{sub x} nanoparticles have an unusual coordination mode. Scanning tunneling microscopy and density-functional calculations point to the presence of Ce{sub 2}O{sub 3} dimers, which form diagonal arrays that have specific orientations of 0, 24, and 42{sup o} with respect to the [1 -1 0] direction of the titania substrate. At high coverages of ceria on TiO{sub 2}(110), the surface exhibits two types of terraces. In one type, the morphology is not very different from that observed at low ceria coverage. However, in the second type of terrace, there is a compact array of ceria particles with structures that do not match the structures of CeO{sub 2}(111) or CeO{sub 2}(110). The titania substrate imposes on the ceria nanoparticles nontypical coordination modes, enhancing their chemical reactivity. This phenomenon leads to a larger dispersion of supported metal nanoparticles (M = Au, Cu, Pt) and makes possible the direct participation of the oxide in catalytic reactions. The M/CeO{sub x}/TiO{sub 2}(110) surfaces display an extremely high catalytic activity for the water-gas shift reaction that follows the sequence Au/CeO{sub x}/TiO{sub 2}(110) < Cu/CeO{sub x}/TiO{sub 2}(110) < Pt/CeO{sub x}/TiO{sub 2}(110). For low coverages of Cu and CeO{sub x}, Cu/CeO{sub x}/TiO{sub 2}(110) is 8-12 times more active than Cu(111) or Cu/ZnO industrial catalysts. In the M/CeO{sub x}/TiO{sub 2}(110) systems, there is a strong coupling of the chemical properties of the admetal and the mixed-metal oxide: The adsorption and dissociation of water probably take place on the oxide, CO adsorbs on the admetal nanoparticles, and all subsequent reaction steps occur at the oxide-admetal interface. The high catalytic activity of the M/CeO{sub x}/TiO{sub 2}(110) surfaces reflects the unique properties of the mixed-metal oxide at the nanometer level.

Rodriguez, J.A.; Park, J.B.; Graciani, J.; Evans, J.; Stacchiola, D.; Senanayake, S.D.; Barrio, L.; Liu, P.; Sanz, J.F.; Hrbek, J.

2010-01-13T23:59:59.000Z

299

NATURE STUDY  

Science Journals Connector (OSTI)

...last two numbers of SCIENCE have appeared articles by Drs. Wheeler and Chapman on the abuses of nature writing as exemplified...imprint of Rand, IeNally and Co., 1903, and its author is Katherine E. Dopp, of the Extension Division of the Chicago University...

E. C. CASE

1904-04-01T23:59:59.000Z

300

Marketing Mother Natures Molecules  

Science Journals Connector (OSTI)

Marketing Mother Natures Molecules ... Yet molecules made by Mother Nature, or derivatives thereof, still account for nearly half of the drugs on the market. ...

LISA JARVIS

2012-02-19T23:59:59.000Z

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.


301

Measurement of low radioactivity background in a high voltage cable by high resolution inductively coupled plasma mass spectrometry  

SciTech Connect

The measurement of naturally occurring low level radioactivity background in a high voltage (HV) cable by high resolution inductively coupled plasma mass spectrometry (HR ICP MS) is presented in this work. The measurements were performed at the Chemistry Service of the Gran Sasso National Laboratory. The contributions to the radioactive background coming from the different components of the heterogeneous material were separated. Based on the mass fraction of the cable, the whole contamination was calculated. The HR ICP MS results were cross-checked by gamma ray spectroscopy analysis that was performed at the low background facility STELLA (Sub Terranean Low Level Assay) of the LNGS underground lab using HPGe detectors.

Vacri, M. L. di; Nisi, S.; Balata, M. [Gran Sasso National Laboratory, Chemistry Service, SS 17bis km 18.910, 67100 Assergi (Aq) (Italy)] [Gran Sasso National Laboratory, Chemistry Service, SS 17bis km 18.910, 67100 Assergi (Aq) (Italy)

2013-08-08T23:59:59.000Z

302

Metal-insulator transition in expanded alkali-metal fluids and alkali-metalrare-gas films  

Science Journals Connector (OSTI)

We have developed a theoretical model for expanded alkali metals and alkali-metalrare-gas films that is based on a physically realistic picture of the atomic-scale structure of these materials. It emphasizes the disorder in the systems, in particular the random atomic coordination number. Using this model we have calculated the density- and the energy-dependent conductivity as a function of the mean alkali-metal atomic coordination number. Although the theory contains only two parameters, both of which are fixed by the properties of pure materials at normal temperatures, we have been able to explain results measured over a temprature range from 4.2 to >2000 K in a variety of different alkali-metal systems. Conductivity and magnetic-susceptibility measurements, in particular, have been considered in some detail. In addition, the theory provides insight into the nature and location of the metal-insulator transition, the nature of the critical point for the alkali metals, and the thermal instability of the alkali-metalrare-gas films.

Judy R. Franz

1984-02-15T23:59:59.000Z

303

Metal Hydrides - Science Needs  

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

Storage Grand Challenge Pre-Solicitation Meeting, June 19, 2003 1 Metal Hydrides - Science Needs TRADITIONAL METALLIC HYDRIDES: 1.5 to 2 wt.% H. Well studied. COMPLEX...

304

Probing metal solidification nondestructively  

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

Probing metal solidification nondestructively This is the first time that high-energy protons have been used to nondestructively image a large metal sample during melting and...

305

Probing metal solidification nondestructively  

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

Probing metal solidification nondestructively This is the first time that high-energy protons have been used to nondestructively image a large metal sample during melting...

306

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

SciTech Connect

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

307

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

308

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),

309

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

310

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

311

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

312

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

313

Standard Model tests with trapped radioactive atoms  

E-Print Network (OSTI)

We review the use of laser cooling and trapping for Standard Model tests, focusing on trapping of radioactive isotopes. Experiments with neutral atoms trapped with modern laser cooling techniques are testing several basic predictions of electroweak unification. For nuclear $\\beta$ decay, demonstrated trap techniques include neutrino momentum measurements from beta-recoil coincidences, along with methods to produce highly polarized samples. These techniques have set the best general constraints on non-Standard Model scalar interactions in the first generation of particles. They also have the promise to test whether parity symmetry is maximally violated, to search for tensor interactions, and to search for new sources of time reversal violation. There are also possibilites for exotic particle searches. Measurements of the strength of the weak neutral current can be assisted by precision atomic experiments using traps of small numbers of radioactive atoms, and sensitivity to possible time-reversal violating electric dipole moments can be improved.

J. A. Behr; G. Gwinner

2009-03-04T23:59:59.000Z

314

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

315

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

316

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

317

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

318

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,

319

Metal Surface Decontamination by the PFC Solution  

SciTech Connect

PFC (per-fluorocarbon) spray decontamination equipment was fabricated and its decontamination behavior was investigated. Europium oxide powder was mixed with the isotope solution which contains Co-60 and Cs-137. The different shape of metal specimens artificially contaminated with europium oxide powder was used as the surrogate contaminants. Before and after the application of the PFC spray decontamination method, the radioactivity of the metal specimens was measured by MCA. The decontamination factors were in the range from 9.6 to 62.4. The spent PFC solution was recycled by distillation. Before and after distillation, the turbidity of PFC solution was also measured. From the test results, it was found that more than 98% of the PFC solution could be recycled by a distillation. (authors)

Hui-Jun Won; Gye-Nam Kim; Wang-Kyu Choi; Chong-Hun Jung; Won-Zin Oh [Korea Atomic Energy Research Institute - KAERI, P.O.Box 105, Yuseong, Daejeon, Korea, 305-353 (Korea, Republic of)

2006-07-01T23:59:59.000Z

320

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

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

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 _______

322

Electrically Driven Technologies for Radioactive Aerosol Abatement  

SciTech Connect

The purpose of this research project was to develop an improved understanding of how electriexecy driven processes, including electrocoalescence, acoustic agglomeration, and electric filtration, may be employed to efficiently treat problems caused by the formation of aerosols during DOE waste treatment operations. The production of aerosols during treatment and retrieval operations in radioactive waste tanks and during thermal treatment operations such as calcination presents a significant problem of cost, worker exposure, potential for release, and increased waste volume.

David W. DePaoli; Ofodike A. Ezekoye; Costas Tsouris; Valmor F. de Almeida

2003-01-28T23:59:59.000Z

323

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 ...........................................

324

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 ...........................................

325

Radioactive waste management in the former USSR  

SciTech Connect

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01T23:59:59.000Z

326

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

327

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.

328

Organic fluorine in human serum: natural versus industrial sources  

Science Journals Connector (OSTI)

...highly inadvisable to locate a chemical waste disposal site adjacent to a radioac-tive waste disposal site. Naturally occur-ring organic substances...EPA-52015-761020 (1977). 3. The hydrology of the Maxey Flats site has been described in H. H. Zehner...

J Belisle

1981-06-26T23:59:59.000Z

329

Natural ventilation of the Paintings Room in the Altamira cave  

Science Journals Connector (OSTI)

... Radon-222 is a noble gas of the radioactive series of 238U, an element that ... per 106). Because of its gaseous nature and its greater concentration within the Earth, radon escapes through the interstices of the soil to the atmosphere, with an exhalation rate ...

P. L. Fernndez; I. Gutierrez; L. S. Quinds; J. Soto; E. Villar

1986-06-05T23:59:59.000Z

330

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

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

331

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

332

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

333

Initial Evaluation of Processing Methods for an Epsilon Metal Waste Form  

SciTech Connect

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

334

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.

Day, Delbert E. (Rolla, MO)

1998-01-01T23:59:59.000Z

335

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

336

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

337

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

338

Comprehensive low-level radioactive waste management plan for the Commonwealth of Kentucky  

SciTech Connect

Part I of the Comprehensive Low-Level Radioactive Waste Management Plan for the Commonwealth of Kentucky discusses the alternatives that have been examined to manage the low-level radioactive waste currently generated in the state. Part II includes a history of the commercial operation of the Maxey Flats Nuclear Waste Disposal Site in Fleming County, Kentucky. The reasons for closure of the facility by the Human Resources Cabinet, the licensing agency, are identified. The site stabilization program managed by the Natural Resources and Environmental Protection Cabinet is described in Chapter VI. Future activities to be conducted at the Maxey Flats Disposal Site will include site stabilization activities, routine operations and maintenance, and environmental monitoring programs as described in Chapter VII.

Carr, R.M.; Mills, D.; Perkins, C.; Riddle, R.

1984-03-01T23:59:59.000Z

339

Advanced technologies for decontamination and conversion of scrap metal  

SciTech Connect

In October 1993, Manufacturing Sciences Corporation was awarded DOE contract DE-AC21-93MC30170 to develop and test recycling of radioactive scrap metal (RSM) to high value and intermediate and final product forms. This work was conducted to help solve the problems associated with decontamination and reuse of the diffusion plant barrier nickel and other radioactively contaminated scrap metals present in the diffusion plants. Options available for disposition of the nickel include decontamination and subsequent release or recycled product manufacture for restricted end use. Both of these options are evaluated during the course of this research effort. work during phase I of this project successfully demonstrated the ability to make stainless steel from barrier nickel feed. This paved the way for restricted end use products made from stainless steel. Also, after repeated trials and studies, the inducto-slag nickel decontamination process was eliminated as a suitable alternative. Electro-refining appeared to be a promising technology for decontamination of the diffusion plant barrier material. Goals for phase II included conducting experiments to facilitate the development of an electro-refining process to separate technetium from nickel. In parallel with those activities, phase II efforts were to include the development of the necessary processes to make useful products from radioactive scrap metal. Nickel from the diffusion plants as well as stainless steel and carbon steel could be used as feed material for these products.

MacNair, V.; Muth, T.; Shasteen, K.; Liby, A.; Hradil, G.; Mishra, B.

1996-12-31T23:59:59.000Z

340

Heavy metal biosensor  

DOE Patents (OSTI)

Compositions and methods are provided for detection of certain heavy metals using bacterial whole cell biosensors.

Hillson, Nathan J; Shapiro, Lucille; Hu, Ping; Andersen, Gary L

2014-04-15T23:59:59.000Z

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.


341

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.

342

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.

343

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.

344

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.

345

The Molecular Scale Nature of Copper (II) and Arsenate Bonding with Goethite-Humate Complexes.  

E-Print Network (OSTI)

??In soils, interactions between clay minerals and natural organic matter are known to affect the cycling of heavy metals and anions. Contaminant structures at mineral (more)

Alcacio, Tim

2001-01-01T23:59:59.000Z

346

E-Print Network 3.0 - alkali-metal vapor density Sample Search...  

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

Physics 65 nature physics | VOL 3 | APRIL 2007 | www.nature.comnaturephysics 227 REVIEW ARTICLE Summary: in a high-density alkali-metal vapor in low magnetic fields. Phys....

347

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"

348

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

349

Upgrading the Radioactive Waste Management Infrastructure in Azerbaijan  

SciTech Connect

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

350

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

351

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

352

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

353

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

354

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

355

2p radioactivity studies with a TPC  

SciTech Connect

After the discovery of two-proton radioactivity in 2002, an important effort has been made in order to observe each emitted particle individually. Energy and angular correlations between the protons should reveal details about the mechanism of this exotic decay mode. In this framework, an experiment has been performed at LISE/GANIL, where the two protons emitted in the decay of {sup 54}Zn have been individually observed for the first time. Angular and energy correlations were determined and allowed a first comparison with theoretical predictions.

Ascher, P.; Audirac, L.; Blank, B.; Delalee, F.; Demonchy, C. E.; Giovinazzo, J.; Leblanc, S.; Pedroza, J.-L.; Pibernat, J.; Serani, L. [Centre d'Etudes Nucleaires de Bordeaux Gradignan-Universite Bordeaux 1-UMR 5797 CNRS/IN2P3, Chemin du Solarium, BP120, 33175 Gradignan (France); Adimi, N. [Centre d'Etudes Nucleaires de Bordeaux Gradignan-Universite Bordeaux 1-UMR 5797 CNRS/IN2P3, Chemin du Solarium, BP120, 33175 Gradignan (France); Faculte de Physique, USTHB, B.P.32, El Alia, 16111 Bab Ezzouar, Alger (Algeria); Borcea, C.; Companis, I. [National Institute for Physics and Nuclear Engineering, P.O. Box MG6, Bucharest-Margurele (Romania); Brown, B. A. [Department of Physics and Astronomy, and National Superconducting Cyclotron Laboratory, Michigan State University, East Lansing, Michigan 48824-1321 (United States); Oliveira Santos, F. de; Grevy, S.; Thomas, J.-C. [Grand Accelerateur National d'Ions Lourds, CEA/DSM-CNRS/IN2P3, 14076 Caen Cedex05 (France); Grigorenko, L. V.; Perrot, L. [Flerov Laboratory of Nuclear Reactions, JINR, Dubna 141980 (Russian Federation); Srivastava, P. [Nuclear Physics Group, Department of Physics, University of Allahabad (India); and others

2011-11-30T23:59:59.000Z

356

Sealed Radioactive Source Accountability and Control Guide  

Directives, Delegations, and Requirements

For use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection. This Guide provides an acceptable methodology for establishing and operating a sealed radioactive source accountability and control program that will comply with U.S. Department of Energy (DOE) requirements specified in Title 10 of the Code of Federal Regulations (CFR), Part 835, Occupational Radiation Protection (DOE 1998a), hereinafter referred to as 10 CFR 835. In particular, this Guide provides guidance for achieving compliance with subpart M of 10 CFR 835. Canceled by DOE G 441.1-1B.

1999-04-15T23:59:59.000Z

357

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

358

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

359

Corrosion resistant storage container for radioactive material  

DOE Patents (OSTI)

A corrosion resistant long-term storage container for isolating radioactive waste material in a repository. 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 judxtaposed 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, Donald G. (Bayport, NY); Davis, Mary S. (Wading River, NY)

1990-01-01T23:59:59.000Z

360

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

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)

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

362

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

363

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 ...............

364

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

365

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 ................................................

366

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..........................

367

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..........................

368

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 ................................................

369

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..........................

370

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

371

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

372

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..........................

373

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 ...............

374

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..........................

375

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..........................

376

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..........................

377

Speciation of heavy metals in cement-stabilized waste forms: A micro-spectroscopic study  

E-Print Network (OSTI)

Assuring safe disposal and long-term storage of haz- ardous and radioactive wastes represents a primary en- vironmental task of industrial societies. The long-term disposal of the hazardous wastes is associatedSpeciation of heavy metals in cement-stabilized waste forms: A micro-spectroscopic study M. Vespa

378

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...

379

Enhancements to System for Tracking Radioactive Waste Shipments...  

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

now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track...

380

EIS-0286: Hanford Solid (Radioactive and Hazardous) Waste Program  

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

The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) analyzes the proposed waste management practices at the Hanford Site.

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

Geopolymeric Agent for Immobilization of Radioactive Ashes after Biomass Burning  

Science Journals Connector (OSTI)

Solidification of low-level radioactive wastes obtained after biomass burning was studied. Two solidification modes using Portland...- 6 g cm- 2 day- 1.... Thus, su...

A. D. Chervonnyi; N. A. Chervonnaya

2003-03-01T23:59:59.000Z

382

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...

383

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

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

of scientific research experiments at Oak Ridge National Lab. By accelerating intense beams of light ions to strike a target, the facility creates short-lived, radioactive nuclei...

384

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

385

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

386

Natural Ores as Oxygen Carriers in Chemical Looping Combustion  

Science Journals Connector (OSTI)

Natural Ores as Oxygen Carriers in Chemical Looping Combustion ... Chemical looping combustion (CLC) is a combustion technology that utilizes oxygen from oxygen carriers (OC), such as metal oxides, instead of air to combust fuels. ...

Hanjing Tian; Ranjani Siriwardane; Thomas Simonyi; James Poston

2013-01-02T23:59:59.000Z

387

Frontiers in Assessing the Role of Chemical Speciation and Natural Attenuation on the Bioavailability  

E-Print Network (OSTI)

1 Frontiers in Assessing the Role of Chemical Speciation and Natural Attenuation components. Applications of these techniques to assess metal and organic chemical sorption/release, natural widely employed to provide an indirect assessment ofchemical speciation and association ofcontaminants

Sparks, Donald L.

388

Metal-Air Batteries  

SciTech Connect

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

389

Fire hazard analysis of the radioactive mixed waste trenchs  

SciTech Connect

This Fire Hazards Analysis (FHA) is intended to assess comprehensively the risk from fire associated with the disposal of low level radioactive mixed waste in trenches within the lined landfills, provided by Project W-025, designated Trench 31 and 34 of the Burial Ground 218-W-5. Elements within the FHA make recommendations for minimizing risk to workers, the public, and the environment from fire during the course of the operation`s activity. Transient flammables and combustibles present that support the operation`s activity are considered and included in the analysis. The graded FHA contains the following elements: description of construction, protection of essential safety class equipment, fire protection features, description of fire hazards, life safety considerations, critical process equipment, high value property, damage potential--maximum credible fire loss (MCFL) and maximum possible fire loss (MPFL), fire department/brigade response, recovery potential, potential for a toxic, biological and/or radiation incident due to a fire, emergency planning, security considerations related to fire protection, natural hazards (earthquake, flood, wind) impact on fire safety, and exposure fire potential, including the potential for fire spread between fire areas. Recommendations for limiting risk are made in the text of this report and printed in bold type. All recommendations are repeated in a list in Section 18.0.

McDonald, K.M. [Westinghouse Hanford Co., Richland, WA (United States)

1995-04-27T23:59:59.000Z

390

DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS  

SciTech Connect

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

391

Testing atomic mass models with radioactive beams  

SciTech Connect

Significantly increased yields of new or poorly characterized exotic isotopes that lie far from beta-decay stability can be expected when radioactive beams are used to produce these nuclides. Measurements of the masses of these new species are very important. Such measurements are motivated by the general tendency of mass models to diverge from one another upon excursions from the line of beta-stability. Therefore in these regions (where atomic mass data are presently nonexistent or sparse) the models can be tested rigorously to highlight the features that affect the quality of their short-range and long-range extrapolation properties. Selection of systems to study can be guided, in part, by a desire to probe those mass regions where distinctions among mass models are most apparent and where yields of exotic isotopes, produced via radioactive beams, can be optimized. Identification of models in such regions that have good predictive properties will aid materially in guiding the selection of additional experiments which ultimately will provide expansion of the atomic mass database for further refinement of the mass models. 6 refs., 5 figs.

Haustein, P.E.

1989-01-01T23:59:59.000Z

392

Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal  

SciTech Connect

This report presents a history of commercial low-level radioactive waste disposal in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the last decade to ensure the safe disposal of low-level radioactive waste in the 1990s and beyond. These steps include the issuance of comprehensive State and Federal regulations governing the disposal of low-level radioactive waste, and the enactment of Federal laws making States responsible for the disposal of such waste generated within their borders.

Not Available

1994-08-01T23:59:59.000Z

393

Synthesis Of Fluorescent Metal Nanoclusters  

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

Synthesis Of Fluorescent Metal Nanoclusters Synthesis Of Fluorescent Metal Nanoclusters Fluorescent metal nanoclusters were prepared. Available for thumbnail of Feynman Center...

394

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 ................................................

395

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

396

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..............................................................

397

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 ................................................

398

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

399

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 ................................................

400

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 ................................................

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

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

402

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

403

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

404

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 ................................................

405

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

406

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

407

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

408

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 ................................................

409

NATURAL GAS MARKET ASSESSMENT  

E-Print Network (OSTI)

CALIFORNIA ENERGY COMMISSION NATURAL GAS MARKET ASSESSMENT PRELIMINARY RESULTS In Support.................................................................................... 6 Chapter 2: Natural Gas Demand.................................................................................................. 10 Chapter 3: Natural Gas Supply

410

,"Missouri Natural Gas Summary"  

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

Gas Wells (MMcf)","Missouri Natural Gas Gross Withdrawals from Oil Wells (MMcf)","Missouri Natural Gas Gross Withdrawals from Shale Gas (Million Cubic Feet)","Missouri Natural...

411

The Nature of Glass Leaching  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

G. L. McVay; C. Q. Buckwalter

412

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

413

MECS 2006- Fabricated Metals  

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

Manufacturing Energy and Carbon Footprint for Fabricated Metals (NAICS 332) Sector with Total Energy Input, October 2012 (MECS 2006)

414

Short Communication Kinetics and thermodynamics of heavy metal ions sequestration onto novel  

E-Print Network (OSTI)

biomasses had been chosen and utilized by researchers to sequester toxic heavy metal ions from industrialShort Communication Kinetics and thermodynamics of heavy metal ions sequestration onto novel is generally considered as the most toxic metal in natural ecosystems (Clarkson, 1993). Over the years, various

Gong, Jian Ru

415

Deposition of Contiguous Metal Adlayer on Transition Metal Nanostructu...  

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

and Abstract Primary Lab Date Application 20100099012 Application 20100099012 Electrocatalyst Synthesized by Depositing a Contiguous Metal Adlayer on Transition Metal...

416

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

417

Combustible radioactive waste treatment by incineration and chemical digestion  

SciTech Connect

A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste.

Stretz, L.A.; Crippen, M.D.; Allen, C.R.

1980-05-28T23:59:59.000Z

418

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

419

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

420

A model approach to radioactive waste disposal at Sellafield  

E-Print Network (OSTI)

A model approach to radioactive waste disposal at Sellafield R. 5. Haszeldine* and C. Mc of the great environmentalproblems of our age is the safe disposal of radioactive waste for geological time periods. Britain is currently investigating a potential site for underground burial of waste, near

Haszeldine, Stuart

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

Radiation issues in a radioactive ion decay ring  

Science Journals Connector (OSTI)

......disposed of as radioactive waste. Table 3. Specific activity...effective dose per unit release for long-term water releases for two critical...et al. The acceleration and storage of radioactive ions for Neutrino...and 18Ne) circulating in a storage ring. Since the beam is not......

M. Magistris; M. Silari

2005-12-20T23:59:59.000Z

422

Characterization of plutonium in Maxey Flats radioactive trench leachates  

SciTech Connect

Plutonium in trench leachates at the Maxey Flats radioactive waste disposal site exists as dissolved species, primarily complexes of the tetravalent ion with strong organic ligands such as ethylenediaminetetraacetic acid. The complexes are not sorbed well by sediment and are only partly precipitated by ferric hydroxide. These results indicate the importance of isolating radioactive waste from organic matter. 3 tables.

Cleveland, J.M.; Rees, T.F.

1981-06-26T23:59:59.000Z

423

Fluorescent Functionalized Mesoporous Silica for Radioactive Material Extraction  

SciTech Connect

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

424

Enhancements to System for Tracking Radioactive Waste Shipments Benefit  

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

Enhancements to System for Tracking Radioactive Waste Shipments Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. CARLSBAD, N.M. - EM's Carlsbad Field Office (CBFO) recently deployed a new version of the Transportation Tracking and Communication System (TRANSCOM) that is compatible with mobile devices, including smartphones. The recent enhancement, TRANSCOM version 3.0, improves the user interface

425

Security for Radioactive Sources: Fact Sheet | National Nuclear Security  

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

for Radioactive Sources: Fact Sheet | National Nuclear Security for Radioactive Sources: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Security for Radioactive Sources: Fact Sheet Fact Sheet Security for Radioactive Sources: Fact Sheet Mar 23, 2012 Radioactive materials are a critical and beneficial component of global

426

Atlantic Interstate Low-Level Radioactive Waste Management Compact (South  

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

Atlantic Interstate Low-Level Radioactive Waste Management Compact Atlantic Interstate Low-Level Radioactive Waste Management Compact (South Carolina) Atlantic Interstate Low-Level Radioactive Waste Management Compact (South Carolina) < Back Eligibility Utility Commercial Agricultural Investor-Owned Utility Industrial Construction Municipal/Public Utility Local Government Installer/Contractor Rural Electric Cooperative Tribal Government Program Info Start Date 1986 State South Carolina Program Type Environmental Regulations Siting and Permitting Provider Atlantic Compact Commission The Atlantic (Northeast) Interstate Low-Level Radioactive Waste Management Compact is a cooperative effort to plan, regulate, and administer the disposal of low-level radioactive waste in the region. The states of Connecticut, New Jersey, and South Carolina are party to this compact

427

First of Hanford's Highly Radioactive Sludge Moved Away from River |  

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

First of Hanford's Highly Radioactive Sludge Moved Away from First of Hanford's Highly Radioactive Sludge Moved Away from River First of Hanford's Highly Radioactive Sludge Moved Away from River July 13, 2012 - 12:00pm Addthis Media Contacts Geoff Tyree, DOE Geoffrey.Tyree@rl.doe.gov 509-376-4171 Dee Millikin, CH2M HILL Dee_Millikin@rl.doe.gov 509-376-1297 RICHLAND, Wash. - Workers have started moving highly radioactive material, called sludge, away from the Columbia River, marking a significant milestone in the U. S. Department of Energy (DOE)'s cleanup of the Hanford Site in Washington State. Today, DOE contractor CH2M HILL Plateau Remediation Company (CH2M HILL) safely transferred the first large container of highly radioactive sludge from a basin next to a former plutonium production reactor to dry storage in the center of the site. Today's transfer is the first of six shipments

428

Radioactive Materials at SSRL | Stanford Synchrotron Radiation Lightsource  

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

Radioactive Materials at SSRL Radioactive Materials at SSRL Contact Information SSRL Safety Officer (650) 926-3861 SSRL Radiation Protection Group (650) 926-4299 SSRLRadMat@SLAC.STANFORD.EDU Throughout the course of an SSRL Experimental Run, there are requests from users to transport and use small amounts of radioactive material in their experiments, either as stand alone samples or in a matrix of other materials. There is no minimum quantity for declaring the use of radioactive samples at SSRL. The purpose of this procedure is to enable Users, SSRL and SLAC staff to know what radiological controls will be implemented for these materials, based on the isotope, its toxicity risk and radiological controls. Radioactive materials at SSRL are classified into 4 classification Groups based on the radiotoxicity tables, see below.

429

Mission Plan for the Civilian Radioactive Waste Management Program |  

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

Mission Plan for the Civilian Radioactive Waste Management Program Mission Plan for the Civilian Radioactive Waste Management Program Mission Plan for the Civilian Radioactive Waste Management Program Summary In response to the the requirement of the Nuclear Waste Policy Act of 1982, the Office of Civilian Radioactive Waste Management in the Department of Energy (DOE) has prepared this Mission Plan for the Civilian Radioactive Waste Management Program. The Mission Plan is divided into two parts. Part I describes the overall goals, objectives, and strategy for the disposal of spent nuclear fuel and high-level waste. It explains that, to meet the directives of the Nuclear Waste Policy Act, the DOE intends to site, design, construct., and start operating a mined geologic repository by January 31, 1998. The Act specifies that the costs of these

430

Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) |  

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

Low-Level Radioactive Waste Disposal Regional Facility Act Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) < Back Eligibility Utility Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Program Info State Pennsylvania Program Type Environmental Regulations Fees This act establishes a low-level radioactive waste disposal regional facility siting fund that requires nuclear power reactor constructors and operators to pay to the Department of Environmental Resources funds to be utilized for disposal facilities. This act ensures that nuclear facilities and the Department comply with the Low-Level Radioactive Disposal Act. The regional facility siting fund is used for reimbursement of expenses

431

DOE - Safety of Radioactive Material Transportation  

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

What are full-scale tests? What are scale-model tests? What is computer analysis? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. A packaging is certified when it can survive a sequence of impact, crush, puncture, fire, and immersion tests designed to replicate transport accident conditions. Type B Packages must meet the testing requirements of: Compliance Testing, as defined in 10 CFR Part 71.85 and 10 CFR Part 71.87 Normal Conditions of Transport, Ten tests as defined in 10 CFR Part 71.71 Hypothetical Accident Conditions, Six tests as defined in 10 CFR Part 71.73 The ability of radioactive material packages to withstand testing environments can be demonstrated by full-scale testing, scale-model

432

DOE - Safety of Radioactive Material Transportation  

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

Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Dose Rate Calculator Click to use calculator. This tool calculates a dose rate (DR) at 2 meters (about 6 ft) from the surface of a package containing radioactive material IF you know the dose rate at 1 meter (about 3 ft). It will also calculate the reverse; DR at 1 meter if you know the DR at 2 meters. These two distances are used by the Nuclear Regulatory Commission to define acceptable dose rates for packages. Dose (Rad) Biological Effect < 5 rad No immediate observable effects 5 - 50 rad Slight blood changes may be detected by medical evaluation 50 - 150 rad Slight blood changes will be noted and likely symptoms of nausea, fatigue, vomiting, etc.

433

Astronomy with Radioactivities: Chapter 9, Nuclear Reactions  

E-Print Network (OSTI)

Nuclear reaction rates determine the abundances of isotopes in stellar burning processes. A multitude of reactions determine the reaction flow pattern which is described in terms of reaction network simulations. The reaction rates are determined by laboratory experiments supplemented by nuclear reaction and structure theory. We will discuss the experimental approach as well as the theoretical tools for obtaining the stellar reaction rates. A detailed analysis of a reaction is only possible for a few selected cases which will be highlighted in this section. The bulk of nuclear reaction processes is however described in terms of a statistical model approach, which relies on global nuclear structure and reaction parameters such as level density and mass and barrier penetration, respectively. We will discuss a variety of experimental facilities and techniques used in the field, this includes low energy stable beam experiments, measurements at radioactive beam accelerators, and neutron beam facilities.

M. Wiescher; T. Rauscher

2010-11-01T23:59:59.000Z

434

Radioactive Waste Management Complex performance assessment: Draft  

SciTech Connect

A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

1990-06-01T23:59:59.000Z

435

Submersible purification system for radioactive water  

DOE Patents (OSTI)

A portable, submersible water purification system for use in a pool of water containing radioactive contamination includes a prefilter for filtering particulates from the water. A resin bed is then provided for removal of remaining dissolved, particulate, organic, and colloidal impurities from the prefiltered water. A sterilizer then sterilizes the water. The prefilter and resin bed are suitably contained and are submerged in the pool. The sterilizer is water tight and located at the surface of the pool. The water is circulated from the pool through the prefilter, resin bed, and sterilizer by suitable pump or the like. In the preferred embodiment, the resin bed is contained within a tank which stands on the bottom of the pool and to which a base mounting the prefilter and pump is attached. An inlet for the pump is provided adjacent the bottom of the pool, while the sterilizer and outlet for the system is located adjacent the top of the pool.

Abbott, Michael L. (Fort Collins, CO); Lewis, Donald R. (Pocatello, ID)

1989-01-01T23:59:59.000Z

436

Room air monitor for radioactive aerosols  

DOE Patents (OSTI)

A housing assembly for use with a room air monitor for simultaneous collection and counting of suspended particles includes a casing containing a combination detector-preamplifier system at one end, a filter system at the other end, and an air flow system consisting of an air inlet formed in the casing between the detector-preamplifier system and the filter system and an air passageway extending from the air inlet through the casing and out the end opposite the detector-preamplifier combination. The filter system collects suspended particles transported directly through the housing by means of the air flow system, and these particles are detected and examined for radioactivity by the detector-preamplifier combination. 2 figs.

Balmer, D.K.; Tyree, W.H.

1987-03-23T23:59:59.000Z

437

Standard guide for sampling radioactive tank waste  

E-Print Network (OSTI)

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

438

17 - Immobilisation of Radioactive Waste in Glass  

Science Journals Connector (OSTI)

Radionuclide immobilisation mechanisms are examined for vitreous wasteforms. Both borosilicate and phosphate glasses are described in detail, including the ability of cations to enter into the glass network structure. The role of various cations is considered, including boron, intermediates, and modifiers and elements difficult to immobilise. Selection rules for designing nuclear wasteform silicate glasses are outlined. Glass composite materials to immobilise glass-immiscible waste components are discussed. Both one- and two-stage vitrification technologies are described. An overview is given of the development of vitrification technology, including current operational data on radioactive waste vitrification facilities. Calcination processes are considered in detail, including typical properties of waste calcination products. Recent developments in vitrification are given, including descriptions of cold crucible induction-heated melters and in situ vitrification. Limitations caused by radionuclide volatility are examined. Acceptance criteria are given for vitreous wasteforms.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

439

DOE - Office of Legacy Management -- Curtiss-Wright Corp Metals Processing  

Office of Legacy Management (LM)

Curtiss-Wright Corp Metals Curtiss-Wright Corp Metals Processing Div - NY 40 FUSRAP Considered Sites Site: Curtiss-Wright Corp., Metals Processing Div. (NY.40 ) Eliminated from further consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: Curtiss-Wright Corporation NY.40-1 Location: Buffalo , New York NY.40-1 Evaluation Year: 1987 NY.40-2 Site Operations: Performed casting, forging, and extrusion operations for the U.S. Air Force and the AEC. NY.40-1 NY.40-2 Site Disposition: Eliminated - Referred to DOD NY.40-2 NY.40-3 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium NY.40-1 Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP - Referred to DOD NY.40-2

440

Market Digest: Natural Gas  

Reports and Publications (EIA)

The Energy Information Administration's Natural Gas Market Digest provides information and analyses on all aspects of natural gas markets.

2014-01-01T23:59:59.000Z

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.


441

Evaluation of Trenchless Installation Technology for Radioactive Wastewater Piping Applications  

SciTech Connect

The U.S. Department of Energy (DOE) Office of Environmental Management (EM) cleanup mission at Oak Ridge National Laboratory (ORNL) includes dispositioning facilities, contaminated legacy materials/waste, and contamination sources and remediation of soil under facilities, groundwater, and surface water to support final Records of Decision (RODs). The Integrated Facilities Disposition Project (IFDP) is a roughly $15B project for completion of the EM mission at Oak Ridge, with a project duration of up to 35 years. The IFDP Mission Need Statement - Critical Decision-0 (CD-0) - was approved by DOE in July 2007, and the IFDP Alternative Selection and Cost Range - Critical Decision-1 (CD-1) - was approved in November 2008. The IFDP scope includes reconfiguration of waste collection and treatment systems as needed to complete the IFDP remediation and decontamination and decommissioning (D&D) missions in a safe and cost-effective manner while maintaining compliance with all governing regulations and bodies and preserving the support of continuing operations at ORNL. A step in the CD-1 approval process included an external technical review (ETR) of technical approaches proposed in the CD-1 document related to the facility reconfiguration for the ORNL radioactive waste and liquid low-level waste management systems. The ETR team recommended that the IFDP team consider the use of trenchless technologies for installing pipelines underground in and around contaminated sites as part of the alternatives evaluations required in support of the CD-2 process. The team specifically recommended evaluating trenchless technologies for installing new pipes in existing underground pipelines as an alternative to conventional open trench installation methods. Potential benefits could include reduction in project costs, less costly underground piping, fewer disruptions of ongoing and surface activities, and lower risk for workers. While trenchless technologies have been used extensively in the sanitary sewer and natural gas pipeline industries, they have been used far less in contaminated environments. Although trenchless technologies have been used at ORNL in limited applications to install new potable water and gas lines, the technologies have not been used in radioactive applications. This study evaluates the technical risks, benefits, and economics for installing gravity drained and pressurized piping using trenchless technologies compared to conventional installation methods for radioactive applications under ORNL geological conditions. A range of trenchless installation technologies was reviewed for this report for general applicability for replacing existing contaminated piping and/or installing new pipelines in potentially contaminated areas. Installation methods that were determined to have potential for use in typical ORNL contaminated environments were then evaluated in more detail for three specific ORNL applications. Each feasible alternative was evaluated against the baseline conventional open trench installation method using weighted criteria in the areas of environment, safety, and health (ES&H); project cost and schedule; and technical operability. The formulation of alternatives for evaluation, the development of selection criteria, and the scoring of alternatives were performed by ORNL staff with input from vendors and consultants. A description of the evaluation methodology and the evaluation results are documented in the following sections of this report.

Robinson, Sharon M [ORNL; Jubin, Robert Thomas [ORNL; Patton, Bradley D [ORNL; Sullivan, Nicholas M [ORNL; Bugbee, Kathy P [ORNL

2009-09-01T23:59:59.000Z

442

s.haszeldine@ed.ac.uk Radioactive waste Cumbria 6, 7 Sept 2012 1 Geological disposal of radioactive  

E-Print Network (OSTI)

of Edinburgh Professor of Geology Nuclear waste ­ exists and has to be solved Nuclear power ­ is likely_and_Copeland.html #12;Nuclear power s.haszeldine@ed.ac.uk Radioactive waste Cumbria 6, 7 Sept 2012 2 First civil nuclear waste Cumbria 6, 7 Sept 2012 15 Thus, the nuclear industry has calculated that the escape of radioactive

443

Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal  

SciTech Connect

This report presents a history of commercial low-level radioactive waste management in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the 1980s to ensure the safe disposal of low-level waste in the 1990s and beyond. These steps include the issuance of Title 10 Code of Federal Regulations Part 61, Licensing Requirements for the Land Disposal of Radioactive Waste, the Low-Level Radioactive Waste Policy Act of 1980, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and steps taken by states and regional compacts to establish additional disposal sites. 42 refs., 13 figs., 1 tab.

Not Available

1990-10-01T23:59:59.000Z

444

E-Print Network 3.0 - administered radioactive material Sample...  

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

10 The New Orphaned Radioactive Sources Program in the United States International Conference on the Safety of Radiation Sources and the Security of Radioactive Summary: on the...

445

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone  

E-Print Network (OSTI)

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone formations, the French national radioactive waste management agency (ANDRA) started in 2000

Boyer, Edmond

446

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal...  

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

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Christine...

447

Extraction process for removing metallic impurities from alkalide metals  

DOE Patents (OSTI)

A development is described for removing metallic impurities from alkali metals by employing an extraction process wherein the metallic impurities are extracted from a molten alkali metal into molten lithium metal due to the immiscibility of the alkali metals in lithium and the miscibility of the metallic contaminants or impurities in the lithium. The purified alkali metal may be readily separated from the contaminant-containing lithium metal by simple decanting due to the differences in densities and melting temperatures of the alkali metals as compared to lithium.

Royer, L.T.

1987-03-20T23:59:59.000Z

448

The Extraction of Heavy Metals by Means of a New Electrolytic Method  

SciTech Connect

The extraction of metals in known metallurgical methods is pursued on the basis of separating as much as possible the desired metal's content from the ore concentrate, in the most economical manner. When these principles are also applied to the extraction of heavy metals, the related environmental factors do not readily meet with requirements. Today, an acceptable extraction technology for metals must satisfy the need to produce the deep separation of metals from their source in both economical and environmentally safe manner. This pertains to the direction of our ongoing research and development, among others in the field of environmental remediation. Earlier, we successfully addressed in an environmentally safe manner the selective extraction of radioactive isotopes from liquid radioactive wastes, produced at Armenia's Metzamor Nuclear Power Plant and implemented a functioning LRW station at the NPP. Currently, we extended our new electrodialysis-based electrolytic method in a laboratory scale, for the extraction and deep separation of different metals, including the heavy metals. Our new method, its efficiency, economy and full compliance with environmental issues will be presented.

Guiragossian, Z. G.; Martoyan, G. A.; Injeyan, S. G.; Tonikyan, S. G.; Nalbandyan, G. G.

2003-02-25T23:59:59.000Z

449

SOLID PHASE MICROEXTRACTION SAMPLING OF FIRE DEBRIS RESIDUES IN THE PRESENCE OF RADIONUCLIDE SURROGATE METALS  

SciTech Connect

The Federal Bureau of Investigation (FBI) Laboratory currently does not have on site facilities for handling radioactive evidentiary materials and there are no established FBI methods or procedures for decontaminating highly radioactive fire debris (FD) evidence while maintaining evidentiary value. One experimental method for the isolation of FD residue from radionuclide metals involves using solid phase microextraction (SPME) fibers to remove the residues of interest. Due to their high affinity for organics, SPME fibers should have little affinity for most (radioactive) metals. The focus of this research was to develop an examination protocol that was applicable to safe work in facilities where high radiation doses are shielded from the workers (as in radioactive shielded cells or ''hot cells''). We also examined the affinity of stable radionuclide surrogate metals (Co, Ir, Re, Ni, Ba, Cs, Nb, Zr and Nd) for sorption by the SPME fibers. This was done under exposure conditions that favor the uptake of FD residues under conditions that will provide little contact between the SPME and the FD material (such as charred carpet or wood that contains commonly-used accelerants). Our results from mass spectrometric analyses indicate that SPME fibers show promise for use in the room temperature head space uptake of organic FD residue (namely, diesel fuel oil, kerosene, gasoline and paint thinner) with subsequent analysis by gas chromatography (GC) with mass spectrometric (MS) detection. No inorganic forms of ignitable fluids were included in this study.

Duff, M; Keisha Martin, K; S Crump, S

2007-03-23T23:59:59.000Z

450

Sumitomo Metal Industries Ltd Sumitomo Metals | Open Energy Information  

Open Energy Info (EERE)

Sumitomo Metal Industries Ltd Sumitomo Metals Sumitomo Metal Industries Ltd Sumitomo Metals Jump to: navigation, search Name Sumitomo Metal Industries Ltd (Sumitomo Metals) Place Osaka-shi, Osaka, Japan Zip 540-0041 Sector Solar Product Engaged in the steel, engineering, and electronics businesses; works on fuel cell component technology and manufactures silicon wafers for the solar sector. References Sumitomo Metal Industries Ltd (Sumitomo Metals)[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Sumitomo Metal Industries Ltd (Sumitomo Metals) is a company located in Osaka-shi, Osaka, Japan . References ↑ "Sumitomo Metal Industries Ltd (Sumitomo Metals)" Retrieved from "http://en.openei.org/w/index.php?title=Sumitomo_Metal_Industries_Ltd_Sumitomo_Metals&oldid=351744"

451

Natural analogues of nuclear waste glass corrosion.  

SciTech Connect

This report reviews and summarizes studies performed to characterize the products and processes involved in the corrosion of natural glasses. Studies are also reviewed and evaluated on how well the corrosion of natural glasses in natural environments serves as an analogue for the corrosion of high-level radioactive waste glasses in an engineered geologic disposal system. A wide range of natural and experimental corrosion studies has been performed on three major groups of natural glasses: tektite, obsidian, and basalt. Studies of the corrosion of natural glass attempt to characterize both the nature of alteration products and the reaction kinetics. Information available on natural glass was then compared to corresponding information on the corrosion of nuclear waste glasses, specifically to resolve two key questions: (1) whether one or more natural glasses behave similarly to nuclear waste glasses in laboratory tests, and (2) how these similarities can be used to support projections of the long-term corrosion of nuclear waste glasses. The corrosion behavior of basaltic glasses was most similar to that of nuclear waste glasses, but the corrosion of tektite and obsidian glasses involves certain processes that also occur during the corrosion of nuclear waste glasses. The reactions and processes that control basalt glass dissolution are similar to those that are important in nuclear waste glass dissolution. The key reaction of the overall corrosion mechanism is network hydrolysis, which eventually breaks down the glass network structure that remains after the initial ion-exchange and diffusion processes. This review also highlights some unresolved issues related to the application of an analogue approach to predicting long-term behavior of nuclear waste glass corrosion, such as discrepancies between experimental and field-based estimates of kinetic parameters for basaltic glasses.

Abrajano, T.A. Jr.; Ebert, W.L.; Luo, J.S.

1999-01-06T23:59:59.000Z

452

Identification of Metal Reductases using Proteomic Analysis  

SciTech Connect

Central to the NABIR goal to develop the scientific basis for in situ remediation of radioactive contaminants is the fundamental understanding of microorganisms with dissimilatory metal reducing activity. In order to effectively exploit these bacteria, it is necessary to know which enzymes and pathways are involved. Additionally, it would be advantageous to understand the similarities and differences of these pathways across different bacteria for effective deployment in bioremediation, as well as to identify new microbes capable of such activities. Most approaches to identify these enzymes or enzyme complexes rely on biochemical purification to homogeneity with subsequent Nterminal sequencing of digested peptides. However, loss of activity before achieving purity often necessitates repetition of the entire process. Newly developed proteomics capabilities at PNNL allow for the identification of many proteins from a single sample through mass spectrometry analysis.

Lipton, Mary

2006-06-01T23:59:59.000Z

453

State-of-the-art report on low-level radioactive waste treatment  

SciTech Connect

An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out.

Kibbey, A.H.; Godbee, H.W.

1980-09-01T23:59:59.000Z

454

Safety and Security Technologies for Radioactive Material Shipments  

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

and Security Technologies for and Security Technologies for Radioactive Material Shipments Safety & Security Technologies Study Started in 2005 with OCRWM Funding. OCRWM funding ended in 2009. EM gave CVSA funding to finish the report. CVSA Ad Hoc RAM/Security/ITS Committee Examined current and emerging technologies for safety and security of radioactive material shipments Site visits Product reviews HMCRP HM-04 report on emerging technologies Safety & Security Technologies Study Completed several site visits to look at current technologies being used. Technologies were broken down into five categories. 1. Inspection Technologies 2. Security Technologies 3. Radioactive Material Dose Rate Measurement and

455

Management of Disused Radioactive Sealed Sources in Egypt - 13512  

SciTech Connect

The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Egypt depends on the safe and secure management of disused radioactive sealed sources. In the past years have determined the necessity to formulate and apply the integrated management program for radioactive sealed sources to assure harmless and ecological rational management of disused sealed sources in Egypt. The waste management system in Egypt comprises operational and regulatory capabilities. Both of these activities are performed under legislations. The Hot Laboratories and Waste Management Center HLWMC, is considered as a centralized radioactive waste management facility in Egypt by law 7/2010. (authors)

Mohamed, Y.T.; Hasan, M.A.; Lasheen, Y.F. [Hot Laboratories and Waste Management Center, Egyptian Atomic Energy Authority, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Egyptian Atomic Energy Authority, 11787, Cairo (Egypt)

2013-07-01T23:59:59.000Z

456

Environmental Radioactivity Study in Surface Sediments of Guacanayabo Gulf (Cuba)  

SciTech Connect

Sediment samples have been collected in the Guacanayabo gulf located in the southeast Cuba, to determinate the radioactivity levels of {sup 210}Pb, {sup 234}Th, {sup 214}Pb, {sup 137}Cs, {sup 232}Th and {sup 40}K using Low-Background Gamma Spectrometry and to evaluate its impact in the habitat of important marine species for fishery industry. The obtained results show the lowest radioactivity levels determined in Cuban marine environments. The species capture declination in the last years is not originated by radioactive pollution of the zone.

Reyes, H.; Rizo, O. Diaz; Bernal, J. L.; D'Alessandro, K.; Padilla, F.; Corrales, Y.; Casanova, O. A.; Gelen, A.; Martinez, Y.; Aguilar, J.; Arado, J. O. [Instituto Superior de Tecnologias y Ciencias Aplicadas (InSTEC), Habana 10400, POB 6163 (Cuba); Lopez-Pino, N. [Instituto Superior de Tecnologias y Ciencias Aplicadas (InSTEC), Habana 10400, POB 6163 (Cuba); Instituto de Fisica da USP, LAL, Rua do Matao, Travessa R., 187, 05508-900, SP (Brazil); Maidana, N. L. [Instituto de Fisica da USP, LAL, Rua do Matao, Travessa R., 187, 05508-900, SP (Brazil)

2009-06-03T23:59:59.000Z

457

Decontaminating metal surfaces  

DOE Patents (OSTI)

Radioactively contaminated surfaces can be electrolytically decontaminated with greatly increased efficiencies by using electrolytes containing higher than heretofore conventional amounts of nitrate, e.g., >600 g/1 of NaNO/sub 3/, or by using nitrate-containing electrolytes which are acidic, e.g., of a pH < 6.

Childs, E.L.

1984-01-23T23:59:59.000Z

458

Decontaminating metal surfaces  

DOE Patents (OSTI)

Radioactively contaminated surfaces can be electrolytically decontaminated with greatly increased efficiencies by using electrolytes containing higher than heretofore conventional amounts of nitrate, e.g.,>600 g/l of NaNO.sub.3, or by using nitrate-containing electrolytes which are acidic, e.g., of a pH<6.

Childs, Everett L. (Boulder, CO)

1984-11-06T23:59:59.000Z

459

Two stage, low temperature, catalyzed fluidized bed incineration with in situ neutralization for radioactive mixed wastes  

SciTech Connect

A two stage, low temperature, catalyzed fluidized bed incineration process is proving successful at incinerating hazardous wastes containing nuclear material. The process operates at 550{degrees}C and 650{degrees}C in its two stages. Acid gas neutralization takes place in situ using sodium carbonate as a sorbent in the first stage bed. The feed material to the incinerator is hazardous waste-as defined by the Resource Conservation and Recovery Act-mixed with radioactive materials. The radioactive materials are plutonium, uranium, and americium that are byproducts of nuclear weapons production. Despite its low temperature operation, this system successfully destroyed poly-chlorinated biphenyls at a 99.99992% destruction and removal efficiency. Radionuclides and volatile heavy metals leave the fluidized beds and enter the air pollution control system in minimal amounts. Recently collected modeling and experimental data show the process minimizes dioxin and furan production. The report also discusses air pollution, ash solidification, and other data collected from pilot- and demonstration-scale testing. The testing took place at Rocky Flats Environmental Technology Site, a US Department of Energy facility, in the 1970s, 1980s, and 1990s.

Wade, J.F.; Williams, P.M.

1995-05-17T23:59:59.000Z

460

Applications of RESRAD family of computer codes to sites contaminated with radioactive residues.  

SciTech Connect

The RESIL4D family of computer codes was developed to provide a scientifically defensible answer to the question ''How clean is clean?'' and to provide useful tools for evaluating human health risk at sites contaminated with radioactive residues. The RESRAD codes include (1) RESRAD for soil contaminated with radionuclides; (2) RESRAD-BUILD for buildings contaminated with radionuclides; (3) RESRAD-CHEM for soil contaminated with hazardous chemicals; (4) RESRAD-BASELINE for baseline risk assessment with measured media concentrations of both radionuclides and chemicals; (5) RESRAD-ECORISK for ecological risk assessment; (6) RESRAD-RECYCLE for recycle and reuse of radiologically contaminated metals and equipment; and (7) RESRAD-OFFSITE for off-site receptor radiological dose assessment. Four of these seven codes (RESRAD, RESRAD-BUILD, RESRAD-RECYCLE, and RESRAD-OFFSITE) also have uncertainty analysis capabilities that allow the user to input distributions of parameters. RESRAD has been widely used in the United States and abroad and approved by many federal and state agencies. Experience has shown that the RESRAD codes are useful tools for evaluating sites contaminated with radioactive residues. The use of RESRAD codes has resulted in significant savings in cleanup cost. Analysis of 19 site-specific uranium guidelines is discussed in the paper.

Yu, C.; Kamboj, S.; Cheng, J.-J.; LePoire, D.; Gnanapragasam, E.; Zielen, A.; Williams, W. A.; Wallo, A.; Peterson, H.

1999-10-21T23:59:59.000Z

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.


461

Assessment of radioactive wastes from a DCLL fusion reactor: Disposal in El Cabril facility  

Science Journals Connector (OSTI)

Abstract Under the Spanish Breeding Blanket Technology Programme TECNO_FUS a conceptual design of a DCLL (Dual-Coolant LithiumLead) blanket-based reactor is being revised. The dually cooled breeding zone is composed of He/LiPb and SiC as material of the liquid metal flow channel inserts. Structural materials are ferritic-martensitic steel (Eurofer) for the blanket and austenitic steel (SS316LN) for the vacuum vessel (VV) and the cryostat. In this work, radioactive wastes are assessed in order to determine if they can be disposed as low and intermediate level radioactive waste (LILW) in the Spanish near surface disposal facility of El Cabril. Also, unconditional clearance and recycling waste management options are studied. The neutron transport calculations have been performed with MCNPX code, while the ACAB code is used for calculations of the inventory of activation products and for activation analysis, in terms of waste management ratings for the options considered. Results show that the total amount of the cryostat can be disposed in El Cabril joined to the outer layer of both VV and channel inserts, whereas only concrete-made biological shield can be managed through clearance and none of the steels can be recycled. Those results are compared with those corresponding to French regulation, showing similar conclusions.

Raquel Garca; Juan Pablo Cataln; Javier Sanz

2014-01-01T23:59:59.000Z

462

NE-23 Disposal of Offsite-Generated Defense Radioactive Waste, Ventron  

Office of Legacy Management (LM)

pi/L +3 pi/L +3 *3L 52. NE-23 Disposal of Offsite-Generated Defense Radioactive Waste, Ventron FUSRAP Site Jill E. Lytle, DP-12 NE-23 The Office of Remedial Action and Waste Technology has received a request from the Technical Services Division, DOE-Oak Ridge Operations Office, for a determination of the appropriate disposal location for the material which will result from remedial action of the Ventron site in Beverly, Massachusetts. The Ventron site was used from 1942 to 1948 under contract to the ME0 and AEC for converting uranium oxide to uranium metal powder, as well as later operations involving recovery of uranium from scrap uranium and turnings from the fuel fabrication plant at Hanford, Washington. Full-scale remedial action, anticipated to result in approximately 5,000

463

PERFORMANCE TESTING OF SPRING ENERGIZED C-RINGS FOR USE IN RADIOACTIVE MATERIAL PACKAGINGS CONTAINING TRITIUM  

SciTech Connect

This paper describes the sealing performance testing and results of silver-plated inconel Spring Energized C-Rings used for tritium containment in radioactive shipping packagings. The test methodology used follows requirements of the American Society of Mechanical Engineers (ASME) summarized in ASME Pressure Vessel Code (B&PVC), Section V, Article 10, Appendix IX (Helium Mass Spectrometer Test - Hood Technique) and recommendations by the American National Standards Institute (ANSI) described in ANSI N14.5-1997. The tests parameters bound the predicted structural and thermal responses from conditions defined in the Code of Federal Regulations 10 CFR 71. The testing includes an evaluation of the effects of pressure, temperature, flange deflection, surface roughness, permeation, closure torque, torque sequencing and re-use on performance of metal C-Ring seals.

Blanton, P; Kurt Eberl, K

2007-10-23T23:59:59.000Z

464

Investigation of the possibility of using hydrogranulation in reprocessing radioactive wastes of radiochemical production facilities  

SciTech Connect

Radio-chemical production facilities are constantly accumulating liquid radioactive wastes (still residues as the result of evaporation of extraction and adsorption solutions etc.) which are a complex multicomponent mixtures. The wastes are frequently stored for extended periods of time while awaiting disposition and in some cases, and this is much worse, they are released into the environment. In this report, I would like to draw your attention to some results we have obtained from investigations aimed at simplifying handing of such wastes by the precipitation of hard to dissolve metal hydroxides, the flocculation of the above into granules with the help of surface-active agents (in this case a polyacrylamide - PAA), quickly precipitated and easily filtered. The precipitate may be quickly dried and calcinated, if necessary, and transformed into a dense oxide sinter. In other words it may be transformed into a material convenient for storage or burial.

Revyakin, V.; Borisov, L.M. [All Russian Scientific and Research Institute of Non-Organic Materials, Moscow (Russian Federation)

1996-05-01T23:59:59.000Z

465

Photoactivated metal removal  

SciTech Connect

The authors propose the use of photochromic dyes as light activated switches to bind and release metal ions. This process, which can be driven by solar energy, can be used in environmental and industrial processes to remove metals from organic and aqueous solutions. Because the metals can be released from the ligands when irradiated with visible light, regeneration of the ligands and concentration of the metals may be easier than with conventional ion exchange resins. Thus, the process has the potential to be less expensive than currently used metal extraction techniques. In this paper, the authors report on their studies of the metal binding of spirogyran dyes and the hydrolytic stability of these dyes. They have prepared a number of spirogyrans and measured their binding constants for calcium and magnesium. They discuss the relationship of the structure of the dyes to their binding strengths. These studies are necessary towards determining the viability of this technique.

Nimlos, M.R.; Filley, J.; Ibrahim, M.A.; Watt, A.S.; Blake, D.M.

1999-07-01T23:59:59.000Z

466

Metal atomization spray nozzle  

DOE Patents (OSTI)

A spray nozzle for a magnetohydrodynamic atomization apparatus has a feed passage for molten metal and a pair of spray electrodes mounted in the feed passage. The electrodes, diverging surfaces which define a nozzle throat and diverge at an acute angle from the throat. Current passes through molten metal when fed through the throat which creates the Lorentz force necessary to provide atomization of the molten metal. 6 figures.

Huxford, T.J.

1993-11-16T23:59:59.000Z

467

Advanced technologies for decontamination and conversion of scrap metals  

SciTech Connect

Recycle of radioactive scrap metals (RSM) from decommissioning of DOE uranium enrichment and nuclear weapons manufacturing facilities is mandatory to recapture the value of these metals and avoid the high cost of disposal by burial. The scrap metals conversion project detailed below focuses on the contaminated nickel associated with the gaseous diffusion plants. Stainless steel can be produced in MSC`s vacuum induction melting process (VIM) to the S30400 specification using nickel as an alloy constituent. Further the case alloy can be rolled in MSC`s rolling mill to the mechanical property specification for S30400 demonstrating the capability to manufacture the contaminated nickel into valuable end products at a facility licensed to handle radioactive materials. Bulk removal of Technetium from scrap nickel is theoretically possible in a reasonable length of time with the high calcium fluoride flux, however the need for the high temperature creates a practical problem due to flux volatility. Bulk decontamination is possible and perhaps more desirable if nickel is alloyed with copper to lower the melting point of the alloy allowing the use of the high calcium fluoride flux. Slag decontamination processes have been suggested which have been proven technically viable at the Colorado School of Mines.

Muth, T.R. [Manufacturing Sciences Corp., Oak Ridge, TN (United States); Moore, J.; Olson, D.; Mishra, B. [Colorado School of Mines, Golden, CO (United States)

1994-12-31T23:59:59.000Z

468

Determination of dispersivities from a natural-gradient dispersion test  

E-Print Network (OSTI)

, and radioactive wastes. Contaminant hydrogeology is presently a focal point in the realm of hydrologic modeling. Generally, models are designed to represent simplified versions of reality and The style and format of this document was taken from the Journal... dispersivities, v ia a graphical approach, from a natural-gradient dispersion test in which artificial pollution was injected into an aquifer. The dispersion test was conducted by Sud icky et al. (1983) in order to characterize the dispersive properties...

Hoover, Caroline Marie

1985-01-01T23:59:59.000Z

469

Fabricated Metals (2010 MECS)  

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

Manufacturing Energy and Carbon Footprint for Fabricated Metals Sector (NAICS 332) Energy use data source: 2010 EIA MECS (with adjustments) Footprint Last Revised: February 2014

470

EMSL - trace metals  

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

trace-metals en Microbial Reductive Transformation of Phyllosilicate Fe(III) and U(VI) in Fluvial Subsurface Sediments. http:www.emsl.pnl.govemslwebpublications...

471

Measurements of natural radioactivity and radon exhalation rates from different brands of cement used in Pakistan  

Science Journals Connector (OSTI)

......these radionuclides in large amounts of waste products used in the cement manufacturing, like phosphogypsum, coal fly ash, shale ash, some rare minerals and so on. Fly ash is obtained from coal-fired power plants and certainly contains......

S. A. Mujahid; A. Rahim; S. Hussain; M. Farooq

2008-06-01T23:59:59.000Z

472

Public exposure to hazards associated with natural radioactivity in open-pit mining in Ghana  

Science Journals Connector (OSTI)

......uranium and non-uranium mines(2,4...the long-lived uranium/radium and thorium...made between the standard and the sample...Anglogold Ashanti. Review of Operations...Community Development Plan, Iduapriem and...International Basic Safety Standards (BSS) for protection......

E. O. Darko; A. Faanu; A. R. Awudu; G. Emi-Reynolds; J. Yeboah; O. C. Oppon; E. H. K. Akaho

2010-01-01T23:59:59.000Z

473

Natural radioactivity in tap waters of Eastern Black Sea region of Turkey  

Science Journals Connector (OSTI)

......and an appreciable fraction is deposited in the bone, the remaining fraction being distributed...obvious example. The release of 137Cs is estimated...Chernobyl reactor fire(3). The Chernobyl...greatest portion of airborne 222Rn from water...Chernobyl nuclear reactor fire. REFERENCES 1......

U. evik; N. Damla; G. Karahan; N. elebi; A. I. Kobya

2006-04-01T23:59:59.000Z

474

Public exposure to hazards associated with natural radioactivity in open-pit mining in Ghana  

Science Journals Connector (OSTI)

......addition, the wastes are in most...monitoring and control of NORMS in...monitoring and control of NORMS in...collected from the plant areas and other...tailings from the wastes dumps. The...wells and water treatment plants for...the detector system at the peak...for adults integrated over a period......

E. O. Darko; A. Faanu; A. R. Awudu; G. Emi-Reynolds; J. Yeboah; O. C. Oppon; E. H. K. Akaho

2010-01-01T23:59:59.000Z

475

Natural gamma radioactivity in the villages of Kanyakumari District, Tamil Nadu, India  

Science Journals Connector (OSTI)

......Terrestrial gamma radiation dose rate is also an important...contribution to the average dose rate received by the...population(6,7). The estimation of radiation dose distribution is important...side (Gulf of Mannar/Bay of Bengal coast). The district......

Jeni Chandar Padua; M. R. Basil Rose

2013-08-01T23:59:59.000Z

476

High Naturally Occurring Radioactivity in Fossil Groundwater from the Middle East  

Science Journals Connector (OSTI)

226Ra, 228Ra, and 224Ra?223Ra isotopes were determined by a radon counter (21), ? spectrometer, and delayed coincidence ? counter (22), respectively (see the Supporting Information, Supplementary Text S1). ... This study was supported by the U.S. Agency for International Development, by the Bureau for Global Programs, Field Support and Research, and by the Center for Economic Growth and Agriculture Development, The Middle East Regional Cooperation program (MERC Project M25-060). ... The second series of papers (II) will be dealing with desalination projects in the country. ...

Avner Vengosh; Daniella Hirschfeld; David Vinson; Gary Dwyer; Hadas Raanan; Omar Rimawi; Abdallah Al-Zoubi; Emad Akkawi; Amer Marie; Gustavo Haquin; Shikma Zaarur; Jiwchar Ganor

2009-02-19T23:59:59.000Z

477

Natural radioactivity in tap waters of Eastern Black Sea region of Turkey  

Science Journals Connector (OSTI)

......source for ionising radiation in daily life as far as normal background...Sample collection The water demand is supplied by surface water...Algeria (2.6-14 Bq l1) and Egypt (0.074-2.33 Bq l1...water in some areas of Upper Egypt. Turkish J. Eng. Environ......

U. evik; N. Damla; G. Karahan; N. elebi; A. I. Kobya

2006-04-01T23:59:59.000Z

478

Remedial actions at the former Vitro Rare Metals plant site, Canonsburg, Washington County, Pennsylvania. Final Environmental Impact Statement. Volume I  

SciTech Connect

The environmental impacts associated with remedial actions in connection with residual radioactive materials remaining at the inactive uranium processing site located in Canonsburg, Washington County, Pennsylvania are evaluated. The Canonsburg site is an 18.5-acre property that was formerly owned by the Vitro Rare Metals Company. The expanded Canonsburg site would be 30-acre property that would include the Canonsburg site (the former Vitro Rare Metals plant), seven adjacent private houses, and the former Georges Pottery property. During the period 1942 through 1957 the Vitro Manufacturing Company and its successor, the Vitro Corporation of America, processed onsite residues and ores, and government-owned ores, concentrates, and scraps to extract uranium and other rare metals. The Canonsburg site is now the Canon Industrial Park. In addition to storing the residual radioactive materials of this process at the Canonsburg site, about 12,000 tons of radioactively contaminated materials were transferred to a railroad landfill in Burrell Township, Indiana County, Pennsylvania. This Canonsburg FEIS evaluates five alternatives for removing the potential public health hazard associated with the radioactively contaminated materials. In addition to no action, these alternatives involve various combinations of stabilization of the radioactively contaminated materials in place or decontamination of the Canonsburg and Burrell sites by removing the radioactively contaminated materials to another location. In addition to the two sites mentioned, a third site located in Hanover Township, Washington County, Pennsylvania has been considered as a disposal site to which the radioactively contaminated materials presently located at either of the other two sites might be moved.

Not Available

1983-07-01T23:59:59.000Z

479

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

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

High-Activity Radioactive Materials Removed From Mexico | National Nuclear High-Activity Radioactive Materials Removed From Mexico | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > High-Activity Radioactive Materials Removed From Mexico Press Release High-Activity Radioactive Materials Removed From Mexico Nov 15, 2013 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA)

480

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

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

00: Managing Treatment, Storage, and Disposal of Radioactive 00: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste SUMMARY This EIS evaluates the potential 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 from nuclear defense and research activities at a variety of sites around the United States. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 7, 2011 EIS-0200-SA-03: Supplement Analysis Treatment of Transuranic Waste at the Idaho National Laboratory, Carlsbad Field Office March 7, 2008 EIS-0200: Amendment to the Record of Decision Treatment and Storage of Transuranic Waste

Note: This page contains sample records for the topic "naturally radioactive metallic" from the National Library of EnergyBeta (NLEBeta).
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481

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 Northwest Interstate Compact on Low-Level Radioactive Waste Management (Multiple States) Northwest Interstate Compact on Low-Level Radioactive Waste Management (Multiple States) < Back Eligibility Utility Fed. Government Commercial Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Rural Electric Cooperative Tribal Government Institutional Nonprofit Program Info Start Date 1981 State Alaska Program Type Siting and Permitting Provider Northwest Interstate Compact The Northwest Interstate Compact on Low-Level Radioactive Waste Management, enacted in 1981, was ratified by Congress in 1985. The Compact is a cooperative effort of the party states to protect their citizens, and maintain and enhance economic viability, while sharing the responsibilities

482

EM Employs Innovative Technology to Remove Radioactive Sludge | Department  

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

Employs Innovative Technology to Remove Radioactive Sludge Employs Innovative Technology to Remove Radioactive Sludge EM Employs Innovative Technology to Remove Radioactive Sludge September 1, 2012 - 12:00pm Addthis Testing and equipment simulations ensure first-of-a-kind technological processes for sludge removal can be conducted safely and efficiently. Testing and equipment simulations ensure first-of-a-kind technological processes for sludge removal can be conducted safely and efficiently. RICHLAND, Wash. - The Richland Operations Office and contractor CH2M HILL Plateau Remediation Company successfully removed a portion of a highly radioactive sludge from underwater storage in a large basin adjacent to the K West reactor at the Hanford site this month. In that milestone, workers removed sludge originating from knock-out pots,