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1

Depleted Uranium  

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

Depleted Uranium Depleted Uranium Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Depleted Uranium Depleted uranium is uranium that has had some of its U-235 content removed. Over the last four decades, large quantities of uranium were processed by gaseous diffusion to produce uranium having a higher concentration of uranium-235 than the 0.72% that occurs naturally (called "enriched" uranium) for use in U.S. national defense and civilian applications. "Depleted" uranium is also a product of the enrichment process. However, depleted uranium has been stripped of some of its natural uranium-235 content. Most of the Department of Energy's (DOE) depleted uranium inventory contains between 0.2 to 0.4 weight-percent uranium-235, well

2

Environmental Impacts of Options for Disposal of Depleted Uranium...  

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

study by Oak Ridge National Laboratory evaluated the acceptability of several depleted uranium conversion products at potential LLW disposal sites to provide a basis for DOE...

3

Including environmental concerns in management strategies for depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

One of the major programs within the Office of Nuclear Energy, Science, and Technology of the US Department of Energy (DOE) is the depleted uranium hexafluoride (DUF{sub 6}) management program. The program is intended to find a long-term management strategy for the DUF{sub 6} that is currently stored in approximately 46,400 cylinders at Paducah, KY; Portsmouth, OH; and Oak Ridge, TN, USA. The program has four major components: technology assessment, engineering analysis, cost analysis, and the environmental impact statement (EIS). From the beginning of the program, the DOE has incorporated the environmental considerations into the process of strategy selection. Currently, the DOE has no preferred alternative. The results of the environmental impacts assessment from the EIS, as well as the results from the other components of the program, will be factored into the strategy selection process. In addition to the DOE`s current management plan, other alternatives continued storage, reuse, or disposal of depleted uranium, will be considered in the EIS. The EIS is expected to be completed and issued in its final form in the fall of 1997.

Goldberg, M. [Argonne National Laboratory, Washington, DC (United States); Avci, H.I. [Argonne National Lab., IL (United States); Bradley, C.E. [USDOE, Washington, DC (United States)

1995-12-31T23:59:59.000Z

4

Depleted Uranium Hexafluoride Management  

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

OFFICE OF DEPLETED URANIUM HEXAFLUORIDE MANAGEMENT Issuance Of Final Report On Preconceptual Designs For Depleted Uranium Hexafluoride Conversion Plants The Department of Energy...

5

Depleted Uranium Health Effects  

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

Depleted Uranium Health Effects Depleted Uranium Health Effects Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Depleted Uranium Health Effects Discussion of health effects of external exposure, ingestion, and inhalation of depleted uranium. Depleted uranium is not a significant health hazard unless it is taken into the body. External exposure to radiation from depleted uranium is generally not a major concern because the alpha particles emitted by its isotopes travel only a few centimeters in air or can be stopped by a sheet of paper. Also, the uranium-235 that remains in depleted uranium emits only a small amount of low-energy gamma radiation. However, if allowed to enter the body, depleted uranium, like natural uranium, has the potential for both chemical and radiological toxicity with the two important target organs

6

FAQ 23-How much depleted uranium -- including depleted uranium...  

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

is stored in the United States? How much depleted uranium -- including depleted uranium hexafluoride -- is stored in the United States? In addition to the depleted uranium stored...

7

DOE/EA-1607: Final Environmental Assessment for Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium (June 2009)  

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

μCi/cc microcuries per cubic centimeter μCi/cc microcuries per cubic centimeter MAP mitigation action plan MEI maximally exposed individual mg/kg milligrams per kilogram mrem millirem mSv millisievert MT metric ton MTCA Model Toxics Control Act MTU metric tons of uranium N/A not applicable Final Environmental Assessment: Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium vi NAAQS National Ambient Air Quality Standards NEF National Enrichment Facility NEPA National Environmental Policy Act NRC U.S. Nuclear Regulatory Commission NU natural uranium NUF 6 natural uranium hexafluoride pCi/g picocuries per gram PEIS programmatic environmental impact statement PM 2.5 particulate matter with a diameter of 2.5 microns or less PM 10 particulate matter with a diameter of 10 microns or less

8

Depleted Uranium Hexafluoride Management  

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

for for DUF 6 Conversion Project Environmental Impact Statement Scoping Meetings November/December 2001 Overview Depleted Uranium Hexafluoride (DUF 6 ) Management Program DUF 6 EIS Scoping Briefing 2 DUF 6 Management Program Organizational Chart DUF 6 Management Program Organizational Chart EM-10 Policy EM-40 Project Completion EM-20 Integration EM-50 Science and Technology EM-31 Ohio DUF6 Management Program EM-32 Oak Ridge EM-33 Rocky Flats EM-34 Small Sites EM-30 Office of Site Closure Office of Environmental Management EM-1 DUF 6 EIS Scoping Briefing 3 DUF 6 Management Program DUF 6 Management Program * Mission: Safely and efficiently manage the DOE inventory of DUF 6 in a way that protects the health and safety of workers and the public, and protects the environment DUF 6 EIS Scoping Briefing 4 DUF 6 Inventory Distribution

9

Depleted uranium valuation  

SciTech Connect

The following uses for depleted uranium were examined to determine its value: a substitute for lead in shielding applications, feed material in gaseous diffusion enrichment facilities, feed material for an advanced enrichment concept, Mixed Oxide (MOx) diluent and blanket material in LMFBRs, and fertile material in LMFBR systems. A range of depleted uranium values was calculated for each of these applications. The sensitivity of these values to analysis assumptions is discussed. 9 tables.

Lewallen, M.A.; White, M.K.; Jenquin, U.P.

1979-04-01T23:59:59.000Z

10

Environmental acceptability of high-performance alternatives for depleted uranium penetrators  

SciTech Connect

The Army`s environmental strategy for investigating material substitution and management is to measure system environmental gains/losses in all phases of the material management life cycle from cradle to grave. This study is the first in a series of new investigations, applying material life cycle concepts, to evaluate whether there are environmental benefits from increasing the use of tungsten as an alternative to depleted uranium (DU) in Kinetic Energy Penetrators (KEPs). Current military armor penetrators use DU and tungsten as base materials. Although DU alloys have provided the highest performance of any high-density alloy deployed against enemy heavy armor, its low-level radioactivity poses a number of environmental risks. These risks include exposures to the military and civilian population from inhalation, ingestion, and injection of particles. Depleted uranium is well known to be chemically toxic (kidney toxicity), and workplace exposure levels are based on its renal toxicity. Waste materials containing DU fragments are classified as low-level radioactive waste and are regulated by the Nuclear Regulatory Commission. These characteristics of DU do not preclude its use in KEPs. However, long-term management challenges associated with KEP deployment and improved public perceptions about environmental risks from military activities might be well served by a serious effort to identify, develop, and substitute alternative materials that meet performance objectives and involve fewer environmental risks. Tungsten, a leading candidate base material for KEPS, is potentially such a material because it is not radioactive. Tungsten is less well studied, however, with respect to health impacts and other environmental risks. The present study is designed to contribute to the understanding of the environmental behavior of tungsten by synthesizing available information that is relevant to its potential use as a penetrator.

Kerley, C.R.; Easterly, C.E.; Eckerman, K.F. [and others] [and others

1996-08-01T23:59:59.000Z

11

Depleted uranium management alternatives  

SciTech Connect

This report evaluates two management alternatives for Department of Energy depleted uranium: continued storage as uranium hexafluoride, and conversion to uranium metal and fabrication to shielding for spent nuclear fuel containers. The results will be used to compare the costs with other alternatives, such as disposal. Cost estimates for the continued storage alternative are based on a life-cycle of 27 years through the year 2020. Cost estimates for the recycle alternative are based on existing conversion process costs and Capital costs for fabricating the containers. Additionally, the recycle alternative accounts for costs associated with intermediate product resale and secondary waste disposal for materials generated during the conversion process.

Hertzler, T.J.; Nishimoto, D.D.

1994-08-01T23:59:59.000Z

12

Video: The Depleted Uranium Hexafluoride Story  

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

Depleted UF6 Story The Depleted Uranium Hexafluoride Story An overview of Uranium, its isotopes, the need and history of diffusive separation, the handling of the Depleted Uranium...

13

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

DRAFT ENVIRONMENTAL IMPACT DRAFT ENVIRONMENTAL IMPACT STATEMENT FOR CONSTRUCTION AND OPERATION OF A DEPLETED URANIUM HEXAFLUORIDE CONVERSION FACILITY AT THE PADUCAH, KENTUCKY, SITE DECEMBER 2003 U.S. Department of Energy-Oak Ridge Operations Office of Environmental Management Cover Sheet Paducah DUF 6 DEIS: December 2003 iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Environmental Impact Statement (DEIS) for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site (DOE/EIS-0359) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831

14

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

DRAFT ENVIRONMENTAL IMPACT DRAFT ENVIRONMENTAL IMPACT STATEMENT FOR CONSTRUCTION AND OPERATION OF A DEPLETED URANIUM HEXAFLUORIDE CONVERSION FACILITY AT THE PORTSMOUTH, OHIO, SITE DECEMBER 2003 U.S. Department of Energy-Oak Ridge Operations Office of Environmental Management Cover Sheet Portsmouth DUF 6 DEIS: December 2003 iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Environmental Impact Statement (DEIS) for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site (DOE/EIS-0360) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831

15

Depleted Uranium Technical Brief  

E-Print Network (OSTI)

. This Technical Brief specifically addresses DU in an environmental contamination setting and specifically does.S. Department of Energy (DOE) and other govern ment sources. DU occurs in a number of different compounds airborne releases of uranium at one DOE facility amounted to 310,000 kg between 1951 and 1988, which

16

FAQ 6-What is depleted uranium?  

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

depleted uranium? What is depleted uranium? Depleted uranium is created during the processing that is done to make natural uranium suitable for use as fuel in nuclear power plants...

17

What is Depleted Uranium?  

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

What is Uranium? What is Uranium? Uranium and Its Compounds line line What is Uranium? Chemical Forms of Uranium Properties of Uranium Compounds Radioactivity and Radiation Uranium Health Effects What is Uranium? Physical and chemical properties, origin, and uses of uranium. Properties of Uranium Uranium is a radioactive element that occurs naturally in varying but small amounts in soil, rocks, water, plants, animals and all human beings. It is the heaviest naturally occurring element, with an atomic number of 92. In its pure form, uranium is a silver-colored heavy metal that is nearly twice as dense as lead. In nature, uranium atoms exist as several isotopes, which are identified by the total number of protons and neutrons in the nucleus: uranium-238, uranium-235, and uranium-234. (Isotopes of an element have the

18

FAQ 26-Are there any uses for depleted uranium?  

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

uses for depleted uranium? Are there any uses for depleted uranium? Several current and potential uses exist for depleted uranium. Depleted uranium could be mixed with highly...

19

Polyethylene Encapsulated Depleted Uranium  

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

Poly DU Poly DU Polyethylene Encapsulated Depleted Uranium Technology Description: Brookhaven National Laboratory (BNL) has completed preliminary work to investigate the feasibility of encapsulating DU in low density polyethylene to form a stable, dense product. DU loadings as high as 90 wt% were achieved. A maximum product density of 4.2 g/cm3 was achieved using UO3, but increased product density using UO2 is estimated at 6.1 g/cm3. Additional product density improvements up to about 7.2 g/cm3 were projected using DU aggregate in a hybrid technique known as micro/macroencapsulation.[1] A U.S. patent for this process has been received.[2] Figure 1 Figure 1: DU Encapsulated in polyethylene samples produced at BNL containing 80 wt % depleted UO3 A recent DU market study by Kapline Enterprises, Inc. for DOE thoroughly identified and rated potential applications and markets for DU metal and oxide materials.[3] Because of its workability and high DU loading capability, the polyethylene encapsulated DU could readily be fabricated as counterweights/ballast (for use in airplanes, helicopters, ships and missiles), flywheels, armor, and projectiles. Also, polyethylene encapsulated DU is an effective shielding material for both gamma and neutron radiation, with potential application for shielding high activity waste (e.g., ion exchange resins, glass gems), spent fuel dry storage casks, and high energy experimental facilities (e.g., accelerator targets) to reduce radiation exposures to workers and the public.

20

Depleted uranium disposal options evaluation  

SciTech Connect

The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D. [Science Applications International Corp., Idaho Falls, ID (United States). Waste Management Technology Div.

1994-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Depleted Uranium and Uranium Alloys  

Science Conference Proceedings (OSTI)

...Naturally occurring uranium makes up 0.0004% of the crust of the Earth; it is 40 times more plentiful than silver, and 800 times more plentiful than gold. Natural uranium contains approximately 0.7% fissionable U 235 and 99.3%

22

Depleted Uranium De-conversion  

E-Print Network (OSTI)

This Environmental Report (ER) constitutes one portion of an application being submitted by International Isotopes Fluorine Products (IIFP) to construct and operate a facility that will utilize depleted DUF6 to produce high purity inorganic fluorides, uranium oxides, and anhydrous hydrofluoric acid. The proposed IIFP facility will be located near Hobbs, New Mexico. IIFP has prepared the ER to meet the requirements specified in 10 CFR 51, Subpart A, particularly those requirements set forth in 10 CFR 51.45(b)-(e). The organization of this ER is generally consistent with NUREG-1748, Environmental Review Guidance for Licensing Actions Associated with NMSS Programs, Final Report. The Environmental Report for this proposed facility provides information that is specifically required by the NRC to assist it in meeting its obligations under the National Environmental Policy Act (NEPA) of 1969 and the agencys NEPA-implementing regulations. This ER demonstrates that the environmental protection measures proposed by IIFP are adequate to protect both the environment and the health and safety of the public. This Environmental Report evaluates the potential environmental impacts of the Proposed Action and its reasonable alternatives. This ER also describes the environment potentially affected by IIEFs proposal,

Fluorine Extraction Process

2009-01-01T23:59:59.000Z

23

Depleted Uranium (DU) Dioxide Fill  

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

Fill Depleted Uranium (DU) Dioxide Fill DU dioxide in the form of sand may be used to fill the void spaces in the waste package after the package is loaded with SNF. This...

24

Press Release: DOE Seeks Public Input for Depleted Uranium Hexafluorid...  

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

Perry, (865) 576-0885 September 24, 2001 www.oakridge.doe.gov DOE SEEKS PUBLIC INPUT FOR DEPLETED URANIUM HEXAFLUORIDE ENVIRONMENTAL IMPACT STATEMENT Public Meetings Planned in...

25

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

1: Main Text and Appendixes A-H 1: Main Text and Appendixes A-H June 2004 U.S. Department of Energy Office of Environmental Management Cover Sheet Portsmouth DUF 6 Conversion Final EIS iii COVER SHEET * RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site (DOE/EIS-0360) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Ports_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process, contact:

26

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

2: Comment and Response Document 2: Comment and Response Document June 2004 U.S. Department of Energy Office of Environmental Management Comment & Response Document Portsmouth DUF 6 Conversion Final EIS iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site (DOE/EIS-0360) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Ports_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process, contact:

27

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

2: Comment and Response Document 2: Comment and Response Document June 2004 U.S. Department of Energy Office of Environmental Management Comment & Response Document Paducah DUF 6 Conversion Final EIS iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site (DOE/EIS-0359) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Pad_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process,

28

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

1: Main Text and Appendixes A-H 1: Main Text and Appendixes A-H June 2004 U.S. Department of Energy Office of Environmental Management Cover Sheet Paducah DUF 6 Conversion Final EIS iii COVER SHEET * RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site (DOE/EIS-0359) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Pad_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process, contact:

29

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and  

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

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium The U.S. Department of Energy (DOE) owns and manages an inventory of depleted uranium (DU), natural uranium (NU), and low-enriched uranium (LEU) that is currently stored in large cylinders as depleted uranium hexafluoride (DUF6), natural uranium hexafluoride (NUF6), and low-enriched uranium hexafluoride (LEUF6) at the DOE Paducah site in western Kentucky (DOE Paducah) and the DOE Portsmouth site near Piketon in south-central Ohio (DOE Portsmouth)1. This inventory exceeds DOE's current and projected energy and defense program needs. On March 11, 2008, the Secretary of Energy issued a policy statement (the

30

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

1 1 Paducah DUF 6 DEIS: December 2003 SUMMARY S.1 INTRODUCTION This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF 6 ) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF 6 stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the Federal Register (FR) on September 18, 2001 (Federal Register, Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF 6 conversion facilities at Portsmouth,

31

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

DOE Green Energy (OSTI)

This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). Although not part of the proposed action, an option of shipping all cylinders (DUF{sub 6}, low-enriched UF{sub 6} [LEU-UF{sub 6}], and empty) stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Paducah rather than to Portsmouth is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Paducah site. A separate EIS (DOE/EIS-0360) evaluates the potential environmental impacts for the proposed Portsmouth conversion facility.

N /A

2003-11-28T23:59:59.000Z

32

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site  

DOE Green Energy (OSTI)

This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Portsmouth site in Ohio (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Portsmouth to a more stable chemical form suitable for use or disposal. The facility would also convert the DUF{sub 6} from the East Tennessee Technology Park (ETTP) site near Oak Ridge, Tennessee. In a Notice of Intent (NOI) published in the Federal Register on September 18, 2001 (Federal Register, Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (United States Code, Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (Code of Federal Regulations, Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a Federal Register Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Portsmouth site; from the transportation of all ETTP cylinders (DUF{sub 6}, low-enriched UF6 [LEU-UF{sub 6}], and empty) to Portsmouth; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). An option of shipping the ETTP cylinders to Paducah is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Portsmouth and ETTP sites. A separate EIS (DOE/EIS-0359) evaluates potential environmental impacts for the proposed Paducah conversion facility.

N /A

2003-11-28T23:59:59.000Z

33

Depleted Uranium Uses: Regulatory Requirements and Issues  

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

1 Depleted Uranium Uses Depleted Uranium Uses Regulatory Requirements Regulatory Requirements and Issues and Issues Nancy L. Ranek Nancy L. Ranek Argonne National Laboratory Argonne National Laboratory August 5, 1998 August 5, 1998 Beneficial Reuse '98 Beneficial Reuse '98 Knoxville, TN Knoxville, TN NOTES Work Performed for: Office of Facilities (NE-40) Office of Nuclear Energy, Science and Technology U.S. Department of Energy Work Performed by: Environmental Assessment Division Argonne National Laboratory 955 L'Enfant Plaza North, S.W. Washington, D.C. 20024 Phone: 202/488-2417 E-mail: ranekn@smtplink.dis.anl.gov 2 2 2 Programmatic Environmental Programmatic Environmental Impact Statement (PEIS) Impact Statement (PEIS) Draft PEIS Published 12/97 * Preferred Alternative = 100% Use

34

FAQ 7-How is depleted uranium produced?  

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

How is depleted uranium produced? How is depleted uranium produced? How is depleted uranium produced? Depleted uranium is produced during the uranium enrichment process. In the United States, uranium is enriched through the gaseous diffusion process in which the compound uranium hexafluoride (UF6) is heated and converted from a solid to a gas. The gas is then forced through a series of compressors and converters that contain porous barriers. Because uranium-235 has a slightly lighter isotopic mass than uranium-238, UF6 molecules made with uranium-235 diffuse through the barriers at a slightly higher rate than the molecules containing uranium-238. At the end of the process, there are two UF6 streams, with one stream having a higher concentration of uranium-235 than the other. The stream having the greater uranium-235 concentration is referred to as enriched UF6, while the stream that is reduced in its concentration of uranium-235 is referred to as depleted UF6. The depleted UF6 can be converted to other chemical forms, such as depleted uranium oxide or depleted uranium metal.

35

Depleted uranium plasma reduction system study  

Science Conference Proceedings (OSTI)

A system life-cycle cost study was conducted of a preliminary design concept for a plasma reduction process for converting depleted uranium to uranium metal and anhydrous HF. The plasma-based process is expected to offer significant economic and environmental advantages over present technology. Depleted Uranium is currently stored in the form of solid UF{sub 6}, of which approximately 575,000 metric tons is stored at three locations in the U.S. The proposed system is preconceptual in nature, but includes all necessary processing equipment and facilities to perform the process. The study has identified total processing cost of approximately $3.00/kg of UF{sub 6} processed. Based on the results of this study, the development of a laboratory-scale system (1 kg/h throughput of UF6) is warranted. Further scaling of the process to pilot scale will be determined after laboratory testing is complete.

Rekemeyer, P.; Feizollahi, F.; Quapp, W.J.; Brown, B.W.

1994-12-01T23:59:59.000Z

36

Potential Uses of Depleted Uranium  

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

POTENTIAL USES OF DEPLETED URANIUM POTENTIAL USES OF DEPLETED URANIUM Robert R. Price U.S. Department of Energy Germantown, Maryland 20874 M. Jonathan Haire and Allen G. Croff Chemical Technology Division Oak Ridge National Laboratory * Oak Ridge, Tennessee 37831-6180 June 2000 For American Nuclear Society 2000 International Winter and Embedded Topical Meetings Washington, D.C. November 12B16, 2000 The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. _________________________

37

Depleted Uranium Uses Research and Development  

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

DU Uses DU Uses Depleted Uranium Uses Research & Development A Depleted Uranium Uses Research and Development Program was initiated to explore beneficial uses of depleted uranium (DU) and other materials resulting from conversion of depleted UF6. A Depleted Uranium Uses Research and Development Program was initiated to explore the safe, beneficial use of depleted uranium and other materials resulting from conversion of depleted UF6 (e.g., fluorine and empty carbon steel cylinders) for the purposes of resource conservation and cost savings compared with disposal. This program explored the risks and benefits of several depleted uranium uses, including uses as a radiation shielding material, a catalyst, and a semi-conductor material in electronic devices.

38

News Media Exits for Depleted Uranium and Depleted UF6 Articles  

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line line Archived News and Events News Media Links News Media Exits for Depleted Uranium and Depleted UF6 Articles Online editions of newspapers that cover Depleted Uranium...

39

Depleted uranium risk assessment for Jefferson Proving Ground using data from environmental monitoring and site characterization. Final report  

SciTech Connect

This report documents the third risk assessment completed for the depleted uranium (DU) munitions testing range at Jefferson Proving Ground (JPG), Indiana, for the U.S. Army Test and Evaluation command. Jefferson Proving Ground was closed in 1995 under the Base Realignment and Closure Act and the testing mission was moved to Yuma Proving Ground. As part of the closure of JPG, assessments of potential adverse health effects to humans and the ecosystem were conducted. This report integrates recent information obtained from site characterization surveys at JPG with environmental monitoring data collected from 1983 through 1994 during DU testing. Three exposure scenarios were evaluated for potential adverse effects to human health: an occasional use scenario and two farming scenarios. Human exposure was minimal from occasional use, but significant risk were predicted from the farming scenarios when contaminated groundwater was used by site occupants. The human health risk assessments do not consider the significant risk posed by accidents with unexploded ordnance. Exposures of white-tailed deer to DU were also estimated in this study, and exposure rates result in no significant increase in either toxicological or radiological risks. The results of this study indicate that remediation of the DU impact area would not substantially reduce already low risks to humans and the ecosystem, and that managed access to JPG is a reasonable model for future land use options.

Ebinger, M.H.; Hansen, W.R.

1996-10-01T23:59:59.000Z

40

Paducah DUF6 Conversion Final EIS - Appendix C: Scoping Summary Report for Depleted Uranium Hexafluoride Conversion Facilities - Environmental Impact Statement Scoping Process  

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

Paducah DUF Paducah DUF 6 Conversion Final EIS APPENDIX C: SCOPING SUMMARY REPORT FOR DEPLETED URANIUM HEXAFLUORIDE CONVERSION FACILITIES ENVIRONMENTAL IMPACT STATEMENT SCOPING PROCESS Scoping Summary Report C-2 Paducah DUF 6 Conversion Final EIS Scoping Summary Report C-3 Paducah DUF 6 Conversion Final EIS APPENDIX C This appendix contains the summary report prepared after the initial public scoping period for the depleted uranium hexafluoride conversion facilities environmental impact statement (EIS) project. The scoping period for the EIS began with the September 18, 2001, publication of a Notice of Intent (NOI) in the Federal Register (66 FR 23213) and was extended to January 11, 2002. The report summarizes the different types of public involvement opportunities provided and the content of the comments received.

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Environmental Risks of Depleted UF6-related Manufacturing Activities  

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

and operation of a facility to fabricate representative products containing depleted uranium. Impacts Analyzed in the PEIS The PEIS evaluated the general environmental impacts...

42

Determination of Depleted Uranium in Environmental Bio-monitor Samples and Soil from Target sites in Western Balkan Region  

Science Conference Proceedings (OSTI)

Lichen and Moss are widely used to assess the atmospheric pollution by heavy metals and radionuclides. In this paper, we report results of uranium and its isotope ratios using mass spectrometric measurements (followed by chemical separation procedure) for mosses, lichens and soil samples from a depleted uranium (DU) target site in western Balkan region. Samples were collected in 2003 from Han Pijesak (Republika Srpska in Bosnia and Hercegovina). Inductively coupled plasma mass spectrometry (ICP-MS) measurements show the presence of high concentration of uranium in some samples. Concentration of uranium in moss samples ranged from 5.2-755.43 Bq/Kg. We have determined {sup 235}U/{sup 238}U isotope ratio using thermal ionization mass spectrometry (TIMS) from the samples with high uranium content and the ratios are in the range of 0.002097-0.002380. TIMS measurement confirms presence of DU in some samples. However, we have not noticed any traces of DU in samples containing lesser amount of uranium or from any samples from the living environment of same area.

Sahoo, Sarata K.; Enomoto, Hiroko; Tokonami, Shinji; Ishikawa, Tetsuo [National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage-ku, Chiba 263-8555 (Japan); Ujic, Predrag; Celikovic, Igor; Zunic, Zora S. [Institute of Nuclear Sciences, Vinca, Mike Petrovica Alasa 12-14, 11000 Belgrade (Serbia)

2008-08-07T23:59:59.000Z

43

A modern depleted uranium manufacturing facility  

SciTech Connect

The Specific Manufacturing Capabilities (SMC) Project located at the Idaho National Engineering Laboratory (INEL) and operated by Lockheed Martin Idaho Technologies Co. (LMIT) for the Department of Energy (DOE) manufactures depleted uranium for use in the U.S. Army MIA2 Abrams Heavy Tank Armor Program. Since 1986, SMC has fabricated more than 12 million pounds of depleted uranium (DU) products in a multitude of shapes and sizes with varying metallurgical properties while maintaining security, environmental, health and safety requirements. During initial facility design in the early 1980`s, emphasis on employee safety, radiation control and environmental consciousness was gaining momentum throughout the DOE complex. This fact coupled with security and production requirements forced design efforts to focus on incorporating automation, local containment and computerized material accountability at all work stations. The result was a fully automated production facility engineered to manufacture DU armor packages with virtually no human contact while maintaining security, traceability and quality requirements. This hands off approach to handling depleted uranium resulted in minimal radiation exposures and employee injuries. Construction of the manufacturing facility was complete in early 1986 with the first armor package certified in October 1986. Rolling facility construction was completed in 1987 with the first certified plate produced in the fall of 1988. Since 1988 the rolling and manufacturing facilities have delivered more than 2600 armor packages on schedule with 100% final product quality acceptance. During this period there was an annual average of only 2.2 lost time incidents and a single individual maximum radiation exposure of 150 mrem. SMC is an example of designing and operating a facility that meets regulatory requirements with respect to national security, radiation control and personnel safety while achieving production schedules and product quality.

Zagula, T.A.

1995-07-01T23:59:59.000Z

44

Audit Report on "Depleted Uranium Hexafluoride Conversion," DOE...  

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

Marketing Administration Other Agencies You are here Home Audit Report on "Depleted Uranium Hexafluoride Conversion," DOEIG-0642 Audit Report on "Depleted Uranium Hexafluoride...

45

Follow-up of Depleted Uranium Hexafluoride Conversion, IG-0751...  

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

Marketing Administration Other Agencies You are here Home Follow-up of Depleted Uranium Hexafluoride Conversion, IG-0751 Follow-up of Depleted Uranium Hexafluoride...

46

Depleted Uranium Operations at the Y-12 National Security Complex...  

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

Sites Power Marketing Administration Other Agencies You are here Home Depleted Uranium Operations at the Y-12 National Security Complex, G-0570 Depleted Uranium Operations...

47

FAQ 14-What does a depleted uranium hexafluoride cylinder look...  

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

depleted uranium hexafluoride cylinder look like? What does a depleted uranium hexafluoride cylinder look like? A picture is worth a thousand words The pictures below show typical...

48

Depleted Uranium (DU) Cermet Waste Package  

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

Package Package Depleted Uranium (DU) Cermet Waste Package The steel components of the waste package could be replaced with a uranium cermet. The cermet contains uranium dioxide particulates, which are embedded in steel. Cermets are made with outer layers of clean steel; thus, there is no radiation-contamination hazard in handling the waste packages. Because cermets are made of the same materials that would normally be found in the YM repository (uranium dioxide and steel), there are no chemical compatibility issues. From half to all of the DU inventory in the United States could be used for this application. Depleted Uranium Dioxide Steel Cermet Cross Section of a Depleted Uranium Dioxide Steel Cermet Follow the link below for more information on Cermets:

49

Depleted uranium: A DOE management guide  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has a management challenge and financial liability in the form of 50,000 cylinders containing 555,000 metric tons of depleted uranium hexafluoride (UF{sub 6}) that are stored at the gaseous diffusion plants. The annual storage and maintenance cost is approximately $10 million. This report summarizes several studies undertaken by the DOE Office of Technology Development (OTD) to evaluate options for long-term depleted uranium management. Based on studies conducted to date, the most likely use of the depleted uranium is for shielding of spent nuclear fuel (SNF) or vitrified high-level waste (HLW) containers. The alternative to finding a use for the depleted uranium is disposal as a radioactive waste. Estimated disposal costs, utilizing existing technologies, range between $3.8 and $11.3 billion, depending on factors such as applicability of the Resource Conservation and Recovery Act (RCRA) and the location of the disposal site. The cost of recycling the depleted uranium in a concrete based shielding in SNF/HLW containers, although substantial, is comparable to or less than the cost of disposal. Consequently, the case can be made that if DOE invests in developing depleted uranium shielded containers instead of disposal, a long-term solution to the UF{sub 6} problem is attained at comparable or lower cost than disposal as a waste. Two concepts for depleted uranium storage casks were considered in these studies. The first is based on standard fabrication concepts previously developed for depleted uranium metal. The second converts the UF{sub 6} to an oxide aggregate that is used in concrete to make dry storage casks.

NONE

1995-10-01T23:59:59.000Z

50

Regulation of New Depleted Uranium Uses  

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

2-5 2-5 Regulation of New Depleted Uranium Uses Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor The University of Chicago, nor any of their employees or officers, makes any warranty, express 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 privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark,

51

INFORMATION: Management Alert on Environmental Management's Select Strategy for Disposition of Savannah River Site Depleted Uranium Oxides  

SciTech Connect

The Administration and the Congress, through policy statements and passage of the American Recovery and Reinvestment Act of 2009 (Recovery Act), have signaled that they hope that proactive actions by agency Inspectors General will help ensure that Federal Recovery Act activities are transparent, effective and efficient. In that context, the purpose of this management alert is to share with you concerns that have been raised to the Office of Inspector General regarding the planned disposition of the Savannah River Site's (SRS) inventory of Depleted Uranium (DU) oxides. This inventory, generated as a by-product of the nuclear weapons production process and amounting to approximately 15,600 drums of DU oxides, has been stored at SRS for decades. A Department source we deem reliable and credible recently came to the Office of Inspector General expressing concern that imminent actions are planned that may not provide for the most cost effective disposition of these materials. During April 2009, the Department chose to use funds provided under the Recovery Act to accelerate final disposition of the SRS inventory of DU oxides. After coordination with State of Utah regulators, elected officials and the U.S. Nuclear Regulatory Commission, the Department initiated a campaign to ship the material to a facility operated by EnergySolutions in Clive, Utah. Although one shipment of a portion of the material has already been sent to the EnergySolutions facility, the majority of the product remains at SRS. As had been planned, both for the shipment already made and those planned in the near term, the EnergySolutions facility was to have been the final disposal location for the material. Recently, a member of Congress and various Utah State officials raised questions regarding the radioactive and other constituents present in the DU oxides to be disposed of at the Clive, Utah, facility. These concerns revolved around the characterization of the material and its acceptability under existing licensing criteria. As a consequence, the Governor of Utah met with Department officials to voice concerns regarding further shipments of the material and to seek return of the initial shipment of DU oxides to SRS. Utah's objections and the Department's agreement to accede to the State's demands effectively prohibit the transfer of the remaining material from South Carolina to Utah. In response, the Department evaluated its options and issued a draft decision paper on March 1, 2010, which outlined an alternative for temporary storage until the final disposition issue could be resolved. Under the terms of the proposed option, the remaining shipments from SRS are to be sent on an interim basis to a facility owned by Waste Control Specialists (WCS) in Andrews, Texas. Clearly, this choice carries with it a number of significant logistical burdens, including substantial additional costs for, among several items, repackaging at SRS, transportation to Texas, storage at the interim site, and, repackaging and transportation to the yet-to-be-determined final disposition point. The Department source expressed the concern that the proposal to store the material on an interim basis in Texas was inefficient and unnecessary, asserting: (1) that the materials could remain at SRS until a final disposition path is identified, and that this could be done safely, securely and cost effectively; and, (2) that the nature of the material was not subject to existing compliance agreements with the State of South Carolina, suggesting the viability of keeping the material in storage at SRS until a permanent disposal site is definitively established. We noted that, while the Department's decision paper referred to 'numerous project and programmatic factors that make it impractical to retain the remaining inventory at Savannah River,' it did not outline the specific issues involved nor did it provide any substantive economic or environmental analysis supporting the need for the planned interim storage action. The only apparent driver in this case was a Recovery Act-related goal esta

None

2010-04-01T23:59:59.000Z

52

Transcript of Public Scoping Meeting for Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities at Portsmouth, Ohio, and Paducah, Kentucky, held Nov. 28, 2001, Piketon, Ohio  

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

U.S. DEPARTMENT OF ENERGY ENVIRONMENTAL 2 IMPACT STATEMENT 3 FOR DEPLETED URANIUM HEXAFLUORIDE 4 CONVERSION FACILITIES 5 AT PORTSMOUTH, OHIO AND PADUCAH, KENTUCKY 6 7 SCOPING MEETING 8 9 November 28, 2001. 10 11 6:00 p.m. 12 13 Riffe Beavercreek Vocational School 14 175 Beavercreek Road 15 Piketon, Ohio 45661 16 17 FACILITATORS: Darryl Armstrong 18 Harold Munroe 19 Kevin Shaw 20 Gary Hartman 21 22 23 24 Professional Reporters, Inc. (614) 460-5000 or (800) 229-0675 2 1 -=0=- 2 PROCEEDINGS 3 -=0=- 4 MR. ARMSTRONG: I have 6:00, 5 according to my watch. Good evening, ladies 6 and gentlemen. If you'll please take your 7 seats, we'll get started. This meeting is 8 now officially convened. 9 On behalf of DOE, we thank you for 10 attending the environmental impact 11 statement, or EIS, scoping meeting this 12 evening for the depleted uranium conversion 13 facilities. My name is Darryl Armstrong. I 14

53

Record of Decision for Long-term Management and Use of Depleted Uranium Hexafluoride  

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

Record of Decision for Long-Term Management and Use of Depleted Uranium Hexafluoride AGENCY: Department of Energy ACTION: Record of Decision SUMMARY: The Department of Energy ("DOE" or "the Department") issued the Final Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride (Final PEIS) on April 23, 1999. DOE has considered the environmental impacts, benefits, costs, and institutional and programmatic needs associated with the management and use of its approximately 700,000 metric tons of depleted uranium hexafluoride (DUF 6 ). DOE has decided to promptly convert the depleted UF 6 inventory to depleted uranium oxide, depleted uranium metal, or a combination of both. The depleted uranium oxide will be

54

Beneficial Uses of Depleted Uranium  

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

Table 2 (ref. 1). The content of 235 U in DU is dependent on economics. If the cost of natural uranium feed is high relative to the cost of enrichment services, then a low 235 U...

55

FAQ 25-What are the options for managing depleted uranium in...  

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

options for managing depleted uranium in the future? What are the options for managing depleted uranium in the future? The options for managing depleted uranium were evaluated in...

56

Overview of Depleted Uranium Hexafluoride Management Program  

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

DOE's DUF DOE's DUF 6 Cylinder Inventory a Location Number of Cylinders DUF 6 (MT) b Paducah, Kentucky 36,910 450,000 Portsmouth, Ohio 16,041 198,000 Oak Ridge (ETTP), Tennessee 4,683 56,000 Total 57,634 704,000 a The DOE inventory includes DUF 6 generated by the government, as well as DUF 6 transferred from U.S. Enrichment Corporation pursuant to two memoranda of agreement. b A metric ton (MT) is equal to 1,000 kilograms, or 2,200 pounds. Overview of Depleted Uranium Hexafluoride Management Program Over the last four decades, large quantities of uranium were processed by gaseous diffusion to produce enriched uranium for U.S. national defense and civilian purposes. The gaseous diffusion process uses uranium in the form of uranium hexafluoride (UF 6 ), primarily because UF 6 can conveniently be used in

57

Environmental Risks of Depleted UF6 Disposal  

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

Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Disposal A discussion of the environmental impacts...

58

Transcript of Public Scoping Meeting for Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities at Portsmouth, Ohio, and Paducah, Kentucky, held Dec. 4, 2001, Oak Ridge, Tennessee  

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

TRANSCRIPT TRANSCRIPT OF MEETING ______________________________________________________ FACILITATOR: MR. DARRYL ARMSTRONG SPEAKER: MR. DALE RECTOR SPEAKER: MR. NORMAN MULVENON SPEAKER: MS. SUSAN GAWARECKI SPEAKER: MR. GENE HOFFMAN DECEMBER 4, 2001 ____________________________________________________ JOAN S. ROBERTS COURT REPORTER P.O. BOX 5924 OAK RIDGE, TENNESSEE 37831 (865-457-4027) 2 1 MR. ARMSTRONG: TAKE YOUR SEATS AND WE 2 WILL BEGIN THE MEETING. GOOD EVENING, LADIES 3 AND GENTLEMEN. IF YOU WILL, WE WILL START, THE 4 TIME IS NOW 6:02 P.M. THE MEETING IS 5 OFFICIALLY CONVENED. ON BEHALF OF THE 6 DEPARTMENT OF ENERGY, WE THANK YOU FOR 7 ATTENDING THIS ENVIRONMENTAL IMPACT STATEMENT 8 SCOPING MEETING, ALSO KNOWN AS AN EIS SCOPING 9 MEETING, FOR THE DEPLETED URANIUM CONVERSION 10 FACILITIES. MY NAME IS DARRYL ARMSTRONG. I'M 11 AN INDEPENDENT AND NEUTRAL FACILITATOR HIRED BY 12 AGENCIES

59

FAQ 24-Who is responsible for managing depleted uranium?  

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

Who is responsible for managing depleted uranium? Who is responsible for managing depleted uranium? In the United States, the U.S. Department of Energy is responsible for managing...

60

Disposition of Depleted Uranium Oxide  

Science Conference Proceedings (OSTI)

This document summarizes environmental information which has been collected up to June 1983 at Savannah River Plant. Of particular interest is an updating of dose estimates from changes in methodology of calculation, lower cesium transport estimates from Steel Creek, and new sports fish consumption data for the Savannah River. The status of various permitting requirements are also discussed.

Crandall, J.L.

2001-08-13T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect

The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

2000-06-01T23:59:59.000Z

62

Uranio impoverito: perch? (Depleted uranium: why?)  

E-Print Network (OSTI)

In this paper we develop a simple model of the penetration process of a long rod through an uniform target. Applying the momentum and energy conservation laws, we derive an analytical relation which shows how the penetration depth depends upon the density of the rod, given a fixed kinetic energy. This work was sparked off by the necessity of understanding the effectiveness of high density penetrators (e.g. depleted uranium penetrators) as anti-tank weapons.

Germano D'Abramo

2003-05-28T23:59:59.000Z

63

The ultimate disposition of depleted uranium  

SciTech Connect

Significant amounts of the depleted uranium (DU) created by past uranium enrichment activities have been sold, disposed of commercially, or utilized by defense programs. In recent years, however, the demand for DU has become quite small compared to quantities available, and within the US Department of Energy (DOE) there is concern for any risks and/or cost liabilities that might be associated with the ever-growing inventory of this material. As a result, Martin Marietta Energy Systems, Inc. (Energy Systems), was asked to review options and to develop a comprehensive plan for inventory management and the ultimate disposition of DU accumulated at the gaseous diffusion plants (GDPs). An Energy Systems task team, under the chairmanship of T. R. Lemons, was formed in late 1989 to provide advice and guidance for this task. This report reviews options and recommends actions and objectives in the management of working inventories of partially depleted feed (PDF) materials and for the ultimate disposition of fully depleted uranium (FDU). Actions that should be considered are as follows. (1) Inspect UF{sub 6} cylinders on a semiannual basis. (2) Upgrade cylinder maintenance and storage yards. (3) Convert FDU to U{sub 3}O{sub 8} for long-term storage or disposal. This will include provisions for partial recovery of costs to offset those associated with DU inventory management and the ultimate disposal of FDU. Another recommendation is to drop the term tails'' in favor of depleted uranium'' or DU'' because the tails'' label implies that it is waste.'' 13 refs.

Not Available

1990-12-01T23:59:59.000Z

64

Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF4)  

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

6 6 Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF 4 ) Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne's Environmental Assessment Division (EAD). For information on the division's scientific and engineering activities, contact: Director, Environmental Assessment Division Argonne National Laboratory Argonne, Illinois 60439-4832

65

Environmental Risks Associated with Conversion of Depleted UF6  

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

Conversion Conversion Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Conversion A general discussion of the potential environmental impacts associated with depleted UF6 conversion activities. Impacts Analyzed in the PEIS The potential environmental impacts associated with conversion activities will be evaluated in detail as part of the Depleted Uranium Hexafluoride management program after a contract is awarded for conversion services. This page discusses in general the types of impacts that might be associated with the conversion process based on the PEIS analysis. The PEIS evaluated the potential environmental impacts for representative conversion facilities. Conversion to uranium oxide and uranium metal were considered. Potential impacts were evaluated for a representative site, and

66

Selection of a management strategy for depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

A consequence of the uranium enrichment process used in the United States (US) is the accumulation of a significant amount of depleted uranium hexafluoride (UF{sub 6}). Currently, approximately 560,000 metric tons of the material are stored at three different sites. The US Department of Energy (DOE) has recently initiated a program to consider alternative strategies for the cost-effective and environmentally safe long-term management of this inventory of depleted UF{sub 6}. The program involves a technology and engineering assessment of proposed management options (use/reuse, conversion, storage, or disposal) and an analysis of the potential environmental impacts and life-cycle costs of alternative management strategies. The information obtained from the studies will be used by the DOE to select a preferred long-term management strategy. The selection and implementation of a management strategy will involve consideration of a number of important issues such as environmental, health, and safety effects; the balancing of risks versus costs in a context of reduced government spending; socioeconomic implications, including effects on the domestic and international uranium industry; the technical status of proposed uses or technologies; and public involvement in the decision making process. Because of its provisions for considering a wide range of relevant issues and involving the public, this program has become a model for future DOE materials disposition programs. This paper presents an overview of the Depleted Uranium Hexafluoride Management Program. Technical findings of the program to date are presented, and major issues involved in selecting and implementing a management strategy are discussed.

Patton, S.E.; Hanrahan, E.J.; Bradley, C.E.

1995-09-06T23:59:59.000Z

67

Health Risks Associated with Disposal of Depleted Uranium  

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

Disposal DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Disposal of Depleted Uranium A discussion of risks associated with disposal...

68

Challenges dealing with depleted uranium in Germany - Reuse or disposal  

SciTech Connect

During enrichment large amounts of depleted Uranium are produced. In Germany every year 2.800 tons of depleted uranium are generated. In Germany depleted uranium is not classified as radioactive waste but a resource for further enrichment. Therefore since 1996 depleted Uranium is sent to ROSATOM in Russia. However it still has to be dealt with the second generation of depleted Uranium. To evaluate the alternative actions in case a solution has to be found in Germany, several studies have been initiated by the Federal Ministry of the Environment. The work that has been carried out evaluated various possibilities to deal with depleted uranium. The international studies on this field and the situation in Germany have been analyzed. In case no further enrichment is planned the depleted uranium has to be stored. In the enrichment process UF{sub 6} is generated. It is an international consensus that for storage it should be converted to U{sub 3}O{sub 8}. The necessary technique is well established. If the depleted Uranium would have to be characterized as radioactive waste, a final disposal would become necessary. For the planned Konrad repository - a repository for non heat generating radioactive waste - the amount of Uranium is limited by the licensing authority. The existing license would not allow the final disposal of large amounts of depleted Uranium in the Konrad repository. The potential effect on the safety case has not been roughly analyzed. As a result it may be necessary to think about alternatives. Several possibilities for the use of depleted uranium in the industry have been identified. Studies indicate that the properties of Uranium would make it useful in some industrial fields. Nevertheless many practical and legal questions are open. One further option may be the use as shielding e.g. in casks for transport or disposal. Possible techniques for using depleted Uranium as shielding are the use of the metallic Uranium as well as the inclusion in concrete. Another possibility could be the use of depleted uranium for the blending of High enriched Uranium (HEU) or with Plutonium to MOX-elements. (authors)

Moeller, Kai D. [Federal Office for Radiation Protection, Bundesamt fuer Strahlenschutz - BFS, Postfach 10 01 49, D-38201 Salzgitter (Germany)

2007-07-01T23:59:59.000Z

69

Depleted Uranium Dioxide as SNF Waste Package Fill: A Disposal...  

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

DEPLETED URANIUM DIOXIDE AS SNF WASTE PACKAGE FILL: A DISPOSAL OPTION Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6179 Tel: (865)...

70

DOE Issues Request for Quotations for Depleted Uranium Hexafluoride  

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

Issues Request for Quotations for Depleted Uranium Hexafluoride Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services DOE Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services December 12, 2012 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 bill.taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today issued a Request for Quotation (RFQ) for engineering and operations technical services to support the Portsmouth Paducah Project Office and the oversight of operations of the Depleted Uranium Hexafluoride (DUF6) Conversion Project located in Paducah KY, and Portsmouth OH. The RFQ is for a Time-and-Materials Task Order for three years with two one-year option periods. The estimated contract value is approximately $15 - 20 million.

71

DOE Issues Request for Quotations for Depleted Uranium Hexafluoride  

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

Issues Request for Quotations for Depleted Uranium Hexafluoride Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services DOE Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services December 12, 2012 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 bill.taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today issued a Request for Quotation (RFQ) for engineering and operations technical services to support the Portsmouth Paducah Project Office and the oversight of operations of the Depleted Uranium Hexafluoride (DUF6) Conversion Project located in Paducah KY, and Portsmouth OH. The RFQ is for a Time-and-Materials Task Order for three years with two one-year option periods. The estimated contract value is approximately $15 - 20 million.

72

Regulation of new depleted uranium uses.  

DOE Green Energy (OSTI)

This report evaluates how the existing U.S. Nuclear Regulatory Commission (NRC) regulatory structure and pending modifications would affect full deployment into radiologically uncontrolled areas of certain new depleted uranium (DU) uses being studied as part of the U.S. Department of Energy's DU uses research and development program. Such new DU uses include as catalysts (for destroying volatile organic compounds in off-gases from industrial processes and for hydrodesulfurization [HDS] of petroleum fuels), semiconductors (for fabricating integrated circuits, solar cells, or thermoelectric devices, especially if such articles are expected to have service in hostile environments), and electrodes (for service in solid oxide fuel cells, in photoelectrochemical cells used to produce hydrogen, and in batteries). The report describes each new DU use and provides a detailed analysis of whether any existing NRC licensing exemption or general license would be available to users of products and devices manufactured to deploy the new use. Although one existing licensing exemption was found to be possibly available for catalysts used for HDS of petroleum fuels and one general license was found to be possibly available for catalysts, semiconductors, and electrodes used in hydrogen production or batteries, existing regulations would require most users of products and devices deploying new DU uses to obtain specific source material licenses from the NRC or an Agreement State. This situation would not be improved by pending regulatory modifications. Thus, deployment of new DU uses may be limited because persons having no previous experience with NRC or Agreement State regulations may be hesitant to incur the costs and inconvenience of regulatory compliance, unless using a DU-containing product or device offers a substantial economic benefit over nonradioactive alternatives. Accordingly, estimating the risk of deploying new DU-containing products and devices in certain radiologically uncontrolled areas is recommended. If the estimated risks of such deployment are found to be acceptable, then it may be possible to justify adding new exemptions or general licenses to the NRC regulations.

Ranek, N. L.

2003-01-22T23:59:59.000Z

73

Status Report and Proposal Concerning the Supply of Depleted Uranium Metal Bands for a Particle Detector  

E-Print Network (OSTI)

Status Report and Proposal Concerning the Supply of Depleted Uranium Metal Bands for a Particle Detector

1980-01-01T23:59:59.000Z

74

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

Forsberg, C.W.

1998-11-03T23:59:59.000Z

75

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotonically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W.

1997-12-01T23:59:59.000Z

76

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

77

Summary of the engineering analysis report for the long-term management of depleted uranium hexafluoride  

SciTech Connect

The Department of Energy (DOE) is reviewing ideas for the long-term management and use of its depleted uranium hexafluoride. DOE owns about 560,000 metric tons (over a billion pounds) of depleted uranium hexafluoride. This material is contained in steel cylinders located in storage yards near Paducah, Kentucky; Portsmouth, Ohio; and at the East Tennessee Technology Park (formerly the K-25 Site) in Oak Ridge, Tennessee. On November 10, 1994, DOE announced its new Depleted Uranium Hexafluoride Management Program by issuing a Request for Recommendations and an Advance Notice of Intent in the Federal Register (59 FR 56324 and 56325). The first part of this program consists of engineering, costs and environmental impact studies. Part one will conclude with the selection of a long-term management plan or strategy. Part two will carry out the selected strategy.

Dubrin, J.W., Rahm-Crites, L.

1997-09-01T23:59:59.000Z

78

Conversion of depleted uranium hexafluoride to a solid uranium compound  

DOE Patents (OSTI)

A process for converting UF.sub.6 to a solid uranium compound such as UO.sub.2 and CaF. The UF.sub.6 vapor form is contacted with an aqueous solution of NH.sub.4 OH at a pH greater than 7 to precipitate at least some solid uranium values as a solid leaving an aqueous solution containing NH.sub.4 OH and NH.sub.4 F and remaining uranium values. The solid uranium values are separated from the aqueous solution of NH.sub.4 OH and NH.sub.4 F and remaining uranium values which is then diluted with additional water precipitating more uranium values as a solid leaving trace quantities of uranium in a dilute aqueous solution. The dilute aqueous solution is contacted with an ion-exchange resin to remove substantially all the uranium values from the dilute aqueous solution. The dilute solution being contacted with Ca(OH).sub.2 to precipitate CaF.sub.2 leaving dilute NH.sub.4 OH.

Rothman, Alan B. (Willowbrook, IL); Graczyk, Donald G. (Lemont, IL); Essling, Alice M. (Elmhurst, IL); Horwitz, E. Philip (Naperville, IL)

2001-01-01T23:59:59.000Z

79

Calculating Capstone Depleted Uranium Aerosol Concentrations from Beta Activity Measurements  

SciTech Connect

Beta activity measurements were used as surrogate measurements of uranium mass in aerosol samples collected during the field testing phase of the Capstone Depleted Uranium (DU) Aerosol Study. These aerosol samples generated by the perforation of armored combat vehicles were used to characterize the depleted uranium (DU) source term for the subsequent human health risk assessment (HHRA) of Capstone aerosols. Establishing a calibration curve between beta activity measurements and uranium mass measurements is straightforward if the uranium isotopes are in equilibrium with their immediate short-lived, beta-emitting progeny. For DU samples collected during the Capstone study, it was determined that the equilibrium between the uranium isotopes and their immediate short lived, beta-emitting progeny had been disrupted when penetrators had perforated target vehicles. Adjustments were made to account for the disrupted equilibrium and for wall losses in the aerosol samplers. Correction factors for the disrupted equilibrium ranged from 0.16 to 1, and the wall loss correction factors ranged from 1 to 1.92.

Szrom, Fran; Falo, Gerald A.; Parkhurst, MaryAnn; Whicker, Jeffrey J.; Alberth, David P.

2009-03-01T23:59:59.000Z

80

Sampling Plan for Assaying Plates Containing Depleted or Normal Uranium  

Science Conference Proceedings (OSTI)

This paper describes the rationale behind the proposed method for selecting a 'representative' sample of uranium metal plates, portions of which will be destructively assayed at the Y-12 Security Complex. The total inventory of plates is segregated into two populations, one for Material Type 10 (depleted uranium (DU)) and one for Material Type 81 (normal [or natural] uranium (NU)). The plates within each population are further stratified by common dimensions. A spreadsheet gives the collective mass of uranium element (and isotope for DU) and the piece count of all plates within each stratum. These data are summarized in Table 1. All plates are 100% uranium metal, and all but approximately 60% of the NU plates have Kel-F{reg_sign} coating. The book inventory gives an overall U-235 isotopic percentage of 0.22% for the DU plates, ranging from 0.19% to 0.22%. The U-235 ratio of the NU plates is assumed to be 0.71%. As shown in Table 1, the vast majority of the plates are comprised of depleted uranium, so most of the plates will be sampled from the DU population.

Ivan R. Thomas

2011-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Shock induced multi-mode damage in depleted uranium  

SciTech Connect

Recent dynamic damage studies on depleted uranium samples have revealed mixed mode failure mechanisms leading to incipient cracking as well as ductile failure processes. Results show that delamination of inclusions upon compression may provide nucleation sites for damage initiation in the form of crack tip production. However, under tension the material propagates cracks in a mixed shear localization and mode-I ductile tearing and cracking. Cracks tips appear to link up through regions of severe, shear dominated plastic flow. Shock recovery experiments were conducted on a 50 mm single stage light gas gun. Serial metallographic sectioning was conducted on the recovered samples to characterize the bulk response of the sample. Experiments show delaminated inclusions due to uniaxial compression without damage propagation. Further results show the propagation of the damage through tensile loading to the incipient state, illustrating ductile processes coupled with mixed mode-I tensile ductile tearing, shear localization, and mode-I cracking in depleted uranium.

Koller, Darcie D [Los Alamos National Laboratory; Cerreta, Ellen K [Los Alamos National Laboratory; Gray, Ill, George T [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

82

Cermet Waste Packages Using Depleted Uranium Dioxide and Steel  

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

CERMET WASTE PACKAGES USING DEPLETED URANIUM DIOXIDE AND STEEL CERMET WASTE PACKAGES USING DEPLETED URANIUM DIOXIDE AND STEEL Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6180 Tel: (865) 574-6783 Fax: (865) 574-9512 Email: forsbergcw@ornl.gov Manuscript Number: 078 File Name: DuCermet.HLWcon01.article.final Article Prepared for 2001 International High-Level Radioactive Waste Management Conference American Nuclear Society Las Vegas, Nevada April 29-May 3, 2001 Limits: 1500 words; 3 figures Actual: 1450 words; 3 figures Session: 3.6 Disposal Container Materials and Designs The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution,

83

Uranio impoverito: perch'e? (Depleted uranium: why?)  

E-Print Network (OSTI)

In this paper we develop a simple model of the penetration process of a long rod through an uniform target. Applying the momentum and energy conservation laws, we derive an analytical relation which shows how the penetration depth depends upon the density of the rod, given a fixed kinetic energy. This work was sparked off by the necessity of the author of understanding the reasons of the effectiveness of high density penetrators (e.g. depleted uranium penetrators) as anti-tank weapons.

D'Abramo, G

2003-01-01T23:59:59.000Z

84

Radiological Risk Assessment of Capstone Depleted Uranium Aerosols  

SciTech Connect

Assessment of the health risk from exposure to aerosols of depleted uranium (DU) is an important outcome of the Capstone aerosol studies that established exposure ranges to personnel in armored combat vehicles perforated by DU munitions. Although the radiation exposure from DU is low, there is concern that DU deposited in the body may increase cancer rates. Radiation doses to various organs of the body resulting from the inhalation of DU aerosols measured in the Capstone studies were calculated using International Commission on Radiological Protection (ICRP) models. Organs and tissues with the highest calculated committed equivalent 50-yr doses were lung and extrathoracic tissues (nose and nasal passages, pharynx, larynx, mouth and thoracic lymph nodes). Doses to the bone surface and kidney were about 5 to 10% of the doses to the extrathoracic tissues. The methodologies of the ICRP International Steering Committee on Radiation Standards (ISCORS) were used for determining the whole body cancer risk. Organ-specific risks were estimated using ICRP and U.S. Environmental Protection Agency (EPA) methodologies. Risks for crewmembers and first responders were determined for selected scenarios based on the time interval of exposure and for vehicle and armor type. The lung was the organ with the highest cancer mortality risk, accounting for about 97% of the risks summed from all organs. The highest mean lifetime risk for lung cancer for the scenario with the longest exposure time interval (2 h) was 0.42%. This risk is low compared with the natural or background risk of 7.35%. These risks can be significantly reduced by using an existing ventilation system (if operable) and by reducing personnel time in the vehicle immediately after perforation.

Hahn, Fletcher; Roszell, Laurie E.; Daxon, Eric G.; Guilmette, Ray A.; Parkhurst, MaryAnn

2009-02-26T23:59:59.000Z

85

Transpassive electrodissolution of depleted uranium in alkaline electrolytes  

SciTech Connect

To aid in removal of oralloy from the nuclear weapons stockpile, scientists at the Los Alamos National Laboratory Plutonium Facility are decontaminating oralloy parts by electrodissolution in neutral to alkaline electrolytes composed of sodium nitrate and sodium sulfate. To improve the process, electrodissolution experiments were performed with depleted uranium to understand the effects of various operating parameters. Sufficient precipitate was also produced to evaluate the feasibility of using ultrafiltration to separate the uranium oxide precipitates from the electrolyte before it enters the decontamination fixture. In preparation for the experiments, a potential-pH diagram for uranium was constructed from thermodynamic data for fully hydrated species. Electrodissolution in unstirred solutions showed that uranium dissolution forms two layers, an acidic bottom layer rich in uranium and an alkaline upper layer. Under stirred conditions results are consistent with the formation of a yellow precipitate of composition UO{sub 3}{center_dot}2H{sub 2}O, a six electron process. Amperometric experiments showed that current efficiency remained near 100% over a wide range of electrolytes, electrolyte concentrations, pH, and stirring conditions.

Weisbrod, K.R.; Schake, A.R.; Morgan, A.N.; Purdy, G.M.; Martinez, H.E.; Nelson, T.O.

1998-03-01T23:59:59.000Z

86

Use of depleted uranium metal as cask shielding in high-level waste storage, transport, and disposal systems  

SciTech Connect

The US DOE has amassed over 555,000 metric tons of depleted uranium from its uranium enrichment operations. Rather than dispose of this depleted uranium as waste, this study explores a beneficial use of depleted uranium as metal shielding in casks designed to contain canisters of vitrified high-level waste. Two high-level waste storage, transport, and disposal shielded cask systems are analyzed. The first system employs a shielded storage and disposal cask having a separate reusable transportation overpack. The second system employs a shielded combined storage, transport, and disposal cask. Conceptual cask designs that hold 1, 3, 4 and 7 high-level waste canisters are described for both systems. In all cases, cask design feasibility was established and analyses indicate that these casks meet applicable thermal, structural, shielding, and contact-handled requirements. Depleted uranium metal casting, fabrication, environmental, and radiation compatibility considerations are discussed and found to pose no serious implementation problems. About one-fourth of the depleted uranium inventory would be used to produce the casks required to store and dispose of the nearly 15,400 high-level waste canisters that would be produced. This study estimates the total-system cost for the preferred 7-canister storage and disposal configuration having a separate transportation overpack would be $6.3 billion. When credits are taken for depleted uranium disposal cost, a cost that would be avoided if depleted uranium were used as cask shielding material rather than disposed of as waste, total system net costs are between $3.8 billion and $5.5 billion.

Yoshimura, H.R.; Ludwigsen, J.S.; McAllaster, M.E. [and others

1996-09-01T23:59:59.000Z

87

Assessing the risk from the depleted uranium weapons used in Operation Allied Force.  

E-Print Network (OSTI)

The conflict in Yugoslavia has been a source of great concern for the neighboring countries, about the radiological and toxic hazard posed by the alleged presence of depleted uranium in NATO weapons. In the present study a worst-case scenario is assumed mainly to assess the risk for Greece and other neighboring countries of Yugoslavia at similar distances. The risk of the weapons currently in use is proved to be negligible at distances greater than 100 Km. For shorter distances classified data of weapons composition are needed to obtain a reliable assessment. Operation Allied Force (OAF) has been going on for weeks in Yugoslavia with grave environmental consequences in the neighboring countries. Unfortunately, the sophisticated weapons that are being used carry the spectrum of radiological contamination. Over the past decades there has been a tremendous effort in weapons laboratories to use depleted uranium

unknown authors

1999-01-01T23:59:59.000Z

88

Video: The Inside Story (of a Depleted Uranium Hexafluoride Cylinder)  

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

Inside Story Inside Story The Inside Story The Inside Story (of a Depleted Uranium Hexafluoride Cylinder) Probes are used to look at the inside of a Uranium Hexafluoride cylinder. The distribution and structure of the contents are discussed. View this Video in Real Player format Download free RealPlayer SP Highlights of the Video: Video 00:42 10 ton 48Xcylinder of UF6 Video 01:19 Liquid UF6 filling 95% of cylinder volume Video 02:15 Liquid UF6 Video 02:23 Beginning of UF6 phase change from liquid to solid Video 02:32 Solid UF6 Video 03:00 Probe and instrument to investigate inside cylinder Video 04:09 Workers preparing to insert TV camera probe into 48X cylinder containing 10 tons of solid UF6 Video 04:28 Inner surface of head of cylinder showing no corrosion

89

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect

The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

Hightower, J.R.; Trabalka, J.R.

2000-02-01T23:59:59.000Z

90

Background Fact Sheet Transfer of Depleted Uranium and Subsequent Transactions  

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

Background Fact Sheet Background Fact Sheet Transfer of Depleted Uranium and Subsequent Transactions At the direction of Energy Secretary Steven Chu, over many months, the Energy Department (DOE) has been working closely with Energy Northwest (ENW), the Tennessee Valley Authority (TVA), and USEC Inc. (USEC) to develop a plan to address the challenges at USEC's Paducah Gaseous Diffusion Plant (GDP) that advances America's national security interests, protects taxpayers, and provides benefits for TVA and the Bonneville Power Administration's (BPA's) electric ratepayers and business operations. BPA is ENW's sole customer, purchasing 100 percent of ENW's Columbia Generating Station's electric power as part of BPA's overall

91

FAQ 16-How much depleted uranium hexafluoride is stored in the United  

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

How much depleted uranium hexafluoride is stored in the United States? How much depleted uranium hexafluoride is stored in the United States? How much depleted uranium hexafluoride is stored in the United States? U.S. DOE's inventory of depleted UF6 consists of approximately 700,000 metric tons of depleted UF6, containing about 470,000 metric tons of uranium, currently stored at the Paducah Site in Kentucky, the Portsmouth Site in Ohio, and the East Tennessee Technology Park (ETTP) in Tennessee (formerly known as the K-25 Site). This inventory of depleted UF6 is stored in about 57,000 steel cylinders. The inventory is listed in the table below. DOE Inventory of Depleted UF6 Location Total Cylinders Total Depleted UF6 (metric tons) Paducah, Kentucky 36,191 436,400 Portsmouth, Ohio 16,109 195,800 Oak Ridge, Tennessee 4,822 54,300

92

DUF6 Environmental Risks  

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

Risks A discussion of the potential environmental impacts associated with depleted uranium handling or processing facilities. Impacts Considered in the PEIS Depleted uranium...

93

Depleted-Uranium Weapons the Whys and Wherefores  

E-Print Network (OSTI)

The only military application in which present-day depleted-uranium (DU) alloys out-perform tungsten alloys is long-rod penetration into a main battle-tank's armor. However, this advantage is only on the order of 10% and disappearing when the comparison is made in terms of actual lethality of complete anti-tank systems instead of laboratory-type steel penetration capability. Therefore, new micro- and nano-engineered tungsten alloys may soon out-perform existing DU alloys, enabling the production of tungsten munition which will be better than uranium munition, and whose overall life-cycle cost will be less due to the absence of the problems related to the radioactivity of uranium. The reasons why DU weapons have been introduced and used are analysed from the perspective that their radioactivity must have played an important role in the decision making process. It is found that DU weapons belong to the diffuse category of low-radiological-impact nuclear weapons to which emerging types of low-yield, i.e., fourth...

Gsponer, A

2003-01-01T23:59:59.000Z

94

Kr Ion Irradiation Study of the Depleted-Uranium Alloys  

SciTech Connect

Fuel development for the Reduced Enrichment Research and Test Reactor program is tasked with the development of new low-enriched uranium nuclear fuels that can be employed to replace existing highly enriched uranium fuels currently used in some research reactors throughout the world. For dispersion-type fuels, radiation stability of the fuel/cladding interaction product has a strong impact on fuel performance. Three depleted uranium alloys are cast for the radiation stability studies of the fuel/cladding interaction product using Kr ion irradiation to investigate radiation damage from fission products. SEM analysis indicates the presence of the phases of interest: U(Si, Al)3, (U, Mo)(Si, Al)3, UMo2Al20, U6Mo4Al43, and UAl4. Irradiations of TEM disc samples were conducted with 500 keV Kr ions at 200C to ion doses up to 2.5 1015 ions/cm2 (~ 10 dpa) with an Kr ion flux of 1012 ions/cm2-sec (~ 4.0 10-3 dpa/sec). Microstructural evolution of the phases relevant to fuel-cladding interaction products was investigated using transmission electron microscopy.

J. Gan; D. Keiser; B. Miller; M. Kirk; J. Rest; T. Allen; D. Wachs

2010-12-01T23:59:59.000Z

95

Kr ion irradiation study of the depleted-uranium alloys.  

Science Conference Proceedings (OSTI)

Fuel development for the reduced enrichment research and test reactor (RERTR) program is tasked with the development of new low enrichment uranium nuclear fuels that can be employed to replace existing high enrichment uranium fuels currently used in some research reactors throughout the world. For dispersion type fuels, radiation stability of the fuel-cladding interaction product has a strong impact on fuel performance. Three depleted-uranium alloys are cast for the radiation stability studies of the fuel-cladding interaction product using Kr ion irradiation to investigate radiation damage from fission products. SEM analysis indicates the presence of the phases of interest: U(Al, Si){sub 3}, (U, Mo)(Al, Si){sub 3}, UMo{sub 2}Al{sub 20}, U{sub 6}Mo{sub 4}Al{sub 43} and UAl{sub 4}. Irradiations of TEM disc samples were conducted with 500 keV Kr ions at 200 C to ion doses up to 2.5 x 10{sup 19} ions/m{sup 2} ({approx}10 dpa) with an Kr ion flux of 10{sup 16} ions/m{sup 2}/s ({approx}4.0 x 10{sup -3} dpa/s). Microstructural evolution of the phases relevant to fuel-cladding interaction products was investigated using transmission electron microscopy.

Gan, J.; Keiser, D. D.; Miller, B. D.; Kirk, M. A.; Rest, J.; Allen, T. R.; Wachs, D. M. (Materials Science Division); (INL); (Univ. of Wisconsin)

2010-12-01T23:59:59.000Z

96

Repository Applications: Potential Benefits of Using Depleted Uranium (DU)  

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

Repository Applications Repository Applications Repository Applications: Potential Benefits of Using Depleted Uranium (DU) in a Geological Repository The United States is investigating the Yucca Mountain (YM) site in Nevada for the disposal of radioactive spent nuclear fuel (SNF)—the primary waste from nuclear power plants. The SNF would be packaged and then emplaced 200 to 300 m underground in parallel disposal tunnels. The repository isolates the SNF from the biosphere until the radionuclides decay to safe levels. DU may improve the performance of geological repositories for disposal of SNF via three mechanisms: Radiation shielding for waste packages to protect workers Lowering the potential for long-term nuclear criticality in the repository Reducing the potential for releases of radionuclides from the SNF

97

Military use of depleted uranium assessment of prolonged population exposure  

E-Print Network (OSTI)

This work is an exposure assessment for a population living in an area contaminated by use of depleted uranium (DU) weapons. RESRAD 5.91 code is used to evaluate the average effective dose delivered from 1, 10, 20 cm depths of contaminated soil, in a residential farmer scenario. Critical pathway and group are identified in soil inhalation or ingestion and children playing with the soil, respectively. From available information on DU released on targeted sites, both critical and average exposure can leave to toxicological hazards; annual dose limit for population can be exceeded on short-term period (years) for soil inhalation. As a consequence, in targeted sites cleaning up must be planned on the basis of measured concentration, when available, while special cautions have to be adopted altogether to reduce unaware exposures, taking into account the amount of the avertable dose.

Giannardi, C

2001-01-01T23:59:59.000Z

98

EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio  

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

60: Depleted Uranium Oxide Conversion Product at the 60: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site Summary This site-specific EIS analyzes the construction, operation, maintenance, and decontamination and decommissioning of the proposed depleted uranium hexafluoride (DUF6) conversion facility at three alternative locations within the Portsmouth site; transportation of all cylinders (DUF6, enriched, and empty) currently stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Portsmouth; construction of a new cylinder storage yard at Portsmouth (if required) for ETTP cylinders; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and sale of the hydrogen fluoride

99

Capstone Depleted Uranium Aerosol Biokinetics, Concentrations, and Doses  

SciTech Connect

One of the principal goals of the Capstone Depleted Uranium (DU) Aerosol Study was to quantify and characterize DU aerosols generated inside armored vehicles by perforation with a DU penetrator. This study consequently produced a database in which the DU aerosol source terms were specified both physically and chemically for a variety of penetrator-impact geometries and conditions. These source terms were used to calculate radiation doses and uranium concentrations for various scenarios as part of the Capstone DU Human Health Risk Assessment (HHRA). This paper describes the scenario-related biokinetics of uranium, and summarizes intakes, chemical concentrations to the organs, and E(50) and HT(50) for organs and tissues based on exposure scenarios for personnel in vehicles at the time of perforation as well as for first responders. For a given exposure scenario (duration time and breathing rates), the range of DU intakes among the target vehicles and shots was not large, about a factor of 10, with the lowest being from a ventilated operational Abrams tank and the highest being for an unventilated Abrams with DU penetrator perforating DU armor. The ranges of committed effective doses were more scenario-dependent than were intakes. For example, the largest range, a factor of 20, was shown for scenario A, a 1-min exposure, whereas, the range was only a factor of two for the first-responder scenario (E). In general, the committed effective doses were found to be in the tens of mSv. The risks ascribed to these doses are discussed separately.

Guilmette, Raymond A.; Miller, Guthrie; Parkhurst, MaryAnn

2009-02-26T23:59:59.000Z

100

Characterization of Thermal Properties of Depleted Uranium Metal Microspheres  

E-Print Network (OSTI)

Nuclear fuel comes in many forms; oxide fuel is the most commonly used in current reactor systems while metal fuel is a promising fuel type for future reactors due to neutronic performance and increased thermal conductivity. As a key heat transfer parameter, thermal conductivity describes the heat transport properties of a material based upon the density, specific heat, and thermal diffusivity. A materials ability to transport thermal energy through its structure is a measurable property known as thermal diffusivity; the units for thermal diffusivity are given in area per unit time (e.g., m2/s). Current measurement methods for thermal diffusivity include LASER (or light) Flash Analysis and the hot-wire method. This study examines an approach that combines these previous two methods to characterize the diffusivity of a packed bed of microspheres of depleted uranium (DU) metal, which have a nominal diameter of 250 micrometers. The new apparatus is designated as the Crucible Heater Test Assembly (CHTA), and it induces a radial transient across a packed sample of microspheres then monitors the temperature profile using an array of thermocouples located at different distances from the source of the thermal transient. From the thermocouple data and an accurate time log, the thermal diffusivity of the sample may be calculated. Results indicate that DU microspheres have very low thermal conductivity, relative to solid uranium metal, and rapidly form an oxidation layer. At 500C, the thermal conductivity of the DU microspheres was 0.431 13% W/m-K compared to approximately 32 W/m-K for solid uranium metal. Characterization of the developed apparatus revealed a method that may be useful for measuring the thermal diffusivity of powders and liquids.

Humrickhouse, Carissa Joy

2012-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Attainable Burnup in a LIFE Engine Loaded with Depleted Uranium  

Science Conference Proceedings (OSTI)

The Laser Inertial Fusion-based Energy (LIFE) system uses a laser-based fusion source for electricity production. The (D,T) reaction, beside a pure fusion system, allows the option to drive a sub-critical fission blanket in order to increase the total energy gain. In a typical fusion-fission LIFE engine the fission blanket is a spherical shell around the fusion source, preceded by a beryllium shell for neutron multiplications by means of (n,2n) reactions. The fuel is in the form of TRISO particles dispersed in carbon pebbles, cooled by flibe. The optimal design features 80 cm thick blanket, 16 cm multiplier, and 20% TRISO packing factor. A blanket loaded with depleted uranium and depleted in a single batch with continuous mixing can achieve burnup as high as {approx}85% FIMA while generating 2,000 MW of total thermal power and producing enough tritium to be used for fusion. A multi-segment blanket with a central promotion shuffling scheme enhances burnup to {approx}90% FIMA, whereas a blanket that is operated with continuous refueling achieves only 82% FIMA under the same constraints of thermal power and tritium self-sufficiency. Both, multi-segment and continuous refueling eliminate the need for a fissile breeding phase.

Fratoni, M; Kramer, K J; Latkowski, J F

2009-11-30T23:59:59.000Z

102

Draft Supplement Analysis for Location(s) to Dispose of Depleted Uranium Oxide Conversion Product Generated from DOE'S Inventory of Depleted Uranium Hexafluoride  

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

DRAFT SUPPLEMENT ANALYSIS FOR LOCATION(S) TO DISPOSE OF DEPLETED DRAFT SUPPLEMENT ANALYSIS FOR LOCATION(S) TO DISPOSE OF DEPLETED URANIUM OXIDE CONVERSION PRODUCT GENERATED FROM DOE'S INVENTORY OF DEPLETED URANIUM HEXAFLUORIDE (DOE/EIS-0359-SA1 AND DOE/EIS-0360-SA1) March 2007 March 2007 i CONTENTS NOTATION........................................................................................................................... iv 1 INTRODUCTION AND BACKGROUND ................................................................. 1 1.1 Why DOE Has Prepared This Draft Supplement Analysis .............................. 1 1.2 Background ....................................................................................................... 3 1.3 Proposed Actions Considered in this Draft Supplement Analysis.................... 4

103

Effect of twinning on texture evolution of depleted uranium using a viscoplastic self-consistent model  

Science Conference Proceedings (OSTI)

Ductility and fracture toughness is a major stumbling block in using depleted uranium as a structural material. The ability to correctly model deformation of uranium can be used to create process path methods to improve its structural design ability. The textural evolution of depleted uranium was simulated using a visco-plastic self consistent model and analyzed by comparing pole figures of the simulations and experimental samples. Depleted uranium has the same structure as alpha uranium, which is an orthorhombic phase of uranium. Both deformation slip and twin systems were compared. The VPSC model was chosen to simulate this material because the model encompasses both low-symmetry materials as well as twinning in materials. This is of particular interest since depleted uranium has a high propensity for twinning, which dominates deformation and texture evolution. Simulated results were compared to experimental results to measure the validity of the model. One specific twin system, the {l_brace}176{r_brace}[512] twin, was of specific notice. The VPSC model was used to simulate the influence of this twin on depleted uranium and was compared with a mechanically shocked depleted uranium sample. Under high strain rate shock deformation conditions, the {l_brace}176{r_brace}[512] twin system appears to be a dominant deformation system. By simulating a compression process using the VPSC model with the {l_brace}176{r_brace}[512] twin as the dominant deformation mode, a favorable comparison could be made between the experimental and simulated textures. (authors)

Ho, J.; Garmestani, H. [Georgia Inst. of Technology, Atlanta, GA 30332-0245 (United States); Burrell, R.; Belvin, A. [Y-12 National Security Complex, Oak Ridge, TN (United States); Li, D. [Fundamental and Computational Sciences Directorate, Pacific Northwest National Laboratory, Richland, WA 99352 (United States); McDowell, D. [Woodruff School of Mechanical Engineering, Atlanta, GA 30332-0245 (United States); Rollett, A. [Dept. of Materials Science and Engineering, Carnegie Mellon Univ., Pittsburgh, PA 15213 (United States)

2012-07-01T23:59:59.000Z

104

Proposal concerning the participation of CERN in the procurement of depleted-uranium sheets for the UA1 calorimeter upgrading  

E-Print Network (OSTI)

Proposal concerning the participation of CERN in the procurement of depleted-uranium sheets for the UA1 calorimeter upgrading

1985-01-01T23:59:59.000Z

105

EIS-0471: Final Environmental Impact Statement | Department of...  

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

EIS-0468: Final Environmental Impact Statement EA-1607: Final Environmental Assessment Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium...

106

Dupoly process for treatment of depleted uranium and production of beneficial end products  

DOE Patents (OSTI)

The present invention provides a process of encapsulating depleted uranium by forming a homogenous mixture of depleted uranium and molten virgin or recycled thermoplastic polymer into desired shapes. Separate streams of depleted uranium and virgin or recycled thermoplastic polymer are simultaneously subjected to heating and mixing conditions. The heating and mixing conditions are provided by a thermokinetic mixer, continuous mixer or an extruder and preferably by a thermokinetic mixer or continuous mixer followed by an extruder. The resulting DUPoly shapes can be molded into radiation shielding material or can be used as counter weights for use in airplanes, helicopters, ships, missiles, armor or projectiles.

Kalb, Paul D. (Wading River, NY); Adams, Jay W. (Stony Brook, NY); Lageraaen, Paul R. (Seaford, NY); Cooley, Carl R. (Gaithersburg, MD)

2000-02-29T23:59:59.000Z

107

Uranium Enrichment  

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

Enrichment Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Uranium Enrichment A description of the uranium enrichment process, including gaseous...

108

Depleted Uranium Hexafluoride Management Program: Data Compilation for the Paducah Site  

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

9 9 Depleted Uranium Hexafluoride Management Program: Data Compilation for the Paducah Site in Support of Site-Specific NEPA Requirements for Continued Cylinder Storage, Cylinder Preparation, Conversion, and Long-Term Storage Activities Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne's Environmental Assessment Division (EAD). For information on the division's scientific and engineering

109

Depleted uranium oxides as spent-nuclear-fuel waste-package fill materials  

SciTech Connect

Depleted uranium dioxide fill inside the waste package creates the potential for significant improvements in package performance based on uranium geochemistry, reduces the potential for criticality in a repository, and consumes DU inventory. As a new concept, significant uncertainties exist: fill properties, impacts on package design, post- closure performance.

Forsberg, C.W.

1997-07-07T23:59:59.000Z

110

A Process for Reducing the Licensing Burden for New Products Containing Depleted Uranium  

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

3-01 3-01 A Process for Reducing the Licensing Burden for New Products Containing Depleted Uranium Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory, a U.S. Department of Energy Office of Science laboratory, is operated by The University of Chicago under contract W-31-109-Eng-38. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor The University of Chicago, nor any of their employees or officers, makes any warranty, express or implied, or assumes

111

Depleted-Uranium Uses R&D Program  

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

curve, indicating that one should be able to use uranium oxides to make very efficient solar cells, semiconductors, or other electronic devices. Figure 3 shows the ideal solar...

112

FAQ 42-What are the potential environmental impacts from disposal...  

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

disposal of depleted uranium as an oxide? What are the potential environmental impacts from disposal of depleted uranium as an oxide? Disposal as oxide could result in adverse...

113

FAQ 38-What are the potential environmental impacts from continued...  

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

continued storage of depleted uranium hexafluoride? What are the potential environmental impacts from continued storage of depleted uranium hexafluoride? In addition to human...

114

DOE Extends Public Comment Period for Uranium Program Environmental...  

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

Other Agencies You are here Home DOE Extends Public Comment Period for Uranium Program Environmental Impact Statement DOE Extends Public Comment Period for Uranium...

115

SALE OF ENRICHED URANIUM AT THE FERNALD ENVIRONMENTAL MANAGEMENT...  

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

Power Marketing Administration Other Agencies You are here Home SALE OF ENRICHED URANIUM AT THE FERNALD ENVIRONMENTAL MANAGEMENT PROJECT, IG-0496 SALE OF ENRICHED URANIUM AT...

116

CRAD, Environmental Protection - Y-12 Enriched Uranium Operations...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Environmental Protection - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of...

117

FAQ 15-What are the dimensions of a depleted uranium hexafluoride cylinder?  

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

are the dimensions of a depleted uranium hexafluoride cylinder? are the dimensions of a depleted uranium hexafluoride cylinder? What are the dimensions of a depleted uranium hexafluoride cylinder? Several different cylinder types are in use, although the vast majority of cylinders are designed to contain 14-tons (12-metric tons) of depleted UF6. The 14-ton-capacity cylinders are 12 ft (3.7 m) long by 4 ft (1.2 m) in diameter, with most having an initial wall thickness of 5/16 in. (0.79 cm) of steel. The cylinders have external stiffening rings that provide support. Lifting lugs for handling are attached to the stiffening rings. A small percentage of the cylinders have skirted ends (extensions of the cylinder walls past the rounded ends of the cylinder). Each cylinder has a single valve for filling and emptying located on one end at the 12 o'clock position. Similar, but slightly smaller, cylinders designed to contain 10 tons (9 metric tons) of depleted UF6 are also in use. Cylinders are manufactured in accordance with an American National Standards Institute standard (ANSI N14.1, American National Standard for Nuclear Materials - Uranium Hexafluoride - Packaging for Transport) as specified in 49 CFR 173.420, the federal regulations governing transport of depleted UF6.

118

Preconceptual design studies and cost data of depleted uranium hexafluoride conversion plants  

SciTech Connect

One of the more important legacies left with the Department of Energy (DOE) after the privatization of the United States Enrichment Corporation is the large inventory of depleted uranium hexafluoride (DUF6). The DOE Office of Nuclear Energy, Science and Technology (NE) is responsible for the long-term management of some 700,000 metric tons of DUF6 stored at the sites of the two gaseous diffusion plants located at Paducah, Kentucky and Portsmouth, Ohio, and at the East Tennessee Technology Park in Oak Ridge, Tennessee. The DUF6 management program resides in NE's Office of Depleted Uranium Hexafluoride Management. The current DUF6 program has largely focused on the ongoing maintenance of the cylinders containing DUF6. However, the long-term management and eventual disposition of DUF6 is the subject of a Programmatic Environmental Impact Statement (PEIS) and Public Law 105-204. The first step for future use or disposition is to convert the material, which requires construction and long-term operation of one or more conversion plants. To help inform the DUF6 program's planning activities, it was necessary to perform design and cost studies of likely DUF6 conversion plants at the preconceptual level, beyond the PEIS considerations but not as detailed as required for conceptual designs of actual plants. This report contains the final results from such a preconceptual design study project. In this fast track, three month effort, Lawrence Livermore National Laboratory and Bechtel National Incorporated developed and evaluated seven different preconceptual design cases for a single plant. The preconceptual design, schedules, costs, and issues associated with specific DUF6 conversion approaches, operating periods, and ownership options were evaluated based on criteria established by DOE. The single-plant conversion options studied were similar to the dry-conversion process alternatives from the PEIS. For each of the seven cases considered, this report contains information on the conversion process, preconceptual plant description, rough capital and operating costs, and preliminary project schedule.

Jones, E

1999-07-26T23:59:59.000Z

119

HIGH-DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE  

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

DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE S.G. Ermichev, V.I. Shapovalov, N.V.Sviridov (RFNC-VNIIEF, Sarov, Russia) V.K. Orlov, V.M. Sergeev, A. G. Semyenov, A.M. Visik, A.A. Maslov, A. V. Demin, D.D. Petrov, V.V. Noskov, V. I. Sorokin, O. I. Uferov (VNIINM, Moscow, Russia) L. Dole (ORNL, Oak Ridge, USA) Abstract - Russia is researching the production and testing of concretes with ceramic aggregate based on depleted uranium dioxide (UO 2 ). These DU concretes are to be used as structural and radiation-shielded material for casks for A-plant spent nuclear fuel transportation and storage. This paper presents the results of studies aimed at selection of ceramics and concrete composition, justification of their production technology, investigation of mechanical properties, and chemical stability.

120

Comparative study of femtosecond and nanosecond laser-induced breakdown spectroscopy of depleted uranium  

SciTech Connect

We present spectra of depleted uranium metal from laser plasmas generated by nanosecond Nd:YAG (1064 nm) and femtosecond Ti:sapphire (800 nm) laser pulses. The latter pulses produce short-lived and relatively cool plasmas in comparison to the longer pulses, and the spectra of neutral uranium atoms appear immediately after excitation. Evidence for nonequilibrium excitation with femtosecond pulses is found in the dependence of spectral line intensities on the pulse chirp.

Emmert, Luke A.; Chinni, Rosemarie C.; Cremers, David A.; Jones, C. Randy; Rudolph, Wolfgang

2011-01-20T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Physicochemical Characterization of Capstone Depleted Uranium Aerosols I: Uranium Concentration in Aerosols as a Function of Time and Particle Size  

SciTech Connect

During the Capstone Depleted Uranium (DU) Aerosol Study, aerosols containing depleted uranium were produced inside unventilated armored vehicles (i.e., Abrams tanks and Bradley Fighting Vehicles) by perforation with large-caliber DU penetrators. These aerosols were collected and characterized, and the data were subsequently used to assess human health risks to personnel exposed to DU aerosols. The DU content of each aerosol sample was first quantified by radioanalytical methods, and selected samples, primarily those from the cyclone separator grit chambers, were analyzed radiochemically. Deposition occurred inside the vehicles as particles settled on interior surfaces. Settling rates of uranium from the aerosols were evaluated using filter cassette samples that collected aerosol as total mass over eight sequential time intervals. A moving filter was used to collect aerosol samples over time particularly within the first minute after the shot. The results demonstrate that the peak uranium concentration in the aerosol occurred in the first 10 s, and the concentration decreased in the Abrams tank shots to about 50% within 1 min and to less than 2% 30 min after perforation. In the Bradley vehicle, the initial (and maximum) uranium concentration was lower than those observed in the Abrams tank and decreased more slowly. Uranium mass concentrations in the aerosols as a function of particle size were evaluated using samples collected in the cyclone samplers, which collected aerosol continuously for 2 h post perforation. The percentages of uranium mass in the cyclone separator stages from the Abrams tank tests ranged from 38% to 72% and, in most cases, varied with particle size, typically with less uranium associated with the smaller particle sizes. Results with the Bradley vehicle ranged from 18% to 29% and were not specifically correlated with particle size.

Parkhurst, MaryAnn; Cheng, Yung-Sung; Kenoyer, Judson L.; Traub, Richard J.

2009-03-01T23:59:59.000Z

122

Metallography of pitted aluminum-clad, depleted uranium fuel  

Science Conference Proceedings (OSTI)

The storage of aluminum-clad fuel and target materials in the L-Disassembly Basin at the Savannah River Site for more than 5 years has resulted in extensive pitting corrosion of these materials. In many cases the pitting corrosion of the aluminum clad has penetrated in the uranium metal core, resulting in the release of plutonium, uranium, cesium-137, and other fission product activity to the basin water. In an effort to characterize the extent of corrosion of the Mark 31A target slugs, two unirradiated slug assemblies were removed from basin storage and sent to the Savannah River Technology Center for evaluation. This paper presents the results of the metallography and photographic documentation of this evaluation. The metallography confirmed that pitting depths varied, with the deepest pit found to be about 0.12 inches (3.05 nun). Less than 2% of the aluminum cladding was found to be breached resulting in less than 5% of the uranium surface area being affected by corrosion. The overall integrity of the target slug remained intact.

Nelson, D.Z.; Howell, J.P.

1994-12-01T23:59:59.000Z

123

Evaluation of depleted uranium in the environment at Aberdeen Proving Grounds, Maryland and Yuma Proving Grounds, Arizona. Final report  

SciTech Connect

This report represents an evaluation of depleted uranium (DU) introduced into the environment at the Aberdeen Proving Grounds (APG), Maryland and Yuma Proving Grounds (YPG) Arizona. This was a cooperative project between the Environmental Sciences and Statistical Analyses Groups at LANL and with the Department of Fishery and Wildlife Biology at Colorado State University. The project represents a unique approach to assessing the environmental impact of DU in two dissimilar ecosystems. Ecological exposure models were created for each ecosystem and sensitivity/uncertainty analyses were conducted to identify exposure pathways which were most influential in the fate and transport of DU in the environment. Research included field sampling, field exposure experiment, and laboratory experiments. The first section addresses DU at the APG site. Chapter topics include bioenergetics-based food web model; field exposure experiments; bioconcentration by phytoplankton and the toxicity of U to zooplankton; physical processes governing the desorption of uranium from sediment to water; transfer of uranium from sediment to benthic invertebrates; spead of adsorpion by benthic invertebrates; uptake of uranium by fish. The final section of the report addresses DU at the YPG site. Chapters include the following information: Du transport processes and pathway model; field studies of performance of exposure model; uptake and elimination rates for kangaroo rates; chemical toxicity in kangaroo rat kidneys.

Kennedy, P.L.; Clements, W.H.; Myers, O.B.; Bestgen, H.T.; Jenkins, D.G. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Fishery and Wildlife Biology

1995-01-01T23:59:59.000Z

124

Reducing the environmental impact of uranium in-situ recovery.  

Science Conference Proceedings (OSTI)

This session will explore the current technical approaches to reducing the environmental effects of uranium ISR in comparison to the historical environmental impact of uranium mining to demonstrate advances in this controversial subject.

Siegel, Malcolm Dean; Simmons, Ardyth

2010-10-01T23:59:59.000Z

125

Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium  

Science Conference Proceedings (OSTI)

Approximately 750,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms are stored at several Department of Energy (DOE) sites throughout the United States. Most of the DU is in the form of DU hexafluoride (DUF6) that resulted from uranium enrichment operations over the last several decades. DOE plans to convert the DUF6 to ''a more stable form'' that could be any one or combination of DU tetrafluoride (DUF4 or green salt), DU oxide (DUO3, DUO2, or DU3O8), or metal depending on the final disposition chosen for any given quantity. Barriers to final disposition of this material have existed historically and some continue today. Currently, the barriers are more related to finding uses for this material versus disposing as waste. Even though actions are beginning to convert the DUF6, ''final'' disposition of the converted material has yet to be decided. Unless beneficial uses can be implemented, DOE plans to dispose of this material as waste. This expresses the main barrier to DU disposition; DOE's strategy is to dispose unless uses can be found while the strategy should be only dispose as a last resort and make every effort to find uses. To date, only minimal research programs are underway to attempt to develop non-fuel uses for this material. Other issues requiring resolution before these inventories can reach final disposition (uses or disposal) include characterization, disposal of large quantities, storage (current and future), and treatment options. Until final disposition is accomplished, these inventories must be managed in a safe and environmentally sound manner; however, this is becoming more difficult as materials and facilities age. The most noteworthy final disposition technical issues include the development of reuse and treatment options.

Gillas, D. L.; Chambers, B. K.

2002-02-26T23:59:59.000Z

126

D0 Decomissioning : Storage of Depleted Uranium Modules Inside D0 Calorimeters after the Termination of D0 Experiment  

Science Conference Proceedings (OSTI)

Dzero liquid Argon calorimeters contain hadronic modules made of depleted uranium plates. After the termination of DO detector's operation, liquid Argon will be transferred back to Argon storage Dewar, and all three calorimeters will be warmed up. At this point, there is no intention to disassemble the calorimeters. The depleted uranium modules will stay inside the cryostats. Depleted uranium is a by-product of the uranium enrichment process. It is slightly radioactive, emits alpha, beta and gamma radiation. External radiation hazards are minimal. Alpha radiation has no external exposure hazards, as dead layers of skin stop it; beta radiation might have effects only when there is a direct contact with skin; and gamma rays are negligible - levels are extremely low. Depleted uranium is a pyrophoric material. Small particles (such as shavings, powder etc.) may ignite with presence of Oxygen (air). Also, in presence of air and moisture it can oxidize. Depleted uranium can absorb moisture and keep oxidizing later, even after air and moisture are excluded. Uranium oxide can powder and flake off. This powder is also pyrographic. Uranium oxide may create health problems if inhaled. Since uranium oxide is water soluble, it may enter the bloodstream and cause toxic effects.

Sarychev, Michael; /Fermilab

2011-09-21T23:59:59.000Z

127

Assessing the Renal Toxicity of Capstone Depleted Uranium Oxides and Other Uranium Compounds  

SciTech Connect

The primary target for uranium toxicity is the kidney. The most frequently used guideline for uranium kidney burdens is the International Commission on Radiation Protection (ICRP) value of 3 g U/g kidney, a value that is based largely upon chronic studies in animals. In the present effort, we have developed a risk model equation to assess potential outcomes of acute uranium exposure. Twenty-seven previously published case studies in which workers were acutely exposed to soluble compounds of uranium (as a result of workplace accidents) were analyzed. Kidney burdens of uranium for these individuals were determined based on uranium in the urine, and correlated with health effects observed over a period of up to 38 years. Based upon the severity of health effects, each individual was assigned a score (- to +++) and then placed into an Effect Group. A discriminant analysis was used to build a model equation to predict the Effect Group based on the amount of uranium in the kidneys. The model equation was able to predict the Effect Group with 85% accuracy. The risk model was used to predict the Effect Group for Soldiers exposed to DU as a result of friendly fire incidents during the 1991 Gulf War. This model equation can also be used to predict the Effect Group of new cases in which acute exposures to uranium have occurred.

Roszell, Laurie E.; Hahn, Fletcher; Lee, Robyn B.; Parkhurst, MaryAnn

2009-02-26T23:59:59.000Z

128

Design of Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety  

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

Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety Matveev V.Z., Morenko A.I., Shapovalov V.I. Russian Federal Nuclear Center - All-Russian Research Institute of Experimental Physics (RFNC-VNIIEF) 37 Mira Prospect, Sarov, Russia, 607190, matveev@vniief.ru Maslov A.A., Orlov V.K., Semenov A.G., Sergeev V.M., Yuferov O.I., Visik A.M. Bochvar Institute of Inorganic Materials (VNIINM) 5-A Rogova street, p.b. 369, Moscow, Russia, 123060, majul2000@mail.ru Abstract - The report is dedicated to a problem of creation of a new generation of dual-purpose transport packing complete sets (TPCS) 1 with advanced safety. These sets are intended for transportation and storage of spent nuclear fuel assemblies (SNFA) 2 of VVER reactors and spent spark elements (SSE)

129

Methods Used to Calculate Doses Resulting from Inhalation of Capstone Depleted Uranium Aerosols  

Science Conference Proceedings (OSTI)

The methods used to calculate radiological and toxicological doses to hypothetical persons inside either a United States Army Abrams tank or Bradley Fighting Vehicle that has been perforated by depleted uranium munitions is described. Data from time- and particle-size-resolved measurements of depleted uranium aerosol as well as particle-size resolved measurements of aerosol solubility in lung fluids for aerosol produced in the breathing zones of the hypothetical occupants were used. The aerosol was approximated as a mixture of nine monodisperse (single particle size) components corresponding to particle size increments measured by the eight stages plus backup filter of the cascade impactors used. A Markov Chain Monte Carlo Bayesian analysis technique was employed, which straightforwardly calculates the uncertainties in doses. Extensive quality control checking of the various computer codes used is described.

Miller, Guthrie; Cheng, Yung-Sung; Traub, Richard J.; Little, Thomas T.; Guilmette, Ray A.

2009-02-26T23:59:59.000Z

130

Summary of the Preliminary Analysis of Savannah River Depleted Uranium Trioxide  

SciTech Connect

This report summarizes a preliminary special analysis of the Savannah River Depleted Uranium Trioxide waste stream (SVRSURANIUM03, Revision 2). The analysis is considered preliminary because a final waste profile has not been submitted for review. The special analysis is performed to determine the acceptability of the waste stream for shallow land burial at the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada National Security Site (NNSS). The Savannah River Depleted Uranium Trioxide waste stream requires a special analysis because the waste streams sum of fractions exceeds one. The 99Tc activity concentration is 98 percent of the NNSS Waste Acceptance Criteria and the largest single contributor to the sum of fractions.

NSTec Environmental Management

2010-10-13T23:59:59.000Z

131

Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel  

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

Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel Vitaly T. Gotovchikov a , Victor A. Seredenko a , Valentin V. Shatalov a , Vladimir N. Kaplenkov a , Alexander S. Shulgin a , Vladimir K. Saranchin a , Michail A. Borik a∗ , Charles W. Forsberg b , All-Russian Research Institute of Chemical Technology (ARRICT) 33, Kashirskoe ave., Moscow, Russia, 115409, E-mail: chem.conv@ru.net Oak Ridge National Laboratory (ORNL) Bethel Wall Road, P.O. Box 2008, MS-6165, Oak Ridge, TN, USA, 37831 Abstract - Induction cold crucible melters (ICCM) have the potential to be a very-low-cost high-throughput method for the production of DUO 2 for SNF casks. The proposed work would develop these melters for this specific application. If a

132

Development of a Novel Depleted Uranium Treatment Process at Lawrence Livermore National Laboratory  

Science Conference Proceedings (OSTI)

A three-stage process was developed at Lawrence Livermore National Laboratory to treat potentially pyrophoric depleted uranium metal wastes. The three-stage process includes waste sorting/rinsing, acid dissolution of the waste metal with a hydrochloric and phosphoric acid solution, and solidification of the neutralized residuals from the second stage with clay. The final product is a solid waste form that can be transported to and disposed of at a permitted low-level radioactive waste disposal site.

Gates-Anderson, D; Bowers, J; Laue, C; Fitch, T

2007-01-22T23:59:59.000Z

133

Depleted uranium oxides as spent-nuclear-fuel waste-package invert and backfill materials  

SciTech Connect

A new technology has been proposed in which depleted uranium, in the form of oxides or silicates, is placed around the outside of the spent nuclear fuel waste packages in the geological repository. This concept may (1) reduce the potential for repository nuclear criticality events and (2) reduce long-term release of radionuclides from the repository. As a new concept, there are significant uncertainties.

Forsberg, C.W.; Haire, M.J.

1997-07-07T23:59:59.000Z

134

The Office of Environmental Management Uranium Enrichment D&D...  

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

Uranium Enrichment D&D The Office of Environmental Management Uranium Enrichment D&D Microsoft Word - B996F741.doc More Documents & Publications Microsoft Word - PSRP Updates...

135

Lawrence Berkeley National Laboratory 1996 Site Environmental Report Vol. I  

E-Print Network (OSTI)

radioactive. uranium, depleted Uranium consisting primarilyoccurring in nature, depleted uranium is man-made. uranium,

2010-01-01T23:59:59.000Z

136

Updated Uranium Fuel Cycle Environmental Impacts for Advanced Reactor Designs  

Science Conference Proceedings (OSTI)

The purpose of this project was to update the environmental impacts from the uranium fuel cycle for select advanced (GEN III+) reactor designs.

Nitschke, R.

2004-10-03T23:59:59.000Z

137

Aerosol Sampling System for Collection of Capstone Depleted Uranium Particles in a High-Energy Environment  

SciTech Connect

The Capstone Depleted Uranium Aerosol Study was undertaken to obtain aerosol samples resulting from a kinetic-energy cartridge with a large-caliber depleted uranium (DU) penetrator striking an Abrams or Bradley test vehicle. The sampling strategy was designed to (1) optimize the performance of the samplers and maintain their integrity in the extreme environment created during perforation of an armored vehicle by a DU penetrator, (2) collect aerosols as a function of time post-impact, and (3) obtain size-classified samples for analysis of chemical composition, particle morphology, and solubility in lung fluid. This paper describes the experimental setup and sampling methodologies used to achieve these objectives. Custom-designed arrays of sampling heads were secured to the inside of the target in locations approximating the breathing zones of the vehicle commander, loader, gunner, and driver. Each array was designed to support nine filter cassettes and nine cascade impactors mounted with quick-disconnect fittings. Shielding and sampler placement strategies were used to minimize sampler loss caused by the penetrator impact and the resulting fragments of eroded penetrator and perforated armor. A cyclone train was used to collect larger quantities of DU aerosol for chemical composition and solubility. A moving filter sample was used to obtain semicontinuous samples for depleted uranium concentration determination. Control for the air samplers was provided by five remotely located valve control and pressure monitoring units located inside and around the test vehicle. These units were connected to a computer interface chassis and controlled using a customized LabVIEW engineering computer control program. The aerosol sampling arrays and control systems for the Capstone study provided the needed aerosol samples for physicochemical analysis, and the resultant data were used for risk assessment of exposure to DU aerosol.

Holmes, Thomas D.; Guilmette, Raymond A.; Cheng, Yung-Sung; Parkhurst, MaryAnn; Hoover, Mark D.

2009-03-01T23:59:59.000Z

138

DOE Extends Public Comment Period for Uranium Program Environmental Impact  

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

Uranium Program Environmental Uranium Program Environmental Impact Statement DOE Extends Public Comment Period for Uranium Program Environmental Impact Statement April 18, 2013 - 1:08pm Addthis Contractor, Bob Darr, S.M. Stoller Corporation Public Affairs, (720) 377-9672, ULinfo@lm.doe.gov GRAND JUNCTION, Colo. - The U.S. Department of Energy (DOE) today announced that the public comment period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS) has been extended to May 31, 2013. Under the Uranium Leasing Program, DOE's Office of Legacy Management manages 31 tracts of land in Mesa, Montrose, and San Miguel counties in Colorado - approximately 25,000 acres - that are leased to private entities for uranium and vanadium mining. No mining operations are active

139

Physicochemical Characterization of Capstone Depleted Uranium Aerosols II: Particle Size Distributions as a Function of Time  

SciTech Connect

The Capstone Depleted Uranium (DU) Aerosol Study, which generated and characterized aerosols containing depleted uranium from perforation of armored vehicles with large-caliber DU penetrators, incorporated a sampling protocol to evaluated particle size distributions. Aerosol particle size distribution is an important parameter that influences aerosol transport and deposition processes as well as the dosimetry of the inhaled particles. These aerosols were collected on cascade impactor substrates using a pre-established time sequence following the firing event to analyze the uranium concentration and particle size of the aerosols as a function of time. The impactor substrates were analyzed using beta spectrometry, and the derived uranium content of each served as input to the evaluation of particle size distributions. Activity median aerodynamic diameters (AMADs) of the particle size distributions were evaluated using unimodal and bimodal models. The particle size data from the impactor measurements was quite variable. Most size distributions measured in the test based on activity had bimodal size distributions with a small particle size mode in the range of between 0.2 and 1.2 um and a large size mode between 2 and 15 um. In general, the evolution of particle size over time showed an overall decrease of average particle size from AMADs of 5 to 10 um shortly after perforation to around 1 um at the end of the 2-hr sampling period. The AMADs generally decreased over time because of settling. Additionally, the median diameter of the larger size mode decreased with time. These results were used to estimate the dosimetry of inhaled DU particles.

Cheng, Yung-Sung; Kenoyer, Judson L.; Guilmette, Raymond A.; Parkhurst, MaryAnn

2009-03-01T23:59:59.000Z

140

Assessing the risk from the depleted uranium weapons used in Operation Allied Force  

E-Print Network (OSTI)

The conflict in Yugoslavia has been a source of great concern for the neighboring countries, about the radiological and toxic hazard posed by the alleged presence of depleted uranium in NATO weapons. In the present study a worst-case scenario is assumed mainly to assess the risk for Greece and other neighboring countries of Yugoslavia at similar distances . The risk of the weapons currently in use is proved to be negligible at distances greater than 100 Km. For shorter distances classified data of weapons composition are needed to obtain a reliable assessment.

Liolios, T E

1999-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Assessing the environmental availability of uranium in soils and sediments  

Science Conference Proceedings (OSTI)

Soils and sediments contaminated with uranium pose certain environmental and ecological risks. At low to moderate levels of contamination, the magnitude of these risks depends not only on the absolute concentrations of uranium in the material but also on the availability of the uranium to drinking water supplies, plants, or higher organisms. Rational approaches for regulating the clean-up of sites contaminated with uranium, therefore, should consider the value of assessing the environmental availability of uranium at the site before making decisions regarding remediation. The purpose of this work is to review existing approaches and procedures to determine their potential applicability for assessing the environmental availability of uranium in bulk soils or sediments. In addition to making the recommendations regarding methodology, the authors have tabulated data from the literature on the aqueous complexes of uranium and major uranium minerals, examined the possibility of predicting environmental availability of uranium based on thermodynamic solubility data, and compiled a representative list of analytical laboratories capable of performing environmental analyses of uranium in soils and sediments.

Amonette, J.E.; Holdren, G.R. Jr.; Krupa, K.M.; Lindenmeier, C.W. [Pacific Northwest Lab., Richland, WA (United States)

1994-06-01T23:59:59.000Z

142

CRAD, Environmental Protection - Y-12 Enriched Uranium Operations Oxide  

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

Environmental Protection - Y-12 Enriched Uranium Operations Environmental Protection - Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Environmental Protection - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a January 2005 assessment of Environmental Compliance program at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Environmental Protection - Y-12 Enriched Uranium Operations Oxide Conversion Facility More Documents & Publications

143

Physicochemical Characterization of Capstone Depleted Uranium Aerosols III: Morphologic and Chemical Oxide Analyses  

Science Conference Proceedings (OSTI)

The impact of depleted uranium (DU) penetrators against an armored target causes erosion and fragmentation of the penetrators, the extent of which is dependent on the thickness and material composition of the target. Vigorous oxidation of the DU particles and fragments creates an aerosol of DU oxide particles and DU particle agglomerations combined with target materials. Aerosols from the Capstone DU aerosol study, in which vehicles were perforated by DU penetrators, were evaluated for their oxidation states using X-ray diffraction (XRD) and particle morphologies using scanning electron microscopy/energy dispersive spectrometry (SEM/EDS). The oxidation state of a DU aerosol is important as it offers a clue to its solubility in lung fluids. The XRD analysis showed that the aerosols evaluated were a combination primarily of U3O8 (insoluble) and UO3 (relatively more soluble) phases, though intermediate phases resembling U4O9 and other oxides were prominent in some samples. Analysis of particle residues in the micrometer-size range by SEM/EDS provided microstructural information such as phase composition and distribution, fracture morphology, size distribution, and material homogeneity. Observations from SEM analysis show a wide variability in the shapes of the DU particles. Some of the larger particles appear to have been fractured (perhaps as a result of abrasion and comminution); others were spherical, occasionally with dendritic or lobed surface structures. Amorphous conglomerates containing metals other than uranium were also common, especially with the smallest particle sizes. A few samples seemed to contain small chunks of nearly pure uranium metal, which were verified by EDS to have a higher uranium content exceeding that expected for uranium oxides. Results of the XRD and SEM/EDS analyses were used in other studies described in this issue of The Journal of Health Physics to interpret the results of lung solubility studies and in selecting input parameters for dose assessments.

Krupka, Kenneth M.; Parkhurst, MaryAnn; Gold, Kenneth; Arey, Bruce W.; Jenson, Evan D.; Guilmette, Raymond A.

2009-03-01T23:59:59.000Z

144

Detection of uranium enrichment activities using environmental monitoring techniques  

SciTech Connect

Uranium enrichment processes have the capability of producing weapons-grade material in the form of highly enriched uranium. Thus, detection of undeclared uranium enrichment activities is an international safeguards concern. The uranium separation technologies currently in use employ UF{sub 6} gas as a separation medium, and trace quantities of enriched uranium are inevitably released to the environment from these facilities. The isotopic content of uranium in the vegetation, soil, and water near the plant site will be altered by these releases and can provide a signature for detecting the presence of enriched uranium activities. This paper discusses environmental sampling and analytical procedures that have been used for the detection of uranium enrichment facilities and possible safeguards applications of these techniques.

Belew, W.L.; Carter, J.A.; Smith, D.H.; Walker, R.L.

1993-03-30T23:59:59.000Z

145

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 calorimeter upgrading  

E-Print Network (OSTI)

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 calorimeter upgrading

1986-01-01T23:59:59.000Z

146

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 experiment  

E-Print Network (OSTI)

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 experiment

1986-01-01T23:59:59.000Z

147

Depleted uranium hexafluoride (DUF{sub 6}) management system--a decision tool  

Science Conference Proceedings (OSTI)

The Depleted Uranium Hexafluoride (DUF{sub 6}) Management System (DMS) is being developed as a decision tool to provide cost and risk data for evaluation of short-and long-term management strategies for depleted uranium. It can be used to assist decision makers on a programmatic or site-specific level. Currently, the DMS allows evaluation of near-term cylinder management strategies such as storage yard improvements, cylinder restocking, and reconditioning. The DMS has been designed to provide the user with maximum flexibility for modifying data and impact factors (e.g., unit costs and risk factors). Sensitivity analysis can be performed on all key parameters such as cylinder corrosion rate, inspection frequency, and impact factors. Analysis may be conducted on a system-wide, site, or yard basis. The costs and risks from different scenarios may be compared in graphic or tabular format. Ongoing development of the DMS will allow similar evaluation of long-term management strategies such as conversion to other chemical forms. The DMS is a Microsoft Windows 3.1 based, stand-alone computer application. It can be operated on a 486 or faster computer with VGA, 4 MB of RAM, and 10 MB of disk space.

Gasper, J.R.; Sutter, R.J.; Avci, H.I. [and others

1995-12-31T23:59:59.000Z

148

Summary of the cost analysis report for the long-term management of depleted uranium hexafluoride  

SciTech Connect

This report is a summary of the Cost Analysis Report which provides comparative cost data for the management strategy alternatives. The PEIS and the Cost Analysis Report will help DOE select a management strategy. The Record of Decision, expected in 1998, will complete the first part of the Depleted Uranium Hexafluoride Management Program. The second part of the Program will look at specific sites and technologies for carrying out the selected strategy. The Cost Analysis Report estimates the primary capital and operating costs for the different alternatives. It reflects the costs of technology development construction of facilities, operation, and decontamination and decommissioning. It also includes potential revenues from the sale of by-products such as anhydrous hydrogen fluoride (ABF). These estimates are based on early designs. They are intended to help in comparing alternatives, rather than to indicate absolute costs for project budgets or bidding purposes. More detailed estimates and specific funding sources will be considered in part two of the Depleted Uranium Hexafluoride Management Program.

Dubrin, J.W.; Rahm-Crites, L.

1997-09-01T23:59:59.000Z

149

Characterization of options and their analysis requirements for the long-term management of depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) is examining alternative strategies for the long-term management of depleted uranium hexafluoride (UF{sub 6}) currently stored at the gaseous diffusion plants at Portsmouth, Ohio, and Paducah, Kentucky, and on the Oak Ridge Reservation in Oak Ridge, Tennessee. This paper describes the methodology for the comprehensive and ongoing technical analysis of the options being considered. An overview of these options, along with several of the suboptions being considered, is presented. The long-term management strategy alternatives fall into three broad categories: use, storage, or disposal. Conversion of the depleted UF6 to another form such as oxide or metal is needed to implement most of these alternatives. Likewise, transportation of materials is an integral part of constructing the complete pathway between the current storage condition and ultimate disposition. The analysis of options includes development of pre-conceptual designs; estimates of effluents, wastes, and emissions; specification of resource requirements; and preliminary hazards assessments. The results of this analysis will assist DOE in selecting a strategy by providing the engineering information necessary to evaluate the environmental impacts and costs of implementing the management strategy alternatives.

Dubrin, J.W.; Rosen, R.S.; Zoller, J.N.; Harri, J.W.; Schwertz, N.L.

1995-12-01T23:59:59.000Z

150

DOE Prepares Programmatic Environmental Impact Statement for the Uranium  

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

Prepares Programmatic Environmental Impact Statement for the Prepares Programmatic Environmental Impact Statement for the Uranium Leasing Program DOE Prepares Programmatic Environmental Impact Statement for the Uranium Leasing Program January 18, 2012 - 3:13pm Addthis DOE Prepares Programmatic Environmental Impact Statement for the Uranium Leasing Program What does this project do? Goal 4. Optimize the use of land and assets The U.S. Department of Energy (DOE) Office of Legacy Management is responsible for administering the DOE Uranium Leasing Program (ULP) and its 31 uranium lease tracts located in the Uravan Mineral Belt of southwestern Colorado. The ULP began in 1948 when Congress authorized the U.S. Atomic Energy Commis-sion (AEC), a predecessor agency of DOE, to withdraw lands from the public domain for the sole purpose of exploring for, developing,

151

Draft Uranium Leasing Program Programmatic Environmental Impact...  

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

five times the uranium concentration; this ratio was selected on the basis of the mining production rate of vanadium versus that of uranium. The RfCs used in the calculation were...

152

Conclusions of the Capstone Depleted Uranium Aerosol Characterization and Risk Assessment Study  

Science Conference Proceedings (OSTI)

The rationale for the Capstone Depleted Uranium (DU) Aerosol Characterization and Risk Assessment Program and its results and applications have been examined in the previous 13 articles of this special issue. This paper summarizes the results and discusses its successes and lessons learned. The robust data from the Capstone DU Aerosol Study have provided a sound basis for assessing the inhalation exposure to DU aerosols and the dose and risk to personnel in combat vehicles at the time of perforation and to those entering immediately after perforation. The Human Health Risk Assessment provided a technically sound process for evaluating chemical and radiological doses and risks from DU aerosol exposure using well-accepted biokinetic and dosimetric models innovatively applied. An independent review of the study process and results is summarized, and recommendations for possible avenues of future study by the authors and by other major reviews of DU health hazards are provided.

Parkhurst, MaryAnn; Guilmette, Raymond A.

2009-02-26T23:59:59.000Z

153

Assessing the risk from the depleted Uranium weapons used in Operation Allied Force.  

E-Print Network (OSTI)

The conflict in Yugoslavia has been a source of great concern due to the radiological and toxic hazard posed by the alleged presence of depleted uranium in NATO weapons. In the present study some worst-case scenaria are assumed in order to assess the risk for Yugoslavia and its neighboring countries. The risk is proved to be negligible for the neighboring countries while for Yugoslavia itself evidence is given that any increase in total long-term cancer mortality will be so low that it will remain undetected. Local radioactive hotspots such as DU weapons fragments and abandoned battle tanks, fortified or contaminated with DU, constitute a post-war hazard which is not studied in this article.

unknown authors

1999-01-01T23:59:59.000Z

154

Oxidation of depleted uranium penetrators and aerosol dispersal at high temperatures  

SciTech Connect

Aerosols dispersed from depleted uranium penetrators exposed to air and air-CO/sub 2/ mixtures at temperatures ranging from 500 to 1000/sup 0/C for 2- or 4-h periods were characterized. These experiments indicated dispersal of low concentrations of aerosols in the respirable size range (typically <10/sup -3/% of penetrator mass at 223 cm/s (5 mph) windspeed). Oxidation was maximum at 700/sup 0/C in air and 800/sup 0/C in 50% air-50% CO/sub 2/, indicating some self-protection developed at higher temperatures. No evidence of self-sustained burning was observed, although complete oxidation can be expected in fires significantly exceeding 4 h, the longest exposure of this series. An outdoor burning experiment using 10 batches of pine wood and paper packing material as fuel caused the highest oxidation rate, probably accelerated by disruption of the oxide layer accompanying broad temperature fluctuation as each fuel batch was added.

Elder, J.C.; Tinkle, M.C.

1980-12-01T23:59:59.000Z

155

Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium  

E-Print Network (OSTI)

The neutron emission rates from five very pure actinide samples (Th-232, Np-237, Pu-239, Pu-241 and depleted uranium) were measured following equilibrium irradiation in fast and thermal neutron fluxes. The relative abundances (alphas) for the first four groups were calculated from the delayed neutron emission (counts vs. time) data using Keepin's 6-group decay constants (lambdas) for Th-232, Pu-239 and depleted uranium (both fast and thermal neutron induced fissions). The relative abundances (alphas) for the first five groups were calculated for the fast neutron induced fission of Np-237 using the 7-group lambdas obtained by Charlton (1997). The relative abundances for the first five groups were also calculated using the 7-group lambdas proposed by Loaiza and Haskin (2000), the 8-group lambdas proposed by Campbell and Spriggs (1998) and the 8-group lambdas proposed by Piksaikin (2000) for all of the samples (fast neutron induced fission only for Th-232 and Np-237, fast and thermal neutron induced fission for the remainder). Fission product yield and delayed neutron emission probability data from the ENDF-349 and JEF 2.2 nuclear data libraries were also used to simulate neutron emission data from the samples. The calculated neutron yield curves were used to obtain group relative abundances for each of the five actinide samples (fast neutron induced fission only for Th-232 and Np-237, fast and thermal neutron induced fission for the remainder) based on each set of proposed lambdas. The relative abundances obtained from the experiments and calculations are compared and the differences are noted and discussed.

Stone, Joseph C.

2001-01-01T23:59:59.000Z

156

ZPR-3 Assembly 11 : A cylindrical sssembly of highly enriched uranium and depleted uranium with an average {sup 235}U enrichment of 12 atom % and a depleted uranium reflector.  

Science Conference Proceedings (OSTI)

Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 11 (ZPR-3/11) was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 12 at.% and a depleted uranium reflector. Approximately 79.7% of the total fissions in this assembly occur above 100 keV, approximately 20.3% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 8 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specificationsa and has historically been used as a data validation benchmark assembly. Loading of ZPR-3 Assembly 11 began in early January 1958, and the Assembly 11 program ended in late January 1958. The core consisted of highly enriched uranium (HEU) plates and depleted uranium plates loaded into stainless steel drawers, which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of two columns of 0.125 in.-wide (3.175 mm) HEU plates, six columns of 0.125 in.-wide (3.175 mm) depleted uranium plates and one column of 1.0 in.-wide (25.4 mm) depleted uranium plates. The length of each column was 10 in. (254.0 mm) in each half of the core. The axial blanket consisted of 12 in. (304.8 mm) of depleted uranium behind the core. The thickness of the depleted uranium radial blanket was approximately 14 in. (355.6 mm), and the length of the radial blanket in each half of the matrix was 22 in. (558.8 mm). The assembly geometry approximated a right circular cylinder as closely as the square matrix tubes allowed. According to the logbook and loading records for ZPR-3/11, the reference critical configuration was loading 10 which was critical on January 21, 1958. Subsequent loadings were very similar but less clean for criticality because there were modifications made to accommodate reactor physics measurements other than criticality. Accordingly, ZPR-3/11 loading 10 was selected as the only configuration for this benchmark. As documented below, it was determined to be acceptable as a criticality safety benchmark experiment. A very accurate transformation to a simplified model is needed to make any ZPR assembly a practical criticality-safety benchmark. There is simply too much geometric detail in an exact (as-built) model of a ZPR assembly, even a clean core such as ZPR-3/11 loading 10. The transformation must reduce the detail to a practical level without masking any of the important features of the critical experiment. And it must do this without increasing the total uncertain

Lell, R. M.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; National Security; Inst. of Physics and Power Engineering

2010-09-30T23:59:59.000Z

157

BLENDING LOW ENRICHED URANIUM WITH DEPLETED URANIUM TO CREATE A SOURCE MATERIAL ORE THAT CAN BE PROCESSED FOR THE RECOVERY OF YELLOWCAKE AT A CONVENTIONAL URANIUM MILL  

SciTech Connect

Throughout the United States Department of Energy (DOE) complex, there are a number of streams of low enriched uranium (LEU) that contain various trace contaminants. These surplus nuclear materials require processing in order to meet commercial fuel cycle specifications. To date, they have not been designated as waste for disposal at the DOE's Nevada Test Site (NTS). Currently, with no commercial outlet available, the DOE is evaluating treatment and disposal as the ultimate disposition path for these materials. This paper will describe an innovative program that will provide a solution to DOE that will allow disposition of these materials at a cost that will be competitive with treatment and disposal at the NTS, while at the same time recycling the material to recover a valuable energy resource (yellowcake) for reintroduction into the commercial nuclear fuel cycle. International Uranium (USA) Corporation (IUSA) and Nuclear Fuel Services, Inc. (NFS) have entered into a commercial relationship to pursue the development of this program. The program involves the design of a process and construction of a plant at NFS' site in Erwin, Tennessee, for the blending of contaminated LEU with depleted uranium (DU) to produce a uranium source material ore (USM Ore{trademark}). The USM Ore{trademark} will then be further processed at IUC's White Mesa Mill, located near Blanding, Utah, to produce conventional yellowcake, which can be delivered to conversion facilities, in the same manner as yellowcake that is produced from natural ores or other alternate feed materials. The primary source of feed for the business will be the significant sources of trace contaminated materials within the DOE complex. NFS has developed a dry blending process (DRYSM Process) to blend the surplus LEU material with DU at its Part 70 licensed facility, to produce USM Ore{trademark} with a U235 content within the range of U235 concentrations for source material. By reducing the U235 content to source material levels in this manner, the material will be suitable for processing at a conventional uranium mill under its existing Part 40 license to remove contaminants and enable the product to re-enter the commercial fuel cycle. The tailings from processing the USM Ore{trademark} at the mill will be permanently disposed of in the mill's tailings impoundment as 11e.(2) byproduct material. Blending LEU with DU to make a uranium source material ore that can be returned to the nuclear fuel cycle for processing to produce yellowcake, has never been accomplished before. This program will allow DOE to disposition its surplus LEU and DU in a cost effective manner, and at the same time provide for the recovery of valuable energy resources that would be lost through processing and disposal of the materials. This paper will discuss the nature of the surplus LEU and DU materials, the manner in which the LEU will be blended with DU to form a uranium source material ore, and the legal means by which this blending can be accomplished at a facility licensed under 10 CFR Part 70 to produce ore that can be processed at a conventional uranium mill licensed under 10 CFR Part 40.

Schutt, Stephen M.; Hochstein, Ron F.; Frydenlund, David C.; Thompson, Anthony J.

2003-02-27T23:59:59.000Z

158

Proceedings of a workshop on uses of depleted uranium in storage, transportation and repository facilities  

SciTech Connect

A workshop on the potential uses of depleted uranium (DU) in the repository was organized to coordinate the planning of future activities. The attendees, the original workshop objective and the agenda are provided in Appendices A, B and C. After some opening remarks and discussions, the objectives of the workshop were revised to: (1) exchange information and views on the status of the Department of Energy (DOE) activities related to repository design and planning; (2) exchange information on DU management and planning; (3) identify potential uses of DU in the storage, transportation, and disposal of high-level waste and spent fuel; and (4) define the future activities that would be needed if potential uses were to be further evaluated and developed. This summary of the workshop is intended to be an integrated resource for planning of any future work related to DU use in the repository. The synopsis of the first day`s presentations is provided in Appendix D. Copies of slides from each presenter are presented in Appendix E.

NONE

1997-12-31T23:59:59.000Z

159

Pyrolitic Uranium Compound (PYRUC)  

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

Pyrolitic Uranium Compound Pyrolitic Uranium Compound (PYRUC) PYRolitic Uranium Compound (PYRUC) is a shielding material consisting of depleted uranium UO2 or UC in either pellet...

160

EIS-0359: Notice of Change in National Environmental Policy ...  

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

Environmental Policy (NEPA) Compliance Approach Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project Notice of Change in National Environmental Policy (NEPA)...

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Uranium Mill Tailings Remedial Action Project 1993 Environmental Report  

SciTech Connect

This annual report documents the Uranium Mill Tailing Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1993, surface remedial action was complete at 10 of the 24 designated UMTRA Project processing sites. In 1993 the UMTRA Project office revised the UMTRA Project Environmental Protection Implementation Plan, as required by the US DOE. Because the UMTRA Project sites are in different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.

Not Available

1994-10-01T23:59:59.000Z

162

DOE Announces Transfer of Depleted Uranium to Advance the U.S...  

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

low-enriched uranium related to NNSA's programs for down-blending surplus U.S. highly enriched uranium. Based on this analysis, Secretary Chu made a determination that the above...

163

Isotopic dilution of {sup 233}U with depleted uranium for criticality safety in processing and disposal  

SciTech Connect

The disposal of excess {sup 233}U as waste is being considered. Because {sup 233}U is a fissile material, a key requirement for processing {sup 233}U to a final waste form and disposing of it is the avoidance of nuclear criticality. For many processing and disposal options, isotopic dilution is the most feasible and preferred option to avoid nuclear criticality. Isotopic dilution is dilution of fissile {sup 233}U with nonfissile {sup 238}U. The use of isotopic dilution removes any need to control nuclear criticality in process or disposal facilities through geometry or chemical composition. Isotopic dilution allows the use of existing waste management facilities that are not designed for significant quantities of fissile materials to be used for processing and disposing of {sup 233}U. The amount of isotopic dilution required to reduce criticality concerns to reasonable levels was determined in this study to be approximately 0.53 wt % {sup 233}U. The numerical calculations used to define this limit consisted of a homogeneous system of silicon dioxide (SiO{sub 2}), water (H{sub 2}O), {sup 233}U and depleted uranium (DU) in which the ratio of each component was varied to learn the conditions of maximum nuclear reactivity. About 188 parts of DU (0.2 wt % {sup 235}U) are required to dilute 1 part of {sup 233}U to this limit in a water-moderated system with no SiO{sub 2} present. Thus for the U.S. inventory of {sup 233}U, several hundred metric tons of DU would be required for isotopic dilution.

Hopper, C.M.; Wright, R.Q.; Elam, K.R.; Forsberg, C.W.

1997-07-01T23:59:59.000Z

164

Expansion of U. S. uranium enrichment capacity. Final environmental statement  

SciTech Connect

Reasonably foreseeable environmental, social, economic, and technological costs and benefits of postulated expansion of U. S. enrichment capacity through the year 2000 and reasonably available alternatives to such expansion are described. Both the gas centrifuge and gaseous diffusion methods for the enrichment of uranium are considered in this impact assessment. (JGB)

1976-04-01T23:59:59.000Z

165

Biological assessment of the effects of construction and operation of a depleted uranium hexafluoride conversion facility at the Paducah, Kentucky, site.  

SciTech Connect

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF6 inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This biological assessment (BA) has been prepared by DOE, pursuant to the National Environmental Policy Act of 1969 (NEPA) and the Endangered Species Act of 1974, to evaluate potential impacts to federally listed species from the construction and operation of a conversion facility at the DOE Paducah site.

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

166

Biological assessment of the effects of construction and operation of a depleted uranium hexafluoride conversion facility at the Paducah, Kentucky, site.  

SciTech Connect

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF6 inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This biological assessment (BA) has been prepared by DOE, pursuant to the National Environmental Policy Act of 1969 (NEPA) and the Endangered Species Act of 1974, to evaluate potential impacts to federally listed species from the construction and operation of a conversion facility at the DOE Paducah site.

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

167

Uranium Mill Tailings Remedial Action Project environmental protection implementation plan  

Science Conference Proceedings (OSTI)

The Uranium Mill Tailings Remedial Action (UMTRA) Project Environmental Protection Implementation Plan (EPIP) has been prepared in accordance with the requirements of the U.S. Department of Energy (DOE) Order 5400.1. The UMTRA EPIP is updated annually. This version covers the time period of 9 November 1994, through 8 November 1995. Its purpose is to provide management direction to ensure that the UMTRA Project is operated and managed in a manner that will protect, maintain, and where necessary, restore environmental quality, minimize potential threats to public health and the environment, and comply with environmental regulations and DOE policies.

Not Available

1994-10-01T23:59:59.000Z

168

Final Environmental assessment for the Uranium Lease Management Program  

SciTech Connect

The US Department of Energy (DOE) has prepared a programmatic environmental assessment (EA) of the proposed action to continue leasing withdrawn lands and DOE-owned patented claims for the exploration and production of uranium and vanadium ores. The Domestic Uranium Program regulation, codified at Title 10, Part 760.1, of the US Code of Federal Regulations (CFR), gives DOE the flexibility to continue leasing these lands under the Uranium Lease Management Program (ULMP) if the agency determines that it is in its best interest to do so. A key element in determining what is in DOE`s ``best interest`` is the assessment of the environmental impacts that may be attributable to lease tract operations and associated activities. On the basis of the information and analyses presented in the EA for the ULMP, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined in the National Environmental Policy Act (NEPA) of 1969 (42 United States Code 4321 et seq.), as amended.Therefore, preparation of an environmental impact statement is not required for the ULMP,and DOE is issuing this Finding, of No Significant Impact (FONSI).

NONE

1995-07-01T23:59:59.000Z

169

Long-term criticality control in radioactive waste disposal facilities using depleted uranium  

SciTech Connect

Plant photosynthesis has created a unique planetary-wide geochemistry - an oxidizing atmosphere with oxidizing surface waters on a planetary body with chemically reducing conditions near or at some distance below the surface. Uranium is four orders of magnitude more soluble under chemically oxidizing conditions than it is under chemically reducing conditions. Thus, uranium tends to leach from surface rock and disposal sites, move with groundwater, and concentrate where chemically reducing conditions appear. Earth`s geochemistry concentrates uranium and can separate uranium from all other elements except oxygen, hydrogen (in water), and silicon (silicates, etc). Fissile isotopes include {sup 235}U, {sup 233}U, and many higher actinides that eventually decay to one of these two uranium isotopes. The potential for nuclear criticality exists if the precipitated uranium from disposal sites has a significant fissile enrichment, mass, and volume. The earth`s geochemistry suggests that isotopic dilution of fissile materials in waste with {sup 238}U is a preferred strategy to prevent long-term nuclear criticality in and beyond the boundaries of waste disposal facilities because the {sup 238}U does not separate from the fissile uranium isotopes. Geological, laboratory, and theoretical data indicate that the potential for nuclear criticality can be minimized by diluting fissile materials with-{sup 238}U to 1 wt % {sup 235}U equivalent.

Forsberg, C.W.

1997-02-19T23:59:59.000Z

170

Uranium Mill Tailings Remedial Action Project Environmental Protection Implementation Plan  

Science Conference Proceedings (OSTI)

The Uranium Mill Tailings Remedial Action (UMTRA) Project Environmental Protection Implementation Plan (EPIP) has been prepared in accordance with the requirements of the US Department of Energy (DOE) Order 5400.1. The UMTRA EPIP covers the time period of November 9, 1993, through November 8, 1994. It will be updated annually. Its purpose is to provide management direction to ensure that the UMTRA Project is operated and managed in a manner that will protect, maintain, and where necessary, restore environmental quality, minimize potential threats to public health and the environment, and comply with environmental regulations and DOE policies. Contents of this report are: (1) general description of the UMTRA project environmental protection program; (2) notifications; (3) planning and reporting; (4) special programs; (5) environmental monitoring programs; (6) quality assurance and data verification; and (7) references.

Vollmer, A.T.

1993-10-01T23:59:59.000Z

171

ZPR-3 Assembly 6F : A spherical assembly of highly enriched uranium, depleted uranium, aluminum and steel with an average {sup 235}U enrichment of 47 atom %.  

SciTech Connect

Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 6 consisted of six phases, A through F. In each phase a critical configuration was constructed to simulate a very simple shape such as a slab, cylinder or sphere that could be analyzed with the limited analytical tools available in the 1950s. In each case the configuration consisted of a core region of metal plates surrounded by a thick depleted uranium metal reflector. The average compositions of the core configurations were essentially identical in phases A - F. ZPR-3 Assembly 6F (ZPR-3/6F), the final phase of the Assembly 6 program, simulated a spherical core with a thick depleted uranium reflector. ZPR-3/6F was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 47 at.%. Approximately 81.4% of the total fissions in this assembly occur above 100 keV, approximately 18.6% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 7 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications and has historically been used as a data validation benchmark assembly. Loading of ZPR-3/6F began in late December 1956, and the experimental measurements were performed in January 1957. The core consisted of highly enriched uranium (HEU) plates, depleted uranium plates, perforated aluminum plates and stainless steel plates loaded into aluminum drawers, which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of three columns of 0.125 in.-wide (3.175 mm) HEU plates, three columns of 0.125 in.-wide depleted uranium plates, nine columns of 0.125 in.-wide perforated aluminum plates and one column of stainless steel plates. The maximum length of each column of core material in a drawer was 9 in. (228.6 mm). Because of the goal to produce an approximately spherical core, core fuel and diluent column lengths generally varied between adjacent drawers and frequently within an individual drawer. The axial reflector consisted of depleted uranium plates and blocks loaded in the available space in the front (core) drawers, with the remainder loaded into back drawers behind the front drawers. The radial reflector consisted of blocks of depleted uranium loaded directly into the matrix tubes. The assembly geometry approximated a reflected sphere as closely as the square matrix tubes, the drawers and the shapes of fuel and diluent plates allowed. According to the logbook and loading records for ZPR-3/6F

Lell, R. M.; McKnight, R. D; Schaefer, R. W.; Nuclear Engineering Division

2010-09-30T23:59:59.000Z

172

Bacterial influence on uranium oxidation reduction reactions : implications for environmental remediation and isotopic composition  

E-Print Network (OSTI)

The bacterial influence on the chemistry and speciation of uranium has some important impacts on the environment, and can be exploited usefully for the purposes of environmental remediation of uranium waste contamination. ...

Mullen, Lisa Maureen

2007-01-01T23:59:59.000Z

173

Uranium Mill Tailings Remedial Action Project. 1995 Environmental Report  

SciTech Connect

In accordance with U.S. Department of Energy (DOE) Order 23 1. 1, Environment, Safety and Health Reporting, the DOE prepares an annual report to document the activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring program. This monitoring must comply with appropriate laws, regulations, and standards, and it must identify apparent and meaningful trends in monitoring results. The results of all monitoring activities must be communicated to the public. The UMTRA Project has prepared annual environmental reports to the public since 1989.

NONE

1996-06-01T23:59:59.000Z

174

Safe Operating Procedure SAFETY PROTOCOL: URANIUM  

E-Print Network (OSTI)

bodies depleted by uranium solution extraction and which remain underground do not constitute byproductEPA Update: NESHAP Uranium Activities Reid J. Rosnick Environmental Protection Agency Radiation Protection Division (6608J) Washington, DC 20460 NMA/NRC Uranium Recovery Workshop July 2, 2009 #12

Farritor, Shane

175

Environmental Survey preliminary report, Portsmouth Uranium Enrichment Complex, Piketon, Ohio  

Science Conference Proceedings (OSTI)

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Portsmouth Uranium Enrichment Complex (PUEC), conducted August 4 through August 15, 1986. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Team specialists are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations performed at PUEC, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by Argonne National Laboratory. When completed, the results will be incorporated into the PUEC Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the PUEC Survey. 55 refs., 22 figs., 21 tabs.

Not Available

1987-08-01T23:59:59.000Z

176

Overview: A Legacy of Uranium Enrichment  

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

A Legacy of Uranium Enrichment Depleted Uranium is a Legacy of Uranium Enrichment Cylinders Photo Next Screen Management Responsibilities...

177

Uranium Mill Tailings Remedial Action Project 1994 environmental report  

Science Conference Proceedings (OSTI)

This annual report documents the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1994, surface remedial action was complete at 14 of the 24 designated UMTRA Project processing sites: Canonsburg, Pennsylvania; Durango, Colorado; Grand Junction, Colorado; Green River Utah, Lakeview, Oregon; Lowman, Idaho; Mexican Hat, Utah; Riverton, Wyoming; Salt Lake City, Utah; Falls City, Texas; Shiprock, New Mexico; Spook, Wyoming, Tuba City, Arizona; and Monument Valley, Arizona. Surface remedial action was ongoing at 5 sites: Ambrosia Lake, New Mexico; Naturita, Colorado; Gunnison, Colorado; and Rifle, Colorado (2 sites). Remedial action has not begun at the 5 remaining UMTRA Project sites that are in the planning stage. Belfield and Bowman, North Dakota; Maybell, Colorado; and Slick Rock, Colorado (2 sites). The ground water compliance phase of the UMTRA Project started in 1991. Because the UMTRA Project sites are.` different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.

NONE

1995-08-01T23:59:59.000Z

178

Hydrologic transport of depleted uranium associated with open air dynamic range testing at Los Alamos National Laboratory, New Mexico, and Eglin Air Force Base, Florida  

SciTech Connect

Hydrologic investigations on depleted uranium fate and transport associated with dynamic testing activities were instituted in the 1980`s at Los Alamos National Laboratory and Eglin Air Force Base. At Los Alamos, extensive field watershed investigations of soil, sediment, and especially runoff water were conducted. Eglin conducted field investigations and runoff studies similar to those at Los Alamos at former and active test ranges. Laboratory experiments complemented the field investigations at both installations. Mass balance calculations were performed to quantify the mass of expended uranium which had transported away from firing sites. At Los Alamos, it is estimated that more than 90 percent of the uranium still remains in close proximity to firing sites, which has been corroborated by independent calculations. At Eglin, we estimate that 90 to 95 percent of the uranium remains at test ranges. These data demonstrate that uranium moves slowly via surface water, in both semi-arid (Los Alamos) and humid (Eglin) environments.

Becker, N.M. [Los Alamos National Lab., NM (United States); Vanta, E.B. [Wright Laboratory Armament Directorate, Eglin Air Force Base, FL (United States)

1995-05-01T23:59:59.000Z

179

TO: Reid Rosnick, Radiation Protection Division, Environmental Protection Agency FROM: Sarah M. Fields, Uranium Watch  

E-Print Network (OSTI)

: Sarah M. Fields, Uranium Watch DATE: November 25, 2009 RE: EPA REVIEW OF 40 CFR PART 61, SUBPART W -- RADON NESHAP FOR OPERATING URANIUM RECOVERY FACILITIES Below are some issues that the Environmental radionuclide NESHAPS in a timely manner. · Failure to properly implement radionuclide NESHAPS for uranium mills

180

A comparison of delayed radiobiological effects of depleted-uranium munitions versus fourth-generation nuclear weapons  

E-Print Network (OSTI)

It is shown that the radiological burden due to the battle-field use of circa 400 tons of depleted-uranium munitions in Iraq (and of about 40 tons in Yugoslavia) is comparable to that arising from the hypothetical battle-field use of more than 600 kt (respectively 60 kt) of high-explosive equivalent pure-fusion fourth-generation nuclear weapons. Despite the limited knowledge openly available on existing and future nuclear weapons, there is sufficient published information on their physical principles and radiological effects to make such a comparison. In fact, it is shown that this comparison can be made with very simple and convincing arguments so that the main technical conclusions of the paper are undisputable -- although it would be worthwhile to supplement the hand calculations presented in the paper by more detailed computer simulations in order to consolidate the conclusions and refute any possible objections.

Gsponer, A; Vitale, B; Gsponer, Andre; Hurni, Jean-Pierre; Vitale, Bruno

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

EIS-0359: Notice of Change in National Environmental Policy ...  

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

EIS-0359: Notice of Change in National Environmental Policy (NEPA) Compliance Approach Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project Notice of Change in...

182

EIS-0360: EPA Notice of Availability of the Final Environmental...  

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

Availability of the Final Environmental Impact Statement Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site The U.S....

183

EIS-0329: Advance Notice of Intent To Prepare an Environmental...  

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

Statement EIS-0329: Advance Notice of Intent To Prepare an Environmental Impact Statement Depleted Uranium Hexafluoride Conversion Facilities The U.S. Department of Energy (DOE) is...

184

FAQ 41-What are the potential environmental impacts from manufacture...  

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

environmental impacts from manufacture of depleted uranium shielded casks? In addition to human health and safety consequences, the PEIS evaluated the potential consequences of...

185

Depleted UF6 Management Program Overview Presentation  

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

Depleted UF6 Management Program Overview Presentation Cylinders Photo Next Screen A Legacy of Uranium Enrichment...

186

DOE Evaluates Environmental Impacts of Uranium Mining on Government Land in  

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

Evaluates Environmental Impacts of Uranium Mining on Government Evaluates Environmental Impacts of Uranium Mining on Government Land in Western Colorado DOE Evaluates Environmental Impacts of Uranium Mining on Government Land in Western Colorado March 15, 2013 - 12:20pm Addthis Contractor, Bob Darr, S.M. Stoller Corporation Public Affairs, (720) 377-9672, ULinfo@lm.doe.gov GRAND JUNCTION, Colo. - The U.S. Department of Energy (DOE) today announced that the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS) is available for public review and comment. Under the Uranium Leasing Program, DOE's Office of Legacy Management manages 31 tracts of land in Mesa, Montrose, and San Miguel counties in Colorado - approximately 25,000 acres - that are leased to private entities for uranium and vanadium mining. No mining operations are active

187

Environmental Microbiology (2002) 4(9), 510-516 Multip,le influences of nitrate on uranium solubility  

E-Print Network (OSTI)

the sulfate was depleted, U(VI) was reduced but there was no cell growth. Addition of as much as S mM uranium(VI) to U(IV) precipitates uranium from solution,D. desulfuricansmight be a usefulorganismfor recovering uranium from contaminatedwaters and wastestreams. Microbial reduction of soluble U(VI) to insoluble U

Lovley, Derek

188

ZPR-3 Assembly 12 : A cylindrical assembly of highly enriched uranium, depleted uranium and graphite with an average {sup 235}U enrichment of 21 atom %.  

Science Conference Proceedings (OSTI)

Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 12 (ZPR-3/12) was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 21 at.%. Approximately 68.9% of the total fissions in this assembly occur above 100 keV, approximately 31.1% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 9 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications and has historically been used as a data validation benchmark assembly. Loading of ZPR-3 Assembly 12 began in late Jan. 1958, and the Assembly 12 program ended in Feb. 1958. The core consisted of highly enriched uranium (HEU) plates, depleted uranium plates and graphite plates loaded into stainless steel drawers which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of two columns of 0.125 in.-wide (3.175 mm) HEU plates, seven columns of 0.125 in.-wide depleted uranium plates and seven columns of 0.125 in.-wide graphite plates. The length of each column was 9 in. (228.6 mm) in each half of the core. The graphite plates were included to produce a softer neutron spectrum that would be more characteristic of a large power reactor. The axial blanket consisted of 12 in. (304.8 mm) of depleted uranium behind the core. The thickness of the radial blanket was approximately 12 in. and the length of the radial blanket in each half of the matrix was 21 in. (533.4 mm). The assembly geometry approximated a right circular cylinder as closely as the square matrix tubes allowed. According to the logbook and loading records for ZPR-3/12, the reference critical configuration was loading 10 which was critical on Feb. 5, 1958. The subsequent loadings were very similar but less clean for criticality because there were modifications made to accommodate reactor physics measurements other than criticality. Accordingly, ZPR-3/12 loading 10 was selected as the only configuration for this benchmark. As documented below, it was determined to be acceptable as a criticality safety benchmark experiment. An accurate transformation to a simplified model is needed to make any ZPR assembly a practical criticality-safety benchmark. There is simply too much geometric detail in an exact (as-built) model of a ZPR assembly, even a clean core such as ZPR-3/12 loading 10. The transformation must reduce the detail to a practical level without masking any of the important features of the critical experiment. And it must d

Lell, R. M.; McKnight, R. D.; Perel, R. L.; Wagschal, J. J.; Nuclear Engineering Division; Racah Inst. of Physics

2010-09-30T23:59:59.000Z

189

Portsmouth DUF6 Conversion Final EIS - Appendix D: Environmental Synopsis for the Depleted UF6 Conversion Project  

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

Portsmouth DUF Portsmouth DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT Environmental Synopsis D-2 Portsmouth DUF 6 Conversion Final EIS ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT (Solicitation No. DE-RP05-01OR22717) October 2002 Environmental Assessment Division Argonne National Laboratory Argonne, Illinois Prepared for Office of Site Closure - Oak Ridge Office (EM-32) Office of Environmental Management U.S. Department of Energy Washington, D.C. October 2002 iii CONTENTS 1 INTRODUCTION........................................................................................................... 1 2 BACKGROUND.............................................................................................................

190

Paducah DUF6 Conversion Final EIS - Appendix D: Environmental Synopsis for the Depleted UF6 Conversion Project  

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

Paducah DUF Paducah DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT Environmental Synopsis D-2 Paducah DUF 6 Conversion Final EIS ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT (Solicitation No. DE-RP05-01OR22717) October 2002 Environmental Assessment Division Argonne National Laboratory Argonne, Illinois Prepared for Office of Site Closure - Oak Ridge Office (EM-32) Office of Environmental Management U.S. Department of Energy Washington, D.C. October 2002 iii CONTENTS 1 INTRODUCTION........................................................................................................... 1 2 BACKGROUND............................................................................................................. 3 3

191

EPA Update: NESHAP Uranium Activities  

E-Print Network (OSTI)

measurements have been performed on high-enriched uranium (HEU) oxide fuel pins and depleted uranium metal

192

Evaluation of the uranium double spike technique for environmental monitoring  

Science Conference Proceedings (OSTI)

Use of a uranium double spike in analysis of environmental samples showed that a {sup 235}U enrichment of 1% ({sup 235}U/{sup 238}U = 0.00732) can be distinguished from natural ({sup 235}U/{sup 238}U = 0.00725). Experiments performed jointly at Los Alamos National Laboratory (LANL) and Oak Ridge National Laboratory (ORNL) used a carefully calibrated double spike of {sup 233}U and {sup 236}U to obtain much better precision than is possible using conventional analytical techniques. A variety of different sampling media (vegetation and swipes) showed that, provided sufficient care is exercised in choice of sample type, relative standard deviations of less than {+-} 0.5% can be routinely obtained. This ability, unavailable without use of the double spike, has enormous potential significance in the detection of undeclared nuclear facilities.

Hemberger, P.H.; Rokop, D.J.; Efurd, D.W.; Roensch, F.R. [Los Alamos National Lab., NM (United States); Smith, D.H.; Turner, M.L.; Barshick, C.M.; Bayne, C.K. [Oak Ridge National Lab., TN (United States)

1998-01-01T23:59:59.000Z

193

Bacterial Community Succession During in situ Uranium Bioremediation: Spatial Similarities Along Controlled Flow Paths  

E-Print Network (OSTI)

problem, and the use of depleted uranium and other heavyenvironmental hazard. Depleted uranium is weakly radioactiveMB. (2004). Depleted and natural uranium: chemistry and

Hwang, Chiachi

2009-01-01T23:59:59.000Z

194

Programmatic Environmental Assessment for the U. S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials  

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

IMPMZT IMPMZT PROGR4MMATIC ENVIRONMENTAL ASSESSME?X FOR THE U.S. DEPARTMENT OF ENERGY, OAK RIDGE OPER4TIOSS IMPLEMENTATION OF A COMPREHENSIVE MANAGEMEKT PROGK4hl FOR THE STORAGE, TRANSPORTATION, AND DISPOSITION OF POTENTIALLY REUSABLE URANJUh4 MATERIALS AGEhCY: U.S. DEPARTMENT OF ENERGY (DOE) ACTION: FINDI?iG OF NO SIGNIFICANT 1~IPAC-I SUMI\!L4RY: The U. S. DOE has completed a Programmatic Environmental Assessment (PE:,4) (DOE/E?,- 1393), which is incorporated herein by this reference. Tile purpose of the PEA is in assess potential enJ?ronmental impacts of the implementation of a comprehek-e management program for potentiaIly reusable ICW enriched uranium (LEU). norr,:al uranium (NU), and depleted uranium (DU). --l?prosimately 14,200 MTU (h?etric Tons of Uranium) of potentially reusable uranium is located at 15s

195

Assessment of the Portsmouth/Paducah Project Office Conduct of Operations Oversight of the Depleted Uranium Hexafluoride Conversion Plants, May 2012  

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

Assessment of the Assessment of the Portsmouth/Paducah Project Office Conduct of Operations Oversight of the Depleted Uranium Hexafluoride Conversion Plants May 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2

196

Assessment of the Portsmouth/Paducah Project Office Conduct of Operations Oversight of the Depleted Uranium Hexafluoride Conversion Plants, May 2012  

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

Assessment of the Assessment of the Portsmouth/Paducah Project Office Conduct of Operations Oversight of the Depleted Uranium Hexafluoride Conversion Plants May 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2

197

Proceedings of Workshop on Uranium Production Environmental Restoration: An exchange between the United States and Germany  

SciTech Connect

Scientists, engineers, elected officials, and industry regulators from the United, States and Germany met in Albuquerque, New Mexico, August 16--20, 1993, in the first joint international workshop to discuss uranium tailings remediation. Entitled ``Workshop on Uranium Production Environmental Restoration: An Exchange between the US and Germany,`` the meeting was hosted by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The goal of the workshop was to further understanding and communication on the uranium tailings cleanup projects in the US and Germany. Many communities around the world are faced with an environmental legacy -- enormous quantities of hazardous and low-level radioactive materials from the production of uranium used for energy and nuclear weapons. In 1978, the US Congress passed the Uranium Mill Tailings Radiation Control Act. Title I of the law established a program to assess the tailings at inactive uranium processing sites and provide a means for joint federal and state funding of the cleanup efforts at sites where all or substantially all of the uranium was produced for sale to a federal agency. The UMTRA Project is responsible for the cleanup of 24 sites in 10 states. Germany is facing nearly identical uranium cleanup problems and has established a cleanup project. At the workshop, participants had an opportunity to interact with a broad cross section of the environmental restoration and waste disposal community, discuss common concerns and problems, and develop a broader understanding of the issues. Abstracts are catalogued individually for the data base.

Not Available

1993-12-31T23:59:59.000Z

198

DOE Extends Public Comment Period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement  

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

The U.S. Department of Energy (DOE) today announced that the public comment period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS) has been extended to May 31, 2013.

199

Floodplain/wetland assessment of the effects of construction and operation ofa depleted uranium hexafluoride conversion facility at the Paducah, Kentucky,site.  

SciTech Connect

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF{sub 6} inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This floodplain/wetland assessment has been prepared by DOE, pursuant to Executive Order 11988 (''Floodplain Management''), Executive Order 11990 (Protection of Wetlands), and DOE regulations for implementing these Executive Orders as set forth in Title 10, Part 1022, of the ''Code of Federal Regulations'' (10 CFR Part 1022 [''Compliance with Floodplain and Wetland Environmental Review Requirements'']), to evaluate potential impacts to floodplains and wetlands from the construction and operation of a conversion facility at the DOE Paducah site. Reconstruction of the bridge crossing Bayou Creek would occur within the Bayou Creek 100-year floodplain. Replacement of bridge components, including the bridge supports, however, would not be expected to result in measurable long-term changes to the floodplain. Approximately 0.16 acre (0.064 ha) of palustrine emergent wetlands would likely be eliminated by direct placement of fill material within Location A. Some wetlands that are not filled may be indirectly affected by an altered hydrologic regime, due to the proximity of construction, possibly resulting in a decreased frequency or duration of inundation or soil saturation and potential loss of hydrology necessary to sustain wetland conditions. Indirect impacts could be minimized by maintaining a buffer near adjacent wetlands. Wetlands would likely be impacted by construction at Location B; however, placement of a facility in the northern portion of this location would minimize wetland impacts. Construction at Location C could potentially result in impacts to wetlands, however placement of a facility in the southeastern portion of this location may best avoid direct impacts to wetlands. The hydrologic characteristics of nearby wetlands could be indirectly affected by adjacent construction. Executive Order 11990, ''Protection of Wetlands'', requires federal agencies to minimize the destruction, loss, or degradation of wetlands, and to preserve and enhance the natural and beneficial uses of wetlands. DOE regulations for implementing Executive Order 11990 as well as Executive Order 11988, ''Floodplain Management'', are set forth in 10 CFR Part 1022. Mitigation for unavoidable impacts may be developed in coordination with the appropriate regulatory agencies. Unavoidable impacts to wetlands that are within the jurisdiction of the USACE may require a CWA Section 404 Permit, which would trigger the requirement for a CWA Section 401 Water Quality Certification from the Commonwealth of Kentucky. A mitigation plan may be required prior to the initiation of construction. Cumulative impacts to floodplains and wetlands are anticipated to be negligible to minor under the proposed action, in conjunction with the effects of existing conditions and other activities. Habitat disturbance would involve settings commonly found i

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

200

Uranium production in Eastern Europe and its environmental impact: A literature survey  

SciTech Connect

A survey of the unclassified literature was made to determine the location, technology, throughput, and environmental status of the uranium mines and mills that have historically made up uranium production capability in Eastern Europe. Included in that survey were the following countries: the former German Democratic Republic (GDR), now part of a reunited Germany, Czechoslovakia, Romania, Bulgaria, Hungary, and Poland. Until recently, uranium was being produced in five of these six countries (Poland stopped production 20 years ago). The production began directly after World War II in support of weapons production in the Soviet Union. Eastern Europe has produced about two-thirds of the total Soviet uranium inventory historically, or about 330,000 metric tonnes of uranium (NM) [730 million pounds of uranium (MlbU)l out of a total of about 490,000 MTU (1090 NlbU).

Norman, R.E.

1993-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Uranium Oxide Semiconductors  

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

of semiconductors, it would consume the annual production rate of depleted uranium from uranium enrichment facilities. For more information: PDF Semiconductive Properties of...

202

MICROBIAL TRANSFORMATIONS OF URANIUM AND ENVIRONMENTAL RESTORATION THROUGH BIOREMEDIATION.  

SciTech Connect

Microorganisms present in the natural environment play a significant role in the mobilization and immobilization of uranium. Fundamental understanding of the mechanisms of microbiological transformations of various chemical forms of uranium present in wastes and contaminated soils and water has led to the development of novel bioremediation processes. One process uses anaerobic bacteria to stabilize the radionuclides and toxic metals from the waste, with a concurrent reduction in volume due to the dissolution and removal of nontoxic elements from the waste matrix. In an another process, uranium and other toxic metals are removed from contaminated soils and wastes by extracting with the chelating agent citric acid. Uranium is recovered from the citric acid extract after biodegradation/photodegradation in a concentrated form as UO{sub 3} {center_dot} 2H{sub 2}O for recycling or appropriate disposal.

FRANCIS,A.J.

2002-09-10T23:59:59.000Z

203

Remediation of uranium contaminated soils with bicarbonate extraction and microbial U(VI) reduction  

E-Print Network (OSTI)

bodies depleted by uranium solution extraction and which remain underground do not constitute byproductEPA Update: NESHAP Uranium Activities Reid J. Rosnick Environmental Protection Agency Radiation Protection Division (6608J) Washington, DC 20460 NMA/NRC Uranium Recovery Workshop July 2, 2009 #12

Lovley, Derek

204

Depleted UF6 Overview Presentation  

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

Information network Web Site. The presentation covers the following topics: The uranium mining and enrichment processes - how depleted UF6 is created, How and where...

205

Control of structure and reactivity by ligand design : applications to small molecule activation by low-valent uranium complexes  

E-Print Network (OSTI)

coordination chemistry is depleted uranium, a by-product innuclear reactors. Depleted uranium Figure 1-1. The periodic

Lam, Oanh Phi

2010-01-01T23:59:59.000Z

206

Programmatic Environmental Report for remedial actions at UMTRA (Uranium Mill Tailings Remedial Action) Project vicinity properties  

Science Conference Proceedings (OSTI)

This Environmental Report (ER) examines the environmental consequences of implementing a remedial action that would remove radioactive uranium mill tailings and associated contaminated materials from 394 vicinity properties near 14 inactive uranium processing sites included in the Uranium Mill Tailings Remedial Action (UMTRA) Project pursuant to Public Law 95--604, the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Vicinity properties are those properties in the vicinity of the UMTRA Project inactive mill sites, either public or private, that are believed to be contaminated by residual radioactive material originating from one of the 14 inactive uranium processing sites, and which have been designated under Section 102(a)(1) of UMTRCA. The principal hazard associated with the contaminated properties results from the production of radon, a radioactive decay product of the radium contained in the tailings. Radon, a radioactive gas, can diffuse through the contaminated material and be released into the atmosphere where it and its radioactive decay products may be inhaled by humans. A second radiation exposure pathway results from the emission of gamma radiation from uranium decay products contained in the tailings. Gamma radiation emitted from contaminated material delivers an external exposure to the whole body. If the concentration of radon and its decay products is high enough and the exposure time long enough, or if the exposure to direct gamma radiation is long enough, cancers (i.e., excess health effects) may develop in persons living and working at the vicinity properties. 3 refs., 7 tabs.

Not Available

1985-03-01T23:59:59.000Z

207

Notice of Intent to Prepare an Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities  

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

123 123 Federal Register / Vol. 66, No. 181 / Tuesday, September 18, 2001 / Notices Section 615-Procedural Safeguards Topic Addressed: Due Process Hearings * Letter dated April 19, 2001 to Virginia Department of Education Director Judith A. Douglas, regarding whether a State educational agency is required to convene a due process hearing initiated by someone other than the parent of a child with a disability or a public agency. Topic Addressed: Surrogate Parents * Letter dated April 16, 2001 to Pinal County, Arizona Deputy County Attorney Linda L. Harant, regarding the appointment of surrogate parents for children who are wards of a tribal court. Topic Addressed: Student Discipline * Letter dated April 16, 2001 to Professor Perry A. Zirkel, regarding the calculation of disciplinary removals of

208

Environmental Evaluation on Atmosphere Radioactive Pollution of Uranium Mine Shaft Ventilation Exhausts  

Science Conference Proceedings (OSTI)

A study on calculation and evaluation on atmosphere radioactive pollution of uranium mine well ventilation exhaust gas is presented in this paper. Neutral atmosphere conditions were taken into consideration. Nuclear industry standards on safety protection ... Keywords: atmosphere pollution, radiation protection, environmental evaluation, control methods

Dong Xie; Zehua Liu; Jun Xiong; Jianxiang Liu

2012-03-01T23:59:59.000Z

209

Remediation and Recovery of Uranium from Contaminated  

E-Print Network (OSTI)

uranium containing the mixture of isotopes occurring in nature; uranium depleted in the isotope 235; Depleted uranium 1000 kilograms; and Thorium 1000 kilograms. #12;INFCIRC/254/Rev.9/Part.1 November 2007 Annex B, section 4.); 2.5. Plants for the separation of isotopes of natural uranium, depleted uranium

Lovley, Derek

210

Environmental monitoring for detection of uranium enrichment operations: Comparison of LEU and HEU facilities  

SciTech Connect

In 1994, the International Atomic Energy Agency (IAEA) initiated an ambitious program of worldwide field trials to evaluate the utility of environmental monitoring for safeguards. Part of this program involved two extensive United States field trials conducted at the large uranium enrichment facilities. The Paducah operation involves a large low-enriched uranium (LEU) gaseous diffusion plant while the Portsmouth facilities include a large gaseous diffusion plant that has produced both LEU and high-enriched uranium (HEU) as well as an LEU centrifuge facility. As a result of the Energy Policy Act of 1992, management of the uranium enrichment operations was assumed by the US Enrichment Corporation (USEC). The facilities are operated under contract by Martin Marietta Utility Services. Martin Marietta Energy Systems manages the environmental restoration and waste management programs at Portsmouth and Paducah for DOE. These field trials were conducted. Samples included swipes from inside and outside process buildings, vegetation and soil samples taken from locations up to 8 km from main sites, and hydrologic samples taken on the sites and at varying distances from the sites. Analytical results from bulk analysis were obtained using high abundance sensitivity thermal ionization mm spectrometers (TIMS). Uranium isotopics altered from the normal background percentages were found for all the sample types listed above, even on vegetation 5 km from one of the enrichment facilities. The results from these field trials demonstrate that dilution by natural background uranium does not remove from environmental samples the distinctive signatures that are characteristic of enrichment operations. Data from swipe samples taken within the enrichment facilities were particularly revealing. Particulate analysis of these swipes provided a detailed ``history`` of both facilities, including the assays of the end product and tails for both facilities.

Hembree, D.M. Jr.; Carter, J.A.; Ross, H.H.

1995-03-01T23:59:59.000Z

211

DOE/EA-1535; Uranium Leasing Program Final Programmatic Environmental Assessment  

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

Leasing Program Leasing Program Final Programmatic Environmental Assessment July 2007 Office of Legacy Management DOE/EA 1535 - Work Performed Under DOE Contract No. for the U.S. Department of Energy Office of Legacy Management. DE-AC01-02GJ79491 Approved for public release; distribution is unlimited. Office of Legacy Management Office of Legacy Management Office of Legacy Management U.S. Department of Energy DOE/EA-1535 Uranium Leasing Program Final Programmatic Environmental Assessment July 2007 U.S. Department of Energy Office of Legacy Management U.S. Department of Energy Uranium Leasing Program Environmental Assessment July 2007 Doc. No. Y0011700 Page iii Contents Abbreviations and Acronyms ........................................................................................................

212

Environmental Assessment DOE/EA-1172 DOE Sale of Surplus Natural and Low Enriched Uranium  

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

DOE/EA-1172 DOE Sale of Surplus Natural and Low Enriched Uranium | October 1996 | For additional information contact: Office of Nuclear Energy, Science and Technology U.S. Department of Energy Washington, DC 20585 ii October 1996 | Table of Contents 1.0 Purpose and Need for Agency Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1 Purpose and Need for Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.2 Relationship to Other DOE NEPA Documents . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.2.1 Environmental Assessment for the Purchase of Russian Low Enriched Uranium Derived from the Dismantlement of Nuclear Weapons in the | Countries of the Former Soviet Union . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 | 1.2.2 Disposition of Surplus Highly Enriched Uranium Final EIS . . . . . . . . 1-2 1.3 Public Comments on the Draft EA

213

Environmental assessment of remedial action at the Maybell uranium mill tailings site near Maybell, Colorado  

SciTech Connect

The purpose of this environmental assessment (EA) is to evaluate the environmental impacts resulting from remedial action at the Maybell uranium mill tailings site near Maybell, Colorado. A biological assessment (Attachment 1) and a floodplain/wetlands assessment (Assessment 2) are included as part of this EA. The following sections and attachments describe the proposed action, affected environment, and environmental impacts associated with the proposed remedial action, including impacts to threatened and endangered species listed or proposed for listing by the US Fish and Wildlife Service.

Not Available

1993-09-01T23:59:59.000Z

214

Environmental Assessment of Remedial Action at the Riverton Uranium Mill Tailings Site, Riverton, Wyoming  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) has prepared an environmental assessment (DOE/EA-0254) on the proposed remedial action at the inactive uranium milling site near Riverton, Wyoming. Based on the analyses in the EA, the DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969 (42 U.S.C. 4321, et seq.). Therefore, the preparation of an environmental impact statement (EIS) is not required.

none,

1987-06-01T23:59:59.000Z

215

Electron Beam Welding of a Depleted Uranium Alloy to Niobium Using a Calibrated Electron Beam Power Density Distribution  

SciTech Connect

Electron beam test welds were made joining flat plates of commercially pure niobium to a uranium-6wt%Nb (binary) alloy. The welding parameters and joint design were specifically developed to minimize mixing of the niobium with the U-6%Nb alloy. A Modified Faraday Cup (MFC) technique using computer-assisted tomography was employed to determine the precise power distribution of the electron beam so that the welding parameters could be directly transferred to other welding machines and/or to other facilities.

Elmer, J.W.; Teruya, A.T.; Terrill, P.E.

2000-08-21T23:59:59.000Z

216

DOE Selects Contractor for Depleted Hexafluoride Conversion Project...  

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

in Paducah, Kentucky and Portsmouth, Ohio. For several decades DOE was responsible for uranium enrichment, the uranium hexafluoride depleted in the 235U isotope (typically down...

217

Depleted UF6 Management Information Network - A resource for...  

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

is an online repository of information about the U.S. Department of Energy's (DOE's) inventory of depleted uranium hexafluoride (DUF6), a product of the uranium enrichment...

218

Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado: Revision 5  

SciTech Connect

Title 1 of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the inactive Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. Title 2 of the UMTRCA authorized the US Nuclear Regulatory Commission (NRC) or agreement state to regulate the operation and eventual reclamation of active uranium processing sites. The uranium mill tailings at the site were removed and reprocessed from 1977 to 1979. The contaminated areas include the former tailings area, the mill yard, the former ore storage area, and adjacent areas that were contaminated by uranium processing activities and wind and water erosion. The Naturita remedial action would result in the loss of 133 acres (ac) of contaminated soils at the processing site. If supplemental standards are approved by the NRC and the state of Colorado, approximately 112 ac of steeply sloped contaminated soils adjacent to the processing site would not be cleaned up. Cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers.

Not Available

1994-10-01T23:59:59.000Z

219

Depleted UF6 Production and Handling Slide Presentation  

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

Production and Handling Depleted UF6 Production and Handling Slide Presentation An online slide presentation about production and handling of depleted UF6, from mining of uranium...

220

U.S. Environmental Protection Agency Evaluation of Uranium Mining TENORM Wastes-Characteristics, Occurrence, and Risks  

Science Conference Proceedings (OSTI)

The U.S. Environmental Protection Agency is completing a multi year effort to issue technical reports and obtain stakeholder views on future programs to mitigate potential hazards associated with uranium mining Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM). The technical reports are the most comprehensive issued by the Agency on this topic, and should have utility for reclamation of abandoned uranium mines, as well as providing information for new mines proposed by the uranium mining industry. This presentation will provide principal results of the three technical reports issued, and elements of the proposed EPA program for uranium mining TENORM. (authors)

Setlow, L.W. [U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (6608J), Washington, DC (United States); Peake, R.T. [U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (6608J), Washington, DC (United States)

2007-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Summary of the Special Analysis of Savannah River Depleted Uranium Trioxide Demonstrating the Before and After Impacts on the DOE Order 435.1 Performance Objective and the Peak Dose  

Science Conference Proceedings (OSTI)

This report summarizes the special analysis (SA) of the Savannah River Depleted Uranium Trioxide waste stream (SVRSURANIUM03, Revision 1) demonstrating the before and after impacts of the waste stream to the DOE Order 435.1 performance objective at the disposal facility, and the peak dose. The Nevada Division of Environmental Protection (NDEP) requested this SA and asked the Nevada Site Office (NSO) to run the SA deterministically and assume that all the model conditions remain the same regardless of the length of time to the peak dose. Although the NDEP accepts that DOE Order 435.1 requires a compliance period of 1,000 years, it also requested to know what year, if any, the specific DOE performance objectives will be exceeded. Given the NDEPs requested model conditions, the SA demonstrates the Rn-222 peak dose will occur in about 2 million years and will exceed the performance objective in about 6,000 years. The 0.25 mSv y-1 all-pathway performance objective was not exceeded for the resident scenario after reaching the 4 million year peak dose.

Shott, G.J.

2011-01-15T23:59:59.000Z

222

FAQ 40-What are the potential environmental impacts from storage...  

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

environmental impacts from storage of depleted uranium as an oxide? Storage as an oxide could result in potential adverse impacts to air, water, and soil quality as a result of...

223

Environmental radioactivity assessment around old uranium mining sites near Mangualde (Viseu), Portugal  

SciTech Connect

Uranium ore was extracted in the surroundings of Mangualde city, North of Portugal, in the mines of Cunha Baixa, Quinta do Bispo and Espinho until a few years ago. Mining waste, milling tailings and acid mine waters are the on site remains of this extractive activity. Environmental radioactivity measurements were performed in and around these sites in order to assess the dispersal of radionuclides from uranium mining waste and the spread of acidic waters resulting from the in situ uranium leaching with sulphuric acid. Results show migration of acid waters into groundwater around the Cunha Baixa mine. This groundwater is tapped by irrigation wells in the agriculture area near the Cunha Baixa village. Water from wells displayed uranium ({sup 238}U) concentrations up to 19x10{sup 3} mBq L{sup -1} and sulphate ion concentrations up to 1070 mg L{sup -1}. These enhanced concentrations are positively correlated with low water pH, pointing to a common origin for radioactivity, dissolved sulphate, and acidity in underground mining works. Radionuclide concentrations were determined in horticulture and farm products from this area also and results suggest low soil to plant transfer of radionuclides and low food chain transfer of radionuclides to man. Analysis of aerosols in surface air showed re suspension of dust from mining and milling waste heaps. Therefore, it is recommended to maintain mine water treatment and to plan remediation of these mine sites in order to prevent waste dispersal in the environment. (authors)

Carvalho, Fernando P.; Torres, Lubelia M.; Oliveira, Joao M. [Instituto Tecnologico e Nuclear, Departamento de Proteccao Radiologica e Seguranca Nuclear, E.N. 10, 2686-953 Sacavem (Portugal)

2007-07-01T23:59:59.000Z

224

Overview of the Capstone Depleted Uranium Study of Aerosols from Impact with Armored Vehicles: Test Setup and Aerosol Generation, Characterization, and Application in Assessing Dose and Risk  

Science Conference Proceedings (OSTI)

The Capstone Depleted Uranium (DU) Aerosol Characterization and Risk Assessment Study was conducted to generate data about DU aerosols generated during the perforation of armored combat vehicles with large-caliber DU penetrators, and to apply the data in assessments of human health risks to personnel exposed to these aerosols, primarily through inhalation, during the 1991 Gulf War or in future military operations. The Capstone study consisted of two components: 1) generating, sampling and characterizing DU aerosols by firing at and perforating combat vehicles and 2) applying the source-term quantities and characteristics of the aerosols to the evaluation of doses and risks. This paper reviews the background of the study including the bases for the study, previous reviews of DU particles and health assessments from DU used by the U.S. military, the objectives of the study components, the participants and oversight teams, and the types of exposures it was intended to evaluate. It then discusses exposure scenarios used in the dose and risk assessment and provides an overview of how the field tests and dose and risk assessments were conducted.

Parkhurst, MaryAnn; Guilmette, Raymond A.

2009-03-01T23:59:59.000Z

225

Environmental assessment of remedial action at the Naturita Uranium Processing Site near Naturita, Colorado. Revision 4  

Science Conference Proceedings (OSTI)

The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contain measures to control the contaminated materials and to protect groundwater quality. Remedial action at the Naturita site must be performed in accordance with these standards and with the concurrence of the US Nuclear Regulatory Commission (NRC) and the state of Colorado. The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to either the Dry Flats disposal site, 6 road miles (mi) [10 kilometers (km)] to the southeast, or a licensed non-DOE disposal facility capable of handling RRM. At either disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed Dry Flats disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. This report discusses environmental impacts associated with the proposed remedial action.

Not Available

1994-05-01T23:59:59.000Z

226

Depleted UF6 Health Risks  

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

(depleted UF6) is released to the atmosphere, the uranium compounds and hydrogen fluoride (HF) gas that are formed by reaction with moisture in the air can be chemically...

227

New chromatographic materials for the separation and concentration of uranium from environmental matrices  

SciTech Connect

Extraction chromatography, in which an inert support is impregnated with an extractant solution to form a chromatographic resin, combines the specificity of extraction with the ease of operation of an ion exchange column, thereby overcoming the principal drawbacks of the two methods when used alone. Previous work in this laboratory on the design of selective extractants for use in nuclear fuel reprocessing and in nuclear waste treatment has led to the development of several new phosphorus-based neutral organic extractants. In this report, we examine the use of two of these materials as stationary phases in extraction chromatography for the isolation of uranium from environmental samples. 2 refs., 2 figs., 1 tab.

Horwitz, E.P.; Dietz, M.L.; Chiarizia, R.; Diamond, H.

1991-01-01T23:59:59.000Z

228

Disposition of highly enriched uranium obtained from the Republic of Kazakhstan. Environmental assessment  

Science Conference Proceedings (OSTI)

This EA assesses the potential environmental impacts associated with DOE`s proposal to transport 600 kg of Kazakhstand-origin HEU from Y-12 to a blending site (B&W Lynchburg or NFS Erwin), transport low-enriched UF6 blending stock from a gaseous diffusion plant to GE Wilmington and U oxide blending stock to the blending site, blending the HEU and uranium oxide blending stock to produce LEU in the form of uranyl nitrate, and transport the uranyl nitrate from the blending site to USEC Portsmouth.

NONE

1995-05-01T23:59:59.000Z

229

Environmental assessment of remedial action at the Slick Rock uranium mill tailings sites, Slick Rock, Colorado  

SciTech Connect

The Uranium Mill Tailings Radiation Control Act of 1978, hereafter referred to as the UMTRCA, authorized the US Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miguel County. The purpose of the cleanup is to reduce the potential health effects associated with the radioactive materials remaining on the processing sites and on vicinity properties (VPs) associated with the sites. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contained measures to control the contaminated materials and to protect the ground water from further degradation. The sites contain concrete foundations of mill buildings, tailings piles, and areas contaminated by windblown and waterborne radioactive tailings materials. The proposed action is to remediate the UC and NC sites by removing all contaminated materials within the designated site boundaries or otherwise associated with the sites, and relocating them to, and stabilizing them at, a location approximately 5 road mi (8 km) northeast of the processing sites on land administered by the US Bureau of Land Management (BLM). Remediation would be performed by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project.

NONE

1995-01-01T23:59:59.000Z

230

Environmental assessment of remedial action at the Maybell uranium mill tailings site near Maybell, Colorado: Revision 2  

SciTech Connect

The purpose of this environmental assessment (EA) is to evaluate the environmental impacts resulting from remedial action at the Maybell uranium mill tailings site near Maybell, Colorado. A biological assessment and a floodplain/wetlands assessment are included as part of this EA. This report and attachments describe the proposed action, affected environment, and environmental impacts associated with the proposed remedial action, including impacts to threatened and endangered species listed or proposed for listing by the US Fish and Wildlife Service (FWS).

Not Available

1994-11-01T23:59:59.000Z

231

Environmental assessment of remedial action at the Maybell Uranium Mill Tailings Site near Maybell, Colorado. Revision 1  

SciTech Connect

The purpose of this environmental assessment (EA) is to evaluate the environmental impacts resulting from remedial action at the Maybell uranium mill tailings site near Maybell, Colorado. A biological assessment (Attachment 1) and a floodplain/wetlands attachments describe the proposed action, affected environment, and environmental impacts associated with the proposed remedial action, including impacts to threatened and endangered species listed or proposed for listing by the US Fish and Wildlife Service (FWS).

Not Available

1994-04-01T23:59:59.000Z

232

Summary: Draft Uranium Leasing Program Programmatic Environmental Impact Statement: DOE/EIS 0472-D, March 2013  

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

Summary: Draft ULP PEIS March 2013 Summary: Draft ULP PEIS March 2013 COVER SHEET 1 2 3 Lead Agency: U.S. Department of Energy (DOE) 4 5 Cooperating Agencies: The cooperating agencies are U.S. Department of the Interior (DOI), 6 Bureau of Land Management (BLM); U.S. Environmental Protection Agency (EPA); Colorado 7 Department of Transportation (CDOT); Colorado Division of Reclamation, Mining, and Safety 8 (CDRMS); Colorado Parks and Wildlife (CPW); Mesa County Commission; Montrose County 9 Commission; San Juan County Commission; San Miguel County Board of Commissioners; the 10 Pueblo of Acoma Tribe; the Pueblo de Cochiti Tribe; the Pueblo de Isleta Tribe; the Navajo 11 Nation; and the Southern Ute Indian Tribe. 12 13 Title: Draft Uranium Leasing Program Programmatic Environmental Impact Statement 14

233

Environmental assessment of remedial action at the Gunnison Uranium Mill Tailings Site, Gunnison, Colorado. [UMTRA Project  

SciTech Connect

This document assesses and compares the environmental impacts of various alternatives for remedial action at the Gunnison uranium of mill tailings site located 0.5 miles south of Gunnison, Colorado. The site covers 56 acres and contains 35 acres of tailings, 2 of the original mill buildings and a water tower. The Uranium Mill Tailings Radiation Control of Act of 1978 (UMTRCA), Public Law 95-604, authorizes the US Department of Energy to clean up the site to reduce the potential health impacts associated with the residual radioactive materials remaining at the site and at associated (vicinity) properties off the site. The US Environmental Protection Agency promulgated standards for the remedial actions (40 CFR 192). Remedial actions must be performed in accordance with these standards and with the occurrence of the Nuclear Regulatory Commission. Four alternatives have been addressed in this document. The first alternative is to consolidate the tailings and associated contaminated soils into a recontoured pile on the southern portion of the existing site. A radon barrier of silty clay would be constructed over the pile and various erosion control measures would be taken to assure the long-term integrity of the pile. Two other alternatives which involve moving the tailings to new locations are assessed in this document. These alternatives generally involve greater short-term impacts and are more costly but would result in the tailings being stabilized in a location farther from the city of Gunnison. The no action alternative is also assessed.

Bachrach, A.; Hoopes, J.; Morycz, D. (Jacobs Engineering Group, Inc., Pasadena, CA (USA)); Bone, M.; Cox, S.; Jones, D.; Lechel, D.; Meyer, C.; Nelson, M.; Peel, R.; Portillo, R.; Rogers, L.; Taber, B.; Zelle, P. (Weston (Roy F.), Inc., Washington, DC (USA)); Rice, G. (Sergent, Hauskins and Beckwith (USA))

1984-12-01T23:59:59.000Z

234

Magnetic Exchange Coupling and Single-Molecule Magnetism in Uranium Complexes  

E-Print Network (OSTI)

greater than 99% U-238 (depleted uranium), which has no neturanium, since this actinide element offers minimal radioactivity (in depleted

Rinehart, Jeffrey Dennis

2010-01-01T23:59:59.000Z

235

Health Risks Associated with Conversion of Depleted UF6  

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

Conversion Conversion DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Conversion A discussion of health risks associated with conversion of depleted UF6 to another chemical form. General Health Risks of Conversion The potential environmental impacts, including potential health risks, associated with conversion activities will be evaluated in detail as part of the Depleted Uranium Hexafluoride management program after a contract is awarded for conversion services. This section discusses in general the types of health risks associated with the conversion process. The conversion of depleted UF6 to another chemical form will be done in an industrial facility dedicated to the conversion process. Conversion will involve the handling of depleted UF6 cylinders. Hazardous chemicals, such

236

Description of the Canadian Particulate-Fill WastePackage (WP) System for Spent-Nuclear Fuel (SNF) and its Applicability to Ligh-Water Reactor SNF WPS with Depleted Uranium-Dioxide Fill  

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

3502 3502 Chemical Technology Division DESCRIPTION OF THE CANADIAN PARTICULATE-FILL WASTE-PACKAGE (WP) SYSTEM FOR SPENT-NUCLEAR FUEL(SNF) AND ITS APPLICABILITY TO LIGHT- WATER REACTOR SNF WPS WITH DEPLETED URANIUM-DIOXIDE FILL Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6180 Tel: (423) 574-6783 Fax: (423) 574-9512 Email: forsbergcw@ornl.gov October 20, 1997 _________________________ Managed by Lockheed Martin Energy Research Corp. under contract DE-AC05-96OR22464 for the * U.S. Department of Energy. iii CONTENTS LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii ACRONYMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

237

EIS-0359: Notice of Change in National Environmental Policy (NEPA)  

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

Notice of Change in National Environmental Policy (NEPA) Notice of Change in National Environmental Policy (NEPA) Compliance Approach EIS-0359: Notice of Change in National Environmental Policy (NEPA) Compliance Approach Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project Notice of Change in National Environmental Policy (NEPA) Compliance Approach for the Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project (4/28/03). The purpose of this Notice is to inform the public of the change in the approach for the NEPA review for the DUF6 conversion projects for Paducah and Portsmouth, and to invite public comments on the revised approach. DOE/EIS-0359, Department of Energy, Notice of Change in National Environmental Policy (NEPA) Compliance Approach for the Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project, 68 FR 22368 (April 2003)

238

Production and Handling Slide 38: 48G Depleted UF6 Storage Cylinder  

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

48G Depleted UF6 Storage Cylinder Refer to caption below for image description After enrichment, depleted uranium hexafluoride is placed in large steel cylinders for storage....

239

EIS-0329: Notice of Intent to Prepare an Environmental Impact Statement |  

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

29: Notice of Intent to Prepare an Environmental Impact 29: Notice of Intent to Prepare an Environmental Impact Statement EIS-0329: Notice of Intent to Prepare an Environmental Impact Statement Depleted Uranium Hexafluoride Conversion Facilities The U.S. Department of Energy (DOE) announces its intention to prepare an Environmental Impact Statement (EIS) for a proposal to construct, operate, maintain, and decontaminate and decommission two depleted uranium hexafluoride (DUF 6) conversion facilities, at Portsmouth, Ohio, and Paducah, Kentucky. Notice of Intent To Prepare an Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities (DOE/EIS-0329) (September 2001) More Documents & Publications EIS-0360: Draft Environmental Impact Statement EIS-0360: Final Environmental Impact Statement

240

Office of Environmental Management uranium enrichment decontamination and decommissioning fund financial statements. September 30, 1994 and 1993  

SciTech Connect

The Energy Policy Act of 1992 (Act) transferred the uranium enrichment enterprise to the United States Enrichment Corporation as of July 1, 1993. However, the Act requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio (diffusion facilities). The Act established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; Pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and Reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

Marwick, P.

1994-12-15T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Office of Environmental Management Uranium Enrichment Decontamination and Decommissioning Fund financial statements, September 30, 1995 and 1994  

SciTech Connect

The Energy Policy Act of 1992 (Act) requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located at the K-25 site in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. The Act transferred the uranium enrichment enterprise to the United States Enrichment Corporation (USEC) as of July 1, 1993, and established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

1996-02-21T23:59:59.000Z

242

EIS-0360: Final Environmental Impact Statement  

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

Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site

243

EIS-0359: Draft Environmental Impact Statement  

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

Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site

244

FAQ 35-What are the potential health risks from disposal of depleted...  

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

health risks from disposal of depleted uranium as an oxide? Once depleted uranium has been converted from UF6 to the oxide form, the risk associated with handling at a disposal...

245

FAQ 33-What are the potential health risks from storage of depleted...  

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

health risks from storage of depleted uranium as an oxide? Once depleted uranium has been converted from UF6 to the oxide form, the risk associated with storage and handling is...

246

Transportation of foreign-owned enriched uranium from the Republic of Georgia. Environmental assessment for Project Partnership  

SciTech Connect

The Department of Energy (DOE) Office of Nonproliferation and National Security (NN) has prepared a classified environmental assessment to evaluate the potential environmental impact for the transportation of 5.26 kilograms of enriched uranium-235 in the form of nuclear fuel, from the Republic of Georgia to the United Kingdom. The nuclear fuel consists of primarily fresh fuel, but also consists of a small quantity (less than 1 kilogram) of partially-spent fuel. Transportation of the enriched uranium fuel would occur via US Air Force military aircraft under the control of the Defense Department European Command (EUCOM). Actions taken in a sovereign nation (such as the Republic of Georgia and the United Kingdom) are not subject to analysis in the environmental assessment. However, because the action would involve the global commons of the Black Sea and the North Sea, the potential impact to the global commons has been analyzed. Because of the similarities in the two actions, the Project Sapphire Environmental Assessment was used as a basis for assessing the potential impacts of Project Partnership. However, because Project Partnership involves a small quantity of partially-spent fuel, additional analysis was conducted to assess the potential environmental impacts and to consider reasonable alternatives as required by NEPA. The Project Partnership Environmental Assessment found the potential environmental impacts to be well below those from Project Sapphire.

1998-03-31T23:59:59.000Z

247

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

Paducah DUF Paducah DUF 6 Conversion Final EIS APPENDIX A: TEXT OF PUBLIC LAW 107-206 PERTINENT TO THE MANAGEMENT OF DUF 6 Public Law 107-206 A-2 Paducah DUF 6 Conversion Final EIS Public Law 107-206 A-3 Paducah DUF 6 Conversion Final EIS APPENDIX A: TEXT OF PUBLIC LAW 107-206 PERTINENT TO THE MANAGEMENT OF DUF 6 Section 502 of Public Law 107-206, "2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States" (signed by the President 08/02/2002) SEC. 502. Section 1 of Public Law 105-204 (112 Stat. 681) is amended - (1) in subsection (b), by striking "until the date" and all that follows and inserting "until the date that is 30 days after the date on which the Secretary of Energy awards a contract under

248

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

Portsmouth DUF Portsmouth DUF 6 Conversion Final EIS APPENDIX A: TEXT OF PUBLIC LAW 107-206 PERTINENT TO THE MANAGEMENT OF DUF 6 Public Law 107-206 A-2 Portsmouth DUF 6 Conversion Final EIS Public Law 107-206 A-3 Portsmouth DUF 6 Conversion Final EIS APPENDIX A: TEXT OF PUBLIC LAW 107-206 PERTINENT TO THE MANAGEMENT OF DUF 6 Section 502 of Public Law 107-206, "2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States" (signed by the President 08/02/2002) SEC. 502. Section 1 of Public Law 105-204 (112 Stat. 681) is amended - (1) in subsection (b), by striking "until the date" and all that follows and inserting "until the date that is 30 days after the date on which the Secretary of Energy awards a contract under

249

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

Portsmouth DUF Portsmouth DUF 6 Conversion Final EIS FIGURE S-1 Regional Map of the Portsmouth, Ohio, Site Vicinity Summary S-18 Portsmouth DUF 6 Conversion Final EIS FIGURE S-3 Three Alternative Conversion Facility Locations within the Portsmouth Site, with Location A Being the Preferred Alternative (A representative conversion facility footprint is shown within each location.) Summary S-20 Portsmouth DUF 6 Conversion Final EIS FIGURE S-4 Conceptual Overall Material Flow Diagram for the Portsmouth Conversion Facility Summary S-21 Portsmouth DUF 6 Conversion Final EIS FIGURE S-5 Conceptual Conversion Facility Site Layout for Portsmouth Summary S-25 Portsmouth DUF 6 Conversion Final EIS FIGURE S-6 Potential Locations for Construction of a New Cylinder Storage Yard at Portsmouth

250

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

Paducah DUF Paducah DUF 6 Conversion Final EIS FIGURE S-1 Regional Map of the Paducah, Kentucky, Site Vicinity Summary S-18 Paducah DUF 6 Conversion Final EIS FIGURE S-3 Three Alternative Conversion Facility Locations within the Paducah Site, with Location A Being the Preferred Alternative (A representative conversion facility footprint is shown within each location.) Summary S-20 Paducah DUF 6 Conversion Final EIS FIGURE S-4 Conceptual Overall Material Flow Diagram for the Paducah Conversion Facility Summary S-21 Paducah DUF 6 Conversion Final EIS FIGURE S-5 Conceptual Conversion Facility Site Layout for Paducah Summary S-28 Paducah DUF 6 Conversion Final EIS FIGURE S-6 Areas of Potential Impact Evaluated for Each Alternative Alternatives 2-7 Paducah DUF 6 Conversion Final EIS

251

DOE/EA-1388: Environmental Assessment of Ground Water Compliance at the Shiprock Uranium Mill Tailings Site (September 2001)  

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

388 388 Environmental Assessment of Ground Water Compliance at the Shiprock Uranium Mill Tailings Site Final September 2001 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work Performed Under DOE Contract No. DE-AC13-96GJ87335 This Page Intentionally Blank DOE Grand Junction Office EA of Ground Water Compliance at the Shiprock Site September 2001 Final Page iii Contents Page Acronyms and Abbreviations ........................................................................................................ vii Executive Summary ....................................................................................................................... ix 1.0 Introduction .............................................................................................................................1

253

Environmental assessment of remedial action at the Lowman Uranium Mill Tailings Site near Lowman, Idaho. Final  

SciTech Connect

This document assesses the environmental impacts of stabilization on site of the contaminated materials at the Lowman uranium mill tailings site. The Lowman site is 0.5 road mile northeast of the unincorporated village of Lowman, Idaho, and 73 road miles from Boise, Idaho. The Lowman site consists of piles of radioactive sands, an ore storage area, abandoned mill buildings, and windblown/waterborne contaminated areas. A total of 29.5 acres of land are contaminated and most of this land occurs within the 35-acre designated site boundary. The proposed action is to stabilize the tailings and other contaminated materials on the site. A radon barrier would be constructed over the consolidated residual radioactive materials and various erosion control measures would be implemented to ensure the long-term stability of the disposal cell. Radioactive constituents and other hazardous constituents were not detected in the groundwater beneath the Lowman site. The groundwater beneath the disposal cell would not become contaminated during or after remedial action so the maximum concentration limits or background concentrations for the contaminants listed in the draft EPA groundwater protection standards would be met at the point of compliance. No significant impacts were identified as a result of the proposed remedial action at the Lowman site.

Not Available

1991-01-01T23:59:59.000Z

254

Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado. Revision 3  

SciTech Connect

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal site, 6 road miles (mi) [10 kilometers (km)] to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The proposed remedial action would result in the loss of approximately 162 ac (66 ha) of soils at the processing and disposal sites; however, 133 ac (55 ha) of these soils at and adjacent to the processing site are contaminated and cannot be used for other purposes. If supplemental standards are approved by the NRC and state of Colorado, approximately 112 ac (45 ha) of contaminated soils adjacent to the processing site would not be cleaned up. This area is steeply sloped. The cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers. Another 220 ac (89 ha) of soils would be temporarily disturbed during the remedial action. The final disposal site would result in approximately 57 ac (23 ha) being removed from livestock grazing and wildlife use.

Not Available

1994-02-01T23:59:59.000Z

255

Environmental assessment of remedial action at the Naturita Uranium processing site near Naturita, Colorado. Revision 2  

SciTech Connect

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal sits, 6 road miles (mi) [10 kilometers (km)) to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal sits would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The proposed remedial action would result in the loss of approximately 162 ac (66 ha) of soils at the processing and disposal sites; however, 133 ac (55 ha) of these soils at and adjacent to the processing site are contaminated and cannot be used for other purposes. If supplemental standards are approved by the NRC and state of Colorado, approximately 112 ac (45 ha) of contaminated soils adjacent to the processing site would not be cleaned up. This area is steeply sloped. The cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers. Another 220 ac (89 ha) of soils would be temporarily disturbed during the remedial action. The final disposal site would result in approximately 57 ac (23 ha) being removed from livestock grazing and wildlife use.

Not Available

1994-01-01T23:59:59.000Z

256

Final environmental assessment for the U.S. Department of Energy, Oak Ridge Operations receipt and storage of uranium materials from the Fernald Environmental Management Project site  

Science Conference Proceedings (OSTI)

Through a series of material transfers and sales agreements over the past 6 to 8 years, the Fernald Environmental Management Project (FEMP) has reduced its nuclear material inventory from 14,500 to approximately 6,800 metric tons of uranium (MTU). This effort is part of the US Department of energy`s (DOE`s) decision to change the mission of the FEMP site; it is currently shut down and the site is being remediated. This EA focuses on the receipt and storage of uranium materials at various DOE-ORO sites. The packaging and transportation of FEMP uranium material has been evaluated in previous NEPA and other environmental evaluations. A summary of these evaluation efforts is included as Appendix A. The material would be packaged in US Department of Transportation-approved shipping containers and removed from the FEMP site and transported to another site for storage. The Ohio Field Office will assume responsibility for environmental analyses and documentation for packaging and transport of the material as part of the remediation of the site, and ORO is preparing this EA for receipt and storage at one or more sites.

NONE

1999-06-01T23:59:59.000Z

257

Environmental assessment of remedial action at the Naturita Uranium processing site near Naturita, Colorado. Revision 1  

SciTech Connect

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal site, 6 road miles (mi) [ 1 0 kilometers (km)] to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial action would result in the loss of approximately 164 ac (66 ha) of soils, but 132 ac (53 ha) of these soils are contaminated and cannot be used for other purposes. Another 154 ac (62 ha) of soils would be temporarily disturbed. Approximately 57 ac (23 ha) of open range land would be permanently removed from livestock grazing and wildlife use. The removal of the contaminated materials would affect the 1 00-year floodplain of the San Miguel River and would result in the loss of riparian habitat along the river. The southwestern willow flycatcher, a Federal candidate species, may be affected by the remedial action, and the use of water from the San Miguel River ``may affect`` the Colorado squawfish, humpback chub, bonytail chub, and razorback sucker. Traffic levels on State Highways 90 and 141 would be increased during the remedial action, as would the noise levels along these transportation routes. Measures for mitigating the adverse environmental impacts of the proposed remedial action are discussed in Section 6.0 of this environmental assessment (EA).

Not Available

1993-08-01T23:59:59.000Z

258

MILDOS - A Computer Program for Calculating Environmental Radiation Doses from Uranium Recovery Operations  

Science Conference Proceedings (OSTI)

The MILDOS Computer Code estimates impacts from radioactive emissions from uranium milling facilities. These impacts are presented as dose commitments to individuals and the regional population within an 80 km radius of the facility. Only airborne releases of radioactive materials are considered: releases to surface water and to groundwater are not addressed in MILDOS. This code is multi-purposed and can be used to evaluate population doses for NEPA assessments, maximum individual doses for predictive 40 CFR 190 compliance evaluations, or maximum offsite air concentrations for predictive evaluations of 10 CFR 20 compliance. Emissions of radioactive materials from fixed point source locations and from area sources are modeled using a sector-averaged Gaussian plume dispersion model, which utilizes user-provided wind frequency data. Mechanisms such as deposition of particulates, resuspension. radioactive decay and ingrowth of daughter radionuclides are included in the transport model. Annual average air concentrations are computed, from which subsequent impacts to humans through various pathways are computed. Ground surface concentrations are estimated from deposition buildup and ingrowth of radioactive daughters. The surface concentrations are modified by radioactive decay, weathering and other environmental processes. The MILDOS Computer Code allows the user to vary the emission sources as a step function of time by adjustinq the emission rates. which includes shutting them off completely. Thus the results of a computer run can be made to reflect changing processes throughout the facility's operational lifetime. The pathways considered for individual dose commitments and for population impacts are: Inhalation External exposure from ground concentrations External exposure from cloud immersion Ingestioo of vegetables Ingestion of meat Ingestion of milk Dose commitments are calculated using dose conversion factors, which are ultimately based on recommendations of the International Commission on Radiological Protection (ICRP). These factors are fixed internally in the code, and are not part of the input option. Dose commitments which are available from the code are as follows: Individual dose commitments for use in predictive 40 CFR 190 compliance evaluations (Radon and short-lived daughters are excluded) Total individual dose commitments (impacts from all available radionuclides are considered) Annual population dose commitments (regional, extraregional, total and cummulative). This model is primarily designed for uranium mill facilities, and should not be used for operations with different radionuclides or processes.

Strange, D. L.; Bander, T. J.

1981-04-01T23:59:59.000Z

259

Solubility of airborne uranium compounds at the Fernald Environmental Management Project  

Science Conference Proceedings (OSTI)

The in vitro volubility of airborne uranium dusts collected at a former uranium processing facility now undergoing safe shutdown, decontamination and dismantling was evaluated by immersing air filters from high volume samplers in simulated lung fluid and measuring the {sup 238}U in sequential dissolution fractions using specific radiochemical analysis for uranium. X rays and photons from the decay of uranium and thorium remaining on the filter after each dissolution period were also directly measured using a planar germanium detector as a means for rapidly evaluating the volubility of the uranium bearing dusts. Results of these analyses demonstrate that two -distinct types of uranium bearing dusts were collected on the filters depending upon the location of the air samplers. The first material exhibited a dissolution half-time much less than one day and was most likely UO{sub 3}. The dissolution rate of the second material, which was most likely U{sub 3}O{sub 8}, exhibited two components. Approximately one-third of this material dissolved with a halftime much less than one day. The remaining two-thirds of the material dissolved with half times between 230 {+-} 16 d and 1350 {+-} 202 d. The dissolution rates for uranium determined by radiochemical analysis and by gamma spectrometry were similar. However, gamma spectrometry analysis suggested a difference between the half times of {sup 238}U and its daughter {sup 234}Th which may have important implications for in vivo monitoring of uranium.

Heffernan, T.E.; Lodwick, J.C.; Spitz, H.; Neton, J.; Soldano, M.

2000-04-04T23:59:59.000Z

260

EIS-0329: Advance Notice of Intent To Prepare an Environmental Impact  

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

329: Advance Notice of Intent To Prepare an Environmental 329: Advance Notice of Intent To Prepare an Environmental Impact Statement EIS-0329: Advance Notice of Intent To Prepare an Environmental Impact Statement Depleted Uranium Hexafluoride Conversion Facilities The U.S. Department of Energy (DOE) is providing advance notice of its intent to prepare an Environmental Impact Statement (EIS) on the proposed construction, operation, and decontamination/decommissioning of two depleted uranium hexafluoride (DUF6) conversion facilities, at Portsmouth, Ohio and Paducah, Kentucky. DOE intends to use the proposed facilities to convert its inventory of DUF6 to a more stable chemical form suitable for storage, beneficial use or disposal. Advance Notice of Intent To Prepare an Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities, DOE/EIS-0329 (May

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Remedial actions at the former Climax Uranium Company, Uranium Mill site, Grand Junction, Mesa County, Colorado. Volume 1, Text: Final environmental impact statement  

SciTech Connect

This statement evaluates and compares the environmental impacts associated with the remedial actions of the residual radioactive materials remaining at the inactive uranium processing site and associated vicinity properties at Grand Junction, Mesa County, Colorado. This statement is also intended to aid the BLM in amending their management framework plans and final resource management plan, as well as assisting in compliance with the withdrawal application as appropriate. The site is a 114-acre tract of private and state owned land which contains approximately 3.1 million cubic yards of tailings and associated contaminated soils. The vicinity properties are homes, businesses, public buildings, and vacant lots which may have been contaminated during construction by the use of tailings as building material. An estimated 3465 vicinity properties would be cleaned up during remedial action of the tailings pile. The tailings were produced by the former Climax Uranium Company which processed uranium ore, which it sold to the US Atomic Energy Commission from 1951 to 1966 and to private sources from 1966 to 1970. This statement evaluates six alternatives for stabilization and disposal of the tailings and other contaminated materials: (1) No action. (2) Stabilization at the Grand Junction site. (3) Disposal at the Cheney Reservoir site with truck transport. (4) Disposal at the Cheney Reservoir site with train and truck transport. (5) Disposal at the Two Road site with truck transport. (6) Disposal at the Two Road site with train and truck transport. All of the alternatives except no action include remedial action at an estimated 3465 vicinity properties. Alternative 3 is DOE`s preferred alternative.

None

1986-12-01T23:59:59.000Z

262

Sustained Removal of Uranium From Contaminated Groundwater  

E-Print Network (OSTI)

approximately 5 mm in diameter by 5 mm tal/. Compositions measured ranged from depleted uranium oxide to mixtures of plutonium and depleted uranium oxide (MOX) and mixed oxides with small percentages of minor.1943 - - - Title: Resonant Ultrasound Spectroscopy Measurements of the Elastic Properties of Uranium

Lovley, Derek

263

In-Situ Evidence for Uranium Immobilization and Remobilization  

E-Print Network (OSTI)

, together with depleted uranium, for fabrication of mixed oxide fuel (MOX) for reuse in a light water with depleted uranium to produce a metallic fuel for a fast reactor. The fast reactor can be designed to produce of depleted uranium and the cost of fabricating the MOX fuel: ( ) ( ) 2,22,22,22,2 bpzupf ++= . (11) The back

Istok, Jonathan "Jack"

264

Disposition of Uranium -233 (sup 233U) in Plutonium Metal and Oxide at the Rocky Flats Environmental Technology Site  

Science Conference Proceedings (OSTI)

This report documents the position that the concentration of Uranium-233 ({sup 233}U) in plutonium metal and oxide currently stored at the DOE Rocky Flats Environmental Technology Site (RFETS) is well below the maximum permissible stabilization, packaging, shipping and storage limits. The {sup 233}U stabilization, packaging and storage limit is 0.5 weight percent (wt%), which is also the shipping limit maximum. These two plutonium products (metal and oxide) are scheduled for processing through the Building 371 Plutonium Stabilization and Packaging System (PuSPS). This justification is supported by written technical reports, personnel interviews, and nuclear material inventories, as compiled in the ''History of Uranium-233 ({sup 233}U) Processing at the Rocky Flats Plant In Support of the RFETS Acceptable Knowledge Program'' RS-090-056, April 1, 1999. Relevant data from this report is summarized for application to the PuSPS metal and oxide processing campaigns.

Freiboth, Cameron J.; Gibbs, Frank E.

2000-03-01T23:59:59.000Z

265

Environmental assessment of remedial action at the Slick Rock uranium mill tailings sites Slick Rock, Colorado. Draft  

SciTech Connect

The Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA) authorized the US Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miguel County. The purpose of the cleanup is to reduce the potential health effects associated with the radioactive materials remaining on the sites and on vicinity properties (VP) associated with the sites. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contained measures to control the contaminated materials and to protect the groundwater from further degradation. Remedial actions at the Slick Rock sites must be performed in accordance with these standards and with the concurrence of the US Nuclear Regulatory Commission (NRC).

1993-06-01T23:59:59.000Z

266

Journal of the Less-Common Metals, I62 (1990) 117-127 117 COMPARISON OF URANIUM AND ZIRCONIUM COBALT FOR  

E-Print Network (OSTI)

surface wastes resulting from uranium solution extraction processes. Underground ore bodies depleted Washington, DC 20460 Uranium Location Database Compilation #12;Table of Contents Abstract............................................................................................................................3 Uranium

Kherani, Nazir P.

267

Available Technologies: Cost-effective Recovery of Uranium ...  

Uranium contamination of groundwater is an environmental problem at many DOE facilities and at uranium mining/processing sites.

268

EPA Review of Standards for Uranium and Thorium Milling Facilities @ 40 CFR Parts 61 and 192.  

E-Print Network (OSTI)

diversity in industrial effluent and sewage contaminated soils. 2008, in prep. New test for depleted uranium A new test to detect depleted uranium in Gulf War veterans has unexpectedly uncovered high levels uranium. But depleted uranium showed up in a related study by the team near a former munitions plant

269

Method for converting uranium oxides to uranium metal  

DOE Green Energy (OSTI)

A process is described for converting scrap and waste uranium oxide to uranium metal. The uranium oxide is sequentially reduced with a suitable reducing agent to a mixture of uranium metal and oxide products. The uranium metal is then converted to uranium hydride and the uranium hydride-containing mixture is then cooled to a temperature less than -100.degree. C. in an inert liquid which renders the uranium hydride ferromagnetic. The uranium hydride is then magnetically separated from the cooled mixture. The separated uranium hydride is readily converted to uranium metal by heating in an inert atmosphere. This process is environmentally acceptable and eliminates the use of hydrogen fluoride as well as the explosive conditions encountered in the previously employed bomb-reduction processes utilized for converting uranium oxides to uranium metal.

Duerksen, Walter K. (Norris, TN)

1988-01-01T23:59:59.000Z

270

Method for converting uranium oxides to uranium metal  

DOE Patents (OSTI)

A process is described for converting scrap and waste uranium oxide to uranium metal. The uranium oxide is sequentially reduced with a suitable reducing agent to a mixture of uranium metal and oxide products. The uranium metal is then converted to uranium hydride and the uranium hydride-containing mixtures is then cooled to a temperature less than -100/sup 0/C in an inert liquid which renders the uranium hydride ferromagnetic. The uranium hydride is then magnetically separated from the cooled mixture. The separated uranium hydride is readily converted to uranium metal by heating in an inert atmosphere. This process is environmentally acceptable and eliminates the use of hydrogen fluoride as well as the explosive conditions encountered in the previously employed bomb-reduction processes utilized for converting uranium oxides to uranium metal.

Duerksen, W.K.

1987-01-01T23:59:59.000Z

271

Environmental Assessment of remedial action at the Ambrosia Lake uranium mill tailings site, Ambrosia Lake, New Mexico  

SciTech Connect

This document assesses and compares the environmental impacts of various alternatives for remedial action at the Ambrosia Lake uranium mill tailings site located near Ambrosia Lake, New Mexico. The designated site covers 196 acres and contains 111 acres of tailings and some of the original mill structures. The Uranium Mill Tailings Radiation Control Act (UMTRCA), Public Law 95-604, authorizes the US Department of Energy to clean up the site to reduce the potential health impacts associated with the residual radioactive materials remaining at the site and at associated properties off the site. The US Environmental Protection Agency promulgated standards for th remedial action (40 CFR Part 192). Remedial action must be performed in accordance with these standards and with the concurrence of the Nuclear Regulatory Commission. The proposed action is to stabilize the tailings at their present location by consolidating the tailings and associated contaminated materials into a recontoured pile. A radon barrier would be constructed over the pile and various erosion protection measures would be taken to assure the long-term stability of the pile. Another alternative which would involve moving the tailings to a new location is also assessed in this document. This alternative would generally involve greater short-term impacts and costs but would result in stabilization of the tailings at an undeveloped location. The no action alternative is also assessed in this document.

Not Available

1987-06-01T23:59:59.000Z

272

Electron Emission from Slightly Oxidized Depleted Uranium Generated by its Own Radioactivity Measured by Electron Spectroscopy, and Electron-Induced Dissociation and Ionization of Hydrogen Near its Surface.  

DOE Green Energy (OSTI)

Energy dependent electron emission (counts per second) between zero and 1.4 keV generated by the natural reactivity of uranium was measured by an electrostatic spectrometer with known acceptance angle and acceptance area. The electron intensity decreases continuously with energy, but at different rates in different energy regimes, suggesting that a variety of processes may be involved in producing the observed electron emission. The spectrum was converted to energy dependent electron flux (e-/cm{sup 2} s) using the assumption that the emission has a cosine angular distribution. The flux decreased rapidly from {approx}10{sup 6}/cm{sup 2}s to {approx}10{sup 5}/cm{sup 2}s in the energy range from zero to 200 eV, and then more slowly from {approx}10{sup 5}/cm{sup 2}s to {approx}3*10{sup 4}/cm{sup 2} s in the range from 200 to 1400 eV. The energy dependent electron mean free path in gases together with literature cross sections for electron induced reactions were used to determine the number of ionization and dissociation reactions per cm{sup 2}s within the inelastic mean free path of electrons, and found to be about 1.3*10{sup 8}/cm{sup 2}s and 1.5*10{sup 7}/cm{sup 2}s, respectively, for hydrogen. An estimate of the number of ionization and dissociation reactions occurring within the total range, rather than the mean free path of electrons in gases resulted in 6.2*10{sup 9}/cm{sup 2}s and 1.3*10{sup 9}/cm{sup 2}s, respectively. The total energy flux carried by electrons from the surface is suspiciously close to the total possible energy generated by one gram of uranium. A likely source of error is the assumption that the electron emission has a cosine distribution. Angular distribution measurements of the electron emission would check that assumption, and actual measurement of the total current emanating from the surface are needed to confirm the value of the current calculated in section II. These results must therefore be used with caution - until they are confirmed by other measurements.

Siekhaus, W J; Nelson, A J

2011-10-26T23:59:59.000Z

273

DOE/EA-1607 FINAL ENVIRONMENTAL ASSESSMENT DISPOSITION OF DOE EXCESS  

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

µCi/cc microcuries per cubic centimeter µCi/cc microcuries per cubic centimeter MAP mitigation action plan MEI maximally exposed individual mg/kg milligrams per kilogram mrem millirem mSv millisievert MT metric ton MTCA Model Toxics Control Act MTU metric tons of uranium N/A not applicable Final Environmental Assessment: Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium vi NAAQS National Ambient Air Quality Standards NEF National Enrichment Facility NEPA National Environmental Policy Act NRC U.S. Nuclear Regulatory Commission NU natural uranium NUF 6 natural uranium hexafluoride pCi/g picocuries per gram PEIS programmatic environmental impact statement PM 2.5 particulate matter with a diameter of 2.5 microns or less PM 10 particulate matter with a diameter of 10 microns or less

274

Environmental proteomics reveals early microbial community responses to biostimulation at a uranium- and nitrate-contaminated site  

Science Conference Proceedings (OSTI)

High performance mass spectrometry instrumentation coupled with improved protein extraction techniques enable metaproteomics to identify active members of soil and groundwater microbial communities. Metaproteomics workflows were applied to study the initial responses (i.e., 4 days post treatment) of the indigenous aquifer microbiota to biostimulation with emulsified vegetable oil (EVO) at a uranium-contaminated site. Members of the Betaproteobacteria (i.e., Dechloromonas, Ralstonia, Rhodoferax, Polaromonas, Delftia, Chromobacterium) and Firmicutes dominated the biostimulated aquifer community. Proteome characterization revealed distinct differences in protein expression between the microbial biomass collected from groundwater influenced by biostimulation and groundwater collected up-gradient of the EVO injection points. In particular, proteins involved in ammonium assimilation, EVO degradation, and polyhydroxybutyrate (PHB) granule formation were prominent following biostimulation. Interestingly, the atypical NosZ of a Dechloromonas sp. was highly expressed suggesting active nitrous oxide (N2O) respiration. c-type cytochromes were barely detected, as was citrate synthase, a biomarker for hexavalent uranium reduction activity, suggesting that metal reduction has not commenced 4 days post EVO delivery. Environmental metaproteomics identified microbial community responses to biostimulation and elucidated active pathways demonstrating the value of this technique for complementing nucleic acid-based approaches.

Chourey, Karuna [ORNL] [ORNL; Nissen, Silke [ORNL] [ORNL; Vishnivetskaya, T. [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Shah, Manesh B [ORNL] [ORNL; Pffifner, Susan [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Hettich, Robert {Bob} L [ORNL; Loeffler, Frank E [ORNL] [ORNL

2013-01-01T23:59:59.000Z

275

APPLIED AND ENVIRONMENTAL MICROBIOLOGY, 0099-2240/98/$04.00 0  

E-Print Network (OSTI)

the fluorescence of natural teeth (a relatively minor historical use). Depleted uranium For inertial guidance quantities of remnant, depleted uranium that is almost pure U-238. Depleted uranium is very stable and very have generated enormous quantities of depleted uranium. The U.S. Department of Energy has over 500

Haygood, Margo G.

276

Record of Decision for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site (DOE/EIS-0360) (07/20/04)  

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

49 49 Federal Register / Vol. 69, No. 143 / Tuesday, July 27, 2004 / Notices halseypj@oro.doe.gov or check the Web site at www.oakridge.doe.gov/em/ssab. SUPPLEMENTARY INFORMATION: Purpose of the Board: The purpose of the Board is to make recommendations to DOE in the areas of environmental restoration, waste management, and related activities. Tentative Agenda 8 a.m.-Introductions, overview of meeting agenda and logistics (Dave Mosby) 8:15 a.m.-Past year evaluation-Board and stakeholder survey results, what worked, what can be improved (Facilitator) 9:50 a.m.-Break 10:05 a.m.-Past year evaluation continued 10:45 a.m.-Summaries and Q&A on the most important issues to DOE, TN Department of Environment & Conservation, and EPA (Facilitator) 11:30 a.m.-Lunch

277

EIS-0359: EPA Notice of Availability of the Draft Environmental Impact  

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

EPA Notice of Availability of the Draft Environmental EPA Notice of Availability of the Draft Environmental Impact Statement EIS-0359: EPA Notice of Availability of the Draft Environmental Impact Statement Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site DOE/EIS-0359, Environmental Protection Agency, Notice of Availability, Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site, 68 FR 66825 (November 2003) More Documents & Publications EIS-0343: EPA Notice of Availability of the Draft Environmental Impact Statement EIS-0360: EPA Notice of Availability of the Draft Environmental Impact Statement EIS-0336: EPA Notice of Availability of the Final Environmental Impact

278

DOE/EIS-0355 Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah, Final Environmental Impact Statement  

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

Volumes IV Volumes IV Chapters 4 -5 Comment Responses U.S. Department of Energy Office of Environmental Management Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah Final Environmental Impact Statement i Contents Volume IV 4.0 Responses............................................................................................................................4-1 4.1 Response Index Tables ..............................................................................................4-1 4.2 Responses to Comments ..........................................................................................4-70 5.0 References...........................................................................................................................5-1

279

Environmental assessment of remedial action at the slick rock Uranium Mill Tailings sites Slick Rock, Colorado  

SciTech Connect

The Uranium Mill Tailings Radiation Control Act of 1978 (42 USC {section} 7901 et seq.), hereafter referred to as the UMTRCA, authorized the U.S. Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miguel County. The purpose of the cleanup is to reduce the potential health effects associated with the radioactive materials remaining on the sites and on vicinity properties (VPs) associated with the sites. Contaminated materials cover an estimated 55 acres of the Union Carbide (UC) processing site and 12 ac of the North Continent (NC) processing site. The total estimated volume of contaminated materials is approximately 61 8,300 cubic yards. In addition to the contamination in the two processing site areas, four VPs were found to contain contamination. As a result of the tailings being exposed to the environment, contamination associated with the UC and NC sites has leached into shallow ground water. Surface water has not been affected. The closest residence is approximately 0.3 air mi from either site. The proposed action is to remediate the UC and NC sites by removing all contaminated materials within the designated site boundaries or otherwise associated with the sites, and relocating them to, and stabilizing them at, a location approximately 5 road mi (8 km) northeast of the sites on land administered by the Bureau of Land Management (BLM). Remediation would be performed by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. All solid contaminated materials would be buried under 5 feet (ft) of rock and soil materials. The proposed disposal site area is currently used by ranchers for cattle grazing over a 7-month period. The closest residence to the proposed disposal site is 2 air mi. An estimated 44 ac of land would be permanently transferred from the BLM to the DOE and restricted from future use.

1994-09-01T23:59:59.000Z

280

ENVIRONMENTAL MANAGEMENT SITE-SPECIFIC ADVISORY BOARD  

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

Washington, D.C. 20585 Washington, D.C. 20585 April 25, 2013 2 Environmental Management Site-Specific Advisory Board - April 25, 2013 Meeting Minutes LIST OF ACRONYMS AB - Advisory Board ANL - Argonne National Laboratory ARP - Accelerator Retrieval Project BNL - Brookhaven National Laboratory BRC - Blue Ribbon Commission CAB - Citizens Advisory Board D&D - Decontamination & Decommissioning DDFO - Deputy Designated Federal Officer DOE - Department of Energy DUF6 - Depleted Uranium Hexafluoride DWPF - Defense Waste Processing Facility EIS - Environmental Impact Statement EM - DOE Office of Environmental Management EM SSAB - DOE Office of Environmental Management Site-Specific Advisory Board EPA - U.S. Environmental Protection Agency FY - Fiscal Year

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Charge Depleting:  

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

0.5 seconds 0.5 seconds Acceleration 1/4 Mile Time: 18.6 seconds Maximum Speed: 83.2 MPH Acceleration 1 Mile Maximum Speed: 100.6 MPH Charge Sustaining: Acceleration 0-60 MPH Time: 10.6 seconds Acceleration 1/4 Mile Time: 18.6 seconds Maximum Speed: 82.8 MPH Acceleration 1 Mile Maximum Speed: 101.9 MPH Brake Test @ 60 MPH Distance Required: 145.1 ft UDDS Fuel Economy 6 HWFET Fuel Economy 6,10 Distance (miles) Fuel Economy (mpg) AC Energy Consumed (kWh) 7 Distance (miles) Fuel Economy (mpg) AC Energy Consumed (kWh) 7 10 118.5 2.85 10 53.0 1.80 20 116.8 5.49 20 56.6 3.37 40 116.0 10.50 40 58.0 6.38 60 90.7 11.34 60 55.3 9.48 80 76.6 11.34 80 51.4 11.11 100 68.0 11.34 100 47.2 11.13 200 50.9 11.34 200 38.7 11.13 Fuel Economy with A/C Off 1 Cold Start Charge Depleting 2 : Fuel Economy: 119.7 MPG AC kWh Consumed 7 : 0.282 kWh/mi Charge Depleting

282

Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Paducah Gaseous Diffusion Plant site  

Science Conference Proceedings (OSTI)

Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. The U-235 atoms are ionized when precisely tuned laser light -- of appropriate power, spectral, and temporal characteristics -- illuminates the uranium vapor and selectively photoionizes the U-235 isotope. A programmatic document for use in screening DOE site to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the PGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. 65 refs., 15 tabs.

Marmer, G.J.; Dunn, C.P.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Yuen, C.R.; Cleland, J.H. (ed.)

1991-09-01T23:59:59.000Z

283

Uranium Mill Tailings Remedial Action Project Annual Environmental Monitoring Report calendar year 1992: Volume 1  

SciTech Connect

This report describes environmental monitoring and compliance at eight UMTRA sites where remedial action was underway during 1992 and at the ten sites that were complete at the end of 1992. Volume I contains information for Ambrosia Lake, NM; Cannonsburg/Burrell, PA; Durango, CO; Falls City, TX; Grand Junction, CO; Green River, UT; and Gunnison, CO. Each site report contains a site description, compliance summary, environmental program information, environmental radiological and non-radiological program information, water resources protection, and quality assurance information.

Not Available

1993-12-31T23:59:59.000Z

284

Controlling uranium reactivity March 18, 2008  

E-Print Network (OSTI)

. Redistribution of depleted uranium (DU soils and water at two US Army proving grounds. Ann. M Health Phys. SocRemediation of uranium contaminated soils with bicarbonate extraction and microbial U(VI) reduction ElizabethJ.P.Phillips, Edward R. Landa and DerekR. Lovley Key words: Bioremediation; Uranium; Mill tailings

Meyer, Karsten

285

The Uranium Institute 24th Annual Symposium  

E-Print Network (OSTI)

:same as iron. 3.2 Preparation A standard analysis of the depleted uranium,provided by COGEMA, is given-sur-Tille, France Abstract : After reviewing briefly the influence of the incorporationof vanadium in the uranium,nickel and iron, on the properties of the uranium-0.2%vanadium alloys. Tensile tests at both ambient and elevated

Laughlin, Robert B.

286

Integration of health physics, safety and operational processes for management and disposition of recycled uranium wastes at the Fernald Environmental Management Project (FEMP)  

Science Conference Proceedings (OSTI)

Fluor Fernald, Inc. (Fluor Fernald), the contractor for the U. S. Department of Energy (DOE) Fernald Environmental Management Project (FEMP), recently submitted a new baseline plan for achieving site closure by the end of calendar year 2006. This plan was submitted at DOE's request, as the FEMP was selected as one of the sites for their accelerated closure initiative. In accordance with the accelerated baseline, the FEMP Waste Management Project (WMP) is actively evaluating innovative processes for the management and disposition of low-level uranium, fissile material, and thorium, all of which have been classified as waste. These activities are being conducted by the Low Level Waste (LLW) and Uranium Waste Disposition (UWD) projects. Alternatives associated with operational processing of individual waste streams, each of which poses potentially unique health physics, industrial hygiene and industrial hazards, are being evaluated for determination of the most cost effective and safe met hod for handling and disposition. Low-level Mixed Waste (LLMW) projects are not addressed in this paper. This paper summarizes historical uranium recycling programs and resultant trace quantity contamination of uranium waste streams with radionuclides, other than uranium. The presentation then describes how waste characterization data is reviewed for radiological and/or chemical hazards and exposure mitigation techniques, in conjunction with proposed operations for handling and disposition. The final part of the presentation consists of an overview of recent operations within LLW and UWD project dispositions, which have been safely completed, and a description of several current operations.

Barber, James; Buckley, James

2003-02-23T23:59:59.000Z

287

Radiochemical Analysis Methodology for uranium Depletion Measurements  

SciTech Connect

This report provides sufficient material for a test sponsor with little or no radiochemistry background to understand and follow physics irradiation test program execution. Most irradiation test programs employ similar techniques and the general details provided here can be applied to the analysis of other irradiated sample types. Aspects of program management directly affecting analysis quality are also provided. This report is not an in-depth treatise on the vast field of radiochemical analysis techniques and related topics such as quality control. Instrumental technology is a very fast growing field and dramatic improvements are made each year, thus the instrumentation described in this report is no longer cutting edge technology. Much of the background material is still applicable and useful for the analysis of older experiments and also for subcontractors who still retain the older instrumentation.

Scatena-Wachel DE

2007-01-09T23:59:59.000Z

288

Assessment of Preferred Depleted Uranium Disposal Forms  

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

. . 7 3.2 PRELIMINARY ASSESSMENT OF DU DISPOSAL AT OTHER SITES . . . . . . . . . . 8 3.3 COSTS OF PRODUCTION, TRANSPORTATION, AND DISPOSAL OF DU WASTE FORMS . . . . . . . . . . ....

289

Tritium Transport Vessel Using Depleted Uranium  

Science Conference Proceedings (OSTI)

Tritium Storage, Distribution, and Transportation / Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

L. K. Heung

290

Depleted Uranium Hexafluoride Management Program: Data Compilation...  

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

Impacts Associated with Continued Storage of the Entire Portsmouth Site Cylinder Inventory . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-51 3.5.1 Approach Used to...

291

Depleted Uranium Hexafluoride Management Program: Data Compilation...  

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

Code USEC United States Enrichment Corporation Chemicals AlF 3 aluminum trifluoride CaF 2 calcium fluoride CO carbon monoxide Fe iron HF hydrogen fluoride HNO 3 nitric acid Mg...

292

Depleted Uranium Hexafluoride Materials Use Roadmap  

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

8 8 U.S. Department of Energy DUF 6 MATERIALS USE ROADMAP Edited by: M. Jonathan Haire Allen G. Croff August 27, 2001 DUF 6 Materials Use Workshop Participants August 24-25, 1999 Name Organization Halil Avci ANL Bob Bernero Consultant Lavelle Clark PNNL Carl Cooley DOE/EM-50 Allen Croff ORNL Juan Ferrada ORNL Charles Forsberg ORNL John Gasper ANL Bob Hightower ORNL Julian Hill PNNL Ed Jones LLNL Asim Khawaja PNNL George Larson Consultant Paul Lessing INEEL Dan O'Connor ORNL Robert Price DOE/NE-30 Nancy Ranek ANL Mark Senderling DOE/RW-46 Roger Spence ORNL John Tseng DOE/EM-21 John Warren DOE/NE-30 Ken Young LLNL iii CONTENTS ACRONYMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v EXECUTIVE SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . .

293

FAQ 19-Is storage of uranium hexafluoride safe?  

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

storage of uranium hexafluoride safe? Is storage of uranium hexafluoride safe? The advanced age of some of the steel cylinders in which the depleted UF6 is contained, and the way...

294

INHERENTLY SAFE IN SITU URANIUM RE OVERY  

Nuclear power and waste opportunities contact us at Mining operations Increased safety of uranium removal Environmentally friendly process

295

W-98: Synergistic Extraction and Solvent Extraction of Uranium from ...  

Science Conference Proceedings (OSTI)

W-42: Evolution of Internal Strain and Microstructure in Depleted Uranium in the Presence of Hydrides W-43: Existence of Niobium in Ductile Iron and Its Effect...

296

DOE/EIS-0355 Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah, Final Environmental Impact Statement  

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

II II Appendices A-H U.S. Department of Energy Office of Environmental Management Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah Final Environmental Impact Statement i Contents Page Volume II Appendix A, Biological Assessment/Screening Level Risk Assessment/Biological Opinion Appendix A1, Biological Assessment A1-1.0 Introduction ..............................................................................................................A1-1 A1-2.0 Species Evaluated.....................................................................................................A1-3 A1-2.1 Critical Habitat..................................................................................................A1-3 A1-3.0 Consultation to Date.................................................................................................A1-4

297

Standing by Ohio: Cleaning Up our Environmental Legacy | Department...  

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

the start-up of operations at the Depleted Uranium Hexafluoride Conversion Plant, or DUF6, as we commonly call it. Depleted uranium hexafluoride has been generated in the United...

298

Ozone depletion, the Greenhouse effect, and climate change. Hearings before the Subcommittee on Environmental Pollution of the Committee on Environment and Public Works, United States Senate, Ninety-Ninth Congress, Second Session, June 10 and 11, 1986  

SciTech Connect

Witnesses at a two-day hearing on the nature and magnitude of possible risks from the greenhouse effect and depletion of the ozone layer and the government's role in addressing these problems included representatives of universities, international environmental and resource institutes and organizations, manufacturers of fluorocarbons, historians, and government agencies. Prompting the hearings was a DOE report on the risks and need for intensive research and international cooperation in the area of environmental policy. Technical presentations were given by experts in atmospheric chemistry and oceanography. Additional material submitted for the record follows the testimony of the 16 witnesses.

1986-01-01T23:59:59.000Z

299

Environmental assessment for the purchase of Russian low enriched uranium derived from the dismantlement of nuclear weapons in the countries of the former Soviet Union  

SciTech Connect

The United States is proposing to purchase from the Russian Federation low enriched uranium (LEU) derived from highly enriched uranium (HEU) resulting from the dismantlement of nuclear weapons in the countries of the former Soviet Union. The purchase would be accomplished through a proposed contract requiring the United States to purchase 15,250 metric tons (tonnes) of LEU (or 22,550 tonnes of UF{sub 6}) derived from blending 500 metric tones uranium (MTU) of HEU from nuclear warheads. The LEU would be in the form of uranium hexafluoride (UF{sub 6}) and would be converted from HEU in Russia. The United States Enrichment Corporation (USEC) is the entity proposing to undertake the contract for purchase, sale, and delivery of the LEU from the Russian Federation. The US Department of Energy (DOE) is negotiating the procedure for gaining confidence that the LEU is derived from HEU that is derived from dismantled nuclear weapons (referred to as ``transparency),`` and would administer the transparency measures for the contract. There are six environments that could potentially be affected by the proposed action; marine (ocean); US ports of entry; truck or rail transportation corridors; the Portsmouth GDP; the electric power industry; and the nuclear fuel cycle industry. These environmental impacts are discussed.

Not Available

1994-01-01T23:59:59.000Z

300

Record of Decision for the Disposition of Surplus Highly Envirched Uranium Final Environmental Impact Statement  

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

19 19 Federal Register / Vol. 61, No. 151 / Monday, August 5, 1996 / Notices contact: Carol M. Borgstrom, Director, Office of NEPA Policy and Assistance (EH-42), U.S. Department of Energy, 1000 Independence Avenue, S.W., Washington, D.C. 20585, Telephone: 202-586-4600 or leave a message at 800-472-2756. SUPPLEMENTARY INFORMATION: On July 17, 1996, the Department published a notice in the Federal Register (61 FR 37247) announcing its intent to prepare an environmental impact statement for interim storage of plutonium at the RFETS and the commencement of a public scoping period that was to continue until August 16, 1996. The July 17, 1996, notice also announced a public scoping meeting scheduled for August 6, 1996. In response to a stakeholder's request, the Department is rescheduling the public scoping meeting

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel ... nuclear reactors, generation, spent fuel. Total Energy. Comprehensive data summaries, comparisons, analysis, and projections ...

302

DOE/EIS-0355 Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah, Final Environmental Impact Statement  

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

I I Chapters 1-11 U.S. Department of Energy Office of Environmental Management COVER SHEET Lead Agency: U.S. Department of Energy Cooperating Agencies: * National Park Service * Bureau of Land Management * U.S. Nuclear Regulatory Commission * U.S. Army Corps of Engineers * U.S. Fish and Wildlife Service * State of Utah * U.S. Environmental Protection Agency * Ute Mountain Ute Tribe * San Juan County * Grand County * City of Blanding * Community of Bluff Title: Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah, Final Environmental Impact Statement (DOE/EIS-0355). Contact: For further information about this Environmental Impact Statement, contact: Don Metzler Moab Federal Project Director U.S. Department of Energy

303

DOE/EIS-0355 Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah, Final Environmental Impact Statement  

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

Summary Summary U.S. Department of Energy Office of Environmental Management COVER SHEET Lead Agency: U.S. Department of Energy Cooperating Agencies: * National Park Service * Bureau of Land Management * U.S. Nuclear Regulatory Commission * U.S. Army Corps of Engineers * U.S. Fish and Wildlife Service * State of Utah * U.S. Environmental Protection Agency * Ute Mountain Ute Tribe * San Juan County * Grand County * City of Blanding * Community of Bluff Title: Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah, Final Environmental Impact Statement (DOE/EIS-0355). Contact: For further information about this Environmental Impact Statement, contact: Don Metzler Moab Federal Project Director U.S. Department of Energy 2597 B ¾ Road

304

Mathematical Geology, Vol. 33, No. 1, 2001 Modeling Uranium Transport in Koongarra,  

E-Print Network (OSTI)

of the given paper consists in obtaining such data for depleted uranium and for four uranium alloys at strain comparison e.g. with depleted uranium. I f we use these materials for design of s t r u c t u r a l p a r Z o Fig. 3 : The effect of the strain rate on the Hugoniot stress -0- ,k A Depleted Uranium A/ o

Hassanizadeh, S. Majid

305

EIS-0360: Draft Environmental Impact Statement | Department of Energy  

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

Draft Environmental Impact Statement Draft Environmental Impact Statement EIS-0360: Draft Environmental Impact Statement Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site The U.S. Department of Energy (DOE) proposes, via a contract awarded at the direction of Congress (Public Law 107-206), to design, construct, and operate two conversion facilities for converting depleted uranium hexafluoride (commonly referred to as DUF6): one at Portsmouth, Ohio, and one at Paducah, Kentucky. DOE intends to use the proposed facilities to convert its inventory of DUF6 to a more stable chemical form suitable for beneficial use or disposal. This site-specific EIS analyzes the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed DUF6 conversion facility at three

306

EIS-0359: Final Environmental Impact Statement | Department of Energy  

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

Final Environmental Impact Statement Final Environmental Impact Statement EIS-0359: Final Environmental Impact Statement Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site The U.S. Department of Energy (DOE) proposes, via a contract awarded at the direction of Congress (Public Law 107-206), to design, construct, and operate two conversion facilities for converting depleted uranium hexafluoride (commonly referred to as DUF6): one at Portsmouth, Ohio, and one at Paducah, Kentucky. DOE intends to use the proposed facilities to convert its inventory of DUF6 to a more stable chemical form suitable for beneficial use or disposal. This site-specific EIS considers the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed DUF6 conversion facility at three

307

Notice of Intent To Prepare an Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities (DOE/EIS-0329) (9/18/01)  

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

23 23 Federal Register / Vol. 66, No. 181 / Tuesday, September 18, 2001 / Notices Section 615-Procedural Safeguards Topic Addressed: Due Process Hearings * Letter dated April 19, 2001 to Virginia Department of Education Director Judith A. Douglas, regarding whether a State educational agency is required to convene a due process hearing initiated by someone other than the parent of a child with a disability or a public agency. Topic Addressed: Surrogate Parents * Letter dated April 16, 2001 to Pinal County, Arizona Deputy County Attorney Linda L. Harant, regarding the appointment of surrogate parents for children who are wards of a tribal court. Topic Addressed: Student Discipline * Letter dated April 16, 2001 to Professor Perry A. Zirkel, regarding the calculation of disciplinary removals of

308

Notice of Change in National Environmental Policy (NEPA) Compliance Approach for the Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project (4/28/03)  

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

68 68 Federal Register / Vol. 68, No. 81 / Monday, April 28, 2003 / Notices ''Browse Pending Collections'' link and by clicking on link number 2270. When you access the information collection, click on ''Download Attachments'' to view. Written requests for information should be addressed to Vivian Reese, Department of Education, 400 Maryland Avenue, SW., Room 4050, Regional Office Building 3, Washington, DC 20202-4651 or to the e-mail address vivan.reese@ed.gov. Requests may also be electronically mailed to the internet address OCIO_RIMG@ed.gov or faxed to 202-708-9346. Please specify the complete title of the information collection when making your request. Comments regarding burden and/or the collection activity requirements should be directed to Joseph Schubart at

309

Notice of Change in National Environmental Policy Act (NEPA) Compliance Approach for the Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project  

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

68 68 Federal Register / Vol. 68, No. 81 / Monday, April 28, 2003 / Notices ''Browse Pending Collections'' link and by clicking on link number 2270. When you access the information collection, click on ''Download Attachments'' to view. Written requests for information should be addressed to Vivian Reese, Department of Education, 400 Maryland Avenue, SW., Room 4050, Regional Office Building 3, Washington, DC 20202-4651 or to the e-mail address vivan.reese@ed.gov. Requests may also be electronically mailed to the internet address OCIO_RIMG@ed.gov or faxed to 202-708-9346. Please specify the complete title of the information collection when making your request. Comments regarding burden and/or the collection activity requirements should be directed to Joseph Schubart at

310

Advance Notice of Intent To Prepare an Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities (DOE/EIS-0329) (5/7/01)  

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

010 010 Federal Register / Vol. 66, No. 88 / Monday, May 7, 2001 / Notices centers. The commenter believes that by working independently of schools, the centers can better assist families who do not feel connected with the schools and provide families with the tools needed to create change in the schools. Discussion: The Secretary is not requiring non-profit organizations to apply in consortium with one or more LEAs. However, the Secretary believes that strengthening school-community- family partnerships will help children in low-performing schools succeed in school. Under the priority, the parent centers still will have considerable autonomy in designing proposals that best meet local needs and in coordinating with low-performing schools in implementing comprehensive strategies to assist children in these

311

APPLIED AND ENVIRONMENTAL MICROBIOLOGY, Oct. 2003, p. 58845891 Vol. 69, No. 10 0099-2240/03/$08.00 0 DOI: 10.1128/AEM.69.10.58845891.2003  

E-Print Network (OSTI)

. All further refueling can be accomplished with natural uranium, depleted uranium, decommissioned and sustain its self with occasional shipments of natural or depleted uranium. The purpose of adding U-238 of depleted uranium and 1.2 million tones worldwide. If breeding is considered, uranium resources can

Lovley, Derek

312

DOE/EA-1312: Environmental Assessment of Ground Water Compliance at the Grand Junction UMTRA Project Site (Climax Uranium Millsite) (September 1999)  

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

2 2 Rev. 0 Environmental Assessment of Ground Water Compliance at the Grand Junction UMTRA Project Site (Climax Uranium Millsite) Final September 1999 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work Performed Under DOE Contract No. DE-AC13-96GJ87335 for the U.S. Department of Energy EA of Ground Water Compliance at the Grand Junction UMTRA Project Site DOE Grand Junction Office Page ii Final September 1999 Contents Executive Summary.........................................................................................................................v 1.0 Introduction...............................................................................................................................1 1.1 Grand Junction UMTRA Project Site Location and Description.........................................1

313

DOE/EA-1313: Environmental Assessment of Ground Water Compliance at the Monument Valley, Arizona, Uranium Mill Tailings Site (03/22/05)  

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

DOE/EA-1313 DOE/EA-1313 Rev. 0 Environmental Assessment of Ground Water Compliance at the Monument Valley, Arizona, Uranium Mill Tailings Site Final March 2005 Prepared by U.S. Department of Energy Office of Legacy Management Grand Junction, Colorado Work Performed Under DOE Contract No. DE-AC01-02GJ79491 for the U.S. Department of Energy Document Number U0069700 This Page Intentionally Blank DOE Office of Legacy Management EA of Ground Water Compliance at the Monument Valley Site March 2005 Final Page iii Contents Page Acronyms and Abbreviations ....................................................................................................... vii Executive Summary.......................................................................................................................

314

EIS-0360: EPA Notice of Availability of the Final Environmental Impact  

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

60: EPA Notice of Availability of the Final Environmental 60: EPA Notice of Availability of the Final Environmental Impact Statement EIS-0360: EPA Notice of Availability of the Final Environmental Impact Statement Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site The U.S. Department of Energy (DOE) proposes, via a contract awarded at the direction of Congress (Public Law 107-206), to design, construct, and operate two conversion facilities for converting depleted uranium hexafluoride (commonly referred to as DUF6): one at Portsmouth, Ohio, and one at Paducah, Kentucky. DOE intends to use the proposed facilities to convert its inventory of DUF6 to a more stable chemical form suitable for beneficial use or disposal. Final Environmental Impact Statement for Construction and Operation of a

315

EIS-0360: EPA Notice of Availability of the Final Environmental Impact  

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

EPA Notice of Availability of the Final Environmental EPA Notice of Availability of the Final Environmental Impact Statement EIS-0360: EPA Notice of Availability of the Final Environmental Impact Statement Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site The U.S. Department of Energy (DOE) proposes, via a contract awarded at the direction of Congress (Public Law 107-206), to design, construct, and operate two conversion facilities for converting depleted uranium hexafluoride (commonly referred to as DUF6): one at Portsmouth, Ohio, and one at Paducah, Kentucky. DOE intends to use the proposed facilities to convert its inventory of DUF6 to a more stable chemical form suitable for beneficial use or disposal. Final Environmental Impact Statement for Construction and Operation of a

316

The Next Generation Safeguards Initiative s High-Purity Uranium-233 Preservation Effort  

Science Conference Proceedings (OSTI)

High-purity 233U serves as a crucial reference material for accurately quantifying and characterizing uranium. The most accurate analytical results which can be obtained only with high-purity 233U certified reference material (CRM) are required when used to confirm compliance with international safeguards obligations and international nonproliferation agreements. The U.S. supply of 233U CRM is almost depleted, and existing domestic stocks of this synthetic isotope are scheduled to be down-blended for disposition with depleted uranium beginning in 2015. Down blending batches of high-purity 233U will permanently eliminate the value of this material as a CRM. Furthermore, no replacement 233U stocks are expected to be produced in the future due to a lack of operating production capability and the high cost of replacing such capability. Therefore, preserving select batches of high-purity 233U is of great value and will assist in retaining current analytical capabilities for uranium-bearing samples. Any organization placing a priority on accurate results of uranium analyses, or on the confirmation of trace uranium in environmental samples, has a vested interest in preserving this material. This paper describes the need for high-purity 233U, the consequences organizations and agencies face if this material is not preserved, and the progress and future plans for preserving select batches of the purest 233U materials from disposition. This work is supported by the Next Generation Safeguards Initiative, Office of Nonproliferation and International Security, National Nuclear Security Administration.

Krichinsky, Alan M [ORNL; Bostick, Debra A [ORNL; Giaquinto, Joseph [ORNL; Bayne, Charles [Hazelwood Services and Manufacturing; Goldberg, Dr. Steven A. [DOE SC - Chicago Office; Humphrey, Dr. Marc [U.S. Department of Energy, NNSA; Hutcheon, Dr. Ian D. [Lawrence Livermore National Laboratory (LLNL); Sobolev, Taissa [U.S. Department of Energy, NNSA

2012-01-01T23:59:59.000Z

317

Uranium mill monitoring for natural fission reactors  

SciTech Connect

Isotopic monitoring of the product stream from operating uranium mills is proposed for discovering other possible natural fission reactors; aspects of their occurrence and discovery are considered. Uranium mill operating characteristics are formulated in terms of the total uranium capacity, the uranium throughput, and the dilution half-time of the mill. The requirements for detection of milled reactor-zone uranium are expressed in terms of the dilution half-time and the sampling frequency. Detection of different amounts of reactor ore with varying degrees of /sup 235/U depletion is considered.

Apt, K.E.

1977-12-01T23:59:59.000Z

318

A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles  

E-Print Network (OSTI)

05-?20 Regarding Depleted Uranium. Rulemaking Issue (Department of Energy depleted uranium Environmental waste (MLLW) and depleted uranium (DU) from

Djokic, Denia

2013-01-01T23:59:59.000Z

319

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 

320

Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Oak Ridge Gaseous Diffusion Plant Site  

Science Conference Proceedings (OSTI)

In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) technology, with the near-term goal to provide the necessary information to make a deployment decision by November 1992. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. A programmatic document for use in screening DOE sites to locate the U-AVLIS production plant was developed and implemented in two parts (Wolsko et al. 1991). The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were then subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the ORGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use, socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3. Following the site description and additional data requirements, Sec. 4 provides a short, qualitative assessment of potential environmental issues. 37 refs., 20 figs., 18 tabs.

Not Available

1991-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Paducah Site 1997 annual environmental report  

Science Conference Proceedings (OSTI)

The Paducah Gaseous Diffusion Plant, located in McCracken County, Kentucky, has been producing enriched uranium since 1952. In July 1993, the US Department of Energy (DOE) leased the production areas of the site to the US Enrichment Corporation (USEC). A subsidiary of Lockheed Martin Corporation, Lockheed Martin Utility Services, manages the leased facilities for USEC. The DOE maintains responsibility for the environmental restoration, waste management, and depleted uranium hexafluoride cylinder program activities at the plant through its management contractor. The purpose of this document is to summarize calendar year 1997 environmental monitoring activities for DOE activities at the Paducah Site managed by Lockheed Martin Energy Systems. The DOE requires all of its facilities to conduct and document such activities annually. This report does not include USEC environmental activities.

NONE

1998-12-01T23:59:59.000Z

322

Paducah site annual environmental for 1996  

SciTech Connect

The Paducah Gaseous Diffusion Plant, located in McCracken County, Kentucky, has been producing enriched uranium since 1952. In July 1993, the US Department of Energy (DOE) leased the production areas of the site to the United States Enrichment Corporation (USEC). A subsidiary of Lockheed Martin Corporation, Lockheed Martin Utility Services, manages the leased facilities for USEC. The DOE maintains responsibility for the environmental restoration, waste management, and depleted uranium hexafluoride cylinder program activities at the plant through its management contractor, Lockheed Martin Energy Systems. The purpose of this document is to summarize calendar year 1996 environmental monitoring activities for DOE activities at the Paducah Site. The DOE requires all of its facilities to conduct and document such activities annually. This report does not include USEC environmental activities.

Belcher, G. [ed.

1997-12-01T23:59:59.000Z

323

Effect of Shim Arm Depletion in the NBSR  

SciTech Connect

The cadmium shim arms in the NBSR undergo burnup during reactor operation and hence, require periodic replacement. Presently, the shim arms are replaced after every 25 cycles to guarantee they can maintain sufficient shutdown margin. Two prior reports document the expected change in the 113Cd distribution because of the shim arm depletion. One set of calculations was for the present high-enriched uranium fuel and the other for the low-enriched uranium fuel when it was in the COMP7 configuration (7 inch fuel length vs. the present 11 inch length). The depleted 113Cd distributions calculated for these cores were applied to the current design for an equilibrium low-enriched uranium core. This report details the predicted effects, if any, of shim arm depletion on the shim arm worth, the shutdown margin, power distributions and kinetics parameters.

Hanson A. H.; Brown N.; Diamond, D.J.

2013-02-22T23:59:59.000Z

324

Uranium and Its Compounds  

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

and Its Compounds Uranium and Its Compounds line line What is Uranium? Chemical Forms of Uranium Properties of Uranium Compounds Radioactivity and Radiation Uranium Health Effects...

325

Uranium tailings bibliography  

SciTech Connect

A bibliography containing 1,212 references is presented with its focus on the general problem of reducing human exposure to the radionuclides contained in the tailings from the milling of uranium ore. The references are divided into seven broad categories: uranium tailings pile (problems and perspectives), standards and philosophy, etiology of radiation effects, internal dosimetry and metabolism, environmental transport, background sources of tailings radionuclides, and large-area decontamination. (JSR)

Holoway, C.F.; Goldsmith, W.A.; Eldridge, V.M.

1975-12-01T23:59:59.000Z

326

Uranium industry annual 1993  

SciTech Connect

Uranium production in the United States has declined dramatically from a peak of 43.7 million pounds U{sub 3}O{sub 8} (16.8 thousand metric tons uranium (U)) in 1980 to 3.1 million pounds U{sub 3}O{sub 8} (1.2 thousand metric tons U) in 1993. This decline is attributed to the world uranium market experiencing oversupply and intense competition. Large inventories of uranium accumulated when optimistic forecasts for growth in nuclear power generation were not realized. The other factor which is affecting U.S. uranium production is that some other countries, notably Australia and Canada, possess higher quality uranium reserves that can be mined at lower costs than those of the United States. Realizing its competitive advantage, Canada was the world`s largest producer in 1993 with an output of 23.9 million pounds U{sub 3}O{sub 8} (9.2 thousand metric tons U). The U.S. uranium industry, responding to over a decade of declining market prices, has downsized and adopted less costly and more efficient production methods. The main result has been a suspension of production from conventional mines and mills. Since mid-1992, only nonconventional production facilities, chiefly in situ leach (ISL) mining and byproduct recovery, have operated in the United States. In contrast, nonconventional sources provided only 13 percent of the uranium produced in 1980. ISL mining has developed into the most cost efficient and environmentally acceptable method for producing uranium in the United States. The process, also known as solution mining, differs from conventional mining in that solutions are used to recover uranium from the ground without excavating the ore and generating associated solid waste. This article describes the current ISL Yang technology and its regulatory approval process, and provides an analysis of the factors favoring ISL mining over conventional methods in a declining uranium market.

Not Available

1994-09-01T23:59:59.000Z

327

FAQ 17-Where is uranium hexafluoride stored in the United States...  

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

Where is uranium hexafluoride stored in the United States? Where is uranium hexafluoride stored in the United States? Most of the depleted UF6 accumulated since the 1940s is stored...

328

Final environmental statement related to the United Nuclear Corporation, Morton Ranch, Wyoming Uranium Mill (Converse County, Wyoming)  

SciTech Connect

Impacts from Morton Ranch Uranium Mill will result in: alterations of up to 270 acres occupied by the mill facilities; increase in the existing background radiation levels; socioeconomic effects on Glenrock and Douglas, Wyoming. Solid waste material (tailings solids) from the mill will be deposited onsite in exhausted surface mine pits. Any license issued for the Morton Ranch mill will be subject to conditions for the protection of the environment.

1979-02-01T23:59:59.000Z

329

EIS-0360: EPA Notice of Availability of the Draft Environmental Impact  

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

Draft Environmental Draft Environmental Impact Statement EIS-0360: EPA Notice of Availability of the Draft Environmental Impact Statement Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site The U.S. Department of Energy (DOE) proposes, via a contract awarded at the direction of Congress (Public Law 107-206), to design, construct, and operate two conversion facilities for converting depleted uranium hexafluoride (commonly referred to as DUF6): one at Portsmouth, Ohio, and one at Paducah, Kentucky. DOE intends to use the proposed facilities to convert its inventory of DUF6 to a more stable chemical form suitable for beneficial use or disposal. This site-specific EIS analyzes the construction, operation, maintenance, and decontamination and

330

P1-04: 3D Microstructural Characterization of Uranium Oxide as a ...  

Science Conference Proceedings (OSTI)

Presentation Title, P1-04: 3D Microstructural Characterization of Uranium ... to obtain Electron Backscatter Diffraction (EBSD) data for depleted UO2 pellets that ...

331

L'URANIUM ET LES ARMES L'URANIUM APPAUVRI. Pierre Roussel*  

E-Print Network (OSTI)

(depleted uranium) · 4 oxidation states (+4, +6 most common) · U(VI) water-soluble, U(IV) in-soluble Metals Uranium ­ heaviest natural element - 17 isotopes · Natural form % = U-238 (99.27), U-235 (0.72), U-234 (0 in nuclear fuel ­ U-235 (readily fissionable) · Used in nuclear and conventional weapons · Uranium enrichment

Paris-Sud XI, Université de

332

Characterization of uranium contaminated soils from DOE Fernald Environmental Management Project Site: Results of Phase 1 characterization  

Science Conference Proceedings (OSTI)

The Integrated Demonstration (ID) for remediation of uranium- contaminated soils has been established by the DOE Office of Technology Development. The Fernald (Feed Materials Production Center) site was selected as the DOE facility for the field demonstration. The principle objective of this ID is to evaluate and compare the versatility, efficiency, and economics of various technologies that may be combined into systems for the removal of uranium from contaminated soils. Several leaching solutions were employed to determine their effectiveness in extracting uranium from the soil. The extractants and their means of preparation were: 0.1 N nitric acid [HNO{sub 3}]: 6.25 mL of concentrated nitric acid was diluted to 1 L with distilled water; 2% ammonium carbonate [(NH{sub 4}){sub 2}CO{sub 3}]: 20 g of (NH{sub 4}){sub 2}CO{sub 3} was dissolved in distilled water and diluted to 1 L; 5% sodium hypochlorite (NaOCl): 50 mL of NaOCl reagent (Cl HCl) in 0.01 N nitric acid: 6.95 g (NH{sub 2}OH{center_dot}HCl) was dissolved and diluted to 1 L with 0.01 N HNO{sub 3}. The 0.01 N nitric acid was prepared by diluting 3 mL concentrated nitric acid to 5 L with distilled water; and the sodium citrate-bicarbonate-dithionite (CBD) method: 0.3 M sodium citrate (88 g tribasic sodium citrate, Na{sub 3}C{sub 6}H{sub 5}O{sub 7}{center_dot}2H{sub 2}O, per liter); 1 M sodium bicarbonate (84 g NaHCO{sub 3} per liter); and 5 g sodium dithionite, Na{sub 2}S{sub 2}O{sub 4}.

Lee, S.Y.; Marsh, J.D. Jr.

1992-01-01T23:59:59.000Z

333

Depleted Uraniuim Dioxide as a Spent-Nuclear-Fuel-Waste Package...  

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

15 DEPLETED URANIUM DIOXIDE AS A SPENT-NUCLEAR-FUEL WASTE-PACKAGE PARTICULATE FILL: FILL BEHAVIOR Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge,...

334

Clean Air Act Requirements: Uranium Mill Tailings  

E-Print Network (OSTI)

EPA'S Clean Air Act Requirements: Uranium Mill Tailings Radon Emissions Rulemaking Reid J. Rosnick Presentation to Environmental Protection Agency Uranium Contamination Radiation Protection Division (6608J requirements for operating uranium mill tailings (Subpart W) Status update on Subpart W activities Outreach

335

Environmental assessment of remedial action at the Slick Rock uranium mill tailings sites, Slick Rock, Colorado. Revision 1  

SciTech Connect

The Uranium Mill Tailings Radiation Control Act of 1978 (42 USC {section}7901 et seq.), hereafter referred to as the UMTRCA, authorized the US Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miquel County. Contaminated materials cover an estimated 63 acres of the Union Carbide (UC) processing site and 15 ac of the North Continent (NC) processing site. The sites are within 1 mile of each other and are adjacent to the Dolores River. The sites contain concrete foundations of mill buildings, tailings piles, and areas contaminated by windblown and waterborne radioactive tailings materials. The total estimated volume of contaminated materials is approximately 621,300 cubic yards (yd{sup 3}). In addition to the contamination in the two processing site areas, four VPs were found to contain contamination. As a result of the tailings being exposed to the environment, contamination associated with the UC and NC sites has leached into shallow ground water. Surface water has not been affected. The closest residence is approximately 0.3 air mi from either site. The proposed action is to remediate the UC and NC sites by removing all contaminated materials within the designing site boundaries or otherwise associated with the sites, and relocating them to, and stabilizing them at, a location approximately 5 road mi northeast of the sites on land administered by the Bureau of Land Management (BLM).

1994-09-01T23:59:59.000Z

336

EA-1172: Sale of Surplus Natural and Low Enriched Uranium, Piketon, Ohio  

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

This EA evaluates the environmental impacts for the proposal to sell uranium for subsequent enrichment and fabrication into commercial nuclear power reactor fuel. The uranium is currently stored...

337

URANIUM ALLOYS  

DOE Patents (OSTI)

A uranium alloy is reported containing from 0.1 to 5 per cent by weight of molybdenum and from 0.1 to 5 per cent by weight of silicon, the balance being uranium.

Colbeck, E.W.

1959-12-29T23:59:59.000Z

338

Characterization of uranium contaminated soils from DOE Fernald Environmental Management Project Site: Results of Phase 1 characterization  

SciTech Connect

The Integrated Demonstration (ID) for remediation of uranium- contaminated soils has been established by the DOE Office of Technology Development. The Fernald (Feed Materials Production Center) site was selected as the DOE facility for the field demonstration. The principle objective of this ID is to evaluate and compare the versatility, efficiency, and economics of various technologies that may be combined into systems for the removal of uranium from contaminated soils. Several leaching solutions were employed to determine their effectiveness in extracting uranium from the soil. The extractants and their means of preparation were: 0.1 N nitric acid [HNO{sub 3}]: 6.25 mL of concentrated nitric acid was diluted to 1 L with distilled water; 2% ammonium carbonate [(NH{sub 4}){sub 2}CO{sub 3}]: 20 g of (NH{sub 4}){sub 2}CO{sub 3} was dissolved in distilled water and diluted to 1 L; 5% sodium hypochlorite (NaOCl): 50 mL of NaOCl reagent (Cl < 6%) was diluted to 1 L with distilled water; 0.1 M ethylenediaminetetraacetric acid, disodium salt (EDTA): 37.224 g EDTA was dissolved in distilled water and diluted to 1 L; 2% citric acid monohydrate solution (H{sub 3}C{sub 6}H{sub 5}O{sub 7}{center_dot}H{sub 2}O): 20 g of critic acid was diluted to 1 L with distilled water; 0.1 M hydroxylamine-hydrochloride (NH{sub 2}OH{center_dot}HCl) in 0.01 N nitric acid: 6.95 g (NH{sub 2}OH{center_dot}HCl) was dissolved and diluted to 1 L with 0.01 N HNO{sub 3}. The 0.01 N nitric acid was prepared by diluting 3 mL concentrated nitric acid to 5 L with distilled water; and the sodium citrate-bicarbonate-dithionite (CBD) method: 0.3 M sodium citrate (88 g tribasic sodium citrate, Na{sub 3}C{sub 6}H{sub 5}O{sub 7}{center_dot}2H{sub 2}O, per liter); 1 M sodium bicarbonate (84 g NaHCO{sub 3} per liter); and 5 g sodium dithionite, Na{sub 2}S{sub 2}O{sub 4}.

Lee, S.Y.; Marsh, J.D. Jr.

1992-01-01T23:59:59.000Z

339

FAQ 37-What are the potential health risks from transportation of depleted  

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

depleted uranium metal or oxide? depleted uranium metal or oxide? What are the potential health risks from transportation of depleted uranium metal or oxide? In the PEIS, risks associated with transportation of depleted uranium oxide and metal were estimated for transport by either rail or truck. Normal transport of oxide or metal would result in low-level external exposure to radiation for persons in the vicinity of a shipment. Based on estimates in the PEIS, the levels of exposure would result in negligible increased cancer risks. Risks from material released in an accident were also estimated. For a hypothetical railcar accident involving powder U3O8 that was assumed to occur in a highly-populated urban area under stable (nighttime) weather conditions, it was estimated that up to 20 people might experience irreversible adverse effects from chemical toxicity, with no fatalities expected. Approximately 2 potential latent cancer fatalities from radiological hazards are estimated for an accident under the same conditions. The probability of such an accident occurring is very low. The consequences from a truck accident would be lower, because trucks have a smaller shipment capacity. The consequences of transportation accidents involving depleted uranium metal would be much smaller than those involving uranium oxide because uranium metal would be in the form of solid blocks and would not be easily dispersed in an accident.

340

Chapter 4. Uranium Mine and Extraction Facility Reclamation This chapter is not intended to serve as guidance, or to supplement EPA or other agency environmental  

E-Print Network (OSTI)

4-1 Chapter 4. Uranium Mine and Extraction Facility Reclamation This chapter is not intended, it is an outline of practices which may or have been used for uranium site restoration. Mining reclamation for uranium mining sites. The existence of bonding requirements and/or financial guarantees in the cases where

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Battery depletion monitor  

SciTech Connect

A cmos inverter is used to compare pacemaker battery voltage to a referenced voltage. When the reference voltage exceeds the measured battery voltage, the inverter changes state to indicate battery depletion.

Lee, Y.S.

1982-01-26T23:59:59.000Z

342

Validation of a Monte Carlo Based Depletion Methodology Using HFIR Post-Irradiation Measurements  

Science Conference Proceedings (OSTI)

Post-irradiation uranium isotopic atomic densities within the core of the High Flux Isotope Reactor (HFIR) were calculated and compared to uranium mass spectrographic data measured in the late 1960s and early 70s [1]. This study was performed in order to validate a Monte Carlo based depletion methodology for calculating the burn-up dependent nuclide inventory, specifically the post-irradiation uranium

Chandler, David [ORNL; Maldonado, G Ivan [ORNL; Primm, Trent [ORNL

2009-11-01T23:59:59.000Z

343

Microstructural Evolution of a Uranium-Zirconium Alloy at Low ...  

Science Conference Proceedings (OSTI)

Uranium-zirconium (U-Zr) alloys represent one of the types of fuels that are under ... Depleted U-10wt%Zr was irradiated to doses of 0.007 and 0.07 dpa.

344

Bugs boost Cold War clean-up: Bacteria could scrub uranium from sites contaminated decades ago. updated at midnight GMTtoday is friday, november 14  

E-Print Network (OSTI)

.7% (no enrichment) and around 20% · Large amount of depleted uranium results from enrichment Energy an integrated facility (Integral Fast Reactor), where only small amounts of natural uranium or waste depleted nuclear fuel cycles Ore · All fuel cycles begin with uranium and/or thorium which are the only naturally

Lovley, Derek

345

Environmental Cleanup Reports | Department of Energy  

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

Environmental Cleanup Reports Environmental Cleanup Reports Environmental Cleanup Reports September 8, 2010 Audit Report: OAS-L-10-10 The Audit of Precious Metals at NNSA Sites August 12, 2010 Audit Letter Report: OAS-RA-L-10-05 Decommissioning and Demolition Activities at Office of Science Sites May 25, 2010 Audit Report: OAS-RA-10-10 Waste Processing and Recovery Act Acceleration Efforts for Contact-Handled Transuranic Waste at the Hanford Site May 3, 2010 Audit Report: OAS-L-10-04 The Interim Treatment of Salt Waste at the Savannah River Site April 23, 2010 Audit Letter Report: OAS-RA-L-10-03 Audit of Moab Mill Tailings Cleanup Project April 9, 2010 Audit Report: OAS-RA-10-07 Management Alert on Environmental Management's Select Strategy for Disposition of Savannah River Site Depleted Uranium Oxides

346

Vol. 58,No.3APPLIED AND ENVIRONMENTAL MICROBIOLOGY, Mar. 1992, p. 850-856 0099-2240/92/030850-07$02.00/0  

E-Print Network (OSTI)

. In this scenario, two steps are taken in this view: first, the depleted Uranium that is rejected after water reactors is enriched Uranium and the fuel for the FNRs is based on Plutonium and depleted Uranium and balanced solution can be found, which reconciles fuel cycle closing, non-depletion of natural resources

Lovley, Derek

347

EIS-0269: Notice of Intent to Prepare a Programmatic Environmental...  

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

Impact Statement Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride, Paducah, Kentucky; Portsmouth, Ohio; and Oak Ridge,...

348

EIS-0360: EPA Notice of Availability of the Draft Environmental...  

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

storage yard at Portsmouth (if required) for ETTP cylinders; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and...

349

DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support  

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

DOE Selects Contractor for Depleted Hexafluoride Conversion Project DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support March 25, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today awarded a competitive small business task order to Navarro Research and Engineering Inc. of Oak Ridge, Tennessee. The award is a $22 million, time and materials task order with a three-year performance period and two one-year extension options. Navarro Research and Engineering Inc. will provide engineering and operations technical support services to the DOE Portsmouth Paducah Project Office (PPPO) in Lexington, Kentucky and the Depleted Uranium Hexafluoride (DUF6) Conversion Project in Paducah, Kentucky and Portsmouth, Ohio.

350

DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support  

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

Contractor for Depleted Hexafluoride Conversion Project Contractor for Depleted Hexafluoride Conversion Project Support DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support March 25, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today awarded a competitive small business task order to Navarro Research and Engineering Inc. of Oak Ridge, Tennessee. The award is a $22 million, time and materials task order with a three-year performance period and two one-year extension options. Navarro Research and Engineering Inc. will provide engineering and operations technical support services to the DOE Portsmouth Paducah Project Office (PPPO) in Lexington, Kentucky and the Depleted Uranium Hexafluoride (DUF6) Conversion Project in Paducah, Kentucky and Portsmouth, Ohio.

351

DOE Announces Policy for Managing Excess Uranium Inventory | Department of  

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

Policy for Managing Excess Uranium Inventory Policy for Managing Excess Uranium Inventory DOE Announces Policy for Managing Excess Uranium Inventory March 12, 2008 - 10:52am Addthis WASHINGTON, DC - U.S. Secretary of Energy Samuel W. Bodman today released a Policy Statement on the management of the Department of Energy's (DOE) excess uranium inventory, providing the framework within which DOE will make decisions concerning future use and disposition of its inventory. During the coming year, DOE will continue its ongoing program for downblending excess highly enriched uranium (HEU) into low enriched uranium (LEU), evaluate the benefits of enriching a portion of its excess natural uranium into LEU, and complete an analysis on enriching and/or selling some of its depleted uranium. Specific transactions are expected to occur in

352

Draft Supplement Analysis for Location(s) to Dispose of Depleted...  

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

Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site, issued by Jessie Hill Roberson, Assistant Secretary for Environmental Management, July 20. DOE,...

353

Rescuing a Treasure Uranium-233  

SciTech Connect

Uranium-233 (233U) is a synthetic isotope of uranium formed under reactor conditions during neutron capture by natural thorium (232Th). At high purities, this synthetic isotope serves as a crucial reference for accurately quantifying and characterizing natural uranium isotopes for domestic and international safeguards. Separated 233U is stored in vaults at Oak Ridge National Laboratory. These materials represent a broad spectrum of 233U from the standpoint isotopic purity the purest being crucial for precise analyses in safeguarding uranium. All 233U at ORNL currently is scheduled to be down blended with depleted uranium beginning in 2015. Such down blending will permanently destroy the potential value of pure 233U samples as certified reference material for use in uranium analyses. Furthermore, no replacement 233U stocks are expected to be produced in the future due to a lack of operating production capability and the high cost of returning to operation this currently shut down capability. This paper will describe the efforts to rescue the purest of the 233U materials arguably national treasures from their destruction by down blending.

Krichinsky, Alan M [ORNL; Goldberg, Dr. Steven A. [DOE SC - Chicago Office; Hutcheon, Dr. Ian D. [Lawrence Livermore National Laboratory (LLNL)

2011-01-01T23:59:59.000Z

354

Enrichment and Location of Uranium Precipitates from Uranyl Carbonate Addition to Tank 43  

SciTech Connect

In order to safety restart the 2H evaporator, plans are to add depleted uranium (DU) as uranyl carbonate to Tank 43 to lower the 235U enrichment in the supernate. This memo examines the enrichment and location of uranium precipitates formed in Tank 43. An assessment of the risks associated with precipitating uranium shows that there is no criticality concern during this operation.

d' Entremont, P.D.

2001-06-04T23:59:59.000Z

355

EIS-0269: Notice of Intent to Prepare a Programmatic Environmental Impact  

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

Notice of Intent to Prepare a Programmatic Environmental Notice of Intent to Prepare a Programmatic Environmental Impact Statement EIS-0269: Notice of Intent to Prepare a Programmatic Environmental Impact Statement Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride, Paducah, Kentucky; Portsmouth, Ohio; and Oak Ridge, Tennessee This impact statement will support management decisions on depleted UF6 by evaluating the environmental impacts of a range of reasonable alternative strategies as well as providing a means for the public to have a meaningful opportunity to be heard on this matter. This NOI informs the public of the proposal, explains the schedule, announces the dates, times, and places for scoping meetings, and solicits public comment. 96-1196.pdf More Documents & Publications

356

Refurbishment of uranium hexafluoride cylinder storage yards C-745-K, L, M, N, and P and construction of a new uranium hexafluoride cylinder storage yard (C-745-T) at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky  

Science Conference Proceedings (OSTI)

The Paducah Gaseous Diffusion Plant (PGDP) is a uranium enrichment facility owned by the US Department of Energy (DOE). A residual of the uranium enrichment process is depleted uranium hexafluoride (UF6). Depleted UF6, a solid at ambient temperature, is stored in 32,200 steel cylinders that hold a maximum of 14 tons each. Storage conditions are suboptimal and have resulted in accelerated corrosion of cylinders, increasing the potential for a release of hazardous substances. Consequently, the DOE is proposing refurbishment of certain existing yards and construction of a new storage yard. This environmental assessment (EA) evaluates the impacts of the proposed action and no action and considers alternate sites for the proposed new storage yard. The proposed action includes (1) renovating five existing cylinder yards; (2) constructing a new UF6 storage yard; handling and onsite transport of cylinders among existing yards to accommodate construction; and (4) after refurbishment and construction, restacking of cylinders to meet spacing and inspection requirements. Based on the results of the analysis reported in the EA, DOE has determined that the proposed action is not a major Federal action that would significantly affect the quality of the human environment within the context of the National Environmental Policy Act of 1969. Therefore, DOE is issuing a Finding of No Significant Impact. Additionally, it is reported in this EA that the loss of less than one acre of wetlands at the proposed project site would not be a significant adverse impact.

NONE

1996-07-01T23:59:59.000Z

357

URANIUM COMPOSITIONS  

DOE Patents (OSTI)

This patent relates to high purity uranium alloys characterized by improved stability to thermal cycling and low thermal neutron absorption. The high purity uranium alloy contains less than 0.1 per cent by weight in total amount of any ore or more of the elements such as aluminum, silicon, phosphorous, tin, lead, bismuth, niobium, and zinc.

Allen, N.P.; Grogan, J.D.

1959-05-12T23:59:59.000Z

358

EA-1172: Final Environmental Assessment | Department of Energy  

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

Low Enriched Uranium This EA evaluates the environmental impacts for the proposal to sell uranium for subsequent enrichment and fabrication into commercial nuclear power reactor...

359

Uranium industry annual 1997  

SciTech Connect

This report provides statistical data on the U.S. uranium industry`s activities relating to uranium raw materials and uranium marketing.

NONE

1998-04-01T23:59:59.000Z

360

Conversion and Blending Facility highly enriched uranium to low enriched uranium as metal. Revision 1  

SciTech Connect

The mission of this Conversion and Blending Facility (CBF) will be to blend surplus HEU metal and alloy with depleted uranium metal to produce an LEU product. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal.

1995-07-05T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Depleted UF6 Conversion facility EIS Topics  

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

Topics Topics Depleted UF6 Conversion Facility EIS Topics A listing of topics included in the Depleted UF6 Conversion Facility EISs. DOE addressed the following environmental issues when assessing the potential environmental impacts of the alternatives in the two site-specific EISs. DOE solicited comment from the Federal agencies, Native American tribes, state and local governments, and the general public on these and any other issues as part of the public scoping process: Potential impacts on health from DUF6 conversion activities, including potential impacts to workers and the public from exposure to radiation and chemicals during routine and accident conditions for the construction, operation, maintenance, and decontamination and decommissioning of DUF6 conversion facilities.

362

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Table 21. Foreign sales of uranium from U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors by origin and delivery year, 2008-2012

363

Inherently safe in situ uranium recovery.  

SciTech Connect

Expansion of uranium mining in the United States is a concern to some environmental groups and sovereign Native American Nations. An approach which may alleviate some problems is to develop inherently safe in situ uranium recovery ('ISR') technologies. Current ISR technology relies on chemical extraction of trace levels of uranium from aquifers that, once mined, can still contain dissolved uranium and other trace metals that are a health concern. Existing ISR operations are few in number; however, high uranium prices are driving the industry to consider expanding operations nation-wide. Environmental concerns and enforcement of the new 30 ppb uranium drinking water standard may make opening new mining operations more difficult and costly. Here we propose a technological fix: the development of inherently safe in situ recovery (ISISR) methods. The four central features of an ISISR approach are: (1) New 'green' leachants that break down predictably in the subsurface, leaving uranium, and associated trace metals, in an immobile form; (2) Post-leachant uranium/metals-immobilizing washes that provide a backup decontamination process; (3) An optimized well-field design that increases uranium recovery efficiency and minimizes excursions of contaminated water; and (4) A combined hydrologic/geochemical protocol for designing low-cost post-extraction long-term monitoring. ISISR would bring larger amounts of uranium to the surface, leave fewer toxic metals in the aquifer, and cost less to monitor safely - thus providing a 'win-win-win' solution to all stakeholders.

Krumhansl, James Lee; Beauheim, Richard Louis; Brady, Patrick Vane; Arnold, Bill Walter; Kanney, Joseph F.; McKenna, Sean Andrew

2009-05-01T23:59:59.000Z

364

Inherently safe in situ uranium recovery.  

SciTech Connect

Expansion of uranium mining in the United States is a concern to some environmental groups and sovereign Native American Nations. An approach which may alleviate some problems is to develop inherently safe in situ uranium recovery ('ISR') technologies. Current ISR technology relies on chemical extraction of trace levels of uranium from aquifers that, once mined, can still contain dissolved uranium and other trace metals that are a health concern. Existing ISR operations are few in number; however, high uranium prices are driving the industry to consider expanding operations nation-wide. Environmental concerns and enforcement of the new 30 ppb uranium drinking water standard may make opening new mining operations more difficult and costly. Here we propose a technological fix: the development of inherently safe in situ recovery (ISISR) methods. The four central features of an ISISR approach are: (1) New 'green' leachants that break down predictably in the subsurface, leaving uranium, and associated trace metals, in an immobile form; (2) Post-leachant uranium/metals-immobilizing washes that provide a backup decontamination process; (3) An optimized well-field design that increases uranium recovery efficiency and minimizes excursions of contaminated water; and (4) A combined hydrologic/geochemical protocol for designing low-cost post-extraction long-term monitoring. ISISR would bring larger amounts of uranium to the surface, leave fewer toxic metals in the aquifer, and cost less to monitor safely - thus providing a 'win-win-win' solution to all stakeholders.

Krumhansl, James Lee; Beauheim, Richard Louis; Brady, Patrick Vane; Arnold, Bill Walter; Kanney, Joseph F.; McKenna, Sean Andrew

2009-05-01T23:59:59.000Z

365

FAQ 3-What are the common forms of uranium?  

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

are the common forms of uranium? are the common forms of uranium? What are the common forms of uranium? Uranium can take many chemical forms. In nature, uranium is generally found as an oxide, such as in the olive-green-colored mineral pitchblende. Uranium oxide is also the chemical form most often used for nuclear fuel. Uranium-fluorine compounds are also common in uranium processing, with uranium hexafluoride (UF6) and uranium tetrafluoride (UF4) being the two most common. In its pure form, uranium is a silver-colored metal. The most common forms of uranium oxide are U3O8 and UO2. Both oxide forms have low solubility in water and are relatively stable over a wide range of environmental conditions. Triuranium octaoxide (U3O8) is the most stable form of uranium and is the form most commonly found in nature. Uranium dioxide (UO2) is the form in which uranium is most commonly used as a nuclear reactor fuel. At ambient temperatures, UO2 will gradually convert to U3O8. Because of their stability, uranium oxides are generally considered the preferred chemical form for storage or disposal.

366

Programmatic Environmental Assessment for the U. S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials  

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

93 93 FINAL Programmatic Environmental Assessment for the U.S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials FINDING OF NO SIGNIFICANT IMPMZT PROGR4MMATIC ENVIRONMENTAL ASSESSME?X FOR THE U.S. DEPARTMENT OF ENERGY, OAK RIDGE OPER4TIOSS IMPLEMENTATION OF A COMPREHENSIVE MANAGEMEKT PROGK4hl FOR THE STORAGE, TRANSPORTATION, AND DISPOSITION OF POTENTIALLY REUSABLE URANJUh4 MATERIALS AGEhCY: U.S. DEPARTMENT OF ENERGY (DOE) ACTION: FINDI?iG OF NO SIGNIFICANT 1~IPAC-I SUMI\!L4RY: The U. S. DOE has completed a Programmatic Environmental Assessment (PE:,4) (DOE/E?,- 1393), which is incorporated herein by this reference. Tile purpose of the

367

Production, depletion trends are keys to predicting ...  

U.S. Energy Information Administration (EIA)

Includes hydropower, solar, wind, geothermal, biomass and ethanol. Nuclear & Uranium. Uranium fuel, nuclear reactors, generation, spent fuel. ... ...

368

DOE Extends Public Comment Period for the Draft Uranium Leasing...  

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

Other Agencies You are here Home DOE Extends Public Comment Period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement DOE Extends Public...

369

EIS-0359: Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky  

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

59: Uranium Hexafluoride Conversion Facility at the Paducah, 59: Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site EIS-0359: Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site Summary This site-specific EIS considers the construction, operation, maintenance, and decontamination and decommissioning of the proposed depleted uranium hexafluoride (DUF6) conversion facility at three locations within the Paducah site; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and sale of the hydrogen fluoride (HF) produced as a conversion co-product; and neutralization of HF to calcium fluoride and its sale or disposal in the event that the HF product is not sold. This EIS also considers a no action alternative that assumes continued storage of DUF6 at the Paducah site. A

370

URANIUM IN ALKALINE ROCKS  

E-Print Network (OSTI)

combine to indicate uranium enrichment of an alkaline magma.uranium, the Ilfmaussaq intrusion contains an unusually high enrichment

Murphy, M.

2011-01-01T23:59:59.000Z

371

The Office of Environmental Management Non-Defense Environmental...  

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

Microsoft Word - PSRP Updates 6-25-10v2 The Office of Environmental Management (EM) Defense Environmental Cleanup The Office of Environmental Management Uranium Enrichment D&D...

372

DOE Prepares Programmatic Environmental Impact Statement for...  

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

You are here Home DOE Prepares Programmatic Environmental Impact Statement for the Uranium Leasing Program DOE Prepares Programmatic Environmental Impact Statement for the...

373

Absorbed Dose Rate Due to Intake of Natural Radionuclides by Tilapia Fish (Tilapia nilotica,Linnaeus, 1758) Estimated Near Uranium Mining at Caetit, Bahia, Brazil  

Science Conference Proceedings (OSTI)

The uranium mining at Caetit (Uranium Concentrate UnitURA) is in its operational phase. Aiming to estimate the radiological environmental impact of the URA

Wagner de S. Pereira; Alphonse Kelecom; Delcy de Azevedo Py Jnior

2008-01-01T23:59:59.000Z

374

Session 9.3: Advances in Depleted Uranium Technology  

E-Print Network (OSTI)

The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes.

Robert R. Price; M. Jonathan Haire; Allen G. Croff; Robert R. Price; M. Jonathan Haire; Allen G. Croff

2001-01-01T23:59:59.000Z

375

Process Control Improvements for Production of Depleted Uranium Hohlraums  

Science Conference Proceedings (OSTI)

Technical Paper / Selected papers from 20th Target Fabrication Meeting, May 20-24, 2012, Santa Fe, NM, Guest Editor: Robert C. Cook

H. Streckert; K. Blobaum; B. Chen; J. E. Fair; N. Hein; A. Nikroo; K. Quan; M. Stadermann

376

Characterization of Blistering and Delamination in Depleted Uranium Hohlraums  

Science Conference Proceedings (OSTI)

Technical Paper / Selected papers from 20th Target Fabrication Meeting, May 20-24, 2012, Santa Fe, NM, Guest Editor: Robert C. Cook

K. J. M. Blobaum; M. Stadermann; J. E. Fair; N. E. Teslich; M. A. Wall; R. J. Foreman; N. Hein; H. Streckert; A. Nikroo

377

Transportation of Depleted Uranium Materials in Support of the...  

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

of the specific radioactive material and its physical form (e.g., solid, liquid, or gas). The regulations also specify many requirements for labeling, marking, training, and...

378

Depleted-Uranium Dioxide as SNF Waste Package Particulate Fill...  

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

Thermal Shunt (Replace Convection) Fill Lowers Temperature (Conductivity > Convective Gas Currents) Limited Convective Currents (Tight Geometry) Heat Transfer (Fuel Basket...

379

NEPA Activities for the Depleted Uranium Hexafluoride Management...  

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

ETTP) to some other stable chemical form acceptable for transportation, beneficial usereuse, andor disposal. Conversion facilities will be constructed at Paducah and...

380

Uranium Mining and Enrichment  

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

Overview Presentation » Uranium Mining and Enrichment Overview Presentation » Uranium Mining and Enrichment Uranium Mining and Enrichment Uranium is a radioactive element that occurs naturally in the earth's surface. Uranium is used as a fuel for nuclear reactors. Uranium-bearing ores are mined, and the uranium is processed to make reactor fuel. In nature, uranium atoms exist in several forms called isotopes - primarily uranium-238, or U-238, and uranium-235, or U-235. In a typical sample of natural uranium, most of the mass (99.3%) would consist of atoms of U-238, and a very small portion of the total mass (0.7%) would consist of atoms of U-235. Uranium Isotopes Isotopes of Uranium Using uranium as a fuel in the types of nuclear reactors common in the United States requires that the uranium be enriched so that the percentage of U-235 is increased, typically to 3 to 5%.

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Introduction Uranium is a common element in nature, and has been used for centuries as a coloring agent in  

E-Print Network (OSTI)

. Redistribution of depleted uranium (DU soils and water at two US Army proving grounds. Ann. M Health Phys. SocRemediation of uranium contaminated soils with bicarbonate extraction and microbial U(VI) reduction ElizabethJ.P.Phillips, Edward R. Landa and DerekR. Lovley Key words: Bioremediation; Uranium; Mill tailings

382

Uranium Management - Preservation of a National Asset  

Science Conference Proceedings (OSTI)

The Uranium Management Group (UMG) was established at the Department of Energy's (DOE's) Oak Ridge Operations in 1999 as a mechanism to expedite the de-inventory of surplus uranium from the Fernald Environmental Management Project site. This successful initial venture has broadened into providing uranium material de-inventory and consolidation support to the Hanford site as well as retrieving uranium materials that the Department had previously provided to universities under the loan/lease program. As of December 31, 2001, {approx} 4,300 metric tons of uranium (MTU) have been consolidated into a more cost effective interim storage location at the Portsmouth site near Piketon, OH. The UMG continues to uphold its corporate support mission by promoting the Nuclear Materials Stewardship Initiative (NMSI) and the twenty-five (25) action items of the Integrated Nuclear Materials Management Plan (1). Before additional consolidation efforts may commence to remove excess inventory from Environmental Management closure sites and universities, a Programmatic Environmental Assessment (PEA) must be completed. Two (2) noteworthy efforts currently being pursued involve the investigation of re-use opportunities for surplus uranium materials and the recovery of usable uranium from the shutdown Portsmouth cascade. In summary, the UMG is available as a DOE complex-wide technical resource to promote the responsible management of surplus uranium.

Jackson, J. D.; Stroud, J. C.

2002-02-27T23:59:59.000Z

383

Uranium (U)  

Science Conference Proceedings (OSTI)

Table 63   Properties of unstable uranium isotopes with α-particle emission...Table 63 Properties of unstable uranium isotopes with α-particle emission Isotope Abundance, % Half-life ( t 1/2 ), years Energy, MeV 234 U 0.0055 2.47 ? 10 5 4.77, 4.72, 4.58, 4.47, 235 U 0.720 7.1 ? 10 6 4.40, 4.2 238 U 99.274 4.51 ? 10 9 4.18...

384

Environmental sampling and analysis as a safeguards tool  

SciTech Connect

Environmental sampling and radionuclide analysis of the resulting material can be utilized as a supplemental approach in safeguarding practices and particularly for detection of undeclared nuclear activities. The production of nuclear weapons could be pursued by uranium enrichment processes to produce highly enriched U-235 or by nuclear reactor operations followed by chemical separations to produce Pu-239. The application of either of these processes results in the production of signature materials, some of which will be released to the environs. Results from the operations of the Hanford production facilities are discussed and indicate the type of signatures that may be expected from plutonium production facilities. These include noble gas emissions from the reactors and chemical separations processes, the production of radionuclides in reactor cooling water followed by their subsequent release to the Columbia River, and the release of mildly contaminated process water from the chemical processing facilities. These signature materials are carried by both gaseous and liqid effluents and enter various compartments of the environment. The types of signature materials which are most likely to be accumulated are discussed, together with examples of the quantities which have been released during past separations. There are numerous processes by which natural uranium may be enriched to produce highly enriched U-235. The most definitive signature of such processes is always a modification in uranium isotope ratios, and materials showing either enriched or depleted uranium in gaseous and liquid effluents provide the best indication that uramium enrichment processes are taking place. Therefore, techniques for sampling and analysis of airborne, waterborne, or deposited uranium in environmental matrices provide a means of detecting uranium enrichment which may lead to proliferation products.

Perkins, R.W.; Wogman, N.A.; Holdren, G.R.

1994-03-01T23:59:59.000Z

385

Uranium-234  

SciTech Connect

Translation of Uran-234 by J. Sehmorak. The following subjects are discussed: /sup 234/U and other natural radioactive isotopes, fractionation of heavy radioactive elements in nature, fractionation of radioactive isotopes, /sup 234/U in nuclear geochemistry, /sup 234/U in uranium minerals, /sup 234/U in continental waters and in quaternary deposits, and /sup 234/U in the ocean. (LK)

Cherdyntsev, V.V.

1971-01-01T23:59:59.000Z

386

The uranium cylinder assay system for enrichment plant safeguards  

Science Conference Proceedings (OSTI)

Safeguarding sensitive fuel cycle technology such as uranium enrichment is a critical component in preventing the spread of nuclear weapons. A useful tool for the nuclear materials accountancy of such a plant would be an instrument that measured the uranium content of UF{sub 6} cylinders. The Uranium Cylinder Assay System (UCAS) was designed for Japan Nuclear Fuel Limited (JNFL) for use in the Rokkasho Enrichment Plant in Japan for this purpose. It uses total neutron counting to determine uranium mass in UF{sub 6} cylinders given a known enrichment. This paper describes the design of UCAS, which includes features to allow for unattended operation. It can be used on 30B and 48Y cylinders to measure depleted, natural, and enriched uranium. It can also be used to assess the amount of uranium in decommissioned equipment and waste containers. Experimental measurements have been carried out in the laboratory and these are in good agreement with the Monte Carlo modeling results.

Miller, Karen A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Rael, Carlos D [Los Alamos National Laboratory; Iwamoto, Tomonori [JNFL; Tamura, Takayuki [JNFL; Aiuchi, Syun [JNFL

2010-01-01T23:59:59.000Z

387

Uranium industry annual 1996  

SciTech Connect

The Uranium Industry Annual 1996 (UIA 1996) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing. The UIA 1996 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. Data on uranium raw materials activities for 1987 through 1996 including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2006, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, uranium imports and exports, and uranium inventories are shown in Chapter 2. A feature article, The Role of Thorium in Nuclear Energy, is included. 24 figs., 56 tabs.

NONE

1997-04-01T23:59:59.000Z

388

Measures of the Environmental Footprint of the Front End of the Nuclear Fuel Cycle  

Science Conference Proceedings (OSTI)

Previous estimates of environmental impacts associated with the front end of the nuclear fuel cycle have focused primarily on energy consumption and CO2 emissions. Results have varied widely. Section 2 of this report provides a summary of historical estimates. This study revises existing empirical correlations and their underlying assumptions to fit to a more complete set of existing data. This study also addresses land transformation, water withdrawals, and occupational and public health impacts associated with the processes of the front end of the once-through nuclear fuel cycle. These processes include uranium mining, milling, refining, conversion, enrichment, and fuel fabrication. Metrics are developed to allow environmental impacts to be summed across the full set of front end processes, including transportation and disposition of the resulting depleted uranium.

Brett Carlsen; Emily Tavrides; Erich Schneider

2010-08-01T23:59:59.000Z

389

Ris-M-2875 Preliminary Environmental  

E-Print Network (OSTI)

Risø-M-2875 Preliminary Environmental Impact Statement for the Kvanefjeld Uranium Mine Kim Environmental Impact Statement for the Kvanefjeld Uranium Mine Kim Pilegaard Abstract. The sources of pollution from a proposed uranium mining and milling complex at Kvanefjeld in South Greenland have been evaluated

390

Ris-M-2875 Preliminary Environmental  

E-Print Network (OSTI)

Risø-M-2875 m Preliminary Environmental Impact Statement for the Kvanefjeld Uranium Mine Kim Environmental Impact Statement for the Kvanefjeld Uranium Mine Kim Pilegaard Abstract. The sources of pollution from a proposed uranium mining and Billing complex at Kvanefjeld in South Greenland have been evaluated

391

ENVIRONMENTAL  

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

797 797 FINAL ENVIRONMENTAL ASSESSMENT FOR DEPARTMENT OF ENERGY LOAN GUARANTEE FOR THE AGUA CALIENTE SOLAR PROJECT IN YUMA COUNTY, ARIZONA U.S. Department of Energy Loan Guarantee Program Office Washington, DC 20585 November 2010 TABLE OF CONTENTS Section Page Executive Summary .................................................................................................................ES-1 Introduction ..........................................................................................................................ES-1 Purpose and Need ...............................................................................................................ES-1 Proposed Action and Alternatives........................................................................................ES-2

392

APPLIED AND ENVIRONMENTAL MICROBIOLOGY, June 2003, p. 36723675 Vol. 69, No. 6 0099-2240/03/$08.00 0 DOI: 10.1128/AEM.69.6.36723675.2003  

E-Print Network (OSTI)

wastes resulting from uranium solution extraction processes. Underground ore bodies depleted total suspended solids TWC Texas Water Commission U uranium AV-5 #12;U3O8 oxide of uranium UIC underground injection control ULD uranium location database UMTRA Uranium Mill Tailings Remedial Action

Lovley, Derek

393

Microbial uptake of uranium, cesium, and radium  

SciTech Connect

The ability of diverse microbial species to concentrate uranium, cesium, and radium was examined. Saccharomyces cerevisiae, Pseudomonas aeruginosa, and a mixed culture of denitrifying bacteria accumulated uranium to 10 to 15% of the dry cell weight. Only a fraction of the cells in a given population had visible uranium deposits in electron micrographs. While metabolism was not required for uranium uptake, mechanistic differences in the metal uptake process were indicated. Uranium accumulated slowly (hours) on the surface of S. cerevisiae and was subject to environmental factors (i.e., temperature, pH, interfering cations and anions). In contrast, P. aeruginosa and the mixed culture of denitrifying bacteria accumulated uranium rapidly (minutes) as dense, apparently random, intracellular deposits. This very rapid accumulation has prevented us from determining whether the uptake rate during the transient between the initial and equilibrium distribution of uranium is affected by environmental conditions. However, the final equilibrium distributions are not affected by those conditions which affect uptake by S. cerevisiae. Cesium and radium were concentrated to a considerably lesser extent than uranium by the several microbial species tested. The potential utility of microorganisms for the removal and concentration of these metals from nuclear processing wastes and several bioreactor designs for contacting microorganisms with contaminated waste streams will be discussed.

Strandberg, G.W.; Shumate, S.E. II; Parrott, J.R. Jr.; McWhirter, D.A.

1980-01-01T23:59:59.000Z

394

Environmental Impact Statements and Environmental Assessments...  

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

1, 1996 EIS-0240: Final Environmental Impact Statement Disposition of Surplus Highly Enriched Uranium previous 1 2 3 4 5 6 7 8 next Energy.gov Careers & Internships...

395

United States Department of Energy, Office of Environmental Management, Uranium Enrichment Decontamination and Decomissioning Fund financial statements, September 30, 1996 and 1995  

SciTech Connect

The Energy Policy Act of 1992 (Act) established the Uranium Enrichment Decontamination and Decommissioning Fund (D and D Fund, or Fund) to pay the costs for decontamination and decommissioning three gaseous diffusion facilities located in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio (diffusion facilities). The Act also authorized the Fund to pay remedial action costs associated with the Government`s operation of the facilities and to reimburse uranium and thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government. The report presents the results of the independent certified public accountants` audit of the D and D Fund financial statements as of September 30, 1996. The auditors have expressed an unqualified opinion on the 1996 statement of financial position and the related statements of operations and changes in net position and cash flows.

1997-05-01T23:59:59.000Z

396

Standing by Ohio: Cleaning Up our Environmental Legacy | Department of  

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

Standing by Ohio: Cleaning Up our Environmental Legacy Standing by Ohio: Cleaning Up our Environmental Legacy Standing by Ohio: Cleaning Up our Environmental Legacy September 14, 2010 - 12:46pm Addthis Deputy Secretary Daniel Poneman observes instrumentation in the X-333 Process Building Control Room during his visit to the Portsmouth Gaseous Diffusion Plant. | DOE photo Deputy Secretary Daniel Poneman observes instrumentation in the X-333 Process Building Control Room during his visit to the Portsmouth Gaseous Diffusion Plant. | DOE photo Daniel B. Poneman Daniel B. Poneman Deputy Secretary of Energy What does this mean for me? This facility will convert more than 250,000 metric tons of depleted uranium hexafluoride into a safer form for reuse or disposal. Southern Ohio will see 160 new jobs over the next 18 years at this

397

Properties of Uranium Compounds  

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

Triuranium Octaoxide (U3O8) Uranium Dioxide (UO2) Uranium Tetrafluoride (U4) Uranyl Fluoride (UO2F2) The physical properties of the pertinent chemical forms of uranium are...

398

Uranium Quick Facts  

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

Uranium Quick Facts Uranium Quick Facts A collection of facts about uranium, DUF6, and DOEs DUF6 inventory. Over the years, the Department of Energy has received numerous...

399

PREPARATION OF URANIUM MONOSULFIDE  

DOE Patents (OSTI)

A process is given for preparing uranium monosulfide from uranium tetrafluoride dissolved in molten alkali metal chloride. A hydrogen-hydrogen sulfide gas mixture passed through the solution precipitates uranium monosulfide. (AEC)

Yoshioka, K.

1964-01-28T23:59:59.000Z

400

URANIUM IN ALKALINE ROCKS  

E-Print Network (OSTI)

1977. "Geology of Brazil's Uranium and Thorium Occurrences,"A tantalo-niobate of uranium, near pyrochlore. Isometric,niobate and tantalate of uranium, with ferrous iron and rare

Murphy, M.

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

EIS-0472: Uranium Leasing Program, Mesa, Montrose, and San Miguel Counties, Colorado  

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

This EIS evaluates the potential environmental impacts of management alternatives for DOEs Uranium Leasing Program, under which DOE administers tracts of land in western Colorado for exploration, development, and the extraction of uranium and vanadium ores.

402

DYNAMIC PROPERTIES OF SHOCK LOADED THIN URANIUM FOILS  

SciTech Connect

A series of spall experiments has been completed with thin depleted uranium targets, nominally 0.1 mm thick. The first set of uranium spall targets was cut and ground to final thickness from electro-refined, high-purity, cast uranium. The second set was rolled to final thickness from low purity uranium. The impactors for these experiments were laser-launched 0.05-mm thick copper flyers, 3 mm in diameter. Laser energies were varied to yield a range of flyer impact velocities. This resulted in varying degrees of damage to the uranium spall targets, from deformation to complete spall or separation at the higher velocities. Dynamic measurements of the uranium target free surface velocities were obtained with dual velocity interferometers. Uranium targets were recovered and sectioned after testing. Free surface velocity profiles were similar for the two types of uranium, but spall strengths (estimated from the magnitude of the pull-back signal) are higher for the high-purity cast uranium. Velocity profiles and microstructural evidence of spall from the sectioned uranium targets are presented.

Robbins, D. L. (David L.); Kelly, A. M. (Anna Marie); Alexander, D. J. (David J.); Hanrahan, R. J. (Robert J.); Snow, R. C. (Ronny C.); Gehr, R. J. (Russell J.); Rupp, Ted Dean,; Sheffield, S. A. (Stephen A.); Stahl, D. B. (David B.)

2001-01-01T23:59:59.000Z

403

Argonne Chemical Sciences & Engineering - Nuclear & Environmental...  

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

Uranium Nuclear & Environmental Processes Home Eliminating the Use of Highly-Enriched Uranium The mission of the U.S. non-proliferation policy is to minimize and, to the...

404

Derived enriched uranium market  

SciTech Connect

The potential impact on the uranium market of highly enriched uranium from nuclear weapons dismantling in the Russian Federation and the USA is analyzed. Uranium supply, conversion, and enrichment factors are outlined for each country; inventories are also listed. The enrichment component and conversion components are expected to cause little disruption to uranium markets. The uranium component of Russian derived enriched uranium hexafluoride is unresolved; US legislation places constraints on its introduction into the US market.

Rutkowski, E.

1996-12-01T23:59:59.000Z

405

NUCLEAR BOMBS FROM LOW- ENRICHED URANIUM OR SPENT FUEL  

E-Print Network (OSTI)

Conventional wisdom says that low-enriched uranium is not suitable for making nuclear weapons. However, an article in USA Today claims that rogue states and terrorists have discovered that this is untrue. Not only that, but terrorists could separate plutonium from irradiated fuel (often called spent fuel) more easily than previously thought. (584.5495) WISE Amsterdam Lowenriched uranium (LEU) is uranium containing up to 20 % uranium-235. Uranium with higher enrichment levels is classified as high-enriched, and is subject to international safeguards because it can be used to make nuclear weapons. However, a USA Today article claims that rogue countries and terrorists have discovered that it is possible to make nuclear weapons with uranium of lower enrichment, according to classified nuclear threat reports (1). The information is not entirely new. Back in 1996, a standard book on nuclear weapons material stated, a self-sustaining chain reaction in a nuclear weapon cannot occur in depleted or natural or low-enriched uranium and is only theoretically IN THIS ISSUE: possible in LEU of roughly 10 percent or greater (2). Fuel for nuclear power reactors would not be suitable this is typically enriched to 3-5 % uranium-235. However, for a rogue state wanting to make high-enriched uranium, it would take less work to start with nuclear fuel than with natural uranium. It could be done in a small and easy to hide uranium enrichment plant perhaps similar to the plant which has recently been discovered in Iran (3). Nevertheless, it would still require a substantial operation, since the fuel would need to be converted to uranium hexafluoride, enriched and then reconverted to uranium metal. More significantly, many research reactors use uranium of just under

unknown authors

2003-01-01T23:59:59.000Z

406

COPPER COATED URANIUM ARTICLE  

DOE Patents (OSTI)

Various techniques and methods for obtaining coppercoated uranium are given. Specifically disclosed are a group of complex uranium coatings having successive layers of nickel, copper, lead, and tin.

Gray, A.G.

1958-10-01T23:59:59.000Z

407

Domestic Uranium Production Report  

U.S. Energy Information Administration (EIA)

Home > Nuclear > Domestic Uranium Production Report Domestic Uranium Production Report Data for: 2005 Release Date: May 15, 2006 Next Release: May 15, 2007

408

Manhattan Project: Uranium cubes  

Office of Scientific and Technical Information (OSTI)

Cubes of uranium metal, Los Alamos, 1945 Events > Difficult Choices, 1942 > More Uranium Research, 1942 Events > Bringing It All Together, 1942-1945 > Basic Research at Los Alamos,...

409

Depleted UF6 Internet Resources  

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

DUF6 Guide DU Uses DUF6 Management and Uses DUF6 Conversion EIS Documents News FAQs Internet Resources Glossary Home Internet Resources Depleted UF6 Internet Resources Links...

410

Chapter 1. Introduction Uranium is a common element in nature that has for centuries been used as a coloring agent in  

E-Print Network (OSTI)

2003 · Fungus catches radioactive fallout 8 May 2002 · Depleted uranium soils battlefields 12 MarchBugs boost Cold War clean-up: Bacteria could scrub uranium from sites contaminated decades ago boost Cold War clean-up Bacteria could scrub uranium from sites contaminated decades ago. 13 October

411

Uranium Industry Annual, 1992  

Science Conference Proceedings (OSTI)

The Uranium Industry Annual provides current statistical data on the US uranium industry for the Congress, Federal and State agencies, the uranium and electric utility industries, and the public. The feature article, ``Decommissioning of US Conventional Uranium Production Centers,`` is included. Data on uranium raw materials activities including exploration activities and expenditures, resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities including domestic uranium purchases, commitments by utilities, procurement arrangements, uranium imports under purchase contracts and exports, deliveries to enrichment suppliers, inventories, secondary market activities, utility market requirements, and uranium for sale by domestic suppliers are presented in Chapter 2.

Not Available

1993-10-28T23:59:59.000Z

412

Finding of No Significant Impact for teh Uranium Leasing Program  

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

Uranium Leasing Program Uranium Leasing Program July 2007 U.S. Department of Energy Office of Legacy Management FONSI for the ULP 1 July 2007 U.S. DEPARTMET OF ENERGY OFFICE OF LEGACY MANAGEMENT FINDING OF NO SIGNIFICANT IMPACT for the URANIUM LEASING PROGRAM PROGRAMMATIC ENVIRONMENTAL ASSESSMENT Agency: Department of Energy Action: Finding of No Significant Impact Summary: In accordance with the National Environmental Policy Act (NEPA) of 1969 (Title 42 United States Code [U.S.C.] 4321 et seq.) and the Council on Environmental Quality (CEQ), the U.S. Department of Energy Office of Legacy Management (DOE) prepared the Uranium Leasing Program Programmatic Environmental Assessment (PEA) (DOE/EA-1535) to evaluate its management alternatives for the future of DOE's Uranium Leasing Program (ULP). The ULP

413

Pennsylvania Natural Gas Underground Storage Depleted Fields...  

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

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Pennsylvania Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1...

414

EIS-0240: Final Environmental Impact Statement | Department of...  

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

EIS-0240: Final Environmental Impact Statement Disposition of Surplus Highly Enriched Uranium This document assesses the environmental impacts that may result from...

415

EIS-0355: EPA Notice of Availability of the Final Environmental...  

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

Notice of Availability of the Final Environmental Impact Statement EIS-0355: EPA Notice of Availability of the Final Environmental Impact Statement Remediation of the Moab Uranium...

416

PRODUCTION OF URANIUM TETRACHLORIDE  

DOE Patents (OSTI)

A process is descrlbed for the production of uranium tetrachloride by contacting uranlum values such as uranium hexafluoride, uranlum tetrafluoride, or uranium oxides with either aluminum chloride, boron chloride, or sodium alumlnum chloride under substantially anhydrous condltlons at such a temperature and pressure that the chlorldes are maintained in the molten form and until the uranium values are completely converted to uranlum tetrachloride.

Calkins, V.P.

1958-12-16T23:59:59.000Z

417

PRODUCTION OF URANIUM MONOCARBIDE  

DOE Patents (OSTI)

A method of making essentially stoichiometric uranium monocarbide by pelletizing a mixture of uranium tetrafluoride, silicon, and carbon and reacting the mixture at a temperature of approximately 1500 to 1700 deg C until the reaction goes to completion, forming uranium monocarbide powder and volatile silicon tetrafluoride, is described. The powder is then melted to produce uranium monocarbide in massive form. (AEC)

Powers, R.M.

1962-07-24T23:59:59.000Z

418

The utilization of uranium industry technology and relevant chemistry to leach uranium from mixed-waste solids  

SciTech Connect

Methods for the chemical extraction of uranium from a number of refractory uranium-containing minerals found in nature have been in place and employed by the uranium mining and milling industry for nearly half a century. These same methods, in conjunction with the principles of relevant uranium chemistry, have been employed at the Oak Ridge National Laboratory (ORNL) to chemically leach depleted uranium from mixed-waste sludge and soil. The removal of uranium from what is now classified as mixed waste may result in the reclassification of the waste as hazardous, which may then be delisted. The delisted waste might eventually be disposed of in commercial landfill sites. This paper generally discusses the application of chemical extractive methods to remove depleted uranium from a biodenitrification sludge and a storm sewer soil sediment from the Y-12 weapons plant in Oak Ridge. Some select data obtained from scoping leach tests on these materials are presented along with associated limitations and observations which might be useful to others performing such test work. 6 refs., 2 tabs.

Mattus, A.J.; Farr, L.L.

1991-01-01T23:59:59.000Z

419

Putting Depleted Uranium to Use: A New Class of Uranium-Based...  

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

of ways, but all suffer major problems: (a) no control of the 6 Fig. 4. Transmission electron microscope (TEM) image of SiO 2 -ordered nanopores (25 D D). (1) location of...

420

Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment |  

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

Uranium Leasing Program Draft Programmatic EIS Issued for Public Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment March 15, 2013 - 11:08am Addthis Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment DOE has issued the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS)(DOE/EIS-0472D) for public review and comment. The document is available here and on the ULP PEIS website. Under the Uranium Leasing Program, the DOE Office of Legacy Management administers 31 tracts of land in Mesa, Montrose, and San Miguel counties that are leased to private entities to mine uranium and vanadium. The program covers an area of approximately 25,000 acres. No mining operations are active on the ULP lands at this time. DOE is preparing the ULP PEIS to

Note: This page contains sample records for the topic "depleted uranium environmental" 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

EA-1290: Disposition of Russian Federation Titled Natural Uranium |  

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

290: Disposition of Russian Federation Titled Natural Uranium 290: Disposition of Russian Federation Titled Natural Uranium EA-1290: Disposition of Russian Federation Titled Natural Uranium SUMMARY This EA evaluates the potential environmental impacts of a proposal to transport up to an average of 9,000 metric tons per year of natural uranium as uranium hexafluoride (UF6) from the United States to the Russian Federation. This amount of uranium is equivalent to 13,3000 metric tons of UF6. The EA also examines the impacts of this action on the global commons. Transfer of natural UF6 to the Russian Federation is part of a joint U.S./Russian program to dispose of highly enriched uranium (HEU) from dismantled Russian nuclear weapons. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD

422

Excess Uranium Inventory Management Plan | Department of Energy  

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

Excess Uranium Inventory Management Plan Excess Uranium Inventory Management Plan Excess Uranium Inventory Management Plan The 2013 Excess Uranium Inventory Management Plan describes a framework for the effective management of the Energy Department's surplus uranium inventory in support of meeting its critical environmental cleanup and national security missions. The Plan is not a commitment to specific activities beyond those that have already been contracted nor is it a restriction on actions that the Department may undertake in the future as a result of changing conditions. It replaces an earlier plan issued in 2008 and reflects updated information on the Department of Energy's management and disposition of its excess uranium inventories. Excess Uranium Inventory Management Plan More Documents & Publications

423

DECONTAMINATION OF URANIUM  

DOE Patents (OSTI)

This patent deals with the separation of rare earth and other fission products from neutron bombarded uranium. This is accomplished by melting the uranium in contact with either thorium oxide, maguesium oxide, alumnum oxide, beryllium oxide, or uranium dioxide. The melting is preferably carried out at from 1150 deg to 1400 deg C in an inert atmosphere, such as argon or helium. During this treatment a scale of uranium dioxide forms on the uranium whtch contains most of the fission products.

Feder, H.M.; Chellew, N.R.

1958-02-01T23:59:59.000Z

424

Overview of AREVA Logistics Business Unit Capabilities and Expertise...  

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

Working Group Topic Groups Rail Key Documents Planning Subgroup Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium EA-1607: Final Environmental...

425

Uranium Hexafluoride (UF6)  

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

Hexafluoride (UF6) Hexafluoride (UF6) Uranium Hexafluoride (UF6) line line Properties of UF6 UF6 Health Effects Uranium Hexafluoride (UF6) Physical and chemical properties of UF6, and its use in uranium processing. Uranium Hexafluoride and Its Properties Uranium hexafluoride is a chemical compound consisting of one atom of uranium combined with six atoms of fluorine. It is the chemical form of uranium that is used during the uranium enrichment process. Within a reasonable range of temperature and pressure, it can be a solid, liquid, or gas. Solid UF6 is a white, dense, crystalline material that resembles rock salt. UF6 crystals in a glass vial image UF6 crystals in a glass vial. Uranium hexafluoride does not react with oxygen, nitrogen, carbon dioxide, or dry air, but it does react with water or water vapor. For this reason,

426

Uranium industry annual 1998  

SciTech Connect

The Uranium Industry Annual 1998 (UIA 1998) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing. It contains data for the period 1989 through 2008 as collected on the Form EIA-858, ``Uranium Industry Annual Survey.`` Data provides a comprehensive statistical characterization of the industry`s activities for the survey year and also include some information about industry`s plans and commitments for the near-term future. Data on uranium raw materials activities for 1989 through 1998, including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment, are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2008, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, and uranium inventories, are shown in Chapter 2. The methodology used in the 1998 survey, including data edit and analysis, is described in Appendix A. The methodologies for estimation of resources and reserves are described in Appendix B. A list of respondents to the ``Uranium Industry Annual Survey`` is provided in Appendix C. The Form EIA-858 ``Uranium Industry Annual Survey`` is shown in Appendix D. For the readers convenience, metric versions of selected tables from Chapters 1 and 2 are presented in Appendix E along with the standard conversion factors used. A glossary of technical terms is at the end of the report. 24 figs., 56 tabs.

NONE

1999-04-22T23:59:59.000Z

427

Uranium industry annual 1994  

SciTech Connect

The Uranium Industry Annual 1994 (UIA 1994) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing during that survey year. The UIA 1994 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. It contains data for the 10-year period 1985 through 1994 as collected on the Form EIA-858, ``Uranium Industry Annual Survey.`` Data collected on the ``Uranium Industry Annual Survey`` (UIAS) provide a comprehensive statistical characterization of the industry`s activities for the survey year and also include some information about industry`s plans and commitments for the near-term future. Where aggregate data are presented in the UIA 1994, care has been taken to protect the confidentiality of company-specific information while still conveying accurate and complete statistical data. A feature article, ``Comparison of Uranium Mill Tailings Reclamation in the United States and Canada,`` is included in the UIA 1994. Data on uranium raw materials activities including exploration activities and expenditures, EIA-estimated resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities, including purchases of uranium and enrichment services, and uranium inventories, enrichment feed deliveries (actual and projected), and unfilled market requirements are shown in Chapter 2.

NONE

1995-07-05T23:59:59.000Z

428

Uranium in the Savannah River Site environment  

SciTech Connect

The purpose of this report is to consolidate the history of environmental uranium studies conducted by SRS and to describe the status of uranium in the environment. The report is intended to be a living document'' that will be updated periodically. This draft issue, February 1992, documents studies that occurred from 1954 to 1989. Data in this report are taken primarily from annual and semiannual environmental reports for SRS. Semiannual reports were published from 1954 through 1962. Annual reports have been published since 1963. Occasionally unpublished data are included in this report for completeness.

Evans, A.G.; Bauer, L.R.; Haselow, J.S.; Hayes, D.W.; Martin, H.L.; McDowell, W.L.; Pickett, J.B.

1992-12-09T23:59:59.000Z

429

Uranium in the Savannah River Site environment  

SciTech Connect

The purpose of this report is to consolidate the history of environmental uranium studies conducted by SRS and to describe the status of uranium in the environment. The report is intended to be a ``living document`` that will be updated periodically. This draft issue, February 1992, documents studies that occurred from 1954 to 1989. Data in this report are taken primarily from annual and semiannual environmental reports for SRS. Semiannual reports were published from 1954 through 1962. Annual reports have been published since 1963. Occasionally unpublished data are included in this report for completeness.

Evans, A.G.; Bauer, L.R.; Haselow, J.S.; Hayes, D.W.; Martin, H.L.; McDowell, W.L.; Pickett, J.B.

1992-12-09T23:59:59.000Z

430

Video: Part of the 'Hole' Story (of Uranium Hexafluoride Cylinders)  

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

Hole Story Hole Story Part of the "Hole" Story (of Uranium Hexafluoride Cylinders) Holes in the depleted Uranium Hexafluoride storage cylinders are investigated. It is shown that corrosion products cause the openings to be self-healing. View this Video in Real Player format Download free RealPlayer SP Highlights of the Video: Video 00:00 Part of the 'Hole' Story Video 00:05 One of the depleted UF6 cylinder storage lots at Portsmouth Video 00:28 48G cylinders, each containing 14 tons of depleted UF6, in storage Video 00:52 Stacked 48G cylinders Video 01:35 UF6 sealed in glass tube Video 02:01 A lifting lug of one cylinder damaging a neighboring cylinder Video 02:37 Damage to small hole cylinder from impact with a lifting lub of an adjoining cylinder

431

Process for electroslag refining of uranium and uranium alloys  

DOE Patents (OSTI)

A process is described for electroslag refining of uranium and uranium alloys wherein molten uranium and uranium alloys are melted in a molten layer of a fluoride slag containing up to about 8 weight percent calcium metal. The calcium metal reduces oxides in the uranium and uranium alloys to provide them with an oxygen content of less than 100 parts per million. (auth)

Lewis, P.S. Jr.; Agee, W.A.; Bullock, J.S. IV; Condon, J.B.

1975-07-22T23:59:59.000Z

432

SOLDERING OF URANIUM  

SciTech Connect

One of Its Monograph Series, The Industrial Atom.'' The joining of uranium to uranium has been done successfully using a number of commercial soft solders and fusible alloys. Soldering by using an ultrasonic soldering iron has proved the best method for making sound soldered joints of uranium to uranium and of uranium to other metals, such as stainless steel. Other method of soldering have shown some promise but did not give reliable joints all the time. The soldering characteristics of uranium may best be compared to those of aluminum. (auth)

Hanks, G.S.; Doll, D.T.; Taub, J.M.; Brundige, E.L.

1957-01-01T23:59:59.000Z

433

URANIUM RECOVERY PROCESS  

DOE Patents (OSTI)

A method is described for recovering uranium values from uranium bearing phosphate solutions such as are encountered in the manufacture of phosphate fertilizers. The solution is first treated with a reducing agent to obtain all the uranium in the tetravalent state. Following this reduction, the solution is treated to co-precipitate the rcduced uranium as a fluoride, together with other insoluble fluorides, thereby accomplishing a substantially complete recovery of even trace amounts of uranium from the phosphate solution. This precipitate usually takes the form of a complex fluoride precipitate, and after appropriate pre-treatment, the uranium fluorides are leached from this precipitate and rccovered from the leach solution.

Bailes, R.H.; Long, R.S.; Olson, R.S.; Kerlinger, H.O.

1959-02-10T23:59:59.000Z

434

PRODUCTION OF PURIFIED URANIUM  

DOE Patents (OSTI)

A pyrometallurgical method for processing nuclear reactor fuel elements containing uranium and fission products and for reducing uranium compound; to metallic uranium is reported. If the material proccssed is essentially metallic uranium, it is dissolved in zinc, the sulution is cooled to crystallize UZn/sub 9/ , and the UZn/sub 9/ is distilled to obtain uranium free of fission products. If the material processed is a uranium compound, the sollvent is an alloy of zinc and magnesium and the remaining steps are the same.

Burris, L. Jr.; Knighton, J.B.; Feder, H.M.

1960-01-26T23:59:59.000Z

435

Method of recovering uranium hexafluoride  

DOE Patents (OSTI)

A method of recovering uranium hexafluoride from gaseous mixtures which comprises adsorbing said uranium hexafluoride on activated carbon is described.

Schuman, S.

1975-12-01T23:59:59.000Z

436

Atomic Data for Uranium (U )  

Science Conference Proceedings (OSTI)

... Uranium (U) Homepage - Introduction Finding list Select element by name. Select element by atomic number. ... Atomic Data for Uranium (U). ...

437

Reference computations of public dose and cancer risk from airborne releases of uranium and Class W plutonium  

Science Conference Proceedings (OSTI)

This report presents ``reference`` computations that can be used by safety analysts in the evaluations of the consequences of postulated atmospheric releases of radionuclides from the Rocky Flats Environmental Technology Site. These computations deal specifically with doses and health risks to the public. The radionuclides considered are Class W Plutonium, all classes of Enriched Uranium, and all classes of Depleted Uranium. (The other class of plutonium, Y, was treated in an earlier report.) In each case, one gram of the respirable material is assumed to be released at ground leveL both with and without fire. The resulting doses and health risks can be scaled to whatever amount of release is appropriate for a postulated accident being investigated. The report begins with a summary of the organ-specific stochastic risk factors appropriate for alpha radiation, which poses the main health risk of plutonium and uranium. This is followed by a summary of the atmospheric dispersion factors for unfavorable and typical weather conditions for the calculation of consequences to both the Maximum Offsite Individual and the general population within 80 km (50 miles) of the site.

Peterson, V.L.

1995-06-06T23:59:59.000Z

438

Uranium Leasing Program | Department of Energy  

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

» Uranium Leasing Program » Uranium Leasing Program Uranium Leasing Program Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado LM currently manages the Uranium Leasing Program and continues to administer 31 lease tracts, all located within the Uravan Mineral Belt in southwestern Colorado. Twenty-nine of these lease tracts are actively held under lease and two lease tracts have been placed in inactive status indefinitely. Administrative duties include the ongoing monitoring and oversight of leaseholders' activities and the annual inspection of these lease tracts to identify and correct safety hazards or other environmental compliance issues. Program Summary Current Status The U.S. Department of Energy (DOE) has extended the public comment

439

Uranium removal from soils: An overview from the Uranium in Soils Integrated Demonstration program  

SciTech Connect

An integrated approach to remove uranium from uranium-contaminated soils is being conducted by four of the US Department of Energy national laboratories. In this approach, managed through the Uranium in Soils Integrated Demonstration program at the Fernald Environmental Management Project, Fernald, Ohio, these laboratories are developing processes that selectively remove uranium from soil without seriously degrading the soil`s physicochemical characteristics or generating waste that is difficult to manage or dispose of. These processes include traditional uranium extractions that use carbonate as well as some nontraditional extraction techniques that use citric acid and complex organic chelating agents such as naturally occurring microbial siderophores. A bench-scale engineering design for heap leaching; a process that uses carbonate leaching media shows that >90% of the uranium can be removed from the Fernald soils. Other work involves amending soils with cultures of sulfur and ferrous oxidizing microbes or cultures of fungi whose role is to generate mycorrhiza that excrete strong complexers for uranium. Aqueous biphasic extraction, a physical separation technology, is also being evaluated because of its ability to segregate fine particulate, a fundamental requirement for soils containing high levels of silt and clay. Interactions among participating scientists have produced some significant progress not only in evaluating the feasibility of uranium removal but also in understanding some important technical aspects of the task.

Francis, C.W. [Oak Ridge National Lab., TN (United States); Brainard, J.R.; York, D.A. [Los Alamos National Lab., NM (United States); Chaiko, D.J. [Argonne National Lab., IL (United States); Matthern, G. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1994-09-01T23:59:59.000Z

440

Performance Assessment Transport Modeling of Uranium at the Area 5 Radioactive Waste Management Site at the Nevada National Security Site  

SciTech Connect

Following is a brief summary of the assumptions that are pertinent to the radioactive isotope transport in the GoldSim Performance Assessment model of the Area 5 Radioactive Waste Management Site, with special emphasis on the water-phase reactive transport of uranium, which includes depleted uranium products.

NSTec Radioactive Waste

2010-10-12T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uranium environmental" 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

Predicting 232U Content in Uranium  

SciTech Connect

The minor isotope 232U may ultimately be used for detection or confirmation of uranium in a variety of applications. The primary advantage of 232 U as an indicator of the presence of enriched uranium is the plentiful and penetrating nature of the radiation emitted by its daughter radionuclide 208Tl. A possible drawback to measuring uranium via 232U is the relatively high uncertainty in 232U abundance both within and between material populations. An important step in assessing this problem is to ascertain what determines the 232U concentration within any particular sample of uranium. To this end, we here analyze the production and eventual enrichment of 232 U during fuel-cycle operations. The goal of this analysis is to allow approximate prediction of 232 U quantities, or at least some interpretation of the results of 232U measurements. We have found that 232U is produced via a number of pathways during reactor irradiation of uranium and is subsequently concentrated during the later enrichment of the uranium' s 235U Content. While exact calculations are nearly impossible for both the reactor-production and cascade-enrichment parts of the prediction problem, estimates and physical bounds can be provided as listed below and detailed within the body of the report. Even if precise calculations for the irradiation and enrichment were possible, the ultimate 212U concentration would still depend upon the detailed fuel-cycle history. Assuming that a thennal-diffusion cascade is used to produce highly enriched uranium (HEU), dilution of reactor-processed fuel at the cascade input and the long-term holdup of 232U within the cascade both affect the 232U concentration in the product. Similar issues could be expected to apply for the other isotope-separation technologies that are used in other countries. Results of this analysis are listed below: 0 The 232U concentration depends strongly on the uranium enrichment, with depleted uranium (DU) containing between 1600 and 8000 times less 232U than HEU does. * The 236U/232U concentration ratio in HEU is likely to be between 10{sup 6} and 2 x 10{sup 7}. 0 Plutonium-production reactors yield uranium with between I and 10 ppt of 232u. 0 Much higher 132U concentrations can be obtained in some situations. * Significant variation in the 232U concentration is inevitable. * Cascade enrichment increases the 232U concentration by a factor of at least 200, and possibly as much as 1000. 0 The actual 232U concentration depends upon the dilution at the cascade input.

AJ Peurrung

1999-01-07T23:59:59.000Z

442

Predicting 232U Content in Uranium  

SciTech Connect

The minor isotope 232U may ultimately be used for detection or confirmation of uranium in a variety of applications. The primary advantage of 232 U as an indicator of the presence of enriched uranium is the plentiful and penetrating nature of the radiation emitted by its daughter radionuclide 208Tl. A possible drawback to measuring uranium via 232U is the relatively high uncertainty in 232U abundance both within and between material populations. An important step in assessing this problem is to ascertain what determines the 232U concentration within any particular sample of uranium. To this end, we here analyze the production and eventual enrichment of 232 U during fuel-cycle operations. The goal of this analysis is to allow approximate prediction of 232 U quantities, or at least some interpretation of the results of 232U measurements. We have found that 232U is produced via a number of pathways during reactor irradiation of uranium and is subsequently concentrated during the later enrichment of the uranium' s 235U Content. While exact calculations are nearly impossible for both the reactor-production and cascade-enrichment parts of the prediction problem, estimates and physical bounds can be provided as listed below and detailed within the body of the report. Even if precise calculations for the irradiation and enrichment were possible, the ultimate 212U concentration would still depend upon the detailed fuel-cycle history. Assuming that a thennal-diffusion cascade is used to produce highly enriched uranium (HEU), dilution of reactor-processed fuel at the cascade input and the long-term holdup of 232U within the cascade both affect the 232U concentration in the product. Similar issues could be expected to apply for the other isotope-separation technologies that are used in other countries. Results of this analysis are listed below: 0 The 232U concentration depends strongly on the uranium enrichment, with depleted uranium (DU) containing between 1600 and 8000 times less 232U than HEU does. * The 236U/232U concentration ratio in HEU is likely to be between 10{sup 6} and 2 x 10{sup 7}. 0 Plutonium-production reactors yield uranium with between I and 10 ppt of 232u. 0 Much higher 132U concentrations can be obtained in some situations. * Significant variation in the 232U concentration is inevitable. * Cascade enrichment increases the 232U concentration by a factor of at least 200, and possibly as much as 1000. 0 The actual 232U concentration depends upon the dilution at the cascade input.

AJ Peurrung

1999-01-07T23:59:59.000Z

443

Uranium from phosphate ores  

SciTech Connect

The following topics are described briefly: the way phosphate fertilizers are made; how uranium is recovered in the phosphate industry; and how to detect covert uranium recovery operations in a phsophate plant.

Hurst, F.J.

1983-01-01T23:59:59.000Z

444

Uranium Health Effects  

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

For inhalation or ingestion of soluble or moderately soluble compounds such as uranyl fluoride (UO2F2) or uranium tetrafluoride (UF4), the uranium enters the bloodstream and...

445

METHOD FOR PURIFYING URANIUM  

DOE Patents (OSTI)

A process is given for purifying a uranium-base nuclear material. The nuclear material is dissolved in zinc or a zinc-magnesium alloy and the concentration of magnesium is increased until uranium precipitates.

Knighton, J.B.; Feder, H.M.

1960-04-26T23:59:59.000Z

446

Uranium Quick Facts  

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

Uranium Quick Facts A collection of facts about uranium, DUF6, and DOEs DUF6 inventory. Over the years, the Department of Energy has received numerous inquiries from the...

447

Cathodoluminescence of uranium oxides  

SciTech Connect

The cathodoluminescence of uranium oxide surfaces prepared in-situ from clean uranium exposed to dry oxygen was studied. The broad asymmetric peak observed at 470 nm is attributed to F-center excitation.

Winer, K.; Colmenares, C.; Wooten, F.

1984-08-09T23:59:59.000Z

448

Bicarbonate leaching of uranium  

SciTech Connect

The alkaline leach process for extracting uranium from uranium ores is reviewed. This process is dependent on the chemistry of uranium and so is independent on the type of mining system (conventional, heap or in-situ) used. Particular reference is made to the geochemical conditions at Crownpoint. Some supporting data from studies using alkaline leach for remediation of uranium-contaminated sites is presented.

Mason, C.

1998-12-31T23:59:59.000Z

449

Uranium industry annual 1995  

SciTech Connect

The Uranium Industry Annual 1995 (UIA 1995) provides current statistical data on the U.S. uranium industry`s activities relating to uranium raw materials and uranium marketing. The UIA 1995 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. It contains data for the period 1986 through 2005 as collected on the Form EIA-858, ``