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


1

EM Waste and Materials Disposition & Transportation | Department...  

Office of Environmental Management (EM)

EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

2

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the  

Broader source: Energy.gov (indexed) [DOE]

99: Disposition of Radioactively Contaminated Nickel Located 99: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications Summary This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold. Public Comment Opportunities No public comment opportunities at this time.

3

Waste and Materials Disposition Information | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Waste and Materials Disposition Waste and Materials Disposition Information Waste and Materials Disposition Information Waste and Materials Disposition Information As the Office of Environmental Management (EM) fulfills its mission, waste and materials disposition plays a vital role in the cleanup of radioactive waste and the environmental legacy of nuclear weapons production and nuclear energy research. Disposal of waste frequently falls on the critical path of cleanup projects. Significant planning resources are spent to identify alternatives and find a path that is cost-effective and in the best interest of the Federal government. In many instances, waste disposition, (processing, treatment and disposal) is part of cleanup agreements and is of interest to stakeholders and requires the oversight of regulators.

4

Fissile Materials Disposition | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Fissile Materials Disposition | National Nuclear Security Administration Fissile Materials Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Fissile Materials Disposition Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition Fissile Materials Disposition Since the end of the Cold War, significant quantities of plutonium and

5

EM Waste and Materials Disposition & Transportation  

Broader source: Energy.gov (indexed) [DOE]

On Closure Success On Closure Success 1 EM Waste and Materials Disposition & Transportation National Transportation Stakeholders Forum Chicago, Illinois May 26, 2010 Frank Marcinowski Acting Chief Technical Officer and Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management DOE's Radioactive Waste Management Priorities * Continue to manage waste inventories in a safe and compliant manner * Address high risk waste in a cost- ff ti effective manner * Maintain and optimize current disposal capability for future generations * Develop future disposal capacity in a complex environment * Promote the development of treatment and disposal alternatives in the 2 and disposal alternatives in the

6

Nuclear Materials Disposition | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Spent Nuclear Fuel Spent nuclear fuel (SNF) is fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing. SNF may include: (1) intact, non-defective fuel assemblies or fuel rods; (2) failed fuel assemblies or fuel rods; (3) segments of fuel rods or pieces of fuel derived from spent fuel rods; and

7

Radioactive Material Transportation Practices  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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

2002-09-23T23:59:59.000Z

8

Processing and Disposition of Special Actinide Target Materials - 13138  

SciTech Connect (OSTI)

The Department of Energy (DOE) manages an inventory of materials that contains a range of long-lived radioactive isotopes that were produced from the 1960's through the 1980's by irradiating targets in high-flux reactors at the Savannah River Site (SRS) to produce special heavy isotopes for DOE programmatic use, scientific research, and industrial and medical applications. Among the products were californium-252, heavy curium (including Cm-246 through Cm-248), and plutonium-242 and -244. Many of the isotopes are still in demand today, and they can be recovered from the remaining targets previously irradiated at SRS or produced from the recovered isotopes. Should the existing target materials be discarded, the plutonium (Pu) and curium (Cm) isotopes cannot be replaced readily with existing production sources. Some of these targets are stored at SRS, while other target material is stored at Oak Ridge National Laboratory (ORNL) at several stages of processing. The materials cannot be stored in their present form indefinitely. Their long-term management involves processing items for beneficial use and/or for disposition, using storage and process facilities at SRS and ORNL. Evaluations are under way for disposition options for these materials, and demonstrations of improved flow sheets to process the materials are being conducted at ORNL and the Savannah River National Laboratory (SRNL). The disposition options and a management evaluation process have been developed. Processing demonstrations and evaluations for these unique materials are under way. (authors)

Robinson, Sharon M.; Patton, Brad D. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)] [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States); Allender, Jeffrey S. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

2013-07-01T23:59:59.000Z

9

Midwestern Radioactive Materials Transportation Committee Agenda...  

Office of Environmental Management (EM)

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

10

SRS - Programs - H Area Nuclear Materials Disposition  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

H Area Nuclear Materials Disposition H Area Nuclear Materials Disposition The primary mission of the H-Canyon Complex is to dissolve, purify and blend-down surplus highly enriched uranium (HEU) and aluminum-clad foreign and domestic research reactor fuel to produce a low enriched uranium (LEU) solution suitable for conversion to commercial reactor fuel. A secondary mission for H-Canyon is to dissolve excess plutonium (Pu) not suitable for MOX and transfer it for vitrification in the Defense Waste Processing Facility at SRS. H Canyon was constructed in the early 1950s and began operations in 1955. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains the process vessels. It is approximately 1,000 feet long with several levels to accommodate the various stages of material stabilization, including control rooms to monitor overall equipment and operating processes, equipment and piping gallery for solution transport, storage, and disposition, and unique overhead bridge cranes to support overall process operations. All work is remotely controlled, and employees are further protected from radiation by thick concrete walls.

11

Container for radioactive materials  

DOE Patents [OSTI]

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

Fields, S.R.

1984-05-30T23:59:59.000Z

12

RADIOACTIVE MATERIALS SENSORS  

SciTech Connect (OSTI)

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

Mayo, Robert M.; Stephens, Daniel L.

2009-09-15T23:59:59.000Z

13

Radioactive Material Transportation Practices Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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

2008-06-04T23:59:59.000Z

14

Fissile material disposition program final immobilization form assessment and recommendation  

SciTech Connect (OSTI)

Lawrence Livermore National Laboratory (LLNL), in its role as the lead laboratory for the development of plutonium immobilization technologies for the Department of Energy`s Office of Fissile Materials Disposition (MD), has been requested by MD to recommend an immobilization technology for the disposition of surplus weapons- usable plutonium. The recommendation and supporting documentation was requested to be provided by September 1, 1997. This report addresses the choice between glass and ceramic technologies for immobilizing plutonium using the can-in-canister approach. Its purpose is to provide a comparative evaluation of the two candidate technologies and to recommend a form based on technical considerations.

Cochran, S.G.; Dunlop, W.H.; Edmunds, T.A.; MacLean, L.M.; Gould, T.H. [Westinghouse Savannah River Co., Aiken, SC (United States)

1997-10-03T23:59:59.000Z

15

Radioactive material in the West Lake Landfill: Summary report  

SciTech Connect (OSTI)

The West Lake Landfill is located near the city of St. Louis in Bridgeton, St. Louis County, Missouri. The site has been used since 1962 for disposing of municipal refuse, industrial solid and liquid wastes, and construction demolition debris. This report summarizes the circumstances of the radioactive material in the West Lake Landfill. The radioactive material resulted from the processing of uranium ores and the subsequent by the AEC of processing residues. Primary emphasis is on the radiological environmental aspects as they relate to potential disposition of the material. It is concluded that remedial action is called for. 8 refs., 2 figs., 1 tab.

none,

1988-06-01T23:59:59.000Z

16

Radioactive waste material melter apparatus  

DOE Patents [OSTI]

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

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

1990-01-01T23:59:59.000Z

17

Storage depot for radioactive material  

DOE Patents [OSTI]

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

Szulinski, Milton J. (Richland, WA)

1983-01-01T23:59:59.000Z

18

Naturally Occurring Radioactive Materials (NORM)  

SciTech Connect (OSTI)

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

Gray, P. [ed.

1997-02-01T23:59:59.000Z

19

Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &  

E-Print Network [OSTI]

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

Sherrill, David

20

Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407  

SciTech Connect (OSTI)

This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

Walker, Stuart [U.S. Environmental Protection Agency (United States)] [U.S. Environmental Protection Agency (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Radioactive waste material disposal  

DOE Patents [OSTI]

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

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

1995-10-24T23:59:59.000Z

22

Radioactive waste material disposal  

DOE Patents [OSTI]

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

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

1995-01-01T23:59:59.000Z

23

Status of nuclear weapons material disposition in Russia  

SciTech Connect (OSTI)

The security of nuclear weapons and fissile material in Russia, the disposition of weapons-usable fissile material in Russia, the Clinton administration`s policies and programs for assisting Russia in improving its security over nuclear weapons and fissile material, and the disposal of Russian weapons-usable fissile materials are discussed in this paper. There are {approximately}30,000 nuclear warheads in the former Soviet Union, {approximately}1000 t of weapon-usable high-enriched uranium (HEU), {approximately} 160 t of separated plutonium in weapons or available for weapons, and {approximately}30 t of separated civil plutonium stored in Russia. Most, if not all, of these inventories are stored under inadequate conditions of physical security and of material control and accounting.

Cochran, T.B.

1994-12-31T23:59:59.000Z

24

Update to the Fissile Materials Disposition program SST/SGT transportation estimation  

SciTech Connect (OSTI)

This report is an update to ``Fissile Materials Disposition Program SST/SGT Transportation Estimation,'' SAND98-8244, June 1998. The Department of Energy Office of Fissile Materials Disposition requested this update as a basis for providing the public with an updated estimation of the number of transportation loads, load miles, and costs associated with the preferred alternative in the Surplus Plutonium Disposition Final Environmental Impact Statement (EIS).

John Didlake

1999-11-15T23:59:59.000Z

25

Plutonium-bearing materials feed report for the DOE Fissile Materials Disposition Program alternatives  

SciTech Connect (OSTI)

This report has identified all plutonium currently excess to DOE Defense Programs under current planning assumptions. A number of material categories win clearly fan within the scope of the MD (Materials Disposition) program, but the fate of the other categories are unknown at the present time. MD planning requires that estimates be made of those materials likely to be considered for disposition actions so that bounding cases for the PEIS (Programmatic Environmental Impact Statement) can be determined and so that processing which may be required can be identified in considering the various alternatives. A systematic analysis of the various alternatives in reachmg the preferred alternative requires an understanding of the possible range of values which may be taken by the various categories of feed materials. One table identifies the current total inventories excess to Defense Program planning needs and represents the bounding total of Pu which may become part of the MD disposition effort for all materials, except site return weapons. The other categories, principally irradiated fuel, rich scrap, and lean scrap, are discussed. Another table summarizes the ranges and expected quantities of Pu which could become the responsibility of the MD program. These values are to be used for assessing the impact of the various alternatives and for scaling operations to assess PEIS impact. Determination of the actual materials to be included in the disposition program will be done later.

Brough, W.G. [Lawrence Livermore National Lab., CA (United States); Boerigter, S.T. [Los Alamos National Lab., NM (United States)

1995-04-06T23:59:59.000Z

26

Radioactive material package seal tests  

SciTech Connect (OSTI)

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

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

1990-01-01T23:59:59.000Z

27

EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials |  

Broader source: Energy.gov (indexed) [DOE]

29: Storage and Disposition of Weapons-Usable Fissile 29: Storage and Disposition of Weapons-Usable Fissile Materials EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials Summary The EIS will evaluate the reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. Public Comment Opportunities None available at this time. Documents Available For Download September 5, 2007 EIS-0229: Supplement Analysis (September 2007) Storage of Surplus Plutonium Materials at the Savannah River Site November 14, 2003 EIS-0229: Record of Decision (November 2003) Storage and Disposition of Weapons-Usable Fissile Materials November 7, 2003 EIS-0229-SA-03: Supplement Analysis Fabrication of Mixed Oxide Fuel Lead Assemblies in Europe

28

Laboratory Surveys when Working with Radioactive Materials  

E-Print Network [OSTI]

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

Jia, Songtao

29

Radioactive Material Use at the EMSL Radiochemistry Annex  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

30

Transporting & Shipping Hazardous Materials at LBNL: Radioactive Materials  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

31

Spills of Radioactive Materials -Emergency Procedures  

E-Print Network [OSTI]

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

Jia, Songtao

32

Diverter assembly for radioactive material  

DOE Patents [OSTI]

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

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

1988-04-11T23:59:59.000Z

33

Radiation Sources and Radioactive Materials (Connecticut)  

Broader source: Energy.gov [DOE]

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

34

Radiation Machines and Radioactive Materials (Iowa)  

Broader source: Energy.gov [DOE]

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

35

Radioactive Material or Multiple Hazardous Materials Decontamination  

Broader source: Energy.gov [DOE]

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

36

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

37

Radioactive materials shipping cask anticontamination enclosure  

DOE Patents [OSTI]

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

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

1982-01-01T23:59:59.000Z

38

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

39

Radioactive Samples / Materials at the APS  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

40

PTS 13.1 Radioactive And Hazardous Material Transportation 4...  

Office of Environmental Management (EM)

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

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Safety and Security Technologies for Radioactive Material Shipments...  

Office of Environmental Management (EM)

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

42

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

E-Print Network [OSTI]

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

Straight, Aaron

43

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

44

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

45

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

46

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

47

Storage and Disposition of Weapons-Usable Fissile Materials  

Broader source: Energy.gov (indexed) [DOE]

86 86 Federal Register / Vol. 63, No. 156 / Thursday, August 13, 1998 / Notices 1 SRS has been identified by DOE as the preferred site for the immobilization disposition facility. responsibilities are to (1) evaluate the standards of accreditation applied to applicant foreign medical schools; and (2) determine the comparability of those standards to standards for accreditation applied to United States medical schools. For Further Information Contact: Bonnie LeBold, Executive Director, National Committee on Foreign Medical Education and Accreditation, 7th and D Streets, S.W., Room 3082, ROB #3, Washington, D.C. 20202-7563. Telephone: (202) 260-3636. Beginning September 28, 1998, you may call to obtain the identity of the countries whose standards are to be evaluated during this

48

Completion of the Radioactive Materials Packaging Handbook  

SciTech Connect (OSTI)

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

Shappert, L.B.

1998-02-01T23:59:59.000Z

49

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

50

EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

Broader source: Energy.gov (indexed) [DOE]

Emer Emer Emer Emer Emer Emergency Response to a T gency Response to a T gency Response to a T gency Response to a T gency Response to a Transportation ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional

51

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

52

Radioactive Material Use at the EMSL Radiochemistry Annex  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

53

Procedures for the Proper Disposition of Equipment and Materials Through  

E-Print Network [OSTI]

Material (ACM) 1. Description a. Asbestos is a naturally occurring fibrous mineral that was used Health and Safety ~ Radiation Protection #12;Environmental Protection ~ Occupational Health and Safety ~ Radiation Protection Table of Contents I. Introduction 1 II. Items Prohibited from Sale or Transfer A

Maroncelli, Mark

54

Radioactive Materials Transportation and Incident Response  

Broader source: Energy.gov (indexed) [DOE]

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

55

Film Badge Application Radioactive Material Package Receipt Log  

E-Print Network [OSTI]

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

Slatton, Clint

56

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect (OSTI)

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

McCarthy, T.L.

1995-12-01T23:59:59.000Z

57

Corrosion resistant storage container for radioactive material  

DOE Patents [OSTI]

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

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

1984-08-30T23:59:59.000Z

58

Corrosion resistant storage container for radioactive material  

DOE Patents [OSTI]

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

Schweitzer, Donald G. (Bayport, NY); Davis, Mary S. (Wading River, NY)

1990-01-01T23:59:59.000Z

59

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

60

Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project  

SciTech Connect (OSTI)

This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

Reynolds, T. D.; Easterling, S. D.

2010-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Study of gel materials as radioactive 222Rn gas detectors  

Science Journals Connector (OSTI)

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

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

2006-09-01T23:59:59.000Z

62

Midwestern Radioactive Materials Transportation Committee Agenda  

Broader source: Energy.gov (indexed) [DOE]

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

63

RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS  

SciTech Connect (OSTI)

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

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

2011-06-06T23:59:59.000Z

64

Experiment Hazard Class 8.1 - Radioactive Materials/Samples  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

65

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

E-Print Network [OSTI]

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

Wechsler, Risa H.

66

Study of gel materials as radioactive 222Rn gas detectors  

Science Journals Connector (OSTI)

......Commercial hair gel material (polyvinyl pyrolydone...radioactive gas in the gel material, and the subsequent...reproducibility of data, easy handling and low cost of the gel material. This detection...aerosols(7). The diagrams of the Marinelli......

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

2006-09-01T23:59:59.000Z

67

Introduction to naturally occurring radioactive material  

SciTech Connect (OSTI)

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

Egidi, P.

1997-08-01T23:59:59.000Z

68

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

Broader source: Energy.gov (indexed) [DOE]

Video User' s Guide Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond

69

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

70

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

71

Radioactive Materials at SSRL | Stanford Synchrotron Radiation Lightsource  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

72

Analysis and section of processes for the disposition of excess fissile material from nuclear weapon dismantlement in the United States  

SciTech Connect (OSTI)

The end of the cold war and the acceleration of nuclear disarmament efforts by the United States (US) and Russia are generating large quantities of surplus fissile nuclear materials that are no longer needed for military purposes. The safe and secure disposition of this surplus material to prevent theft or reuse in weapons has become a high priority for the US Department of Energy (USDOE). Many options exist for storage and disposition (use or disposal) of these surplus materials. The criteria, which have been developed from the basis for a preliminary ``screening`` of options, to eliminate from further consideration those options that do not meet minimal requirements. Factors, or attributes, contained in the screening and selection criteria include: (1) resistance to theft and diversion by unauthorized parties, (2) resistance to retrieval, extraction, and reuse by the host nation, (3) technical viability, (4) environmental, safety, and health impacts, (5) cost effectiveness, (6) timeliness, (7) fostering of progress and cooperation with Russia and others, (8) public and institutional acceptance, and (9) additional benefits. The evaluation of environmental impacts, in accordance with the US National Environmental Policy Ac (NEPA) process, is an integral part of the overall evaluation process. Because of the variety of physical and chemical forms of the nuclear material inventory, and because of the large number of possible disposition technologies and final forms, several hundred possible pathways to disposition have been defined and have undergone a systematic selection process. Also, because nuclear material disposition will have far ranging impacts, extensive public, in the form of public and stakeholder, input was integral to the selection process.

Myers, B.R.; Armantrout, G.A. [Lawrence Livermore National Lab., CA (United States); Erickson, R. [Los Alamos National Lab., NM (United States)

1995-02-01T23:59:59.000Z

73

Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM  

Broader source: Energy.gov (indexed) [DOE]

Integrated Facilities Disposition Project Integrated Facilities Disposition Project Technical Assistance Page 1 of 2 Oak Ridge National Laboratory Y-12 National Security Complex Tennessee Tennessee Assessment of the Integrated Facility Disposition Project at ORNL & Y-12 for Transfer of Facilities & Materials to EM Challenge In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). In parallel with the EM-1 initiative, the Oak Ridge Reservation was conducting a Critical

74

Safety and Security Technologies for Radioactive Material Shipments  

Broader source: Energy.gov (indexed) [DOE]

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

75

Naturally Occurring Radioactive Materials in Cargo at US Borders  

SciTech Connect (OSTI)

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

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

2006-01-01T23:59:59.000Z

76

Transfer of excess nuclear material from Los Alamos to Savannah River site for long-term disposition  

SciTech Connect (OSTI)

Los Alamos National Laboratory is preparing excess nuclear material for shipment to Savannah River Site (SRS) for final disposition. Prior to shipment the nuclear material will be stabilized and packaged to meet strict criteria. The criterion that must be met include: (1) the DOE stabilization, packaging and storage requirements for plutonium bearing materials, DOE-STD-3013, (2) shipping container packaging requirements, (3) SRS packaging and storage criteria, and (4) DOE Material Disposition criteria for either immobilization or MOX reactor fuel. Another issue in preparing for this transfer is the DOE certification of shipping containers and the availability of shipping containers. This transfer of the nuclear material is fully supported by the EM, DP and NN Sections of the DOE, as well as, by LANL and SRS, yet a strong collaboration is needed to meet all established requirements relating to stabilization, packaging, shipment, storage and final disposition. This paper will present the overall objectives, the issues and the planned strategy to accomplish this nuclear material transfer.

Hoth, C. W. (Carl W.); Yarbro, T. F. (Tresa F.); Foster, Lynn A.

2001-06-01T23:59:59.000Z

77

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

78

NNSA: Securing Domestic Radioactive Material | National Nuclear Security  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

NNSA: Securing Domestic Radioactive Material | National Nuclear Security NNSA: Securing Domestic Radioactive Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > NNSA: Securing Domestic Radioactive Material Fact Sheet NNSA: Securing Domestic Radioactive Material Apr 12, 2013 The Department of Energy's National Nuclear Security Administration (NNSA),

79

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

National Nuclear Security Administration (NNSA)

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

80

Sandia technology used to remove radioactive material at Fukushima |  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

technology used to remove radioactive material at Fukushima | technology used to remove radioactive material at Fukushima | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Sandia technology used to remove radioactive material ... Sandia technology used to remove radioactive material at Fukushima Posted By Office of Public Affairs

Note: This page contains sample records for the topic "disposition radioactive materials" 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

NNSA Removes High-Activity Radioactive Materials from Boston | National  

National Nuclear Security Administration (NNSA)

Removes High-Activity Radioactive Materials from Boston | National Removes High-Activity Radioactive Materials from Boston | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > NNSA Removes High-Activity Radioactive Materials from Boston Press Release NNSA Removes High-Activity Radioactive Materials from Boston Nov 22, 2013

82

DOE/EA-1651: Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee (January 2010)  

Broader source: Energy.gov (indexed) [DOE]

51 51 Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee U. S. Department of Energy Oak Ridge Office Oak Ridge, Tennessee January 2010 FINDING OF NO SIGNIFICANT IMPACT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory [DOE/EA-1651]. This environmental assessment (EA) evaluates the impacts of planned activities to modify selected

83

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

National Nuclear Security Administration (NNSA)

2011 In April 2009, President Obama outlined an ambitious agenda to secure vulnerable nuclear material around the world within four years, calling the danger of a terrorist...

84

Used Fuel Disposition Research & Development | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Used Fuel Disposition Used Fuel Disposition Research & Development Used Fuel Disposition Research & Development A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. In order to assure the development of a sustainable nuclear fuel cycle for the nation's energy future, to provide a sound technical basis for implementation of a new national policy for managing the back end of the nuclear fuel cycle, and to better understand, assess, and communicate the

85

Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives  

SciTech Connect (OSTI)

This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

NONE

1997-01-01T23:59:59.000Z

86

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

87

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

88

Removal of radioactive and other hazardous material from fluid waste  

DOE Patents [OSTI]

Hollow glass microspheres obtained from fly ash (cenospheres) are impregnated with extractants/ion-exchangers and used to remove hazardous material from fluid waste. In a preferred embodiment the microsphere material is loaded with ammonium molybdophosphonate (AMP) and used to remove radioactive ions, such as cesium-137, from acidic liquid wastes. In another preferred embodiment, the microsphere material is loaded with octyl(phenyl)-N-N-diisobutyl-carbamoylmethylphosphine oxide (CMPO) and used to remove americium and plutonium from acidic liquid wastes.

Tranter, Troy J. (Idaho Falls, ID); Knecht, Dieter A. (Idaho Falls, ID); Todd, Terry A. (Aberdeen, ID); Burchfield, Larry A. (W. Richland, WA); Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana (Krasnoyarsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Aloy, Albert S. (St. Petersburg, RU); Sapozhnikova, Natalia V. (St. Petersburg, RU)

2006-10-03T23:59:59.000Z

89

PF-4 actinide disposition strategy  

SciTech Connect (OSTI)

The dwindling amount of Security Category I processing and storage space across the DOE Complex has driven the need for more effective storage of nuclear materials at LANL's Plutonium Facility's (PF-4's) vault. An effort was begun in 2009 to create a strategy, a roadmap, to identify all accountable nuclear material and determine their disposition paths, the PF-4 Actinide Disposition Strategy (PADS). Approximately seventy bins of nuclear materials with similar characteristics - in terms of isotope, chemical form, impurities, disposition location, etc. - were established in a database. The ultimate disposition paths include the material to remain at LANL, disposition to other DOE sites, and disposition to waste. If all the actions described in the document were taken, over half of the containers currently in the PF-4 vault would been eliminated. The actual amount of projected vault space will depend on budget and competing mission requirements, however, clearly a significant portion of the current LANL inventory can be either dispositioned or consolidated.

Marcevicius, Robert W [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

90

Disposition of uranium-233  

SciTech Connect (OSTI)

The US is developing a strategy for the disposition of surplus weapons-usable uranium-233 ({sup 233}U). The strategy (1) identifies the requirements for the disposition of surplus {sup 233}U; (2) identifies potential disposition options, including key issues to be resolved with each option; and (3) defines a road map that identifies future key decisions and actions. The disposition of weapons-usable fissile materials is part of a US international arms-control program for reduction of the number of nuclear weapons and the quantities of nuclear-weapons-usable materials worldwide. The disposition options ultimately lead to waste forms requiring some type of geological disposal. Major options are described herein.

Tousley, D.R. [Dept. of Energy, Washington, DC (United States). Office of Fissile Materials Disposition; Forsberg, C.W.; Krichinsky, A.M. [Oak Ridge National Lab., TN (United States)

1997-10-16T23:59:59.000Z

91

Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program  

SciTech Connect (OSTI)

This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

1997-12-01T23:59:59.000Z

92

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials  

SciTech Connect (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing materials. Transportation regulations prohibit shipment of explosives and radioactive materials together. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials (NM), and spent nuclear fuels (SNF) programs within DOEs Environmental Management (EM) organization to address gas generation concerns. This paper presents a "program level" roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This "program level" roadmapping involves linking technology development (and deployment) efforts to the programs needs and requirements for dispositioning the material/waste that generates combustible gas through radiolysis and chemical decomposition. The roadmapping effort focused on needed technical & programmatic support to the baselines (and to alternatives to the baselines) where the probability of success is low (i.e., high uncertainty) and the consequences of failure are relatively high (i.e., high programmatic risk). A second purpose for roadmapping was to provide the basis for coordinating sharing of "lessons learned" from research and development (R&D) efforts across DOE programs to increase efficiency and effectiveness in addressing gas generation issues.

Luke, Dale Elden; Rogers, Adam Zachary; Hamp, S.

2001-03-01T23:59:59.000Z

93

Management of sewage sludge and ash containing radioactive materials.  

SciTech Connect (OSTI)

Approximately 50% of the seven to eight million metric tonnes of municipal sewage sludge produced annually in the US is reused. Beneficial uses of sewage sludge include agricultural land application, land reclamation, forestry, and various commercial applications. Excessive levels of contaminants, however, can limit the potential usefulness of land-applied sewage sludge. A recently completed study by a federal inter-agency committee has identified radioactive contaminants that could interfere with the safe reuse of sewage sludge. The study found that typical levels of radioactive materials in most municipal sewage sludge and incinerator ash do not present a health hazard to sewage treatment plant workers or to the general public. The inter-agency committee has developed recommendations for operators of sewage treatment plants for evaluating measured or estimated levels of radioactive material in sewage sludge and for determining whether actions to reduce potential exposures are appropriate.

Bachmaier, J. T.; Aiello, K.; Bastian, R. K.; Cheng, J.-J.; Chiu, W. A.; Goodman, J.; Hogan, R.; Jones, A. R.; Kamboj, S.; Lenhart, T.; Ott, W. R.; Rubin, A. B.; Salomon, S. N.; Schmidt, D. W.; Setlow, L. W.; Yu, C.; Wolbarst, A. B.; Environmental Science Division; Middlesex County Utilities Authority; U.S. EPA; N.J. Dept of Environmental Protection; NRC

2007-01-01T23:59:59.000Z

94

Hanford Site Shares Lessons Learned in Retrieving Highly Radioactive Material  

Broader source: Energy.gov [DOE]

RICHLAND, Wash. EMs Richland Operations Office (Richland) and its contractor, CH2M HILL Plateau Remediation Company (CH2M HILL), welcomed staff from the Oak Ridge Office of Environmental Management Transuranic (TRU) waste processing team in Tennessee to the Hanford site recently to share lessons learned in the retrieval and processing of highly radioactive material, called sludge.

95

A pill to treat people exposed to radioactive materials  

ScienceCinema (OSTI)

Berkeley Lab's Rebecca Abergel discusses "A pill to treat people exposed to radioactive materials" in this Oct. 28, 2013 talk, which is part of a Science at the Theater event entitled Eight Big Ideas. Go here to watch the entire event with all 8 speakers:

Abergel, Rebecca

2014-06-24T23:59:59.000Z

96

The radioactive materials packaging handbook: Design, operations, and maintenance  

SciTech Connect (OSTI)

As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

1998-08-01T23:59:59.000Z

97

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Who makes rules? What are the requirements? Safety Record USERS OF PACKAGINGS CARRIER PACKAGE TYPE Hospitals and their suppliers common carrier Type A Industrial radiography companies private carrier Type B Soil testing laboratories private carrier Type B Food irradiators contract carrier Type B Medical supply sterilizers contract carrier Type B Academic research institutes common & contract carrier all types Nuclear energy fuel cycle facilities common & contract carrier all types Nuclear weapons complex contract & government carrier all types An agency or company that wants to ship RAM (shipper) often makes arrangements with a common or contract carrier or (where appropriate) a private carrier may transport the material. Packagings may be procured or

98

Detection of radioactive materials at Astrakhan  

SciTech Connect (OSTI)

Astrakhan is the major Russian port on the Caspian Sea. Consequently, it is the node for significant river traffic up the Volga, as well as shipments to and from other seaports on the Caspian Sea. The majority of this latter trade across the Caspian Sea is with Iran. The Second Line of Defense and RF SCC identified Astrakhan as one of the top priorities for upgrading with modern radiation detection equipment. The purpose of the cooperative effort between RF SCC and DOE at Astrakhan is to provide the capability through equipment and training to monitor and detect illegal shipments of nuclear materials through Astrakhan. The first facility was equipped with vehicle and rail portal monitoring systems. The second facility was equipped with pedestrian, vehicle and rail portal monitoring systems. A second phase of this project will complete the equipping of Astrakhan by providing additional rail and handheld systems, along with completion of video systems. Associated with both phases is the necessary equipment and procedural training to ensure successful operation of the equipment in order to detect and deter illegal trafficking in nuclear materials. The presentation will described this project and its overall relationship to the Second Line of Defense Program.

Cantut, L; Dougan, A; Hemberger, P; Kravenchenko, Gromov, A; Martin, D; Pohl, B; Richardson, J H; Williams, H; York, R; Zaitsev, E

1999-07-01T23:59:59.000Z

99

A manual for implementing residual radioactive material guidelines  

SciTech Connect (OSTI)

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material at sites identified by the Formerly Utilized Sites Remedial Action Program (FUSRAP) and the Surplus Facilities Management Program (SFMP). It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. 36 refs., 16 figs, 22 tabs.

Gilbert, T.L.; Yu, C.; Yuan, Y.C.; Zielen, A.J.; Jusko, M.J.; Wallo, A. III

1989-06-01T23:59:59.000Z

100

Digital Radiography of a Drop Tested 9975 Radioactive Materials Packaging  

SciTech Connect (OSTI)

This paper discusses the use of radiography as a tool for evaluating damage to radioactive material packaging subjected to regulatory accident conditions. The Code of Federal Regulations, 10 CFR 71, presents the performance based requirements that must be used in the development (design, fabrication and testing) of a radioactive material packaging. The use of various non-destructive examination techniques in the fabrication of packages is common. One such technique is the use of conventional radiography in the examination of welds. Radiography is conventional in the sense that images are caught one at a time on film stock. Most recently, digital radiography has been used to characterize internal damage to a package subjected to the 30-foot hypothetical accident conditions (HAC) drop. Digital radiography allows for real time evaluation of the item being inspected. This paper presents a summary discussion of the digital radiographic technique and an example of radiographic results of a 9975 package following the HAC 30-foot drop.

Blanton, P.S.

2001-05-30T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program  

Broader source: Energy.gov (indexed) [DOE]

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

102

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents [OSTI]

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

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

1998-05-12T23:59:59.000Z

103

rev September 2003 Radiation Safety Manual Section 11 Procurement of Radioactive Material  

E-Print Network [OSTI]

rev September 2003 Radiation Safety Manual Section 11 ­ Procurement of Radioactive Material Page 11-1 Section 11 Procurement of Radioactive Materials Contents A. Authorization to Order Radioactive Materials. Authorized Investigator Package Monitoring.................................11-3 3. No Contamination Detected

Wilcock, William

104

Safe Use of Radioactive Materials Procedure: 7.542 Created: 3/7/2014  

E-Print Network [OSTI]

-level radioactive waste and still provide for ease of decontamination. Trays made of impervious material (iSafe Use of Radioactive Materials Procedure: 7.542 Created: 3/7/2014 Version: 1.0 Revised of radioactive materials (RAM). They are designed to reduce the risk of a significant contamination event

Jia, Songtao

105

System for chemically digesting low level radioactive, solid waste material  

DOE Patents [OSTI]

An improved method and system for chemically digesting low level radioactive, solid waste material having a high through-put. The solid waste material is added to an annular vessel (10) substantially filled with concentrated sulfuric acid. Concentrated nitric acid or nitrogen dioxide is added to the sulfuric acid within the annular vessel while the sulfuric acid is reacting with the solid waste. The solid waste is mixed within the sulfuric acid so that the solid waste is substantilly fully immersed during the reaction. The off gas from the reaction and the products slurry residue is removed from the vessel during the reaction.

Cowan, Richard G. (Kennewick, WA); Blasewitz, Albert G. (Richland, WA)

1982-01-01T23:59:59.000Z

106

Radioactive Material Use at the EMSL Radiochemistry Annex The EMSL Radiochemistry Annex, located in the 3410 Material Science and  

E-Print Network [OSTI]

contamination during transportation. Dispersible radioactive material must be placed in rigid, leak- tight inner be sufficient such that EMSL staff will not encounter radioactive contamination when they open the shippingRadioactive Material Use at the EMSL Radiochemistry Annex The EMSL Radiochemistry Annex, located

107

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

Science Journals Connector (OSTI)

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

Anar S. Baweja; Bliss L. Tracy

2008-01-01T23:59:59.000Z

108

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

SciTech Connect (OSTI)

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

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

2008-08-07T23:59:59.000Z

109

Depleted uranium disposition study -- Supplement, Revision 1  

SciTech Connect (OSTI)

The Department of Energy Office of Weapons and Materials Planning has requested a supplemental study to update the recent Depleted Uranium Disposition report. This supplemental study addresses new disposition alternatives and changes in status.

Becker, G.W.

1993-11-01T23:59:59.000Z

110

INTRODUCTION In every laboratory where radioactive materials are utilized, it is necessary to maintain a  

E-Print Network [OSTI]

) in their work habits and to minimize the potential for exposures, contamination or release of radioactiveINTRODUCTION In every laboratory where radioactive materials are utilized, it is necessary of Texas the privilege of using large varieties of radioactive materials. Large amounts of activity

111

Best Practices for the Security of Radioactive Materials  

SciTech Connect (OSTI)

This work is funded under a grant provided by the US Department of Health and Human Services, Centers for Disease Control. The Department of Health and Mental Hygiene (DOHMH) awarded a contract to Brookhaven National Laboratory (BNL) to develop best practices guidance for Office of Radiological Health (ORH) licensees to increase on-site security to deter and prevent theft of radioactive materials (RAM). The purpose of this document is to describe best practices available to manage the security of radioactive materials in medical centers, hospitals, and research facilities. There are thousands of such facilities in the United States, and recent studies suggest that these materials may be vulnerable to theft or sabotage. Their malevolent use in a radiological-dispersion device (RDD), viz., a dirty bomb, can have severe environmental- and economic- impacts, the associated area denial, and potentially large cleanup costs, as well as other effects on the licensees and the public. These issues are important to all Nuclear Regulatory Commission and Agreement State licensees, and to the general public. This document outlines approaches for the licensees possessing these materials to undertake security audits to identify vulnerabilities in how these materials are stored or used, and to describe best practices to upgrade or enhance their security. Best practices can be described as the most efficient (least amount of effort/cost) and effective (best results) way of accomplishing a task and meeting an objective, based on repeatable procedures that have proven themselves over time for many people and circumstances. Best practices within the security industry include information security, personnel security, administrative security, and physical security. Each discipline within the security industry has its own 'best practices' that have evolved over time into common ones. With respect to radiological devices and radioactive-materials security, industry best practices encompass both physical security (hardware and engineering) and administrative procedures. Security regimes for these devices and materials typically use a defense-in-depth- or layered-security approach to eliminate single points of failure. The Department of Energy, the Department of Homeland Security, the Department of Defense, the American Society of Industrial Security (ASIS), the Security Industry Association (SIA) and Underwriters Laboratory (UL) all rovide design guidance and hardware specifications. With a graded approach, a physical-security specialist can tailor an integrated security-management system in the most appropriate cost-effective manner to meet the regulatory and non-regulatory requirements of the licensee or client.

Coulter, D.T.; Musolino, S.

2009-05-01T23:59:59.000Z

112

TYPE B RADIOACTIVE MATERIAL PACKAGE FAILURE MODES AND CONTENTS COMPLIANCE  

SciTech Connect (OSTI)

Type B radioactive material package failures can occur due to any one of the following: inadequate design, manufacture, and maintenance of packages, load conditions beyond those anticipated in the regulations, and improper package loading and operation. The rigorous package design evaluations performed in the certification process, robust package manufacture quality assurance programs, and demanding load conditions prescribed in the regulations are all well established. This paper focuses on the operational aspects of Type B package loading with respect to an overbatch which may cause a package failure.

Watkins, R; Steve Hensel, S; Allen Smith, A

2007-02-21T23:59:59.000Z

113

THERMAL UPGRADING OF 9977 RADIOACTIVE MATERIAL (RAM) TYPE B PACKAGE  

SciTech Connect (OSTI)

The 9977 package is a radioactive material package that was originally certified to ship Heat Sources and RTG contents up to 19 watts and it is now being reviewed to significantly expand its contents in support of additional DOE missions. Thermal upgrading will be accomplished by employing stacked 3013 containers, a 3013 aluminum spacer and an external aluminum sleeve for enhanced heat transfer. The 7th Addendum to the original 9977 package Safety Basis Report describing these modifications is under review for the DOE certification. The analyses described in this paper show that this well-designed and conservatively analyzed package can be upgraded to carry contents with decay heat up to 38 watts with some simple design modifications. The Model 9977 package has been designed as a replacement for the Department of Transportation (DOT) Fissile Specification 6M package. The 9977 package is a very versatile Type B package which is certified to transport and store a wide spectrum of radioactive materials. The package was analyzed quite conservatively to increase its usefulness and store different payload configurations. Its versatility is evident from several daughter packages such as the 9978 and H1700, and several addendums where the payloads have been modified to suit the Shipper's needs without additional testing.

Gupta, N.; Abramczyk, G.

2012-03-26T23:59:59.000Z

114

Savannah River Site Waste Disposition Project  

Broader source: Energy.gov (indexed) [DOE]

Terrel J. Spears Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste Disposition Project 2 Waste Disposition Project - Mission Radioactive Liquid Waste - Tank Waste Stabilization and Disposition - Disposition 36 million gallons of radioactive liquid waste - Close 49 underground storage tanks in which the waste now resides 3 36.7 Million 33.7 Mgal (92%) 3.0 Mgal (8%) Saltcake Sludge Salt Supernate Volume Curies 397 Million Curies (MCi) 212 MCi (54%) 185 MCi (46%) Gallons (Mgal) 36.5 Million 33.5 Mgal (92%) 3.0 Mgal (8%) Liquid Waste Background Liquid Waste Background * 2 tanks closed * 49 tanks remaining to close - aging, carbon steel - 27 compliant, 22 non-compliant - 12 have known leak sites

115

NEW APPROACH TO ADDRESSING GAS GENERATION IN RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect (OSTI)

Safety Analysis Reports for Packaging (SARP) document why the transportation of radioactive material is safe in Type A(F) and Type B shipping containers. The content evaluation of certain actinide materials require that the gas generation characteristics be addressed. Most packages used to transport actinides impose extremely restrictive limits on moisture content and oxide stabilization to control or prevent flammable gas generation. These requirements prevent some users from using a shipping container even though the material to be shipped is fully compliant with the remaining content envelope including isotopic distribution. To avoid these restrictions, gas generation issues have to be addressed on a case by case basis rather than a one size fits all approach. In addition, SARP applicants and review groups may not have the knowledge and experience with actinide chemistry and other factors affecting gas generation, which facility experts in actinide material processing have obtained in the last sixty years. This paper will address a proposal to create a Gas Generation Evaluation Committee to evaluate gas generation issues associated with Safety Analysis Reports for Packaging material contents. The committee charter could include reviews of both SARP approved contents and new contents not previously evaluated in a SARP.

Watkins, R; Leduc, D; Askew, N

2009-06-25T23:59:59.000Z

116

SRS - Programs - Liquid Waste Disposition  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

117

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect (OSTI)

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

118

THERMAL PERFORMANCE OF RADIOACTIVE MATERIAL PACKAGES IN TRANSPORT CONFIGURATION  

SciTech Connect (OSTI)

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR Part 71. The packages are transported in specially designed vehicles like Safe Secure Transport (SST) for safety and security. In the transport vehicles, the packages are placed close to each other to maximize the number of units in the vehicle. Since the RAM contents in the packagings produce decay heat, it is important that they are spaced sufficiently apart to prevent overheating of the containment vessel (CV) seals and the impact limiter to ensure the structural integrity of the package. This paper presents a simple methodology to assess thermal performance of a typical 9975 packaging in a transport configuration.

Gupta, N.

2010-03-04T23:59:59.000Z

119

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

120

Integrated Facilities Disposition Program  

Broader source: Energy.gov (indexed) [DOE]

Facilities Facilities Disposition Program Tank Waste Corporate Board Meeting at ORNL Sharon Robinson Dirk Van Hoesen Robert Jubin Brad Patton July 29, 2009 2 Managed by UT-Battelle for the U.S. Department of Energy The Integrated Facility Disposition Program (IFDP) addresses the remaining EM Scope at both ORNL and Y-12 Cost Range: $7 - $14B Schedule: 26 Years 3 Managed by UT-Battelle for the U.S. Department of Energy Scope of work * Treatment and disposition of legacy materials and waste * D&D 327 (1.5 M ft 2 ) excess facilities generating >2 M yd 3 debris * Soil and groundwater remedial actions generating >1 M yd 3 soils * Facilities surveillance and maintenance * Reconfiguration of waste management facilities * Ongoing waste management operations * Project management

Note: This page contains sample records for the topic "disposition radioactive materials" 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

INSTRUCTIONS FOR OPENING RADIONUCLIDE SHIPMENTS All packages containing radioactive material are physically received at the Department of Environmental  

E-Print Network [OSTI]

are monitored and contamination of the package exterior is assessed. The radioactive stock vialINSTRUCTIONS FOR OPENING RADIONUCLIDE SHIPMENTS All packages containing radioactive material radionuclide packages. GENERAL PROCEDURES 1. Radioactive packages must be opened and inspected as soon

Firestone, Jeremy

122

SSRL Radioactive Material Sample Holder Catalog 5/30/14 Page 1 of 17  

E-Print Network [OSTI]

SSRL Radioactive Material Sample Holder Catalog 5/30/14 Page 1 of 17 Hazard Class Category finger under vacuum #12;SSRL Radioactive Material Sample Holder Catalog 5/30/14 Page 2 of 17 1.d USGS polyethylene envelopes. Check for no contamination of each envelope. - External envelope glued onto the cell

Wechsler, Risa H.

123

Albert Einstein College of Medicine Amendment to Non-human Use of Radioactive Material License  

E-Print Network [OSTI]

RSO-2 Rev.0 Albert Einstein College of Medicine Amendment to Non-human Use of Radioactive Material License INSTRUCTIONS: If you wish to make changes to your license to use radioactive material please exposure; Glove box: Mechanical pipettes: Fume hood: Absorbent liner & Tray Shielding: Lead: Lucite: GM

Emmons, Scott

124

Records Disposition  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its management and operating contractors. Cancels DOE O 1324.2 dated 5-28-80. Chg 1 dated 4-9-92. Canceled by DOE O 1324.2B dated 1-12-95.

1988-09-13T23:59:59.000Z

125

PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 |  

Broader source: Energy.gov (indexed) [DOE]

PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 The objective of this surveillance is to evaluate the effectiveness of the contractor's programs, policies, and procedures to transport radioactive and hazardous materials off-site or to receive such materials for routine operations, treatment, storage, or disposal. The Facility Representative observes preparation of materials for shipment and receipt of materials and reviews specific documents to determine compliance with requirements imposed by DOE and by applicable regulations from the U.S. Nuclear Regulatory Commission and the Department of Transportation. PTS13-01.doc More Documents & Publications Order Module--DOE O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, DOE O

126

U.S. Department of Energy Guidelines for Residual Radioactive Material at  

Broader source: Energy.gov (indexed) [DOE]

U.S. Department of Energy Guidelines for Residual Radioactive U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) More Documents & Publications

127

U.S. Department of Energy Guidelines for Residual Radioactive Material at  

Broader source: Energy.gov (indexed) [DOE]

U.S. Department of Energy Guidelines for Residual Radioactive U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) More Documents & Publications

128

Records Disposition  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its operating and onsite service contractors. Cancels DOE O 1324.1 dated 7-10-78. Chg 1 dated 7-2-81. Chg 2 dated 11-9-82. Canceled by DOE O 1324.2A dated 9-13-88.

1980-05-28T23:59:59.000Z

129

Plutonium Disposition Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plutonium Disposition Program Plutonium Disposition Program Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition > Plutonium Disposition Program Plutonium Disposition Program The U.S.-Russia Plutonium Management and Disposition Agreement (PMDA), which entered into force on July 13, 2011, commits each country to dispose of at least 34 metric tons (MT) of weapon-grade plutonium withdrawn from their respective nuclear weapon programs. The U.S. remains firmly committed to its PMDA obligation to dispose of excess weapons plutonium. U.S. Plutonium Disposition The current U.S. plan to dispose of 34 MT of weapon-grade plutonium is to fabricate it into Mixed Oxide (MOX) fuel and irradiate it in existing light water reactors. This approach requires construction of new facilities

130

Disposition of excess highly enriched uranium status and update  

SciTech Connect (OSTI)

This paper presents the status of the US DOE program charged with the disposition of excess highly enriched uranium (HEU). Approximately 174 metric tonnes of HEU, with varying assays above 20 percent, has been declared excess from US nuclear weapons. A progress report on the identification and characterization of specific batches of excess HEU is provided, and plans for processing it into commercial nuclear fuel or low-level radioactive waste are described. The resultant quantities of low enriched fuel material expected from processing are given, as well as the estimated schedule for introducing the material into the commercial reactor fuel market. 2 figs., 3 tabs.

Williams, C.K. III; Arbital, J.G.

1997-09-01T23:59:59.000Z

131

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

132

Albert Einstein College of Medicine Application for Non-human Use of Radioactive Material  

E-Print Network [OSTI]

RSO-1 Rev.0 Albert Einstein College of Medicine Application for Non-human Use of Radioactive pipettes: Fume hood: Absorbent liner & Tray Shielding: Lead: Lucite: GM survey meter: Handling tongs radioactive material is secure against unauthorized access: 9. Please check the type of application below

Emmons, Scott

133

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01T23:59:59.000Z

134

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

135

Storage systems and containers for radioactive materials. February 1971-November 1989 (a Bibliography from the US Patent data base). Report for February 1971-November 1989  

SciTech Connect (OSTI)

This bibliography contains citations of selected patents concerning container designs for storage, shipping, and handling of radioactive materials. Storage equipment and devices such as sheilding, racks, covers, seals, packing materials, and filling systems for containerized radioactive materials are considered. Radioactive materials considered include nuclear fuels, spent fuels, radioactive wastes, and radioactive research materials. High- and low-level radioactive materials are included. (Contains 139 citations fully indexed and including a title list.)

Not Available

1990-03-01T23:59:59.000Z

136

DOE/EA-1651: FINDING OF NO SIGNIFICANT IMPACT Uranium-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (01/13/10)  

Broader source: Energy.gov (indexed) [DOE]

URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory [DOE/EA-1651]. This environmental assessment (EA) evaluates the impacts of planned activities to modify selected Oak Ridge National Laboratory (ORNL) facilities; process the ORNL inventory of uranium-233 (U-233); and transport the processed material to a long-term disposal facility. Small quantities of similar material currently stored at other DOE sites may also be included in this initiative. The

137

Surveillance Guides - PTS 13.1 Radioactive And Hazardous Material Transportation  

Broader source: Energy.gov (indexed) [DOE]

RADIOACTIVE AND HAZARDOUS MATERIALS TRANSPORTATION RADIOACTIVE AND HAZARDOUS MATERIALS TRANSPORTATION 1.0 Objective The objective of this surveillance is to evaluate the effectiveness of the contractor's programs, policies, and procedures to transport radioactive and hazardous materials off-site or to receive such materials for routine operations, treatment, storage, or disposal. The Facility Representative observes preparation of materials for shipment and receipt of materials and reviews specific documents to determine compliance with requirements imposed by DOE and by applicable regulations from the U.S. Nuclear Regulatory Commission and the Department of Transportation. 2.0 References DOE O 460.1A, Packaging and Transportation Safety DOE O 460.2, Chg1, Departmental Materials Transportation and Packaging

138

Alternative technical summary report for direct disposition in deep boreholes: Direct disposal of plutonium metal/plutonium dioxide in compound canisters, Version 4.0. Fissile Materials Disposition Program  

SciTech Connect (OSTI)

This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

139

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

E-Print Network [OSTI]

This thesis addresses the problem of removal of Naturally Occurring Radioactive Materials, NORM, and describes an effective alternative to the current treatment method for their removal. High-pen-meability fracturing, recently established...

Demarchos, Andronikos Stavros

2012-06-07T23:59:59.000Z

140

Ion-exchange material and method of storing radioactive wastes  

DOE Patents [OSTI]

A new cation exchanger is a modified tobermorite containing aluminum isomorphously substituted for silicon and containing sodium or potassium. The exchanger is selective for lead, rubidium, cobalt, and cadmium and is selective for cesium over calcium or sodium. The tobermorites are compatible with cement and are useful for the long-term fixation and storage of radioactive nuclear wastes.

Komarneni, S.; Roy, D.M.

1983-10-31T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

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

SciTech Connect (OSTI)

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

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

1989-01-01T23:59:59.000Z

142

Fissile Material Disposition Program: Deep borehole disposal Facility PEIS date input report for immobilized disposal. Immobilized disposal of plutonium in coated ceramic pellets in grout with canisters. Version 3.0  

SciTech Connect (OSTI)

Following President Clinton`s Non-Proliferation Initiative, launched in September, 1993, an Interagency Working Group (IWG) was established to conduct a comprehensive review of the options for the disposition of weapons-usable fissile materials from nuclear weapons dismantlement activities in the United States and the former Soviet Union. The IWG review process will consider technical, nonproliferation, environmental budgetary, and economic considerations in the disposal of plutonium. The IWG is co-chaired by the White House Office of Science and Technology Policy and the National Security Council. The Department of Energy (DOE) is directly responsible for the management, storage, and disposition of all weapons-usable fissile material. The Department of Energy has been directed to prepare a comprehensive review of long-term options for Surplus Fissile Material (SFM) disposition, taking into account technical, nonproliferation, environmental, budgetary, and economic considerations.

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15T23:59:59.000Z

143

Fast Neutron Radioactivity and Damage Studies on Materials  

E-Print Network [OSTI]

Materials We know that binary Sm x Co y compounds are more radi- ation resistant and have better thermal

Spencer, J.; Anderson, S. D.; Wolf, Z.; Volk, J. T.; Pellett, D.; Boussoufi, M.

2007-01-01T23:59:59.000Z

144

Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program  

SciTech Connect (OSTI)

This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

145

Shipment of Small Quantities of Unspecified Radioactive Material in Chalfant Packagings  

SciTech Connect (OSTI)

In the post 6M era, radioactive materials package users are faced with the disciplined operations associated with use of Certified Type B packagings. Many DOE, commercial and academic programs have a requirement to ship and/or store small masses of poorly characterized or unspecified radioactive material. For quantities which are small enough to be fissile exempt and have low radiation levels, the materials could be transported in a package which provides the required containment level. Because their Chalfant type containment vessels meet the highest standard of containment (helium leak-tight), the 9975, 9977, and 9978 are capable of transporting any of these contents. The issues associated with certification of a high-integrity, general purpose package for shipping small quantities of unspecified radioactive material are discussed and certification of the packages for this mission is recommended.

Smith, Allen; Abramczyk, Glenn; Nathan, Steven; Bellamy, Steve

2009-06-12T23:59:59.000Z

146

U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material  

Broader source: Energy.gov (indexed) [DOE]

Works With Kazakhstan to Stop Nuclear and Radioactive Material Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling May 6, 2006 - 10:34am Addthis WASHINGTON, DC - As part of the overall U.S. strategy to prevent nuclear and dangerous radiological materials from falling into the hands of terrorists, the Department of Energy's National Nuclear Security Administration (NNSA) announced today that an agreement with the government of Kazakhstan had been signed to create a partnership under the Second Line of Defense program. U.S. Ambassador Ordway joined Kazakhstan Customs Control Committee Chairman Askar Shakirov in signing the accord. The agreement will pave the way for NNSA to work collaboratively with the Kazakhstan Customs Control Committee

147

Disposition Schedules | Department of Energy  

Office of Environmental Management (EM)

Disposition Schedules Disposition Schedules The DOE Records Disposition Schedules provide the authority for the transfer, or disposal of records created and maintained by the...

148

U.S. DEPARTMENT OF ENERGY GUIDELINES FOR RESIDUAL RADIOACTIVE MATERIAL AT  

Broader source: Energy.gov (indexed) [DOE]

I I U.S. DEPARTMENT OF ENERGY GUIDELINES FOR RESIDUAL RADIOACTIVE MATERIAL AT FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM AHD REMOTE SURPLUS FACILITIES MANAGEMENT PROGRAM SITES (Revision 2, March 1987) A. INTRODUCTION This document presents U.S. Department of Energy (DOE) radiological protection guidelines for cleanup of residual radioactive material and management of the resulting wastes and residues. It is applicable to si~es - "C-- identified by the Formerly Utilized Sites l{emedia1 Ac:tionProgram (FUSRAP) .and remote sites identified by the Surplus Facilities Management Program (SFMP).* The topics covered are basic dose limits, guidelines and authorized limits for allowable levels of residual radioactive material, and requirements for

149

EIS-0327: Disposition of Scrap Metals Programmatic EIS  

Broader source: Energy.gov [DOE]

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

150

Fluorescent Functionalized Mesoporous Silica for Radioactive Material Extraction  

SciTech Connect (OSTI)

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

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

2012-08-01T23:59:59.000Z

151

Gamma motes for detection of radioactive materials in shipping containers  

SciTech Connect (OSTI)

Shipping containers can be effectively monitored for radiological materials using gamma (and neutron) motes in distributed mesh networks. The mote platform is ideal for collecting data for integration into operational management systems required for efficiently and transparently monitoring international trade. Significant reductions in size and power requirements have been achieved for room-temperature cadmium zinc telluride (CZT) gamma detectors. Miniaturization of radio modules and microcontroller units are paving the way for low-power, deeply-embedded, wireless sensor distributed mesh networks.

Harold McHugh; William Quam; Stephan Weeks; Brendan Sever

2007-04-13T23:59:59.000Z

152

Physical test report for drop test of a 9974 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9974 radioactive material shipping package being dropped onto 6-inch diameter, 40-inch long puncture pin. Also reported are the drop test resuls for a 30-foot impact that failed the drum confinement boundary. The purpose of these drops was to show that the package lid would remain attached to the drum.

Blanton, P.S. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-10-01T23:59:59.000Z

153

Radcalc: An Analytical Tool for Shippers of Radioactive Material and Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) ships radioactive materials in support of its research and development, environmental restoration, and national defense activities. The Radcalc software program assists personnel working on behalf of DOE in packaging and transportation determinations (e.g., isotopic decay, decay heat, regulatory classification, and gas generation) for shipment of radioactive materials and waste. Radcalc performs: - The U.S. Department of Transportation determinations and classifications (i.e., activity concentration for exempt material Type A or B, effective A1/A2, limited quantity, low specific activity, highway route controlled quantity, fissile quantity, fissile excepted, reportable quantity, list of isotopes required on shipping papers) - DOE calculations (i.e., transuranic waste, Pu-239 equivalent curies, fissile-gram equivalents) - The U.S. Nuclear Regulatory Commission packaging category (i.e., Category I, II, or III) - Dose-equivalent curie calculations - Radioactive decay calculations using a novel decay methodology and a decay data library of 1,867 isotopes typical of the range of materials encountered in DOE laboratory environments - Hydrogen and helium gas calculations - Pressure calculations. Radcalc is a validated and cost-effective tool to provide consistency, accuracy, reproducibility, timeliness, quality, compliance, and appropriate documentation to shippers of radioactive materials and waste at DOE facilities nationwide. Hundreds of shippers and engineers throughout the DOE Complex routinely use this software to automate various determinations and to validate compliance with the regulations. The effective use of software by DOE sites contributes toward minimizing risk involved in radioactive waste shipments and assuring the safety of workers and the public. (authors)

Kapoor, A.K. [U.S. Department of Energy, Office of Transportation, Washington, DC (United States); Stuhl, L.A. [EnergySolutions Federal Services, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

154

Request For Records Disposition | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Request For Records Disposition Southeastern Power Administration (SEPA) Request For Records Disposition More Documents & Publications Audit...

155

Combustion aerosols formed during burning of radioactively contaminated materials: Experimental results  

SciTech Connect (OSTI)

Safety assessments and environmental impact statements for nuclear fuel cycle facilities require an estimate of potential airborne releases. Radioactive aerosols generated by fires were investigated in experiments in which combustible solids and liquids were contaminated with radioactive materials and burned. Uranium in powder and liquid form was used to contaminate five fuel types: polychloroprene, polystyrene, polymethylmethacrylate, cellulose, and a mixture of 30% tributylphosphate (TBP) in kerosene. Heat flux, oxygen concentration, air flow, contaminant concentration, and type of ignition were varied in the experiments. The highest release (7.1 wt %) came from burning TBP/kerosene over contaminated nitric acid. Burning cellulose contaminated with uranyl nitrate hexahydrate liquid gave the lowest release (0.01 wt %). Rate of release and particle size distribution of airborne radioactive particles were highly dependent on the type of fuel burned.

Halverson, M.A.; Ballinger, M.Y.; Dennis, G.W.

1987-03-01T23:59:59.000Z

156

APPLICATION FO FLOW FORMING FOR USE IN RADIOACTIVE MATERIAL PACKAGING DESIGNS  

SciTech Connect (OSTI)

This paper reports on the development and testing performed to demonstrate the use of flow forming as an alternate method of manufacturing containment vessels for use in radioactive material shipping packaging designs. Additionally, ASME Boiler and Pressure Vessel Code, Section III, Subsection NB compliance along with the benefits compared to typical welding of containment vessels will be discussed. SRNL has completed fabrication development and the testing on flow formed containment vessels to demonstrate the use of flow forming as an alternate method of manufacturing a welded 6-inch diameter containment vessel currently used in the 9975 and 9977 radioactive material shipping packaging. Material testing and nondestructive evaluation of the flow formed parts demonstrate compliance to the minimum material requirements specified in applicable parts of ASME Boiler and Pressure Vessel Code, Section II. Destructive burst testing shows comparable results to that of a welded design. The benefits of flow forming as compared to typical welding of containment vessels are significant: dimensional control is improved due to no weld distortion; less final machining; weld fit-up issues associated with pipes and pipe caps are eliminated; post-weld non-destructive testing (i.e., radiography and die penetrant tests) is not necessary; and less fabrication steps are required. Results presented in this paper indicate some of the benefits in adapting flow forming to design of future radioactive material shipping packages containment vessels.

Blanton, P.; Eberl, K.; Abramczyk, G.

2012-07-11T23:59:59.000Z

157

Surplus Highly Enriched Uranium Disposition Program plan  

SciTech Connect (OSTI)

The purpose of this document is to provide upper level guidance for the program that will downblend surplus highly enriched uranium for use as commercial nuclear reactor fuel or low-level radioactive waste. The intent of this document is to outline the overall mission and program objectives. The document is also intended to provide a general basis for integration of disposition efforts among all applicable sites. This plan provides background information, establishes the scope of disposition activities, provides an approach to the mission and objectives, identifies programmatic assumptions, defines major roles, provides summary level schedules and milestones, and addresses budget requirements.

NONE

1996-10-01T23:59:59.000Z

158

Radioactive materials released from nuclear power plants: Annual report, 1993. Volume 14  

SciTech Connect (OSTI)

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1993 have been compiled and reported. The summary data for the years 1974 through 1992 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1993 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Tichler, J.; Doty, K.; Lucadamo, K. [Brookhaven National Lab., Upton, NY (United States)

1995-12-01T23:59:59.000Z

159

Real time method and computer system for identifying radioactive materials from HPGe gamma-ray spectroscopy  

DOE Patents [OSTI]

A real-time method and computer system for identifying radioactive materials which collects gamma count rates from a HPGe gamma-radiation detector to produce a high-resolution gamma-ray energy spectrum. A library of nuclear material definitions ("library definitions") is provided, with each uniquely associated with a nuclide or isotope material and each comprising at least one logic condition associated with a spectral parameter of a gamma-ray energy spectrum. The method determines whether the spectral parameters of said high-resolution gamma-ray energy spectrum satisfy all the logic conditions of any one of the library definitions, and subsequently uniquely identifies the material type as that nuclide or isotope material associated with the satisfied library definition. The method is iteratively repeated to update the spectrum and identification in real time.

Rowland, Mark S. (Alamo, CA); Howard, Douglas E. (Livermore, CA); Wong, James L. (Dublin, CA); Jessup, James L. (Tracy, CA); Bianchini, Greg M. (Livermore, CA); Miller, Wayne O. (Livermore, CA)

2007-10-23T23:59:59.000Z

160

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  

Broader source: Energy.gov (indexed) [DOE]

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

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Mixed-layered bismuth-oxygen-iodine materials for capture and waste disposal of radioactive iodine  

DOE Patents [OSTI]

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Krumhansl, James L; Nenoff, Tina M

2013-02-26T23:59:59.000Z

162

DOE Records Disposition Schedule Changes | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Records Disposition Schedule Changes DOE Records Disposition Schedule Changes Disposition Schedule Changes DOE Records Disposition Schedule Changes More Documents & Publications...

163

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

Broader source: Energy.gov (indexed) [DOE]

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

164

Closed source experimental system for soft x-ray spectroscopy of radioactive materials  

Science Journals Connector (OSTI)

An instrumental and experimental setup for soft x-rayspectroscopy meeting the requirements of a closed source for radioactivity is described. The system consists of a vacuum sealed cell containing the sample mounted on a tubing system to ensure compatibility with most standard manipulators. The soft x rays penetrate a thin x-ray window separating the interior of the cell from the vacuum in the experimental chamber. Our first results for single crystal PuO 2 confirm the feasibility of experiments using the setup. The results are consistent with results of first principles calculations and previously recorded spectra obtained using a standard open source setup. The results show that the closed source experimental system can be used to collect valuable experimental data from radioactive materials.

A. Modin; S. M. Butorin; J. Vegelius; A. Olsson; C.-J. Englund; J. Andersson; L. Werme; J. Nordgren; T. Kmbre; G. Skarnemark; B. E. Burakov

2008-01-01T23:59:59.000Z

165

ELUCIDATING THE DIFFERENCES BETWEEN ONSITE AND OFFSITE SHIPMENT OF RADIOACTIVE MATERIALS  

SciTech Connect (OSTI)

Federal regulations stipulate how radioactive materials are transported within the United States. However, the Department of Energy, under Department of Energy Order, has the authority to operate, within the boundaries of their physical site, to other stipulations. In many cases the DOE sites have internal reviews for onsite transfers that rival reviews performed by the regulatory authorities for offsite shipments. Most of the differences are in the level or type of packaging that is required, but in some cases it may be in the amount and type of material that is allowed to be transferred. This paper will describe and discuss those differences and it will discuss ways to effectively align the onsite rules for transferring materials with those for offsite shipment.

Loftin, B.; Watkins, R.

2013-06-19T23:59:59.000Z

166

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

SciTech Connect (OSTI)

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

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

1989-11-01T23:59:59.000Z

167

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

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

168

Experimental determination of the shipboard fire environment for simulated radioactive material packages  

SciTech Connect (OSTI)

A series of eight fire tests with simulated radioactive material shipping containers aboard the test ship Mayo Lykes, a break-bulk freighter, is described. The tests simulate three basic types of fires: engine room fires, cargo fires and open pool fires. Detailed results from the tests include temperatures, heat fluxes and air flows measured during the fires. The first examination of the results indicates that shipboard fires are not significantly different from fires encountered in land transport. 13 refs., 15 figs., 11 tabs.

Koski, J.A.; Bobbe, J.G.; Arviso, M. [and others

1997-03-01T23:59:59.000Z

169

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

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

170

Final Programmatic Environmental Assessment and Finding of No Significant Impact 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  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) proposes to implement a comprehensive management program to safely, efficiently, and effectively manage its potentially reusable low enriched uranium (LEU), normal uranium (NU), and depleted uranium (DU). Uranium materials, which are presently located at multiple sites, are to be consolidated by transporting the materials to one or several storage locations, to facilitate ultimate disposition. Management would include the storage, transport, and ultimate disposition of these materials. This action is needed because of DOE's current missions and functions; increasing budget pressures; the continuing need for good stewardship of resources, including materials in inventory; and continuing DOE attention to considerations of environment, safety, and health. Also, increased pressure on the federal budget requires that DOE take a closer look at materials management in order to ensure maximum cost effectiveness. This includes an examination of feasible uses of this material, consistent with DOE's mission, as well as an examination of management methods that are consistent with environmental requirements and budgetary constraints. DOE needs to implement a long-term (greater than 20 years) management plan for its inventory of potentially reusable LEU, NU, and DU.

N /A

2002-10-16T23:59:59.000Z

171

Evaluation of exposure pathways to man from disposal of radioactive materials into sanitary sewer systems  

SciTech Connect (OSTI)

In accordance with 10 CFR 20, the US Nuclear Regulatory Commission (NRC) regulates licensees` discharges of small quantities of radioactive materials into sanitary sewer systems. This generic study was initiated to examine the potential radiological hazard to the public resulting from exposure to radionuclides in sewage sludge during its treatment and disposal. Eleven scenarios were developed to characterize potential exposures to radioactive materials during sewer system operations and sewage sludge treatment and disposal activities and during the extended time frame following sewage sludge disposal. Two sets of deterministic dose calculations were performed; one to evaluate potential doses based on the radionuclides and quantities associated with documented case histories of sewer system contamination and a second, somewhat more conservative set, based on theoretical discharges at the maximum allowable levels for a more comprehensive list of 63 radionuclides. The results of the stochastic uncertainty and sensitivity analysis were also used to develop a collective dose estimate. The collective doses for the various radionuclides and scenarios range from 0.4 person-rem for {sup 137}Cs in Scenario No. 5 (sludge incinerator effluent) to 420 person-rem for {sup 137}Cs in Scenario No. 3 (sewage treatment plant liquid effluent). None of the 22 scenario/radionuclide combinations considered have collective doses greater than 1000 person-rem/yr. However, the total collective dose from these 22 combinations was found to be about 2100 person-rem.

Kennedy, W.E. Jr.; Parkhurst, M.A.; Aaberg, R.L.; Rhoads, K.C.; Hill, R.L.; Martin, J.B. [Pacific Northwest Lab., Richland, WA (United States)

1992-05-01T23:59:59.000Z

172

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR GENERAL PURPOSE RADIOACTIVE MATERIALS PACKAGINGS  

SciTech Connect (OSTI)

Polyurethane foam has been employed in impact limiters for large radioactive materials packagings since the early 1980's. Its consistent crush response, controllable structural properties and excellent thermal insulating characteristics have made it attractive as replacement for the widely used cane fiberboard for smaller, drum size packagings. Accordingly, polyurethane foam was chosen for the overpack material for the 9977 and 9978 packagings. The study reported here was undertaken to provide data to support the analyses performed as part of the development of the 9977 and 9978, and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2009-02-18T23:59:59.000Z

173

GOLDSIM models of long-term radiation impact of conditionally cleared radioactive material  

Science Journals Connector (OSTI)

Abstract Management of waste materials from the decommissioning of nuclear installations offers opportunities for optimization. Large amounts of waste materials with low contents of various radionuclides could be recycled to save financial resources or repository capacity. The increase of the share of recycled materials compared to the current practice could be accomplished by applying the conditional clearance concept. Conditional clearance, as up to now is an unproven theoretical concept, demands utilization of the cleared material for the previously defined purpose (e.g., building construction). Safety studies needed for realization of this practice have to prove that conditionally cleared material will not cause radiation impact exceeding levels prescribed in health and safety regulations. Safety studies assess radiation impact during all manipulations with low level radioactive material (e.g., melting, component manufacturing, building of construction, etc.) as well as its impact on inhabitants living near the construction built using conditionally cleared material. The article is focused on modeling and calculation of long-term radiation impact on inhabitants living near the constructions. Models (scenarios) of various building applications were simulated using GOLDSIM software with Radionuclide Transport Module. Scenarios were selected according to information from the civil engineering business to cover the types of buildings most suitable for application of conditionally cleared material. The results of the calculations showed that conditional clearance represents no significant safety issue in the long-term. Calculated individual effective doses received by inhabitants did not exceed the given dose constraint (10?Sv/year) in case of any scenario evaluated. Detailed and transparent studies of the long-term impact of conditionally cleared materials are important especially for winning of public acceptance.

Michal Panik; Vladimir Necas

2013-01-01T23:59:59.000Z

174

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

Broader source: Energy.gov (indexed) [DOE]

Assessment of the Integrated Facility Disposition Project at Oak Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

175

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

Broader source: Energy.gov (indexed) [DOE]

the Integrated Facility Disposition Project at Oak the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

176

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers  

SciTech Connect (OSTI)

Six alloys are being considered as possible materials for the fabrication of containers for the disposal of high-level radioactive waste. Three of these candidate materials are copper-based alloys: CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The other three are iron- to nickel-based austenitic materials: Types 304L and 316L stainless steels and Alloy 825. Radioactive waste will include spent-fuel assemblies from reactors as well as waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The waste-package containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr. During the first 50 yr after emplacement, the containers must be retrievable from the disposal site. Shortly after emplacement of the containers in the repository, they will be exposed to high temperatures and high gamma radiation fields from the decay of high-level waste. This radiation will promote the radiolytic decomposition of moist air to hydrogen. This volume surveys the available data on the effects of hydrogen on the six candidate alloys for fabrication of the containers. For copper, the mechanism of hydrogen embrittlement is discussed, and the effects of hydrogen on the mechanical properties of the copper-based alloys are reviewed. The solubilities and diffusivities of hydrogen are documented for these alloys. For the austenitic materials, the degradation of mechanical properties by hydrogen is documented. The diffusivity and solubility of hydrogen in these alloys are also presented. For the copper-based alloys, the ranking according to resistance to detrimental effects of hydrogen is: CDA 715 (best) > CDA 613 > CDA 102 (worst). For the austenitic alloys, the ranking is: Type 316L stainless steel {approx} Alloy 825 > Type 304L stainless steel (worst). 87 refs., 19 figs., 8 tabs.

Gdowski, G.E.; Bullen, D.B. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-08-01T23:59:59.000Z

177

disposition | OpenEI  

Open Energy Info (EERE)

disposition disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035

178

The Evolution of U.S. Transportation Regulations for Radioactive Materials?A Retrospective  

SciTech Connect (OSTI)

The discussion in this Chapter is a highly condensed version of the information presented previously in Chapter 52 of the 2nd Edition of the Companion Guide to the ASME Boiler & Pressure Vessel Code.[1] The full text of the previous Chapter 52, i.e., Development of U.S. Regulations for the Transportation of Radioactive Materials - A Look Back over the Past 40 Years, could not be reproduced here. Therefore, this Chapter offers a high-level overview of the information presented previously, including all of the appropriate references. For the most part, the material that was not included in this version of Chapter 52 is available in the public domain. Due to the sheer volume of the information, readers interested in the preamble-only versions of the material referenced in this Chapter are redirected to Reference [1]. Readers interested in the full-text versions of the material referenced in this Chapter are redirected to the appropriate Federal Register and/or U.S. Nuclear Regulatory Commission (NRC) websites. Because some of the material dates back to pre-website times, readers interested in the full-text versions of some of the references may have to rely on the services of their local libraries.

Hafner, R

2008-04-28T23:59:59.000Z

179

Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177  

SciTech Connect (OSTI)

The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (?49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leaving the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)

Lindsay, Haile; Garcia-Santos, Norma; Saverot, Pierre; Day, Neil; Gambone Rodriguez, Kimberly; Cruz, Luis; Sotomayor-Rivera, Alexis; Vechioli, Lucieann; Vera, John; Pstrak, David [United States Nuclear Regulatory Commission, Mail Stop EBB-03D-02M, 6003 Executive Boulevard, Rockville, MD 20852 (United States)

2012-07-01T23:59:59.000Z

180

Request For Records Disposition | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Request For Records Disposition Spent Nuclear Fuels Request For Records Disposition More Documents & Publications The Report To The President And...

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Plutonium Disposition Program | National Nuclear Security Administration  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Home > Media Room > Fact Sheets > Plutonium Disposition Program Home > Media Room > Fact Sheets > Plutonium Disposition Program Fact Sheet Plutonium Disposition Program Jun 26, 2013 SUPPORTING NUCLEAR NONPROLIFERATION Weapon-grade plutonium and highly enriched uranium (HEU) are the critical ingredients for making a nuclear weapon. With the end of the Cold War, hundreds of tons of these materials were determined to be surplus to U.S. and Russian defense needs. Denying access to plutonium and HEU is the best way to prevent nuclear proliferation to rogue states and terrorist organizations. The most certain method to prevent these materials from falling into the wrong hands is to dispose of them. During the April 2010 Nuclear Security Summit, Secretary of State Hillary Rodham Clinton and Russian Foreign Minister Sergey Lavrov signed a protocol

182

Transportation requirements for the disposition of excess weapon plutonium by burning in fission reactors  

SciTech Connect (OSTI)

Both the US and Russia are planning to dispose of about 50 Mg of excess weapon plutonium over a 25-year period. One option is to transfer the plutonium to Advanced Light Water (power) Reactors (ALWRs) for use as fuel. Subsequent disposal would then be considered commercial spent fuel. This disposition option, like others, involves the transportation of plutonium in various material forms as it proceeds through various points in the recovery operation. This paper examines both the disposition option and the issues surrounding the transportation of 50 Mg of excess plutonium within the US under current regulatory and infrastructure constraints. Transportation issues include criticality control, shielding, and containment of the contents. Allowable limits on each of these issues are specified by the applicable (or selected) regulation. The composition and form of the radioactive materials to be transported will determine, in part, the applicable portions of the regulations as well as the packaging design. The regulations and the packaging design, along with safeguard and security issues, will determine the quantity of plutonium or fuel assemblies per package as well as the number of packages per shipment and the type of highway carrier. For the disposition of 50 Mg of weapon plutonium using ALWRs in a 25-year campaign, the annual shipment rates are determined for the various types of carriers.

Hovingh, J.; Walter, C.E.

1996-01-01T23:59:59.000Z

183

Ion implantation effects in insulators and the long-term stability of radioactive waste storage materials  

Science Journals Connector (OSTI)

Most insulator materials so far proposed for storing high-level radioactive wastes, such as glass and and the constituent minerals of ceramics are nuclear track detectors. Lead ion implantation experiments show that such materials should be transformed into giant nuclear tracks, when the internal fluence of heavy recoils emitted during the ?-decay of actinide elements stored in them exceeds a critical value, which corresponds to an equivalent storage period of a few thousand years for the wastes expected from a pressurized water reactor. In contrast, actinide bearing minerals are much more stable against ?-recoil damage. As nuclear tracks are extremely chemical reactive, ?-recoil damage is expected to shorten the lifetime of storage materials such as glass and ceramics against dissolution in ground waters. Fortunately new nuclear track concepts are already yielding guidelines for predicting and improving the long-term stability of storage materials. The results of the present studies also bear on the physics of ion implantation phenomena an insulator targets exposed to high fluences of low energy ions.

J.C. Dran; Y. Langevin; M. Maurette; J.C. Petit; B. Vassent

1981-01-01T23:59:59.000Z

184

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

Science Journals Connector (OSTI)

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

D Read; G D Read; M C Thorne

2013-01-01T23:59:59.000Z

185

Manual for implementing residual radioactive material guidelines using RESRAD, Version 5.0  

SciTech Connect (OSTI)

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus.

Yu, C.; Zielen, A.J.; Cheng, J.J. [and others

1993-09-01T23:59:59.000Z

186

Study on release and transport of aerial radioactive materials in reprocessing plants  

SciTech Connect (OSTI)

The release and transport characteristics of radioactive materials at a boiling accident of the high active liquid waste (HALW) in a reprocessing plant have been studied for improving experimental data of source terms of the boiling accident. In the study, a heating test and a thermogravimetry and differential thermal analysis (TG-DTA) test were conducted. In the heating test using a simulated HALW, it was found that ruthenium was mainly released into the air in the form of gas and that non-volatile elements were released into the air in the form of mist. In the TG-DTA test, the rate constants and reaction heat of thermal decomposition of ruthenium nitrosyl nitrate were obtained from TG and DTA curves. (authors)

Amano, Y.; Tashiro, S.; Uchiyama, G.; Abe, H.; Yamane, Y.; Yoshida, K. [Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki, 319-1195 (Japan); Kodama, T. [Japan Nuclear Fuel Ltd., 4-108 Okitsuke, Obuchi, Rokkasho-mura, Kamikita-gun, Aomori, 039-3212 (Japan)

2013-07-01T23:59:59.000Z

187

INVESTIGATION OF THE PRESENCE OF DRUGSTORE BEETLES WITHIN CELOTEX ASSEMBLIES IN RADIOACTIVE MATERIAL PACKAGINGS  

SciTech Connect (OSTI)

During normal operations at the Department of Energy's Hanford Site in Hanford, WA, drugstore beetles, (Stegobium paniceum (L.) Coleoptera: Anobiidae), were found within the fiberboard subassemblies of two 9975 Shipping Packages. Initial indications were that the beetles were feeding on the Celotex{trademark} assemblies within the package. Celotex{trademark} fiberboard is used in numerous radioactive material packages serving as both a thermal insulator and an impact absorber for both normal conditions of transport and hypothetical accident conditions. The Department of Energy's Packaging Certification Program (EM-63) directed a thorough investigation to determine if the drugstore beetles were causing damage that would be detrimental to the safety performance of the Celotex{trademark}. The Savannah River National Laboratory is conducting the investigation with entomological expertise provided by Clemson University. The two empty 9975 shipping packages were transferred to the Savannah River National Laboratory in the fall of 2007. This paper will provide details and results of the ongoing investigation.

Loftin, B; Glenn Abramczyk, G

2008-06-04T23:59:59.000Z

188

Demonstration of a computer model for residual radioactive material guidelines, RESRAD  

SciTech Connect (OSTI)

A computer model was developed to calculate residual radioactive material guidelines for the US Department of Energy (DOE). This model, called RESRAD, can be run on IBM or IBM-compatible microcomputer. Seven potential exposure pathways from contaminated soil are analyzed, including external radiation exposure and internal radiation exposure from inhalation and food digestion. The RESRAD code has been applied to several DOE sites to derive soil cleanup guidelines. The experience gained indicates that a comprehensive set of site-specific hydrogeologic and geochemical input parameters must be used for a realistic pathway analysis. The RESRAD code is a useful tool; it is easy to run and very user-friendly. 6 refs., 12 figs.

Yu, C.; Yuan, Y.C.; Zielen, A.J.; Wallo, A. III (Argonne National Lab., IL (USA); USDOE, Washington, DC (USA))

1989-01-01T23:59:59.000Z

189

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

Broader source: Energy.gov (indexed) [DOE]

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

190

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

Broader source: Energy.gov (indexed) [DOE]

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

191

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR RADIOACTIVE MATERIALS PACKAGINGS.  

SciTech Connect (OSTI)

Polyurethane foam has been widely used as an impact absorbing and thermal insulating material for large radioactive materials packages, since the 1980's. With the adoption of the regulatory crush test requirement, for smaller packages, polyurethane foam has been adopted as a replacement for cane fiberboard, because of its ability to withstand the crush test. Polyurethane foam is an engineered material whose composition is much more closely controlled than that of cane fiberboard. In addition, the properties of the foam can be controlled by controlling the density of the foam. The conditions under which the foam is formed, whether confined or unconfined have an affect on foam properties. The study reported here reviewed the application of polyurethane foam in RAM packagings and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2007-05-15T23:59:59.000Z

192

IMPACT OF TARGET MATERIAL ACTIVATION ON PERSONNEL EXPOSURE AND RADIOACTIVE CONTAMINATION IN THE NATIONAL IGNITION FACILITY  

SciTech Connect (OSTI)

Detailed activation analyses are performed for the different materials under consideration for use in the target capsules and hohlraums used during the ignition campaign on the National Ignition Facility. Results of the target material activation were additionally used to estimate the levels of contamination within the NIF target chamber and the workplace controls necessary for safe operation. The analysis examined the impact of using Be-Cu and Ge-doped CH capsules on the external dose received by workers during maintenance activities. Five days following a 20 MJ shot, dose rates inside the Target Chamber (TC) due to the two proposed capsule materials are small ({approx} 1 {micro}rem/h). Gold and depleted-uranium (DU) are considered as potential hohlraum materials. Following a shot, gold will most probably get deposited on the TC first wall. On the other hand, while noble-gas precursors from the DU are expected to stay in the TC, most of the noble gases are pumped out of the chamber and end up on the cryopumps. The dose rates inside the TC due to activated gold or DU, at 5 days following a 20 MJ shot, are about 1 mrem/h. Dose rates in the vicinity of the cryo-pumps (containing noble 'fission' gases) drop-off to about 1 mrem/h during the first 12 hours following the shot. Contamination from activation of NIF targets will result in the NIF target chamber exceeding DOE surface contamination limits. Objects removed from the TC will need to be managed as radioactive material. However, the results suggest that airborne contamination from resuspension of surface contamination will not be significant and is at levels that can be managed by negative ventilation when accessing the TC attachments.

Khater, H; Epperson, P; Thacker, R; Beale, R; Kohut, T; Brereton, S

2009-06-30T23:59:59.000Z

193

DEVELOPMENT OF A NEW TYPE A(F)RADIOACTIVE MATERIAL PACKAGING FOR THE DEPARTMENT OF ENERGY  

SciTech Connect (OSTI)

In a coordinated effort, the Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) proposed the elimination of the Specification Packaging from 49 CFR 173.[1] In accordance with the Federal Register, issued on October 1, 2004, new fabrication of Specification Packages would no longer be authorized. In accordance with the NRC final rulemaking published January 26, 2004, Specification Packagings are mandated by law to be removed from service no later than October 1, 2008. This coordinated effort and resulting rulemaking initiated a planned phase out of Specification Type B and Type A fissile (F) material transportation packages within the Department of Energy (DOE) and its subcontractors. One of the Specification Packages affected by this regulatory change is the UN1A2 Specification Package, per DOT 49 CFR 173.417(a)(6). To maintain continuing shipments of DOE materials currently transported in UN1A2 Specification Package after the existing authorization expires, a replacement Type A(F) material packaging design is under development by the Savannah River National Laboratory. This paper presents a summary of the prototype design effort and testing of the new Type A(F) Package development for the DOE. This paper discusses the progress made in the development of a Type A Fissile Packaging to replace the expiring 49 CFR UN1A2 Specification Fissile Package. The Specification Package was mostly a single-use waste disposal container. The design requirements and authorized radioactive material contents of the UN1A2 Specification Package were defined in 49 CFR. A UN1A2 Specification Package was authorized to ship up to 350 grams of U-235 in any enrichment and in any non-pyrophoric form. The design was specified as a 55-gallon 1A2 drum overpack with a body constructed from 18 gauge steel with a 16 gauge drum lid. Drum closure was specified as a standard 12-gauge ring closure. The inner product container size was not specified but was listed as any container that met Specification 7A requirements per 49 CFR 178.350. Specification 7A containers were required to withstand Type A packaging tests required by 49CFR173.465 with compliance demonstrated through testing, analysis or similarity to other containers. The maximum weight of the 7A product container, the radioactive content, and any internal packaging was limited to 200 lbs. The total gross weight for the UN1A2 Specification Package was limited to 350 lbs. No additional restrictions were applied. Authorization for use did not require the UN1A2 Specification Package to be tested to the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) required for performance based, Type A(F) packages certified by the NRC or DOE. The Type A(F) Packaging design discussed in this paper is required to be in compliance with the regulatory safety requirements defined in Code of Federal Regulations (CFR) 10 CFR 71.41 through 71.47 and 10 CFR71.71. Sub-criticality of content must be maintained under the Hypothetical Accident Conditions specified under 10 CFR71.73. These federal regulations, and other applicable DOE Orders and Guides, govern design requirements for a Type A(F) package. Type A(F) packages with less than an A2 quantity of radioactive material are not required to have a leak testable boundary. With this exception a Type A(F) package design is subject to the same test requirements set forth for the design of a performance based Type B packaging.

Blanton, P.; Eberl, K.

2008-09-14T23:59:59.000Z

194

Reactor-Based Plutonium Disposition: Opportunities, Options, and Issues  

SciTech Connect (OSTI)

The end of the Cold War has created a legacy of surplus fissile materials (plutonium and highly enriched uranium) in the United States (U.S.) and the former Soviet Union. These materials pose a danger to national and international security. During the past few years, the U.S. and Russia have engaged in an ongoing dialog concerning the safe storage and disposition of surplus fissile material stockpiles. In January 1997, the Department of Energy (DOE) announced the U. S. would pursue a dual track approach to rendering approximately 50 metric tons of plutonium inaccessible for use in nuclear weapons. One track involves immobilizing the plutonium by combining it with high-level radioactive waste in glass or ceramic ''logs''. The other method, referred to as reactor-based disposition, converts plutonium into mixed oxide (MOX) fuel for nuclear reactors. The U.S. and Russia are moving ahead rapidly to develop and demonstrate the technology required to implement the MOX option in their respective countries. U.S. MOX fuel research and development activities were started in the 1950s, with irradiation of MOX fuel rods in commercial light water reactors (LWR) from the 1960s--1980s. In all, a few thousand MOX fuel rods were successfully irradiated. Though much of this work was performed with weapons-grade or ''near'' weapons-grade plutonium--and favorable fuel performance was observed--the applicability of this data for licensing and use of weapons-grade MOX fuel manufactured with modern fuel fabrication processes is somewhat limited. The U.S. and Russia are currently engaged in an intensive research, development, and demonstration program to support implementation of the MOX option in our two countries. This paper focuses on work performed in the U.S. and provides a brief summary of joint U.S./Russian work currently underway.

Greene, S.R.

1999-07-17T23:59:59.000Z

195

Americium/Curium Disposition Life Cycle Planning Study  

SciTech Connect (OSTI)

At the request of the Department of Energy Savannah River Office (DOE- SR), Westinghouse Savannah River Company (WSRC) evaluated concepts to complete disposition of Americium and Curium (Am/Cm) bearing materials currently located at the Savannah River Site (SRS).

Jackson, W.N. [Westinghouse Savannah River Company, AIKEN, SC (United States); Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

1998-04-30T23:59:59.000Z

196

Materials performance in a high-level radioactive waste vitrification system  

SciTech Connect (OSTI)

The Defense Waste Processing Facility (DWPF) is a Department of Energy Facility designed to vitrify highly radioactive waste. An extensive materials evaluation program has been completed on key components in the DWPF after twelve months of operation using nonradioactive simulated wastes. Results of the visual inspections of the feed preparation system indicate that the system components, which were fabricated from Hastelloy C-276, should achieve their design lives. Significant erosion was observed on agitator blades that process glass frit slurries; however, design modifications should mitigate the erosion. Visual inspections of the DWPF melter top head and off gas components, which were fabricated from Inconel 690, indicated that varying degrees of degradation occurred. Most of the components will perform satisfactorily for their two year design life. The components that suffered significant attack were the borescopes, primary film cooler brush, and feed tubes. Changes in the operation of the film cooler brush and design modifications to the feed tubes and borescopes is expected to extend their service lives to two years. A program to investigate new high temperature engineered materials and alloys with improved oxidation and high temperature corrosion resistance will be initiated.

Imrich, K.J.; Chandler, G.T.

1996-06-17T23:59:59.000Z

197

RADIATION HEAT TRANSFER ENVIRONMENT IN FIRE AND FURNACE TESTS OF RADIOACTIVE MATERIALS PAKCAGES  

SciTech Connect (OSTI)

The Hypothetical Accident Conditions (HAC) sequential test of radioactive materials packages includes a thermal test to confirm the ability of the package to withstand a transportation fire event. The test specified by the regulations (10 CFR 71) consists of a 30 minute, all engulfing, hydrocarbon fuel fire, with an average flame temperature of at least 800 C. The requirements specify an average emissivity for the fire of at least 0.9, which implies an essentially black radiation environment. Alternate test which provide equivalent total heat input at the 800 C time averaged environmental temperature may also be employed. When alternate tests methods are employed, such as furnace or gaseous fuel fires, the equivalence of the radiation environment may require justification. The effects of furnace and open confinement fire environments are compared with the regulatory fire environment, including the effects of gases resulting from decomposition of package overpack materials. The results indicate that furnace tests can produce the required radiation heat transfer environment, i.e., equivalent to the postulated pool fire. An open enclosure, with transparent (low emissivity) fire does not produce an equivalent radiation environment.

Smith, A

2008-12-31T23:59:59.000Z

198

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental  

Broader source: Energy.gov (indexed) [DOE]

3-S2: Surplus Plutonium Disposition Supplemental 3-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement Summary This EIS analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives. The original EIS is available here. For more information, see: www.nnsa.energy.gov/nepa/spdsupplementaleis Public Comment Opportunities None available at this time. Documents Available for Download April 25, 2013 EIS-0283-S2: Interim Action Determination Surplus Plutonium Disposition Supplemental Environmental Impact Statement (K-Area Materials Storage (KAMS) Area Expansion at the Savannah River Site)

199

PATRAM '92: 10th international symposium on the packaging and transportation of radioactive materials [Papers presented by Sandia National Laboratories  

SciTech Connect (OSTI)

This document provides the papers presented by Sandia Laboratories at PATRAM '92, the tenth International symposium on the Packaging and Transportation of Radioactive Materials held September 13--18, 1992 in Yokohama City, Japan. Individual papers have been cataloged separately. (FL)

none,

1992-01-01T23:59:59.000Z

200

Characterizing Surplus US Plutonium for Disposition - 13199  

SciTech Connect (OSTI)

The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems. (authors)

Allender, Jeffrey S. [Savannah River National Laboratory, Aiken SC 29808 (United States)] [Savannah River National Laboratory, Aiken SC 29808 (United States); Moore, Edwin N. [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)] [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Characterizing surplus US plutonium for disposition  

SciTech Connect (OSTI)

The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems.

Allender, Jeffrey S.; Moore, Edwin N.

2013-02-26T23:59:59.000Z

202

Methods of chemical analysis for organic waste constituents in radioactive materials: A literature review  

SciTech Connect (OSTI)

Most of the waste generated during the production of defense materials at Hanford is presently stored in 177 underground tanks. Because of the many waste treatment processes used at Hanford, the operations conducted to move and consolidate the waste, and the long-term storage conditions at elevated temperatures and radiolytic conditions, little is known about most of the organic constituents in the tanks. Organics are a factor in the production of hydrogen from storage tank 101-SY and represent an unresolved safety question in the case of tanks containing high organic carbon content. In preparation for activities that will lead to the characterization of organic components in Hanford waste storage tanks, a thorough search of the literature has been conducted to identify those procedures that have been found useful for identifying and quantifying organic components in radioactive matrices. The information is to be used in the planning of method development activities needed to characterize the organics in tank wastes and will prevent duplication of effort in the development of needed methods.

Clauss, S.A.; Bean, R.M.

1993-02-01T23:59:59.000Z

203

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

SciTech Connect (OSTI)

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

Smith, K.P.

1992-12-01T23:59:59.000Z

204

Major Risk Factors to the Integrated Facility Disposition Project  

Broader source: Energy.gov (indexed) [DOE]

Oak Ridge Reservation Tennessee Major Risk Factors to the Integrated Facility Disposition Project (IFDP) Challenge The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). These include: environmental remediation, regulatory compliance, deactivation and decommissioning (D&D) activities, and disposition of legacy materials and waste, along with the ongoing modernization, reindustrialization, and reconfiguration initiatives at the Oak Ridge National Laboratory and at the Y-12 National Security Complex. The balancing of the broad nature of these activities and issues at ORO are a key challenge for the IFDP especially since their interrelationship is not always obvious.

205

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  

Broader source: Energy.gov (indexed) [DOE]

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

206

Confidentiality and the Desire for Open Communication in the Transport of Radioactive Material to a National Repository  

Broader source: Energy.gov (indexed) [DOE]

Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and the Desire for Open the Desire for Open Communication in the Communication in the Transport of Radioactive Transport of Radioactive Material to a National Material to a National Repository Repository A presentation to the A presentation to the DOE Transportation External Coordination (TEC) DOE Transportation External Coordination (TEC) Working Group Meeting Working Group Meeting Albuquerque, NM Albuquerque, NM 21 21 - - 23 April 2004 23 April 2004 Ronald B. Pope Consultant April 2004 April 2004 Confidentiality Confidentiality - - TEC Working TEC Working Group Group - - Albuquerque Albuquerque 2 2 Objectives Objectives Address and prompt TEC discussion on issues Address and prompt TEC discussion on issues

207

Physical test report to drop test of a 9975 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9975 radioactive material shipping package being dropped 30 feet onto a unyielding surface followed by a 40-inch puncture pin drop. The purpose of these drops was to show that the package lid would remain attached to the drum. The 30-foot drop was designed to weaken the lid closure lug while still maintaining maximum extension of the lugs from the drum surface. This was accomplished by angling the drum approximately 30 degrees from horizontal in an inverted position. In this position, the drum was rotated slightly so as not to embed the closure lugs into the drum as a result of the 30-foot drop. It was determined that this orientation would maximize deformation to the closure ring around the closure lug while still maintaining the extension of the lugs from the package surface. The second drop was from 40 inches above a 40-inch tall 6-inch diameter puncture pin. The package was angled 10 degrees from vertical and aligned over the puncture pin to solidly hit the drum lug(s) in an attempt to disengage the lid when dropped.Tests were performed in response to DOE EM-76 review Q5 inquires that questioned the capability of the 9975 drum lid to remain in place under this test sequence. Two packages were dropped utilizing this sequence, a 9974 and 9975. Test results for the 9974 package are reported in WSRC-RP-97-00945. A series of 40-inch puncture pin tests were also performed on undamaged 9975 and 9974 packages.

Blanton, P.S.

1997-11-11T23:59:59.000Z

208

Method for making a low density polyethylene waste form for safe disposal of low level radioactive material  

DOE Patents [OSTI]

In the method of the invention low density polyethylene pellets are mixed in a predetermined ratio with radioactive particulate material, then the mixture is fed through a screw-type extruder that melts the low density polyethylene under a predetermined pressure and temperature to form a homogeneous matrix that is extruded and separated into solid monolithic waste forms. The solid waste forms are adapted to be safely handled, stored for a short time, and safely disposed of in approved depositories.

Colombo, P.; Kalb, P.D.

1984-06-05T23:59:59.000Z

209

A workshop on developing risk assessment methods for medical use of radioactive material. Volume 2: Supporting documents  

SciTech Connect (OSTI)

A workshop was held at the Idaho National Engineering Laboratory, August 16--18, 1994 on the topic of risk assessment on medical devices that use radioactive isotopes. Its purpose was to review past efforts to develop a risk assessment methodology to evaluate these devices, and to develop a program plan and a scoping document for future methodology development. This report contains presentation material and a transcript of the workshop. Participants included experts in the fields of radiation oncology, medical physics, risk assessment, human-error analysis, and human factors. Staff from the US Nuclear Regulatory Commission (NRC) associated with the regulation of medical uses of radioactive materials and with research into risk-assessment methods participated in the workshop. The workshop participants concurred in NRC`s intended use of risk assessment as an important technology in the development of regulations for the medical use of radioactive material and encouraged the NRC to proceed rapidly with a pilot study. Specific recommendations are included in the executive summary and the body of this report.

Tortorelli, J.P. [ed.] [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-08-01T23:59:59.000Z

210

Disposition of Surplus Highly Enriched Uranium  

Broader source: Energy.gov (indexed) [DOE]

EIS-0240-S EIS-0240-S For Further Information Contact: U.S. Departmel>t of Energy Office of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 . This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 @ Printed with soy ink on recycled paper. .__- -. @ .: Depafimmt of Energy . i i~t " Wastin@on, DC 20585 June 1996 Dear hterested

211

Disposition of Surplus Highly Enriched Uranium  

Broader source: Energy.gov (indexed) [DOE]

. . ------- .--- --. ---- DOE/EIS-0240 I United States Department of Energy I For Further Information Contact: U.S. Department of Energy Otice of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 1 I ---- I I . I I I I This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices. Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: I Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 , @ Printed with soy ink on recycled paper. -_. - COVERS~ET

212

Assistant Manager for Waste Disposition  

Broader source: Energy.gov [DOE]

The incumbent of this position is responsible for providing overall leadership and direction for oversight of assigned contractor and Federal programs and activities associated with the disposition...

213

The ultimate disposition of depleted uranium  

SciTech Connect (OSTI)

Depleted uranium (DU) is produced as a by-product of the uranium enrichment process. Over 340,000 MTU of DU in the form of UF{sub 6} have been accumulated at the US government gaseous diffusion plants and the stockpile continues to grow. An overview of issues and objectives associated with the inventory management and the ultimate disposition of this material is presented.

Lemons, T.R. [Uranium Enrichment Organization, Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

214

Major Risk Factors Integrated Facility Disposition Project -...  

Office of Environmental Management (EM)

Integrated Facility Disposition Project - Oak Ridge Major Risk Factors Integrated Facility Disposition Project - Oak Ridge Full Document and Summary Versions are available for...

215

Radioactive material (RAM) transportation accident and incident experience in the U.S.A. (1971--1997)  

SciTech Connect (OSTI)

The Radioactive Materials Incident Report (RMIR) database was developed in 1981 at the Transportation Technology Center of Sandia National Laboratories to support its research and development activities for the US Department of Energy (DOE). This database contains information about radioactive materials transportation incidents that have occurred in the US since 1971. These data were drawn from the US Department of Transportation`s (DOT) Hazardous Materials Incident Report system, from Nuclear Regulatory Commission (NRC) files, and from various agencies including state radiological control offices. Support for the RMIR data base is funded by the National Transportation Program (EM-70) of the US Department of Energy. Transportation events in RMIR are classified in one of the following ways: as a transportation accident, as a handling accident, or as a reported incident. This presentation will provide definitions for these classifications and give examples of each. The primary objective of this presentation is to provide information on nuclear materials transportation accident incident events in the US for the period 1971--1997. Among the areas to be examined are: transportation accidents by mode, package response during accidents and an examination of accidents where release of contents has occurred.

McClure, J.D.; Yoshimura, H.R.; Fagan, H.F. [Sandia National Labs., Albuquerque, NM (United States). Transportation Systems Analysis Dept.; Thomas, T. [Dept. of Energy National Transportation Program (United States)

1997-11-01T23:59:59.000Z

216

Benchmark studies of induced radioactivity produced in LHC materials, part II: remanent dose rates  

Science Journals Connector (OSTI)

......production of radioactive isotopes as well as their decay...carbon composites, boron nitride, aluminium...step (calculation of isotopes), the FLUKA implementation...benchmark(6,7). Isotope information was written...uncertainty for the determination of the effective centre......

M. Brugger; H. Khater; S. Mayer; A. Prinz; S. Roesler; L. Ulrici; H. Vincke

2005-12-20T23:59:59.000Z

217

STATEMENT OF TRAINING AND EXPERIENCE (Radioactive Material User) Print Name: _______________________________________________ Permit Supervisor: ___________________________________  

E-Print Network [OSTI]

and Practices of Radiation Protection [ ] YES [ ] NO Radioactivity measurement, monitoring techniques [ ] STAFF [ ] GRADUATE STUDENT [ ] POST DOC [ ] UNDERGRADUATE STUDENT I plan to use (check all that apply. [Radiation Safety Courses at other institutions and lectures on the topics as part of college level

Firestone, Jeremy

218

Disposition of Surplus Highly Enriched Uranium  

Broader source: Energy.gov (indexed) [DOE]

@ @ Printed with soy ink on recycled paper. ,, ,, This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors horn the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 ' Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 Department of Energy Washington, DC 20585 June 1996 Dear hterested Party: The Disposition of Surplus Highly Enriched Uranium Final Environmental Impact Statemnt is enclosed for your information. This document has been prepared in accordance

219

Update of the Used Fuel Disposition Campaign Implementation Plan  

SciTech Connect (OSTI)

This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign (UFDC) supports achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program The implementation plan begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste). These target dates and goals are summarized in section III. This implementation plan will be maintained as a living document and will be updated as needed in response to progress in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program.

Jens Birkholzer; Robert MacKinnon; Kevin McMahon; Sylvia Saltzstein; Ken Sorenson; Peter Swift

2014-09-01T23:59:59.000Z

220

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network  

SciTech Connect (OSTI)

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-10-28T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network  

SciTech Connect (OSTI)

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

222

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

SciTech Connect (OSTI)

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

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

2007-06-06T23:59:59.000Z

223

Draft Surplus Plutonium Disposition Supplemental Environmental...  

National Nuclear Security Administration (NNSA)

materials production activities at SRS have produced HLW that is stored on site in tanks. The function of DWPF is to vitrify the low-volume, high- activity radioactive...

224

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has made significant progress with regard to disposition planning for 174 metric tons (MTU) of surplus Highly Enriched Uranium (HEU). Approximately 55 MTU of this 174 MTU are ''offspec'' HEU. (''Off-spec'' signifies that the isotopic or chemical content of the material does not meet the American Society for Testing and Materials standards for commercial nuclear reactor fuel.) Approximately 33 of the 55 MTU have been allocated to off-spec commercial reactor fuel per an Interagency Agreement between DOE and the Tennessee Valley Authority (1). To determine disposition plans for the remaining {approx}22 MTU, the DOE National Nuclear Security Administration (NNSA) Office of Fissile Materials Disposition (OFMD) and the DOE Office of Environmental Management (EM) co-sponsored this technical study. This paper represents a synopsis of the formal technical report (NNSA/NN-0014). The {approx} 22 MTU of off-spec HEU inventory in this study were divided into two main groupings: one grouping with plutonium (Pu) contamination and one grouping without plutonium. This study identified and evaluated 26 potential paths for the disposition of this HEU using proven decision analysis tools. This selection process resulted in recommended and alternative disposition paths for each group of HEU. The evaluation and selection of these paths considered criteria such as technical maturity, programmatic issues, cost, schedule, and environment, safety and health compliance. The primary recommendations from the analysis are comprised of 7 different disposition paths. The study recommendations will serve as a technical basis for subsequent programmatic decisions as disposition of this HEU moves into the implementation phase.

Bridges, D. N.; Boeke, S. G.; Tousley, D. R.; Bickford, W.; Goergen, C.; Williams, W.; Hassler, M.; Nelson, T.; Keck, R.; Arbital, J.

2002-02-27T23:59:59.000Z

225

Radioactive Waste Radioactive Waste  

E-Print Network [OSTI]

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

Slatton, Clint

226

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

SciTech Connect (OSTI)

Residual radioactive material guidelines for uranium in soil were derived for the Middlesex Sampling Plant (MSP) site in Middlesex, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. The site became contaminated from operations conducted in support of the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) between 1943 and 1967. Activities conducted at the site included sampling, storage, and shipment of uranium, thorium, and beryllium ores and residues. Uranium guidelines for single radioisotopes and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the MSP site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The RESRAD computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation. Four scenarios were considered for the site. These scenarios vary regarding future land use at the site, sources of water used, and sources of food consumed.

Dunning, D.E. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1995-02-01T23:59:59.000Z

227

Development of a computer model for calculation of radioactive materials into the atmosphere after an accident  

SciTech Connect (OSTI)

Secondary atmospheric contamination with radioactive dust and chemical species deposited on the ground and resuspended by wind occur very widely. This process is particularly pronounced in case of extensive contamination of soil and under extreme weather conditions, for example, during dust storms. The mechanism of wind dust generation consists in the following. At low wind speed U=2-3 m/s, which is most common in midlatitude, small radioactive dust particles (diameter of hundredth of a micron to 10-20 microns) are lifted from soil surface due to turbulent vortexes. Under the gravitational force the particles of 1-2 micron diameter practically do not settle. Larger dust particles cannot remain in the air for a long time: they are lifted by turbulent vortexes and settle, their motion in the wind flow is jump-wise and the interaction of particles with the flow is called saltation /I/. Saltation is the main mechanism of dust generation up to the wind velocity at which wind erosion starts. The size of dust particles can be as large as 100 pm. When dropping they can be ricocheting from ground or pass the impulse to other particles which begin rolling over and jumping up. The process of dust transport by wind can be compared to a chain reaction. At the velocity of 10 m/s large particles of about 500 pm stop skipping and roll over only, while particles of more than 1 mm remain stationary. Thus, the fine fraction is blown out from the polydispersed soil particles. The intensity of wind resuspension of radioactive dust from the ground is characterized either by a resuspension factor or a resuspension rate.

Schershakov, V. [Federal Information Analytical Centre, Obinski (Russia)

1997-11-01T23:59:59.000Z

228

disposition. prices | OpenEI  

Open Energy Info (EERE)

disposition. prices disposition. prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

229

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15T23:59:59.000Z

230

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

RS-Weapons X-Rays REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY...

231

Facility Disposition Safety Strategy RM | Department of Energy  

Office of Environmental Management (EM)

Facility Disposition Safety Strategy RM Facility Disposition Safety Strategy RM The Facility Disposition Safety Strategy (FDSS) Review Module is a tool that assists DOE federal...

232

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For Records Disposition Autnority Records Dispostion-Coal Distribution Data...

233

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Request for Records Disposition Authority REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications Request For Records Disposition Authority Request For Records...

234

Request For Records Disposition Authority | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Authority Request For Records Disposition Authority National Archives Pacific Southwest Region Request For Records Disposition Authority More...

235

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

Broader source: Energy.gov (indexed) [DOE]

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

236

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

Broader source: Energy.gov (indexed) [DOE]

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

237

Radiation sensitive devices and systems for detection of radioactive materials and related methods  

DOE Patents [OSTI]

Radiation sensitive devices include a substrate comprising a radiation sensitive material and a plurality of resonance elements coupled to the substrate. Each resonance element is configured to resonate responsive to non-ionizing incident radiation. Systems for detecting radiation from a special nuclear material include a radiation sensitive device and a sensor located remotely from the radiation sensitive device and configured to measure an output signal from the radiation sensitive device. In such systems, the radiation sensitive device includes a radiation sensitive material and a plurality of resonance elements positioned on the radiation sensitive material. Methods for detecting a presence of a special nuclear material include positioning a radiation sensitive device in a location where special nuclear materials are to be detected and remotely interrogating the radiation sensitive device with a sensor.

Kotter, Dale K

2014-12-02T23:59:59.000Z

238

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

SciTech Connect (OSTI)

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

Blanton, P; Kurt Eberl, K

2007-10-23T23:59:59.000Z

239

Used Fuel Disposition R&D Documents | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Used Fuel Disposition Used Fuel Disposition Research & Development » Used Fuel Disposition R&D Documents Used Fuel Disposition R&D Documents December 4, 2013 Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) This report documents the first phase of a multi-year project to understand the technical feasibility and logistical implications of direct disposal of spent nuclear fuel in existing dual-purpose canisters (DPCs) and other types of storage casks. October 25, 2013 Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs Deep borehole disposal is one alternative for the disposal of spent nuclear fuel and other radioactive waste forms; identifying a site or areas with favorable geological, hydrogeological, and geochemical conditions is one of

240

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 | Department of  

Broader source: Energy.gov (indexed) [DOE]

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored onsite in either wet pools or in dry storage systems with ultimate disposal envisioned in a deep mined geologic repository. This report provides an estimate of potential waste inventory and waste form characteristics for the DOE used nuclear fuel and high-level radioactive waste and a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. Fuel Cycle Potential Waste Inventory for Disposition R5a.docx More Documents & Publications Repository Reference Disposal Concepts and Thermal Load Management Analysis

Note: This page contains sample records for the topic "disposition radioactive materials" 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

EA-1488: Environmental Assessment for the U-233 Disposition, Medical  

Broader source: Energy.gov (indexed) [DOE]

488: Environmental Assessment for the U-233 Disposition, 488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee The purpose of the proposed action evaluated in this environmental assessment (EA) is the processing of uranium-233 (233U) stored at the Oak Ridge National Laboratory (ORNL) and other small quantities of similar material currently stored at other U. S. Department of Energy (DOE) sites in order to render it suitable for safe, long-term, economical storage. The 233U is stored within Bldg. 3019A, which is part of the Bldg. 3019

242

Recovering Americium and Curium from Mark-42 Target Materials- New Processing Approaches to Enhance Separations and Integrate Waste Stream Disposition - 12228  

SciTech Connect (OSTI)

Oak Ridge National Laboratory (ORNL) is investigating flowsheets to enhance processing efficiencies and to address waste streams associated with recovery of americium (Am) and curium (Cm) from Mark-42 (Mk-42) target materials stored at ORNL. The objective of this work was to identify the most effective flowsheet with which to process the 104 Mk-42 oxide capsules holding a total of 80 g of plutonium (Pu), 190 g of Cm, 480 g of Am, and 5 kg of lanthanide (Ln) oxides for the recovery and purification of the Am/Cm for future use as feedstock for heavy actinide production. Studies were also conducted to solidify the process flowsheet waste streams for disposal. ORNL is investigating flowsheets to enhance processing efficiencies and address waste streams associated with recovery of Am and Cm from Mk-42 target materials stored at ORNL. A series of small-scale runs are being performed to demonstrate an improved process to recover Am/Cm and to optimize the separations of Ln fission products from the Am/Cm constituents. The first of these runs has been completed using one of the Am/Cm/Ln oxide capsules stored at ORNL. The demonstration run showed promising results with a Ln DF of 40 for the Am/Cm product and an Am/Cm DF of 75 for the Ln product. In addition, the total losses of Am, Cm, and Ln to the waste solvents and raffinates were very low at <0.2%, 0.02%, and 0.04%, respectively. However, the Ln-actinide separation was less than desired. For future Reverse TALSPEAK demonstration runs, several parameters will be adjusted (flow rates, the ratio of scrub to strip stages, etc.) to improve the removal of Ln from the actinides. The next step will also include scale-up of the processing flowsheet to use more concentrated solutions (15 g/L Ln versus 5 g/L) and larger volumes and to recycle the HDEHP solvent. This should improve the overall processing efficiency and further reduce losses to waste streams. Studies have been performed with simulated wastes to develop solidification processes for disposal of the secondary waste streams generated by this flowsheet. Formulations were successfully developed for all the waste simulants. Additional tests with actual waste will be the next step in this effort. Future plans are to process all of the remaining 103 capsules in storage at ORNL. A nine-capsule test is now under way to provide additional information to scale-up the process to a target 20-capsule batch size for future processing runs. (authors)

Patton, Brad D.; Benker, Dennis; Collins, Emory D.; Mattus, Catherine H.; Robinson, Sharon M.; Wham, Robert M. [Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)

2012-07-01T23:59:59.000Z

243

Thermal Analysis and Test Results for the Overpack of a Typical Radioactive Materials Package  

SciTech Connect (OSTI)

In the course of the development and certification of the 9975 Package, extensive thermal analyses were performed and the package subjected to the regulatory HAC thermal test. The results of the thermal analysis and materials tests of the cane fiberboard overpack material were evaluated in comparison with the package HAC thermal test results. The evaluation confirmed that the thermal analysis correctly predicted the performance of the 9975 in the HAC fire test. The post test examination revealed that the heat affected region of the Celotex(R) overpack correlated well with the calculated temperature distribution

Smith, A.C.

2003-05-06T23:59:59.000Z

244

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

Broader source: Energy.gov (indexed) [DOE]

LEAVE BLANK (NARA use only) LEAVE BLANK (NARA use only) JOB NUMBER To: NATIONAL ARCHIVES & RECORDS ADMINISTRATION 8601 ADELPHI ROAD, COLLEGE PARK, MD 20740-6001 Date Received 1. FROM (Agency or establishment) NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C 3303a, the disposition request, including amendments is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. 2. MAJOR SUB DIVISION 3. MINOR SUBDIVISION 4. NAME OF PERSON WITH WHOM TO CONFER 5. TELEPHONE DATE ARCHIVIST OF THE UNITED STATES 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the records proposed for disposal on the attached______page(s) are not needed now for the business of this agency or will not be

245

Assuring Access to Low-Level Radioactive Waste Disposal Facilities for Non-DOE Users of Radioactive Materials: Solutions -Outside the Box  

SciTech Connect (OSTI)

This paper proposes both near-term and long-term solutions for disposal of low-level radioactive waste (LLRW) Classes B and C generated by non-DOE organizations in thirty-six states that will lose access to the Barnwell, SC disposal facility on July 1, 2008. The solutions proposed here call for the federal government, specifically the US Department of Energy (DOE), to play a key role and are outside the existing interstate compact framework established by the Low-Level Radioactive Waste Policy Act of 1980 (amended in 1985) and subsequent state ratification and Congressional consent statutes. (authors)

Pasternak, A.D. [Ph.D. California Radioactive Materials Management Forum, Lafayette, CA (United States)

2008-07-01T23:59:59.000Z

246

Direct conversion of surplus fissile materials, spent nuclear fuel, and other materials to high-level-waste glass  

SciTech Connect (OSTI)

With the end of the cold war the United States, Russia, and other countries have excess plutonium and other materials from the reductions in inventories of nuclear weapons. The United States Academy of Sciences (NAS) has recommended that these surplus fissile materials (SFMs) be processed so they are no more accessible than plutonium in spent nuclear fuel (SNF). This spent fuel standard, if adopted worldwide, would prevent rapid recovery of SFMs for the manufacture of nuclear weapons. The NAS recommended investigation of three sets of options for disposition of SFMs while meeting the spent fuel standard: (1) incorporate SFMs with highly radioactive materials and dispose of as waste, (2) partly burn the SFMs in reactors with conversion of the SFMs to SNF for disposal, and (3) dispose of the SFMs in deep boreholes. The US Government is investigating these options for SFM disposition. A new method for the disposition of SFMs is described herein: the simultaneous conversion of SFMs, SNF, and other highly radioactive materials into high-level-waste (HLW) glass. The SFMs include plutonium, neptinium, americium, and {sup 233}U. The primary SFM is plutonium. The preferred SNF is degraded SNF, which may require processing before it can be accepted by a geological repository for disposal.

Forsberg, C.W.; Elam, K.R.

1995-01-31T23:59:59.000Z

247

DOE/EIS-0240-SA-1: Supplement Analysis for the Disposition of Surplus Highly Enriched Uranium (October 2007)  

Broader source: Energy.gov (indexed) [DOE]

0-SA1 0-SA1 SUPPLEMENT ANALYSIS DISPOSITION OF SURPLUS HIGHLY ENRICHED URANIUM October 2007 U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. i TABLE OF CONTENTS 1.0 Introduction and Purpose .................................................................................................................1 2.0 Background......................................................................................................................................1 2.1 Scope of the HEU EIS............................................................................................................ 2 2.2 Status of Surplus HEU Disposition Activities .......................................................................

248

Application of a passive electrochemical noise technique to localized corrosion of candidate radioactive waste container materials  

SciTech Connect (OSTI)

One of the key engineered barriers in the design of the proposed Yucca Mountain repository is the waste canister that encapsulates the spent fuel elements. Current candidate metals for the canisters to be emplaced at Yucca Mountain include cast iron, carbon steel, Incoloy 825 and titanium code-12. This project was designed to evaluate passive electrochemical noise techniques for measuring pitting and corrosion characteristics of candidate materials under prototypical repository conditions. Experimental techniques were also developed and optimized for measurements in a radiation environment. These techniques provide a new method for understanding material response to environmental effects (i.e., gamma radiation, temperature, solution chemistry) through the measurement of electrochemical noise generated during the corrosion of the metal surface. In addition, because of the passive nature of the measurement the technique could offer a means of in-situ monitoring of barrier performance.

Korzan, M.A.

1994-05-01T23:59:59.000Z

249

Survey of the degradation modes of candidate materials for high-level radioactive waste disposal containers  

SciTech Connect (OSTI)

Oxidation and atmospheric corrosion data suggest that addition of Cr provides the greatest improvement in oxidation resistance. Cr-bearing cast irons are resistant to chloride environments and solutions containing strongly oxidizing constituents. Weathering steels, including high content and at least 0.04% Cu, appear to provide adequate resistance to oxidation under temperate conditions. However, data from long-term, high-temperature oxidation studies on weathering steels were not available. From the literature, it appears that the low alloy steels, plain carbon steels, cast steels, and cast irons con-ode at similar rates in an aqueous environment. Alloys containing more than 12% Cr or 36% Ni corrode at a lower rate than plain carbon steels, but pitting may be worse. Short term tests indicate that an alloy of 9Cr-1Mo may result in increased corrosion resistance, however long term data are not available. Austenitic cast irons show the best corrosion resistance. A ranking of total corrosion performance of the materials from most corrosion resistant to least corrosion resistant is: Austenitic Cast Iron; 12% Cr = 36% Ni = 9Cr-1Mo; Carbon Steel = Low Alloy Steels; and Cast Iron. Since the materials to be employed in the Advanced Conceptual Design (ACD) waste package are considered to be corrosion allowance materials, the austenitic cast irons, high Cr steels, high Ni steels and the high Cr-Mo steels should not be considered as candidates for the outer containment barrier. Based upon the oxidation and corrosion data available for carbon steels, low alloy steels, and cast irons, a suitable list of candidate materials for a corrosion allowance outer barrier for an ACD waste package could include, A516, 2.25%Cr -- 1%Mo Steel, and A27.

Vinson, D.W.; Nutt, W.M.; Bullen, D.B. [Iowa State Univ. of Science and Technology, Ames, IA (United States)

1995-06-01T23:59:59.000Z

250

Evaluation of geologic materials to limit biological intrusion into low-level radioactive waste disposal sites  

SciTech Connect (OSTI)

This report describes the results of a three-year research program to evaluate the performance of selected soil and rock trench cap designs in limiting biological intrusion into simulated waste. The report is divided into three sections including a discussion of background material on biological interactions with waste site trench caps, a presentation of experimental data from field studies conducted at several scales, and a final section on the interpretation and limitations of the data including implications for the user.

Hakonson, T.E.

1986-02-01T23:59:59.000Z

251

USING A RISK-BASED METHODOLOGY FOR THE TRANSFER OF RADIOACTIVE MATERIAL WITHIN THE SAVANNAH RIVER SITE BOUNDARY  

SciTech Connect (OSTI)

Shipment of radioactive materials (RAM) is discussed in the Code of Federal Regulations in parts of both 49 CFR and 10 CFR. The regulations provide the requirements and rules necessary for the safe shipment of RAM across public highways, railways, waterways, and through the air. These shipments are sometimes referred to as in-commerce shipments. Shipments of RAM entirely within the boundaries of Department of Energy sites, such as the Savannah River Site (SRS), can be made using methodology allowing provisions to maintain equivalent safety while deviating from the regulations for in-commerce shipments. These onsite shipments are known as transfers at the SRS. These transfers must follow the requirements approved in a site-specific Transportation Safety Document (TSD). The TSD defines how the site will transfer materials so that they have equivalence to the regulations. These equivalences are documented in an Onsite Safety Assessment (OSA). The OSA can show how a particular packaging used onsite is equivalent to that which would be used for an in-commerce shipment. This is known as a deterministic approach. However, when a deterministic approach is not viable, the TSD allows for a risk-based OSA to be written. These risk-based assessments show that if a packaging does not provide the necessary safety to ensure that materials are not released (during normal or accident conditions) then the worst-case release of materials does not result in a dose consequence worse than that defined for the SRS. This paper will discuss recent challenges and successes using this methodology at the SRS.

Loftin, B.; Watkins, R.; Loibl, M.

2010-06-03T23:59:59.000Z

252

Fundamental properties of monolithic bentonite buffer material formed by cold isostatic pressing for high-level radioactive waste repository  

SciTech Connect (OSTI)

The methods of fabrication, handling, and emplacement of engineered barriers used in a deep geological repository for high level radioactive waste should be planned as simply as possible from the engineering and economic viewpoints. Therefore, a new concept of a monolithic buffer material around a waste package have been proposed instead of the conventional concept with the use of small blocks, which would decrease the cost for buffer material. The monolithic buffer material is composed of two parts of highly compacted bentonite, a cup type body and a cover. As the forming method of the monolithic buffer material, compaction by the cold isostatic pressing process (CIP) has been employed. In this study, monolithic bentonite bodies with the diameter of about 333 mm and the height of about 455 mm (corresponding to the approx. 1/5 scale for the Japanese reference concept) were made by the CIP of bentonite powder. The dry densities: {rho}d of the bodies as a whole were measured and the small samples were cut from several locations to investigate the density distribution. The swelling pressure and hydraulic conductivity as function of the monolithic body density for CIP-formed specimens were also measured. High density ({rho}d: 1.4--2.0 Mg/m{sup 3}) and homogeneous monolithic bodies were formed by the CIP. The measured results of the swelling pressure (3--15 MPa) and hydraulic conductivity (0.5--1.4 x 10{sup {minus}13} m/s) of the specimens were almost the same as those for the uniaxial compacted bentonite in the literature. It is shown that the vacuum hoist system is an applicable handling method for emplacement of the monolithic bentonite.

Kawakami, S.; Yamanaka, Y.; Kato, K.; Asano, H.; Ueda, H.

1999-07-01T23:59:59.000Z

253

Survey of the degradation modes of candidate materials for high-level radioactive waste disposal containers. Final report  

SciTech Connect (OSTI)

One of the most significant factors impacting the performance of waste package container materials under repository relevant conditions is the thermal environment. This environment will be affected by the areal power density of the repository, which is dictated by facility design, and the dominant heat transfer mechanism at the site. The near-field environment will evolve as radioactive decay decreases the thermal output of each waste package. Recent calculations (Buscheck and Nitao, 1994) have addressed the importance of thermal loading conditions on waste package performance at the Yucca Mountain site. If a relatively low repository thermal loading design is employed, the temperature and relative humidity near the waste package may significantly affect the degradation of corrosion allowance barriers due to moist air oxidation and radiolytically enhanced corrosion. The purpose this report is to present a literature review of the potential degradation modes for moderately corrosion resistant nickel copper and nickel based candidate materials that may be applicable as alternate barriers for the ACD systems in the Yucca Mountain environment. This report presents a review of the corrosion of nickel-copper alloys, summaries of experimental evaluations of oxidation and atmospheric corrosion in nickel-copper alloys, views of experimental studies of aqueous corrosion in nickel copper alloys, a brief review of galvanic corrosion effects and a summary of stress corrosion cracking in these alloys.

Vinson, D.W.; Bullen, D.B. [Iowa State Univ. of Science and Technology, Ames, IA (United States)

1995-09-22T23:59:59.000Z

254

INMM 55th Annual Meeting, July 2024, 2014, Atlanta Marriott Marquis, Atlanta, Georgia, USA Transport Security for Nuclear and Other Radioactive Materials --A DOE Training Course  

E-Print Network [OSTI]

Laboratory. The course was developed by Argonne for the U.S. Department of Energy Packaging Certification of Energy, Washington, D.C. 20585 ABSTRACT In early December of 2013, a weeklong training course on security Transport Security for Nuclear and Other Radioactive Materials -- A DOE Training Course Ronald B. Pope, Yung

Kemner, Ken

255

Neutron Assay System for Confinement Vessel Disposition  

SciTech Connect (OSTI)

Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the CVs. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of special nuclear material (SNM) in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le}100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

256

MINIMIZING WASTE AND COST IN DISPOSITION OF LEGACY RESIDUES  

SciTech Connect (OSTI)

Research is being conducted at the Los Alamos National Laboratory (LANL) which is directed toward development of a quantitative basis for disposition of actinide-bearing process residues (both legacy residues and residues generated from ongoing programmatic operations). This research is focused in two directions: (1) identifying minimum negative consequence (waste, dose, cost) dispositions working within regulatory safeguards termination criteria, and (2) evaluating logistics/consequences of across-the-board residue discards such as authorized at Rocky Flats under a safeguards termination variance. The first approach emphasizes Laboratory commitments to environmental stewardship, worker safety, and fiscal responsibility. This approach has been described as the Plutonium Disposition Methodology (PDM) in deference to direction provided by DOE Albuquerque. The second approach is born of the need to expedite removal of residues from storage for programmatic and reasons and residue storage safety concerns. Any disposition path selected must preserve the legal distinction between residues as Special Nuclear Material (SNM) and discardable materials as waste in order to insure the continuing viability of Laboratory plutonium processing facilities for national security operations.

J. BALKEY; M. ROBINSON

2001-05-01T23:59:59.000Z

257

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range  

SciTech Connect (OSTI)

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

NONE

1997-06-01T23:59:59.000Z

258

Regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees. Draft report for comment  

SciTech Connect (OSTI)

Potential accidents for 15 types of fuel cycle and other radioactive material licensees were analyzed. The most potentially hazardous accident, by a large margin, was determined to be the sudden rupture of a heated multi-ton cylinder of UF/sub 6/. Acute fatalities offsite are probably not credible. Acute permanent injuries may be possible for many hundreds of meters, and clinically observable transient effects of unknown long term consequences may be possible for distances up to a few miles. These effects would be caused by the chemical toxicity of the UF/sub 6/. Radiation doses would not be significant. The most potentially hazardous accident due to radiation exposure was determined to be a large fire at certain facilities handling large quantities of alpha-emitting radionuclides (i.e., Po-210, Pu-238, Pu-239, Am-241, Cm-242, Cm-244) or radioiodines (I-125 and I-131). However, acute fatalities or injuries to people offsite due to accidental releases of these materials do not seem plausible. The only other significant accident was identified as a long-term pulsating criticality at fuel cycle facilities handling high-enriched uranium or plutonium. An important feature of the most serious accidents is that releases are likely to start without prior warning. The releases would usually end within about half an hour. Thus protective actions would have to be taken quickly to be effective. There is not likely to be enough time for dose projections, complicated decisionmaking during the accident, or the participation of personnel not in the immediate vicinity of the site. The appropriate response by the facility is to immediately notify local fire, police, and other emergency personnel and give them a brief predetermined message recommending protective actions. Emergency personnel are generally well qualified to respond effectively to small accidents of these types.

McGuire, S.A.

1985-06-01T23:59:59.000Z

259

The Savannah River Site's liquid radioactive waste operations involves the man  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Site's liquid radioactive waste operations involves the management of space in the Site's Site's liquid radioactive waste operations involves the management of space in the Site's 49 underground waste tanks, including the removal of waste materials. Once water is removed from the waste tanks, two materials remain: salt and sludge waste. Removing salt waste, which fills approximately 90 percent of the tank space in the SRS tank farms, is a major step toward closing the Site's waste tanks that currently contain approximately 38 million gallons of waste. Due to the limited amount of tank space available in new-style tanks, some salt waste must be dispositioned in the interim to ensure sufficient tank space for continued sludge washing and to support the initial start-up and salt processing operations at the Salt Waste Processing Facility (SWPF).

260

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

Science Journals Connector (OSTI)

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

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

2004-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Radioactive waste disposal package  

DOE Patents [OSTI]

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

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

262

Facility Disposition Safety Strategy RM  

Broader source: Energy.gov (indexed) [DOE]

Facility Disposition Safety Strategy Review Module Facility Disposition Safety Strategy Review Module March 2010 CD-0 O 0 OFFICE OF Facilit C CD-1 F ENVIRO Standard R ty Dispos Rev Critical Decis CD-2 M ONMENTAL Review Plan sition Saf view Module sion (CD) Ap CD March 2010 L MANAGE n (SRP) fety Strat e pplicability D-3 EMENT tegy CD-4 Post Ope eration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital Assets, DOE-STD-1189-2008,

263

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

Broader source: Energy.gov (indexed) [DOE]

3 of 5 3 of 5 Volume II Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume II United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition

264

Disposition options for {sup 233}U  

SciTech Connect (OSTI)

The United States is implementing a program to dispose of excess nuclear-weapons-usable materials--including {sup 233}U. A series of studies have identified multiple {sup 233}U disposition options, and these options are described herein. Most of the options involve adding depleted uranium containing {sup 238}U to the {sup 233}U. Converting the {sup 233}U into a mixture of <12 wt % {sup 233}U in {sup 238}U converts the weapons-usable {sup 233}U into nonweapons-usable {sup 233}U. For {sup 233}U that is considered waste, further isotopic dilution to <0.66 wt % {sup 233}U in {sup 238}U minimizes potential long-term repository criticality concerns and in many cases minimizes final waste volumes.

Forsberg, C.W.; Icenhour, A.S.; Krichinsky, A.M.

1998-04-27T23:59:59.000Z

265

The ultimate disposition of depleted uranium  

SciTech Connect (OSTI)

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

266

REEVALUATION OF WATERBORNE RELEASES OF RADIOACTIVE MATERIALS FROM THE MAYAK PRODUCTION ASSOCIATION INTO THE TECHA RIVER IN 1949-1951  

SciTech Connect (OSTI)

The Mayak Production Association was the first site for the production of weapon-grade plutonium in Russia. Early operations led to the waterborne release of large amounts of radioactive materials into the small Techa River. Residents living downstream used river water for drinking and other purposes. The releases and subsequent flooding resulted in the deposition of sediments along the shoreline and on floodplain soil. Primary routes of exposure were external dose from the deposited sediments and the ingestion of 90Sr and other radionuclides. Study of the Techa River Cohort has revealed an increased incidence of leukemia and solid cancers. These epidemiologic studies are supported by extensive dose-reconstruction activities that have led to the creation of various versions of a Techa River Dosimetry System (TRDS). The correctness of the TRDS has been challenged by the allegation that releases of short-lived radionuclides were much larger than those used in the TRDS. Although the dosimetry system depends more upon the measurements of 90Sr in humans and additional measurements of radionuclides and of exposure rates in the environment, a major activity has been undertaken to define more precisely the time-dependent rates of release and radionuclide composition of the releases. The major releases occurred during 1950-1951. In addition to routine releases major accidental releases occurred. The re-evaluated amount of total release is 114 PBq, about half of which was from accidents that occurred in late 1951. The composition of the radionuclides released has also been re-evaluated; this composition changed with time.

Degteva, M. O.; Shagina, N. B.; Vorobiova, M. I.; Anspaugh, L. R.; Napier, Bruce A.

2012-01-01T23:59:59.000Z

267

PAVAN: an atmospheric-dispersion program for evaluating design-basis accidental releases of radioactive materials from nuclear power stations  

SciTech Connect (OSTI)

This report provides a user's guide for the NRC computer program, PAVAN, which is a program used by the US Nuclear Regulatory Commission to estimate downwind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Such an assessment is required by 10 CFR Part 100 and 10 CFR Part 50. The program implements the guidance provided in Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants. Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases (e.g., through building penetrations and vents) or elevated releases from free-standing stacks. Various options may be selected by the user. They can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. It cannot handle multiple emission sources. A description of the main program and all subroutines is provided. Also included as appendices are a complete listing of the program and two test cases with the required data inputs and the resulting program outputs.

Bander, T.J.

1982-11-01T23:59:59.000Z

268

Microsoft PowerPoint - REVWaste_Disposition_Update.061411.pptx  

Broader source: Energy.gov (indexed) [DOE]

Materials and Disposition Update Materials and Disposition Update Environmental Management Site-Specific www.em.doe.gov 1 Environmental Management Site-Specific Advisory Board Chairs' Meeting June 15, 2011 Shirley J. Olinger EM Associate Principal Deputy for Corporate Operations DOE's Waste Management Priorities Continue to manage waste inventories in a safe and compliant manner. Address high risk waste in a cost- effective manner. Maintain and optimize current disposal capability for future generations. www.em.doe.gov 2 Develop future disposal capacity in a complex environment. Promote the development of treatment and disposal alternatives in the commercial sector. Review current policies and directives and provide needed oversight. Completed Legacy TRU Sites Teledyne-Brown ARCO Energy Technology Engineering Center

269

Summary - Major Risk Factors Integrated Facility Disposition...  

Office of Environmental Management (EM)

& ORNL, Oak Ridge, TN EM Project: Integrated Facility Disposition Project (IFDP) ETR Report Date: August 2008 ETR-15 United States Department of Energy Office of Environmental...

270

Uranium Downblending and Disposition Project Technology Readiness...  

Broader source: Energy.gov (indexed) [DOE]

Assessment EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory,...

271

Plutonium Disposition Program | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

accumulating newly separated weapon-grade plutonium. RUSSIAN PLUTONIUM DISPOSITION Russia plans to dispose of its 34 metric tons of weapon-grade plutonium by fabricating it...

272

Used Fuel Disposition Campaign Preliminary Quality Assurance...  

Broader source: Energy.gov (indexed) [DOE]

Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to...

273

Weapons Dismantlement and Disposition NNSS Capabilities  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has tasked the WDD working group to disposition the large inventory of legacy classified weapon components scattered across the complex.

Pat Arnold

2011-12-01T23:59:59.000Z

274

DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM...  

Broader source: Energy.gov (indexed) [DOE]

authorities which are under the moratorium on the destruction of health related records as of March 2008. DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM...

275

Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money  

SciTech Connect (OSTI)

The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude.

Brill, Angie; Boles, Roger; Byars, Woody

2003-02-26T23:59:59.000Z

276

DOE - Office of Legacy Management -- Sandia National Laboratories...  

Office of Legacy Management (LM)

- California (004) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials...

277

UW EH&S Radiation Safety Office Box 354400 201 Hall Health Seattle WA 98195-4400 206-543-0463 FORM 160 RADIOACTIVE MATERIAL DELIVERY AND USAGE RECORD (5/00)  

E-Print Network [OSTI]

160 RADIOACTIVE MATERIAL DELIVERY AND USAGE RECORD (5/00) AUI Name PO # AUI # Item # Order Date Order be surveyed if they are labeled with a Radioactive White I, Yellow II or Yellow III label. Swipes CONTAMINATION (WAC 246-221-160(4)): contamination

Wilcock, William

278

Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium  

SciTech Connect (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

279

Request For Records Disposition Authority | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Records Schedule Contractor Checks Request For Records Disposition Authority More Documents & Publications DOE-STD-4001-2000 DOE Records Disposition Schedule Changes Audit Letter...

280

Request For Records Disposition Authority | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Fossil Energy Equity Re-determination Records Request For Records Disposition Authority More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Inspection Report:...

Note: This page contains sample records for the topic "disposition radioactive materials" 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

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

Pacific Northwest Lab: Richland Operations Office REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For...

282

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES...  

Broader source: Energy.gov (indexed) [DOE]

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) This document lists the...

283

Applying Risk Communication to the Transportation of Radioactive...  

Office of Environmental Management (EM)

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

284

I REQUEST FOR RECORDS DISPOSITION AUTHORITY  

Broader source: Energy.gov (indexed) [DOE]

REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY LEAVE BL ...A (NARA use only1 JOB NUMBER TO: NATIONAL ARCHIVES & RECORDS ADMINISTRATION In accordance with the provisions of 44 U.S.C. 3303a, the Office of the Chief Information Officer disposition request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. Records Management Division N1-434-02-2 Date received 860 1 ADELPHI ROAD COLLEGE PARK, MD 20740-600 1 1. FROM (Agency or establishment) Department of Energy , ( / I 4 30 -A&&& NOTIFICATION TO AGENCY 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the

285

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

Broader source: Energy.gov (indexed) [DOE]

1nstrlrcrlons on reverts) 1nstrlrcrlons on reverts) ' 0 NATIONAL ARCMVES and RECORDS AD~~INISTRAT~ON (NIR) WASHINGTON, DC 20408 1. FROM (Agency or estabi~shment) Department of Energy Washington, DC 20585 . '2. MAJOR SUBDIVISION fn lccordance w i l h the provirions o f 4 4 DOE~NEVADA OPERATIONS OFFICE U.S.C. 3 3 0 3 r the disposition r e q u c ~ t , including rmtndments, i s approvtd n c t p l 3. MINOR SUBOlVlStON lor ilemr that mky be mrrkcd 'dir wition not approved' o r withdmwn' in c&mn lo. '4. NAME O F PERSON WITH WHOM TO CONFER 5. TELEPHONE Mary Ann Wallace -301 903 4353 6. AGENCY CERTIFICATION I hereby certify that I am authorized to a d for this to th#disposit-ion of its records and that the records roposed for disposal on the P now needed for the business of this agency or wil not be needed after the concurrence f

286

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

Broader source: Energy.gov (indexed) [DOE]

m m - REQUEST FOR RECORDS DISPOSITION AUTHORITY (See Instructions on reverse) GENERAL SERVICES ADMINISTRATION N A T I O N A L ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 1. F R O M ( A g e n c y o r e s t a b l i s h m e n t ) jepartment of Energy 2. MAJOR S U B D I V I S I O N Oak Ridse Operations Office 3. M I N O R S U B D I V I S I O N 4 . N A M E O F PERSON W I T H W H O M T O C O N F E R ( 5 . T E L E P H O N E E X T . L E A V E B L A N K - JOB N O . d/-d33P PO- ZJ - - - - p p D A T E R E C E I V E D p - NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C. 3303a the disposal request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. - DATE ARCHIVIST

287

Used Fuel Disposition Campaign International Activities Implementation Plan  

Broader source: Energy.gov (indexed) [DOE]

International Activities International Activities Implementation Plan Used Fuel Disposition Campaign International Activities Implementation Plan The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through

288

On Going TRU Waste Disposition  

SciTech Connect (OSTI)

The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

289

Final Environmental Assessment for Waste Disposition Activities at the Paducah Site Paducah, Kentucky  

Broader source: Energy.gov (indexed) [DOE]

0-347(doc)/093002 0-347(doc)/093002 1 FINDING OF NO SIGNIFICANT IMPACT WASTE DISPOSITION ACTIVITIES AT THE PADUCAH SITE PADUCAH, KENTUCKY AGENCY: U.S. DEPARTMENT OF ENERGY ACTION: FINDING OF NO SIGNIFICANT IMPACT SUMMARY: The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low- level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is

290

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Carter, J.

2011-01-03T23:59:59.000Z

291

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

292

TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION  

SciTech Connect (OSTI)

Supporting nuclear nonproliferation and global security principles, beginning in 1994 the United States has withdrawn more than 50 metric tons (MT) of government-controlled plutonium from potential use in nuclear weapons. The Department of Energy (DOE), including the National Nuclear Security Administration, established protocols for the tracking of this "excess" and "surplus" plutonium, and for reconciling the current storage and utilization of the plutonium to show that its management is consistent with the withdrawal policies. Programs are underway to ensure the safe and secure disposition of the materials that formed a major part of the weapons stockpile during the Cold War, and growing quantities have been disposed as waste, after which they are not included in traditional nuclear material control and accountability (NMC&A) data systems. A combination of resources is used to perform the reconciliations that form the basis for annual reporting to DOE, to U.S. Department of State, and to international partners including the International Atomic Energy Agency.

Allender, J.; Beams, J.; Sanders, K.; Myers, L.

2013-07-16T23:59:59.000Z

293

EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement  

Broader source: Energy.gov [DOE]

This EIS analyzes the potential environmental impacts associated with alternatives for the disposition of surplus plutonium.

294

IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION  

SciTech Connect (OSTI)

This report provides a technical basis for estimating the level of corrosion products in materials stored in DOE-STD-3013 containers based on extrapolating available chemical sample results. The primary focus is to estimate the levels of nickel, iron, and chromium impurities in plutonium-bearing materials identified for disposition in the United States Mixed Oxide fuel process.

Allender, J; Moore, E

2010-07-14T23:59:59.000Z

295

Used Fuel Disposition Campaign Disposal  

Broader source: Energy.gov (indexed) [DOE]

Campaign Disposal Research and Development Roadmap Prepared for U.S. Department of Energy Used Fuel Disposition Campaign September 2012 FCR&D-USED-2011-000065 REV 1 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or

296

Waste Disposition Update by Christine Gelles  

Broader source: Energy.gov (indexed) [DOE]

Waste Disposition Update Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o Waste Stream Highlights o DOE Transportation Update o Greater Than Class C (GTCC) Low Level Waste Environmental Impact Statement o Blue Ribbon Commission on America's Nuclear Future o Nuclear Regulatory Commission's LLW Regulatory Initiatives Discussion Topics www.em.doe.gov 3 Waste Stream Highlights www.em.doe.gov 4 o Within current budget outlook, it is especially critical that EM ensures safe, reliable and cost effective disposition paths exist. o The program's refocused organization and the detailed

297

Accelerating the disposition of transuranic waste from LANL - 9495  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that time frame. This paper presents progress in dispositioning legacy and newly-generated transuranic waste (TRU) from ongoing missions at the LANL. The plans for, and lessons learned, in dispositioning several hundred high-activity TRU waste drums are reviewed. This waste population was one of the highest risks at LANL. Technical challenges in disposition of the high-activity drums are presented. These provide a preview of challenges to be addressed in dispositioning the remaining 6,800 m{sup 3} of TRU stored above ground and 2,400 m{sup 3} of TRU waste that is 'retrievably' stored below-grade. LANL is using subcontractors for much of this work and has formed a strong partnership with WIPP and its contractor to address this cleanup challenge.

Shepard, Mark D [Los Alamos National Laboratory; Stiger, Susan G [Los Alamos National Laboratory; Blankenhorn, James A [Los Alamos National Laboratory; Rael, George J [Los Alamos National Laboratory; Moody, David C [U.S DOE

2009-01-01T23:59:59.000Z

298

DOE/EIS-0283-SA1: Supplement Analysis and Amended Record of Decision for Changes Needed To the Surplus Plutonium Disposition Program (4/24/03)  

Broader source: Energy.gov (indexed) [DOE]

3-SA1 3-SA1 April 2003 Changes Needed To The Surplus Plutonium Disposition Program SUPPLEMENT ANALYSIS AND AMENDED RECORD OF DECISION U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. Table of Contents i Table of Contents List of Figures ................................................................................................................................. ii List of Tables .................................................................................................................................. ii List of Acronyms ...........................................................................................................................

299

Excess plutonium disposition using ALWR technology  

SciTech Connect (OSTI)

The Office of Nuclear Energy of the Department of Energy chartered the Plutonium Disposition Task Force in August 1992. The Task Force was created to assess the range of practicable means of disposition of excess weapons-grade plutonium. Within the Task Force, working groups were formed to consider: (1) storage, (2) disposal,and(3) fission options for this disposition,and a separate group to evaluate nonproliferation concerns of each of the alternatives. As a member of the Fission Working Group, the Savannah River Technology Center acted as a sponsor for light water reactor (LWR) technology. The information contained in this report details the submittal that was made to the Fission Working Group of the technical assessment of LWR technology for plutonium disposition. The following aspects were considered: (1) proliferation issues, (2) technical feasibility, (3) technical availability, (4) economics, (5) regulatory issues, and (6) political acceptance.

Phillips, A. (ed.); Buckner, M.R.; Radder, J.A.; Angelos, J.G.; Inhaber, H.

1993-02-01T23:59:59.000Z

300

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

Broader source: Energy.gov (indexed) [DOE]

Instructions on reverse) Instructions on reverse) LEAVE BLANK - GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 I . F R O M (Agency or ertabluhmentJ D A T E RECEIVED NOTIF~CATION TO AGENCY Department of Energy 2. MAJ0.R S U B D I V I S I O N I 4 . N A M E O F PERSON W I T H W H O M T O CONFER 15. TELEPHONE E X T . \OATS l A R C H l V l S T O F T H E U N I T E D STATES In accordance with the provisions of 44 U.S.C. 3303 the dispoal request. including amendmentr, is approved . 3. M I N O R S U B D I V I S I O N except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records;

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite  

SciTech Connect (OSTI)

Specimens of titanate ceramics containing approximately 10 mass% 238Pu were tested to determine the long-term effects of radiation-induced damage from the ? decay of 239Pu that would have been disposed of in the nuclear-waste repository at Yucca Mountain. These tests provided information on the changes in bulk properties such as dimensions, densities, and chemical durability. Although these materials become amorphous at low doses, the specimens remained physically strong. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, in combination with results reported previously on similar materials, the material remains a physically viable material for the disposition of surplus weapons-grade Pu.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2008-01-15T23:59:59.000Z

302

Naturally occurring radioactive material (NORM V): proceedings of an international symposium, Seville, Spain, 1922 March 2007  

Science Journals Connector (OSTI)

......their decay chain members in rare earth minerals is often enough...occupational exposure during rare earth production gives rise...variety of monazite mining and rare earth recovery industries...environmental weathering of stacked phosphogypsum waste materials, with observed......

William E. Kennedy; Jr.

2010-03-01T23:59:59.000Z

303

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

Broader source: Energy.gov (indexed) [DOE]

Summary Final Environmental Impact Statement November 1999 Summary DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Summary United States Department of Energy Office of Fissile Materials Disposition November 1999 Summary i Table of Contents S.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-1 Purpose of and Need for the Proposed Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-3 Issues Identified During the Scoping Period . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Issues Already Intended for Inclusion in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Additional Issues That Need to Be Addressed in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . S-5 Issues That Need to Be or Are Already Addressed Elsewhere . . . . . . . . . . . . . . . .

304

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

Broader source: Energy.gov (indexed) [DOE]

2 of 5 2 of 5 Volume I - Part B Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume I - Part B United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director

305

Used fuel disposition campaign international activities implementation plan.  

SciTech Connect (OSTI)

The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through information exchange and a broader participation of experts in the field. U.S. participation in international UNF and HLW exchanges leads to safe management of nuclear materials, increased security through global oversight, and protection of the environment worldwide. Such interactions offer the opportunity to develop consensus on policy, scientific, and technical approaches. Dialogue to address common technical issues helps develop an internationally recognized foundation of sound science, benefiting the U.S. and participating countries. The UNF and HLW management programs in nuclear countries are at different levels of maturity. All countries utilizing nuclear power must store UNF, mostly in wet storage, and HLW for those countries that reprocess UNF. Several countries either utilize or plan to utilize dry storage systems for UNF, perhaps for long periods of time (several decades). Geologic disposal programs are at various different states, ranging from essentially 'no progress' to selected sites and pending license applications to regulators. The table below summarizes the status of UNF and HLW management programs in several countriesa. Thus, the opportunity exists to collaborate at different levels ranging from providing expertise to those countries 'behind' the U.S. to obtaining access to information and expertise from those countries with more mature programs. The U.S. fuel cycle is a once through fuel cycle involving the direct disposal of UNF, as spent nuclear fuel, in a geologic repository (previously identified at Yucca Mountain, Nevada), following at most a few decades of storage (wet and dry). The geology at Yucca Mountain, unsaturated tuff, is unique among all countries investigating the disposal of UNF and HLW. The decision by the U.S. Department of Energy to no longer pursue the disposal of UNF at Yucca Mountain and possibly utilize very long term storage (approaching 100 years or more) while evaluating future fuel cycle alternatives for managing UNF, presents a different UNF and HLW management R&D portfolio that has been pursued in the U.S. In addition, the research and development activities managed by OCRWM have been transferred to DOE-NE. This requires a reconsideration of how the UFDC will engage in cooperative and collaborative activities with other countries. This report presents the UFDC implementation plan for international activities. The DOE Office of Civilian Radioactive Waste Management (OCRWM) has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organization for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited OCRWM through the acquisition and exchange of information, database development, and peer reviews by experts from other countries. DOE-NE cooperates and collaborates with other countries in similar 'arenas' with similar objectives and realizing similar benefits. However the DOE-NE focus has not typically been in the area of UNF and HLW management. This report will first summarize these recent cooperative and collaborative activities. The manner that the UFDC will cooperate and collaborate in the future is expected to change as R&D is conducted regarding long-term storage and the potential disposal of UNF and HLW in different geolo

Nutt, W. M. (Nuclear Engineering Division)

2011-06-29T23:59:59.000Z

306

U.S. and Russia Sign Plutonium Disposition Agreement | National...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Our Jobs Working at NNSA Blog Home About Us Our History NNSA Timeline U.S. and Russia Sign Plutonium Disposition Agreement U.S. and Russia Sign Plutonium Disposition...

307

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

U. S. Atomic Energy Commision REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY DOE-HDBK-1109-97 DOE-HDBK-1109-97...

308

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

E-Print Network [OSTI]

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

Maxwell, Bruce D.

309

Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite  

SciTech Connect (OSTI)

This is the second of two papers on the results of radiation-induced damage accumulation in titanate ceramics that potentially could be used for weapons grade plutonium disposition. In the first paper we discussed the results from pyrochlore (betafite) based ceramics. In this paper, we discuss the effects of radiation-induced damage on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics from the alpha decay of 238Pu. Macro (bulk) and micro (X-ray diffraction) swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. It took approximately 740 days (2.6?1018 ?/g) for the specimens to become X-ray amorphouslonger for the swelling to saturate. Unlike what we observed for the pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)?10-3 g/(m2?d). Very little pH dependence was observed for zirconolite specimens and, like we observed for the pyrochlore-bearing ceramics in this study, there was no dependence on the amount of radiation-induced damage. As with the pyrochlore, these materials did not become substantially friable with increasing radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2008-01-15T23:59:59.000Z

310

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

SciTech Connect (OSTI)

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

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

1996-05-01T23:59:59.000Z

311

Enhancing Railroad Hazardous Materials Transportation Safety...  

Office of Environmental Management (EM)

Enhancing Railroad Hazardous Materials Transportation Safety Enhancing Railroad Hazardous Materials Transportation Safety Presented by Kevin R. Blackwell, Radioactive Materials...

312

Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

Alfred Wickline

2007-06-01T23:59:59.000Z

313

Waste Isolation Pilot Plant Materials Interface Interactions Test: Papers presented at the Commission of European Communities workshop on in situ testing of radioactive waste forms and engineered barriers  

SciTech Connect (OSTI)

The three papers in this report were presented at the second international workshop to feature the Waste Isolation Pilot Plant (WIPP) Materials Interface Interactions Test (MIIT). This Workshop on In Situ Tests on Radioactive Waste Forms and Engineered Barriers was held in Corsendonk, Belgium, on October 13--16, 1992, and was sponsored by the Commission of the European Communities (CEC). The Studiecentrum voor Kernenergie/Centre D`Energie Nucleaire (SCK/CEN, Belgium), and the US Department of Energy (via Savannah River) also cosponsored this workshop. Workshop participants from Belgium, France, Germany, Sweden, and the United States gathered to discuss the status, results and overviews of the MIIT program. Nine of the twenty-five total workshop papers were presented on the status and results from the WIPP MIIT program after the five-year in situ conclusion of the program. The total number of published MIIT papers is now up to almost forty. Posttest laboratory analyses are still in progress at multiple participating laboratories. The first MIIT paper in this document, by Wicks and Molecke, provides an overview of the entire test program and focuses on the waste form samples. The second paper, by Molecke and Wicks, concentrates on technical details and repository relevant observations on the in situ conduct, sampling, and termination operations of the MIIT. The third paper, by Sorensen and Molecke, presents and summarizes the available laboratory, posttest corrosion data and results for all of the candidate waste container or overpack metal specimens included in the MIIT program.

Molecke, M.A.; Sorensen, N.R. [eds.] [Sandia National Labs., Albuquerque, NM (US); Wicks, G.G. [ed.] [Westinghouse Savannah River Technology Center, Aiken, SC (US)

1993-08-01T23:59:59.000Z

314

LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

315

Development of a Techno-Economic Model to Optimize DOE Spent Nuclear Fuel Disposition  

SciTech Connect (OSTI)

The National Spent Nuclear Fuel (NSNF) Program is evaluating final disposition of spent nuclear fuel (SNE) in the Department of Energy (DOE) complex. Final disposition of SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the EMT process for fuels at several locations. The set of questions addresses all issues associated with design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs can be applied to determine the life cycle cost of each option. This technique can also be applied to other treatment techniques for treating SNF.

Ramer, R. J.; Plum, M. M.; Adams, J. P.; Dahl, C. A.

1998-02-01T23:59:59.000Z

316

ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1997-08-01T23:59:59.000Z

317

Uranium Compounds and Other Natural Radioactivities  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

318

Update of the Used Fuel Disposition Campaign Implementation Plan |  

Broader source: Energy.gov (indexed) [DOE]

Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan The Used Fuel Disposition Campaign will identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign supports achievement of the overarching Fuel Cycle Research and Development Program mission and objectives. Activities will be sufficiently flexible to accommodate any of the potential fuel cycle options for used fuel management. Update of the Used Fuel Disposition Campaign Implementation Plan

319

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

SciTech Connect (OSTI)

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

Dominick, J

2008-12-18T23:59:59.000Z

320

Request For Records Disposition Authority: Strategic Petroleum Reserve  

Broader source: Energy.gov (indexed) [DOE]

Request For Records Disposition Authority: Strategic Petroleum Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Paper case files pertaining to environmental permit applications, permits and related correspondence as well as NEPA correspondence within of the Strategic Petroleum Reserve Project Management Office (SPRPMO) Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office More Documents & Publications 2012 Annual Planning Summary for Fossil Energy, National Energy Technology Laboratory, RMOTC, and Strategic Petroleum Reserve Field Office CX-002673: Categorical Exclusion Determination CX-009794: Categorical Exclusion Determination

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Request For Records Disposition Authority-Nuclear Weapons | Department...  

Broader source: Energy.gov (indexed) [DOE]

For Records Disposition Authority-Nuclear Weapons This document identifies the nuclear weapon records generated by the Department of Energy's (DOE) Nuclear Weapons Complex Request...

322

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Nuclear Power Plant Docket Records REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications PIA - Savannah River Remediation Accreditation Boundary (SRR AB) REQUEST...

323

EA-1488: Environmental Assessment for the U-233 Disposition,...  

Office of Environmental Management (EM)

Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee...

324

Request For Records Disposition Autnority | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Autnority Request For Records Disposition Autnority Published Posters. Posters depicting Department of Energy facilities, research projects, security awareness themes, and related...

325

Used Fuel Disposition Campaign Phase I Ring Compression Testing...  

Broader source: Energy.gov (indexed) [DOE]

Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression...

326

Major Risk Factors to the Integrated Facility Disposition Project  

Broader source: Energy.gov [DOE]

The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks atthe Oak Ridge Reservation (ORO).

327

Consent Order, Uranium Disposition Services, LLC- NCO-2010-01  

Broader source: Energy.gov [DOE]

Issued to Uranium Disposition Services, LLC related to Construction Deficiencies at the DUF6 Conversion Buildings at the Portsmouth and Paducah Gaseous Diffusion Plants

328

Office of UNF Disposition International Program - Strategic Plan |  

Broader source: Energy.gov (indexed) [DOE]

UNF Disposition International Program - Strategic Plan UNF Disposition International Program - Strategic Plan Office of UNF Disposition International Program - Strategic Plan The Department of Energy's Office of Nuclear Energy, Used Nuclear Fuel Disposition Research and Development Office (UFD), performs the critical mission of addressing the need for an integrated strategy that combines safe storage of spent nuclear fuel with expeditious progress toward siting and licensing a disposal facility or facilities. The UFD International Program plays a key role in this effort. International collaboration provides a forum for exchanging strategies, expertise, and technologies with other nations that have also been investigating solutions to the problems of nuclear waste disposal-information that otherwise would have

329

Sample results from the integrated salt disposition program macrobatch 6 tank 21H qualifications MST solids sample  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.

Peters, T. B.

2013-02-26T23:59:59.000Z

330

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final...  

Office of Environmental Management (EM)

: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition...

331

Radiation damage effects in candidate titanates for Pu disposition: Zirconolite  

Science Journals Connector (OSTI)

Results from studies of radiation-induced damage from the alpha decay of 238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. Approximately 2.6נ1018?/g were needed to render the specimens X-ray amorphous more to saturate the swelling. Unlike pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)נ10?3g/(m2d) with very little pH dependence and no dependence on the amount of radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.

D.M. Strachan; R.D. Scheele; E.C. Buck; A.E. Kozelisky; R.L. Sell; R.J. Elovich; W.C. Buchmiller

2008-01-01T23:59:59.000Z

332

Radioactive ion detector  

DOE Patents [OSTI]

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

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

1997-08-12T23:59:59.000Z

333

Radioactive ion detector  

DOE Patents [OSTI]

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

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

1997-01-01T23:59:59.000Z

334

Properties and Dispositions: Some Metaphysical Remarks on Quantum Ontology  

Science Journals Connector (OSTI)

After some suggestions about how to clarify the confused metaphysical distinctions between dispositional and non?dispositional or categorical properties I review some of the main interpretations of QM in order to show that with the relevant exception of Bohms minimalist interpretation quantum ontology is irreducibly dispositional. Such an irreducible character of dispositions must be explained differently in different interpretations but the reducibility of the contextual properties in the case of Bohmian mechanics is guaranteed by the fact that the positions of particles play the role of the categorical basis a role that in other interpretations cannot be filled by anything else. In Bohrs and Everett?type interpretations dispositionalism is instrumentalism in disguise.

Mauro Dorato

2006-01-01T23:59:59.000Z

335

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

Broader source: Energy.gov (indexed) [DOE]

Used Fuel Disposition Campaign Preliminary Quality Assurance Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications

336

Hight-Level Waste & Facilities Disposition  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

High-Level Waste (HLW) and Facilities Disposition Final High-Level Waste (HLW) and Facilities Disposition Final Environmental Impact Statement You are here: DOE-ID Home > Environmental Management > Idaho High-Level Waste (HLW) Table of Contents Documents are in the Adobe® PDF format and require the Adobe® Reader to access them. If you do not currently have the Acrobat Reader, you can download the Free Adobe Reader at http://get.adobe.com/reader/ Icon link to Free Adobe Acrobat Reader software * Large chapters broken down into sections Summary* Cover [ Adobe Acrobat File Size 1.48 MB] Section, 1.0 [ Adobe Acrobat File Size 612 KB] Section, 2.0 [ Adobe Acrobat File Size 251 KB] Sections, 3.0 - 3.2.1a [ Adobe Acrobat File Size 1.4 MB] Section, 3.2.1b [ Adobe Acrobat File Size 2.0 MB] Sections, 3.2.2 - 4.0 [ Adobe Acrobat File Size 1.4 MB]

337

Management of nuclear materials and non-HLW | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

the consolidation and disposition of nuclear materials, including plutonium, uranium, and nuclear waste in accordance with applicable statutes, DOE Orders and international...

338

Radioactivity and Radiation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

339

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

Broader source: Energy.gov (indexed) [DOE]

5 of 5 5 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part B Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

340

EIS-0283DS Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement, April 1999  

Broader source: Energy.gov (indexed) [DOE]

Sheet Sheet Responsible Agency: United States Department of Energy (DOE) Title: Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement (Supplement) (DOE/EIS-0283-DS) Locations of Candidate Sites: Idaho, North Carolina, South Carolina, Texas, Virginia, and Washington Contacts: For further information on the Supplement contact: For further information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Office of Fissile Materials Disposition U.S. Department of Energy P.O. Box 23786 Washington, DC 20026-3786 Voice: (202) 586-5368 Ms. Carol Borgstrom, Director Office of NEPA Policy and Assistance Office of Environment, Safety and Health U.S. Department of Energy 1000 Independence Ave., SW

Note: This page contains sample records for the topic "disposition radioactive materials" 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

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

Broader source: Energy.gov (indexed) [DOE]

4 of 5 4 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part A Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

342

Material corrosion issues for nuclear waste disposition in Yucca Mountain  

Science Journals Connector (OSTI)

For more than two decades, an extensive scientific effort has been underway to determine whether Yucca Mountain, Nevada, is a suitable site for...

Raul B. Rebak

2008-01-01T23:59:59.000Z

343

Materials  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

2 MAG LAB REPORTS Volume 18 No. 1 CONDENSED MATTER SCIENCE Technique development, graphene, magnetism & magnetic materials, topological insulators, quantum fl uids & solids,...

344

HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY  

Broader source: Energy.gov (indexed) [DOE]

- - HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY (See ~nstructions on reverse) / GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, D C 20408 1 . F R O M (Agency orestablishment) U.S. Department of Energy 2 . MAJOR SUBDIVISION Oak Ridge Operations Office 3. M I N O R SUBDIVISION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records; that the records proposed for disposal in this Request of 4 page(s) are not now needed for the business of this agency or will not be needed after the retention periods specified; and that written concurrence from the General Accounting Office, if required under the provisions of Title 8 of the GAO Manual for Guidance of Federal Agencies, is

345

REQUEST FOR RECORDS DISPOSITION AUTHORITY S  

Broader source: Energy.gov (indexed) [DOE]

S S e e Instructions o n reverse) NATIONAL ARCHIVES and RECORDS ADMINISTRATION (NIR) WASHINGTON. DC 20408 , - - 1. FROM (Agency or establishment) Department of Energy 2. MAJOR SUBDIVISION Assistant Secretary For Fossil Energy (FE-1) I 3. MINOR SUBDIVISION Office of Naval Petroleum and Shale Oil 4 . NAME OF PERSON WITH WHOM TO CON I 1 Jerry Hinkle (FE 47) 1(202)586-43 80 I I / 6. AGENCY CERTIFICATION I NOTIFICATION TO AGENCY i I In accordance with the provisions of 44 U.S.C. 3303a the disposition request, including amendments, is ap roved except for items that may be marke! "dis osition not approved" or "withdrawn" in c o L n 10. I hereby certify that I am authorized to act for this agency in yatters pertaining to of its records and that the records roposed for disposal on the attached

346

Impact of the deployment schedule of fast breeding reactors in the frame of French act for nuclear materials and radioactive waste management  

SciTech Connect (OSTI)

In the frame of the French Act of June 28, 2006 on 'a sustainable management of nuclear materials and radioactive waste' EDF R and D assesses various research scenarios of transition between the actual French fleet and a Generation IV fleet with a closed fuel cycle where plutonium is multi-recycled. The basic scenarios simulate a deployment of 60 GWe of Sodium-cooled Fast Reactors (SFRs) in two steps: one third from 2040 to 2050 and the rest from 2080 to 2100 (scenarios 2040). These research scenarios assume that SFR technology will be ready for industrial deployment in 2040. One of the many sensitivity analyses that EDF, as a nuclear power plant operator, must evaluate is the impact of a delay of SFR technology in terms of uranium consumptions, plutonium needs and fuel cycle utilities gauging. The sensitivity scenarios use the same assumptions as scenarios 2040 but they simulate a different transition phase: SFRs are deployed in one step between 2080 and 2110 (scenarios 2080). As the French Act states to conduct research on minor actinides (MA) management, we studied different options for 2040 and 2080 scenarios: no MA transmutation, americium transmutation in heterogeneous mode based on americium Bearing Blankets (AmBB) in SFRs and all MA transmutation in heterogeneous mode based on MA Bearing Blankets (MABB). Moreover, we studied multiple parameters that could impact the deployment of these reactors (SFR load factor, increase of the use of MOX in Light Water Reactors, increase of the cooling time in spent nuclear fuel storage...). Each scenario has been computed with the EDF R and D fuel cycle simulation code TIRELIRE-STRATEGIE and optimized to meet various fuel cycle constraints such as using the reprocessing facility with long period of constant capacity, keeping the temporary stored mass of plutonium and MA under imposed limits, recycling older assemblies first... These research scenarios show that the transition from the current PWR fleet to an equivalent fleet of Generation IV SFR can follow different courses. The design of SFR-V2B that we used in our studies needs a high inventory of plutonium resulting in tension on this resource. Several options can be used in order to loosen this tension: our results lead to favour the use of axial breeding blanket in SFR. Load factor of upcoming reactors has to be regarded with attention as it has a high impact on plutonium resource for a given production of electricity. The deployment of SFRs beginning in 2080 instead of 2040 following the scenarios we described creates higher tensions on reprocessing capacity, separated plutonium storage and spent fuel storage. In the frame of the French Act, we studied minor actinides transmutation. The flux of MA in all fuel cycle plants is really high, which will lead to decay heat, a and neutron emission related problems. In terms of reduction of MA inventories, the deployment of MA transmutation cycle must not delay the installation of SFRs. The plutonium production in MABB and AmBB does not allow reducing the use of axial breeding blankets. The impact of MA or Am transmutation over the high level waste disposal is more important if the SFRs are deployed later. Transmutation option (americium or all MA) does not have a significant impact on the number of canister produced nor on its long-term thermal properties. (authors)

Le Mer, J.; Garzenne, C.; Lemasson, D. [Electricite de France R and D, 1, Avenue du General De Gaulle, 92141 Clamart (France)

2012-07-01T23:59:59.000Z

347

Life cycle costs for the domestic reactor-based plutonium disposition option  

SciTech Connect (OSTI)

Projected constant dollar life cycle cost (LCC) estimates are presented for the domestic reactor-based plutonium disposition program being managed by the US Department of Energy Office of Fissile Materials Disposition (DOE/MD). The scope of the LCC estimate includes: design, construction, licensing, operation, and deactivation of a mixed-oxide (MOX) fuel fabrication facility (FFF) that will be used to purify and convert weapons-derived plutonium oxides to MOX fuel pellets and fabricate MOX fuel bundles for use in commercial pressurized-water reactors (PWRs); fuel qualification activities and modification of facilities required for manufacture of lead assemblies that will be used to qualify and license this MOX fuel; and modification, licensing, and operation of commercial PWRs to allow irradiation of a partial core of MOX fuel in combination with low-enriched uranium fuel. The baseline cost elements used for this document are the same as those used for examination of the preferred sites described in the site-specific final environmental impact statement and in the DOE Record of Decision that will follow in late 1999. Cost data are separated by facilities, government accounting categories, contract phases, and expenditures anticipated by the various organizations who will participate in the program over a 20-year period. Total LCCs to DOE/MD are projected at approximately $1.4 billion for a 33-MT plutonium disposition mission.

Williams, K.A.

1999-10-01T23:59:59.000Z

348

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect (OSTI)

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

Not Available

1994-06-01T23:59:59.000Z

349

Development of a techno-economic model to optimization DOE spent nuclear fuel disposition  

SciTech Connect (OSTI)

The purpose of the National Spent Nuclear Fuel (NSNF) Program conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL) is to evaluate what to do with the spent nuclear fuel (SNF) in the Department of Energy (DOE) complex. Final disposition of the SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on the fuel type and the current locations of the fuel. One of the first steps associated with selecting one or more sites for treating the SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the electrometallurgical treatment process for fuels at several locations. The set of questions addresses all issues associated with the design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs will be applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating spent nuclear fuel.

Ramer, R.J.; Plum, M.M.; Adams, J.P.; Dahl, C.A.

1997-11-01T23:59:59.000Z

350

Microsoft PowerPoint - S08-05_Leishear_Salt Disposition Initiative.ppt  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Blending in Nuclear Waste Tanks Blending in Nuclear Waste Tanks Bob Leishear Savannah River Remediation Salt Disposition Engineering November 17, 2010 Print Close 2 Blending in Nuclear Waste Tanks Volume 37.1 Million Gallons (Mgal) Curies 183 MCi (52%) 169 MCi (48%) 352 Million Curies (MCi) 171 MCi (49%) Sludge 34.2 Mgal (92%) 2.9 Mgal (8%) 18.4 Mgal (49%) Salt Supernate 12 MCi (3%) Saltcake 15.8 Mgal (43%) Print Close 3 Blending in Nuclear Waste Tanks Sample of Vitrified Radioactive Glass Print Close 4 Blending in Nuclear Waste Tanks SDU 3 SDU 3 SDU 2 SDU 2 SDU (Vault) 4 SDU (Vault) 4 SDU (Vault) 1 SDU (Vault) 1 Cell A Cell B Saltstone Production Facility Saltstone Production Facility Print Close 5 Blending in Nuclear Waste Tanks Print Close 6 Blending in Nuclear Waste Tanks Sludge Salt Feed Solutions Print Close 7 Experimental Strategy Scale-

351

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

Broader source: Energy.gov (indexed) [DOE]

DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

352

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

Broader source: Energy.gov (indexed) [DOE]

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

353

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

Broader source: Energy.gov (indexed) [DOE]

Preliminary Quality Assurance Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications Used Fuel Disposition Campaign International Activities Implementation Plan

354

AEO2011: Liquid Fuels Supply and Disposition | OpenEI  

Open Energy Info (EERE)

Liquid Fuels Supply and Disposition Liquid Fuels Supply and Disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually

355

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

Broader source: Energy.gov (indexed) [DOE]

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

356

Low Level Waste Disposition - Quantity and Inventory | Department of  

Broader source: Energy.gov (indexed) [DOE]

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

357

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

Broader source: Energy.gov (indexed) [DOE]

Used Fuel Disposition Campaign Disposal Research and Development Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

358

Low Level Waste Disposition - Quantity and Inventory | Department of  

Broader source: Energy.gov (indexed) [DOE]

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

359

Integrated Tool Development for Used Fuel Disposition Natural System  

Broader source: Energy.gov (indexed) [DOE]

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

360

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

Broader source: Energy.gov (indexed) [DOE]

Industry Input on Nickel Disposition Strategy Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

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

Integrated Tool Development for Used Fuel Disposition Natural System  

Broader source: Energy.gov (indexed) [DOE]

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

362

AEO2011: Coal Supply, Disposition, and Prices | OpenEI  

Open Energy Info (EERE)

Supply, Disposition, and Prices Supply, Disposition, and Prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

363

EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing...  

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

Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin...

364

A Study of Cattle Disposition: Exploring QTL Associated with Temperament  

E-Print Network [OSTI]

In any production setting, cattle disposition (temperament) has a great impact on handling and performance. Thus, behavior can be economically important, yielding the rationale for study. Wegenhoft (2005) previously identified several quantitative...

Boldt, Clayton Ryan

2008-05-16T23:59:59.000Z

365

DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS  

SciTech Connect (OSTI)

The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best manage lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost.

Lobdell, D.; Geimer, R.; Larsen, P.; Loveland, K.

2003-02-27T23:59:59.000Z

366

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

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

Raymond L. Murray

2001-01-01T23:59:59.000Z

367

Radioactive waste storage issues  

SciTech Connect (OSTI)

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

Kunz, D.E.

1994-08-15T23:59:59.000Z

368

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING In general, building materials contain low levels of radioactivity. For example, the range of  

E-Print Network [OSTI]

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING MATERIALS In general, building materials contain low, especially in buildings constructed with materials containing uranium TENORM mine wastes. In the Grand the wastes from uranium mines have been removed from mining sites and used in local and nearby communities

369

Materials  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Materials Materials and methods are available as supplementary materials on Science Online. 16. W. Benz, A. G. W. Cameron, H. J. Melosh, Icarus 81, 113 (1989). 17. S. L. Thompson, H. S. Lauson, Technical Rep. SC-RR-710714, Sandia Nat. Labs (1972). 18. H. J. Melosh, Meteorit. Planet. Sci. 42, 2079 (2007). 19. S. Ida, R. M. Canup, G. R. Stewart, Nature 389, 353 (1997). 20. E. Kokubo, J. Makino, S. Ida, Icarus 148, 419 (2000). 21. M. M. M. Meier, A. Reufer, W. Benz, R. Wieler, Annual Meeting of the Meteoritical Society LXXIV, abstr. 5039 (2011). 22. C. B. Agnor, R. M. Canup, H. F. Levison, Icarus 142, 219 (1999). 23. D. P. O'Brien, A. Morbidelli, H. F. Levison, Icarus 184, 39 (2006). 24. R. M. Canup, Science 307, 546 (2005). 25. J. J. Salmon, R. M. Canup, Lunar Planet. Sci. XLIII, 2540 (2012). Acknowledgments: SPH simulation data are contained in tables S2 to S5 of the supplementary materials. Financial support

370

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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

1984-02-06T23:59:59.000Z

371

Evaluation of Trenchless Installation Technology for Radioactive Wastewater Piping Applications  

SciTech Connect (OSTI)

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

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

2009-09-01T23:59:59.000Z

372

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

Peters, T.; Fink, S.

2012-04-24T23:59:59.000Z

373

Bacteria eats radioactive waste  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

374

Plutonium stabilization and disposition focus area, FY 1999 and FY 2000 multi-year program plan  

SciTech Connect (OSTI)

Consistent with the Environmental Management`s (EM`s) plan titled, ``Accelerating Cleanup: Paths to Closure``, and ongoing efforts within the Executive Branch and Congress, this Multi-Year Program Plan (MYPP) for the Plutonium Focus Area was written to ensure that technical gap projects are effectively managed and measured. The Plutonium Focus Area (PFA) defines and manages technology development programs that contribute to the effective stabilization of nuclear materials and their subsequent safe storage and final disposition. The scope of PFA activities includes the complete spectrum of plutonium materials, special isotopes, and other fissile materials. The PFA enables solutions to site-specific and complex-wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. The report describes the current technical activities, namely: Plutonium stabilization (9 studies); Highly enriched uranium stabilization (2 studies); Russian collaboration program (2 studies); Packaging and storage technologies (6 studies); and PFA management work package/product line (3 studies). Budget information for FY 1999 and FY 2000 is provided.

NONE

1998-03-01T23:59:59.000Z

375

Survey of National Programs for Managing High-Level Radioactive  

E-Print Network [OSTI]

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

376

RADIOACTIVITY 1997 BNL Site Environmental Report 4 -1  

E-Print Network [OSTI]

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

377

Enhancements to System for Tracking Radioactive Waste Shipments...  

Broader source: Energy.gov (indexed) [DOE]

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

378

Disposition of fuel elements from the Aberdeen and Sandia pulse reactor (SPR-II) assemblies  

SciTech Connect (OSTI)

We describe the disposition of fuel from the Aberdeen (APR) and the Sandia Pulse Reactors (SPR-II) which were used to provide intense neutron bursts for radiation effects testing. The enriched Uranium - 10% Molybdenum fuel from these reactors was shipped to the Los Alamos National Laboratory (LANL) for size reduction prior to shipment to the Savannah River Site (SRS) for final disposition in the H Canyon facility. The Shipper/Receiver Agreements (SRA), intra-DOE interfaces, criticality safety evaluations, safety and quality requirements and key materials management issues required for the successful completion of this project will be presented. This work is in support of the DOE Consolidation and Disposition program. Sandia National Laboratories (SNL) has operated pulse nuclear reactor research facilities for the Department of Energy since 1961. The Sandia Pulse Reactor (SPR-II) was a bare metal Godiva-type reactor. The reactor facilities have been used for research and development of nuclear and non-nuclear weapon systems, advanced nuclear reactors, reactor safety, simulation sources and energy related programs. The SPR-II was a fast burst reactor, designed and constructed by SNL that became operational in 1967. The SPR-ll core was a solid-metal fuel enriched to 93% {sup 235}U. The uranium was alloyed with 10 weight percent molybdenum to ensure the phase stabilization of the fuel. The core consisted of six fuel plates divided into two assemblies of three plates each. Figure 1 shows a cutaway diagram of the SPR-II Reactor with its decoupling shroud. NNSA charged Sandia with removing its category 1 and 2 special nuclear material by the end of 2008. The main impetus for this activity was based on NNSA Administrator Tom D'Agostino's six focus areas to reenergize NNSA's nuclear material consolidation and disposition efforts. For example, the removal of SPR-II from SNL to DAF was part of this undertaking. This project was in support of NNSA's efforts to consolidate the locations of special nuclear material (SNM) to reduce the cost of securing many SNM facilities. The removal of SPR-II from SNL was a significant accomplishment in SNL's de-inventory efforts and played a key role in reducing the number of locations requiring the expensive security measures required for category 1 and 2 SNM facilities. A similar pulse reactor was fabricated at the Y-12 National Security Complex beginning in the late 1960's. This Aberdeen Pulse Reactor (APR) was operated at the Army Pulse Radiation Facility (APRF) located at the Aberdeen Test Center (ATC) in Maryland. When the APRF was shut down in 2003, a portion of the DOE-owned Special Nuclear Material (SNM) was shipped to an interim facility for storage. Subsequently, the DOE determined that the material from both the SPR-II and the APR would be processed in the H-Canyon at the Savannah River Site (SRS). Because of the SRS receipt requirements some of the material was sent to the Los Alamos National Laboratory (LANL) for size-reduction prior to shipment to the SRS for final disposition.

Mckerley, Bill [Los Alamos National Laboratory; Bustamante, Jacqueline M [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Drypolcher, Anthony F [Los Alamos National Laboratory; Hickey, Joseph [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

379

EA-1290: Disposition of Russian Federation Titled Natural Uranium |  

Broader source: Energy.gov (indexed) [DOE]

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

380

Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 |  

Broader source: Energy.gov (indexed) [DOE]

Savannah River Site Achieves Transuranic Waste Disposition Goal in Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 December 24, 2013 - 12:00pm Addthis Workers gather behind a “Safety and Security begins with Me” banner at the Savannah River Site. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site.

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

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and  

Broader source: Energy.gov (indexed) [DOE]

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

382

Paducah Demolition Debris Shipped for Disposition | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Demolition Debris Shipped for Disposition Demolition Debris Shipped for Disposition Paducah Demolition Debris Shipped for Disposition August 27, 2013 - 12:00pm Addthis The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow. The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow.

383

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect (OSTI)

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

384

End of FY10 report - used fuel disposition technical bases and lessons learned : legal and regulatory framework for high-level waste disposition in the United States.  

SciTech Connect (OSTI)

This report examines the current policy, legal, and regulatory framework pertaining to used nuclear fuel and high level waste management in the United States. The goal is to identify potential changes that if made could add flexibility and possibly improve the chances of successfully implementing technical aspects of a nuclear waste policy. Experience suggests that the regulatory framework should be established prior to initiating future repository development. Concerning specifics of the regulatory framework, reasonable expectation as the standard of proof was successfully implemented and could be retained in the future; yet, the current classification system for radioactive waste, including hazardous constituents, warrants reexamination. Whether or not consideration of multiple sites are considered simultaneously in the future, inclusion of mechanisms such as deliberate use of performance assessment to manage site characterization would be wise. Because of experience gained here and abroad, diversity of geologic media is not particularly necessary as a criterion in site selection guidelines for multiple sites. Stepwise development of the repository program that includes flexibility also warrants serious consideration. Furthermore, integration of the waste management system from storage, transportation, and disposition, should be examined and would be facilitated by integration of the legal and regulatory framework. Finally, in order to enhance acceptability of future repository development, the national policy should be cognizant of those policy and technical attributes that enhance initial acceptance, and those policy and technical attributes that maintain and broaden credibility.

Weiner, Ruth F.; Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Rechard, Robert Paul; Perry, Frank (Los Alamos National Laboratory, Los Alamos, NM); Jenkins-Smith, Hank C. (University of Oklahoma, Norman, OK); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Nutt, Mark (Argonne National Laboratory, Argonne, IL); Cotton, Tom (Complex Systems Group, Washington DC)

2010-09-01T23:59:59.000Z

385

Waste Disposition Update by Doug Tonkay  

Broader source: Energy.gov (indexed) [DOE]

www.em.doe.gov www.em.doe.gov 1 Environmental Management Site-Specific Advisory Chairs Meeting Douglas Tonkay Office of Disposal Operations October 20, 2011 o Continue to manage waste inventories in a safe and compliant manner. o Address high risk waste in a cost- effective manner. o Maintain and optimize current disposal capability for future generations. www.em.doe.gov 2 o Develop future disposal capacity in a complex environment. o Promote the development of treatment and disposal alternatives in the commercial sector. o Review current policies and directives and provide needed oversight. EM is treating radioactive tank waste . . . Hanford - 176M curies Idaho - 37M curies Savannah River Site - 379M curies www.em.doe.gov 3 Hanford ~ 2130 MTHM Idaho ~280 MTHM . . . storing spent nuclear fuel . . .

386

Radioactive Waste Incineration: Status Report  

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

387

Disposition and transportation of surplus radioactive low specific activity nitric acid. Volume 2, Environmental Assessment  

SciTech Connect (OSTI)

This volume consists of two appendices: public comments and DOE responses, and public comments not requiring responses.

NONE

1995-05-01T23:59:59.000Z

388

APS Radioactive Sample Safety Review Committee  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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

389

NEPA Cases Filed in 2010 2010 NEPA Case Dispositions  

Broader source: Energy.gov (indexed) [DOE]

Filed in 2010 2010 NEPA Case Dispositions Filed in 2010 2010 NEPA Case Dispositions Lead Defendant Cases Filed Injunctions - Remands Judgment for defendant 46 ARMY-USACE 6 3 Dismissal w/o settlement 11 DHS-USCG 0 0 Settlement 8 DOD 1 0 Adverse dispositions: 17 DOE-Energy 0 0 TRO 0 DOE-FERC 0 0 Preliminary Injunction 5 DOE-NNSA 1 0 Permanent Injunction 4 DOI-BIA 1 0 Remand 8 DOI-BLM 17 5 DOI-BOEM 5 0 Basis for 2010 NEPA Dispositions DOI-BOR 0 0 Jurisdictional - P prevailed 0 DOI-FWS 6 1 Jurisdictional - D prevailed 12 DOI-OSM 0 1 NEPA - Not required 1 DOI-NPS 2 2 NEPA - Is required 2 DOJ 0 0 CE - Adequate 4 DOS 0 0 CE - Not Adequate 1 DOT-FAA 3 0 EA - Adequate* 11 DOT-FHWA 10 1 EA - Not Adequate* 5 DOT-FTA 2 0 EIS - Adequate* 17 EPA 1 0 EIS - Not Adequate* 5

390

Metabolism and disposition of 1-bromopropane in rats and mice following inhalation or intravenous administration  

Science Journals Connector (OSTI)

Workplace exposure to 1-bromopropane (1-BrP) can potentially occur during its use in spray adhesives, fats, waxes, and resins. 1-BrP may be used to replace ozone depleting solvents, resulting in an increase in its annual production in the US, which currently exceeds 1 million pounds. The potential for human exposure to 1-BrP and the reports of adverse effects associated with potential occupational exposure to high levels of 1-BrP have increased the need for the development of biomarkers of exposure and an improved understanding of 1-BrP metabolism and disposition. In this study, the factors influencing the disposition and biotransformation of 1-BrP were examined in male F344 rats and B6C3F1 mice following inhalation exposure (800ppm) or intravenous administration (5, 20, and 100mg/kg). [1,2,3-13C]1-BrP and [1-14C]1-BrP were administered to enable characterization of urinary metabolites using NMR spectroscopy, LCMS/MS, and HPLC coupled radiochromatography. Exhaled breath volatile organic chemicals (VOC), exhaled CO2, urine, feces, and tissues were collected for up to 48h post-administration for determination of radioactivity distribution. Rats and mice exhaled a majority of the administered dose as either VOC (4072%) or 14CO2 (1030%). For rats, but not mice, the percentage of the dose exhaled as VOC increased between the mid (?50%) and high (?71%) dose groups; while the percentage of the dose exhaled as 14CO2 decreased (19 to 10%). The molar ratio of exhaled 14CO2 to total released bromide, which decreased as dose increased, demonstrated that the proportion of 1-BrP metabolized via oxidation relative to pathways dependent on glutathione conjugation is inversely proportional to dose in the rat. [14C]1-BrP equivalents were recovered in urine (1317%, rats; 1423% mice), feces (rats and mice administered i.v. 5 to 100mg/kg [14C]1-BrP. Metabolites characterized in urine of rats and mice include N-acetyl-S-propylcysteine, N-acetyl-3-(propylsulfinyl)alanine, N-acetyl-S-(2-hydroxypropyl)cysteine, 1-bromo-2-hydroxypropane-O-glucuronide, N-acetyl-S-(2-oxopropyl)cysteine, and N-acetyl-3-[(2-oxopropyl)sulfinyl]alanine. These metabolites may be formed following oxidation of 1-bromopropane to 1-bromo-2-propanol and bromoacetone and following subsequent glutathione conjugation with either of these compounds. Rats pretreated with 1-aminobenzotriazole (ABT), a potent inhibitor of P450 excreted less in urine (?30%), exhaled as 14CO2 (?80%), or retained in liver (?90%), with a concomitant increase in radioactivity expired as VOC (?52%). Following ABT pretreatment, rat urinary metabolites were reduced in number from 10 to 1, N-acetyl-S-propylcysteine, which accounted for >90% of the total urinary radioactivity in ABT pretreated rats. Together, these data demonstrate a role for cytochrome P450 and glutathione in the dose-dependent metabolism and disposition of 1-BrP in the rat.

C.E. Garner; S.C.J. Sumner; J.G. Davis; J.P. Burgess; Y. Yueh; J. Demeter; Q. Zhan; J. Valentine; A.R. Jeffcoat; L.T. Burka; J.M. Mathews

2006-01-01T23:59:59.000Z

391

Metabolism and disposition of 1-bromopropane in rats and mice following inhalation or intravenous administration  

SciTech Connect (OSTI)

Workplace exposure to 1-bromopropane (1-BrP) can potentially occur during its use in spray adhesives, fats, waxes, and resins. 1-BrP may be used to replace ozone depleting solvents, resulting in an increase in its annual production in the US, which currently exceeds 1 million pounds. The potential for human exposure to 1-BrP and the reports of adverse effects associated with potential occupational exposure to high levels of 1-BrP have increased the need for the development of biomarkers of exposure and an improved understanding of 1-BrP metabolism and disposition. In this study, the factors influencing the disposition and biotransformation of 1-BrP were examined in male F344 rats and B6C3F1 mice following inhalation exposure (800 ppm) or intravenous administration (5, 20, and 100 mg/kg). [1,2,3-{sup 13}C]1-BrP and [1-{sup 14}C]1-BrP were administered to enable characterization of urinary metabolites using NMR spectroscopy, LC-MS/MS, and HPLC coupled radiochromatography. Exhaled breath volatile organic chemicals (VOC), exhaled CO{sub 2}, urine, feces, and tissues were collected for up to 48 h post-administration for determination of radioactivity distribution. Rats and mice exhaled a majority of the administered dose as either VOC (40-72%) or {sup 14}CO{sub 2} (10-30%). For rats, but not mice, the percentage of the dose exhaled as VOC increased between the mid ({approx} 50%) and high ({approx} 71%) dose groups; while the percentage of the dose exhaled as {sup 14}CO{sub 2} decreased (19 to 10%). The molar ratio of exhaled {sup 14}CO{sub 2} to total released bromide, which decreased as dose increased, demonstrated that the proportion of 1-BrP metabolized via oxidation relative to pathways dependent on glutathione conjugation is inversely proportional to dose in the rat. [{sup 14}C]1-BrP equivalents were recovered in urine (13-17%, rats; 14-23% mice), feces (< 2%), or retained in the tissues and carcass (< 6%) of rats and mice administered i.v. 5 to 100 mg/kg [{sup 14}C]1-BrP. Metabolites characterized in urine of rats and mice include N-acetyl-S-propylcysteine, N-acetyl-3-(propylsulfinyl)alanine, N-acetyl-S-(2-hydroxypropyl)cysteine, 1-bromo-2-hydroxypropane-O-glucuronide, N-acetyl-S-(2-oxopropyl)cysteine, and N-acetyl-3-[(2-oxopropyl)sulfinyl]alanine. These metabolites may be formed following oxidation of 1-bromopropane to 1-bromo-2-propanol and bromoacetone and following subsequent glutathione conjugation with either of these compounds. Rats pretreated with 1-aminobenzotriazole (ABT), a potent inhibitor of P450 excreted less in urine ({down_arrow}30%), exhaled as {sup 14}CO2 ({down_arrow}80%), or retained in liver ({down_arrow}90%), with a concomitant increase in radioactivity expired as VOC ({up_arrow}52%). Following ABT pretreatment, rat urinary metabolites were reduced in number from 10 to 1, N-acetyl-S-propylcysteine, which accounted for > 90% of the total urinary radioactivity in ABT pretreated rats. Together, these data demonstrate a role for cytochrome P450 and glutathione in the dose-dependent metabolism and disposition of 1-BrP in the rat.

Garner, C.E. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)]. E-mail: cegarner@rti.org; Sumner, S.C.J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Davis, J.G. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Burgess, J.P. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Yueh, Y. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Demeter, J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Zhan, Q. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Valentine, J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Jeffcoat, A.R. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Burka, L.T. [National Institute of Environmental Health Sciences, Research Triangle Park, NC 27709 (United States); Mathews, J.M. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)

2006-08-15T23:59:59.000Z

392

Radioactive waste processing apparatus  

DOE Patents [OSTI]

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

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

1985-08-30T23:59:59.000Z

393

Radioactive Waste Management (Minnesota)  

Broader source: Energy.gov [DOE]

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

394

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect (OSTI)

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the Fission Options'' provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. (Westinghouse Hanford Co., Richland, WA (United States)); Walter, C.E. (Lawrence Livermore National Lab., CA (United States))

1993-02-05T23:59:59.000Z

395

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect (OSTI)

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the ``Fission Options`` provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. [Westinghouse Hanford Co., Richland, WA (United States); Walter, C.E. [Lawrence Livermore National Lab., CA (United States)

1993-02-05T23:59:59.000Z

396

Chapter 22 - Radioactive Waste Disposal  

Science Journals Connector (OSTI)

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

Raymond L. Murray

2009-01-01T23:59:59.000Z

397

Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

Washington, A. L. II; Peters, T. B.

2013-09-19T23:59:59.000Z

398

Used Fuel Disposition Campaign Disposal Research and Development Roadmap  

Broader source: Energy.gov (indexed) [DOE]

Disposal Research and Development Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW) generated by existing and future nuclear fuel cycles. The disposal of SNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has been made in the U.S and other nations, but gaps in knowledge still exist. This document provides an evaluation and prioritization of R&D opportunities

399

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

Broader source: Energy.gov (indexed) [DOE]

Disposal Research and Development Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

400

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

SciTech Connect (OSTI)

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

DOE

2002-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Preliminary siting characterization Salt Disposition Facility - Site B  

SciTech Connect (OSTI)

A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ``Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data.

Wyatt, D.

2000-01-04T23:59:59.000Z

402

Record of decision for the Storage and Disposition of Weapons- Usable  

Broader source: Energy.gov (indexed) [DOE]

14 14 Federal Register / Vol. 62, No. 13 / Tuesday, January 21, 1997 / Notices Responses: 18,620 Burden Hours: 64,310. Abstract: The LESCP is being conducted in response to the legislative requirement in P.L. 103-382, Section 1501 to assess the implementation of Title I and related education reforms. The information will be used to examine changes-over a 3-year period-that are occurring in schools and classrooms. Teachers and teacher aides will complete a mail survey, and district Title I administrators, principals, school-based staff, and parents will be interviewed during on- site field work. [FR Doc. 97-1307 Filed 1-17-97; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY Record of decision for the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic

403

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network [OSTI]

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

404

Upgrading the Radioactive Waste Management Infrastructure in Azerbaijan  

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

405

Savannah River Site Achieves Transuranic Waste Disposition Goal...  

Office of Environmental Management (EM)

liquid waste contractor, Savannah River Remediation (SRR): Closed two more underground tanks containing radioactive waste, helping reduce a significant environmental risk to South...

406

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

from State of New Mexico * Key Regulators * DOE - self regulation for nuclear safety and radioactive waste management * U.S. Environmental Protection Agency - Certification to...

407

Evaluation Of Used Fuel Disposition In Clay-Bearing Rock  

Broader source: Energy.gov [DOE]

Radioactive waste disposal in shale/argillite rock formations has been widely considered given its desirable isolation properties, e.g., low permeability, potential geochemically reduced conditions...

408

Nuclear materials stewardship: Our enduring mission  

SciTech Connect (OSTI)

The US Department of Energy (DOE) and its predecessors have handled a remarkably wide variety of nuclear materials over the past 50 yr. Two fundamental changes have occurred that shape the current landscape regarding nuclear materials. If one recognizes the implications and opportunities, one sees that the stewardship of nuclear materials will be a fundamental and important job of the DOE for the foreseeable future. The first change--the breakup of the Soviet Union and the resulting end to the nuclear arms race--altered US objectives. Previously, the focus was on materials production, weapon design, nuclear testing, and stockpile enhancements. Now the attention is on dismantlement of weapons, excess special nuclear material inventories, accompanying increased concern over the protection afforded to such materials; new arms control measures; and importantly, maintenance of the safety and reliability of the remaining arsenal without testing. The second change was the raised consciousness and sense of responsibility for dealing with the environmental legacies of past nuclear arms programs. Recognition of the need to clean up radioactive contamination, manage the wastes, conduct current operations responsibly, and restore the environment have led to the establishment of what is now the largest program in the DOE. Two additional features add to the challenge and drive the need for recognition of nuclear materials stewardship as a fundamental, enduring, and compelling mission of the DOE. The first is the extraordinary time frames. No matter what the future of nuclear weapons and no matter what the future of nuclear power, the DOE will be responsible for most of the country`s nuclear materials and wastes for generations. Even if the Yucca Mountain program is successful and on schedule, it will last more than 100 yr. Second, the use, management, and disposition of nuclear materials and wastes affect a variety of nationally important and diverse objectives, from national security to the future of nuclear power in this country and abroad, to the care of the environment. Sometimes these objectives are in concert, but often they are seen as competing or being in conflict. By recognizing the corporate responsibility for these materials and the accompanying programs, national decision making will be improved.

Isaacs, T.H. [Lawrence Livermore National Lab., CA (United States)

1998-12-31T23:59:59.000Z

409

Microsoft Word - CX-MountainAvenueDispositionFY12_WEB.doc  

Broader source: Energy.gov (indexed) [DOE]

1, 2012 REPLY TO ATTN OF: KEPR-4 SUBJECT: Environmental Clearance Memorandum Joan Kendall Realty Specialist - TERR-3 Proposed Action: Disposition of Mountain Avenue Substation and...

410

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

What is computer analysis? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Accurate determination of package behavior for impact and puncture accidents can be obtained by testing sub-scale models. This technique is frequently used in conjunction with full-scale tests and computer analyses. Full-scale spent fuel packages can weigh 250,000 pounds (three fully loaded semi-trucks) or more, therefore the ability to determine the behavior with scale-models improves testing safety and reduces testing costs. *** 1/4 Scale Free Drop Test 1/4 Scale Component Free Drop Test 1/3 Scale Puncture Test 1/2 Scale Puncture Test 1/8 Scale Rail Crush Test [scale model DROP test] Click to view picture [scale model component test]

411

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Package Certification Using Computer Analysis Package Certification Using Computer Analysis Engineering Principles Established by Three Early Scientists Engineering Principles Applied to Ancient Structures Description of Computer Model in Computer Analysis Engineered Structures Built WITHOUT the Use of Computer Analysis Structures Analyzed WITH the Use of Computer Analysis What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Computer analysis is an application of known engineering principles that take advantage of high-power computing capabilities in solving the response of computer models to various environments with complex mathematical calculations. Computer analysis can be used for package certification by generating a

412

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

What are examples of severe testing? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. These full-scale tests, conducted at Sandia National Laboratories Transportation Programs, demonstrate how spent fuel casks perform in accident environments that are more similar to what may happen during actual shipments. Each of the tests included the transportation vehicle as well as the cask. The damage to the casks from these tests was less than the damage during the regulatory hypothetical accident tests, demonstrating that the regulatory tests are more severe. DESCRIPTION PHOTO DURING TEST PHOTO AFTER TEST PHOTO OF PACKAGE AFTER TEST VIDEO OF TEST CRASH TEST Cask rail car with a 74 ton Type B Package on it crashing into a 690 ton concrete block at 81 miles per hour [photo]

413

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Free Drop Comparison Crush Comparison Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Hypothetical Accident Conditions: Six tests as defined in 10 CFR Part 71.73 of the NRC transportation regulations were established to provide repeatable and definable conditions that encompass most real-life accidents. The real-life accidents on this page are comparisons to the environments that the regulatory hypothetical accidents protect against. The collision forces or fire temperature and duration that were present in each accident are similar to the conditions that spent fuel casks are designed to survive. Passenger Train and Semi-truck Trailer Collision [DROP scenario] Mack Truck and Subaru Collision [CRUSH scenario] Freight Train and Freight Train Collision

414

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Comments & Questions Gary Lanthrum, DOE/NTP Albuquerque, NM E-mail: glanthrum@doeal.gov Phone: (505) 845-5277 Fax: (505) 845-5508 Ashok K. Kapoor, DOE/NTP Albuquerque, NM E-mail: akapoor@doeal.gov Phone: (505) 845-4574 Fax: (505) 845-5508 David R. Miller, SNL/TP Manager, Albuquerque, NM E-mail: drmille@sandia.gov Phone: (505) 284-2574 Fax: (505) 844-2829 Mona L. Aragon, SNL/TP Advanced Visualization, Albuquerque, NM E-mail: mlrage@sandia.gov Phone: (505) 844-2541 Fax: (505) 844-0244 Doug Ammerman, SNL/TP Structural Analysis, Albuquerque, NM E-mail: djammer@sandia.gov Phone: (505) 845-8158 Fax: (505) 844-0244 Fran Kanipe, SNL/TP Computer Programming, Albuquerque, NM E-mail: flkanip@sandia.gov Phone: (505) 844-1121 Fax: (505) 844-0244 Carlos Lopez, SNL/TP Thermal Analysis, Albuquerque, NM

415

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Photos 30-Foot Free Drop Test jpeg, 788K [photo] Click to view picture 1100-Pound Crush Test jpeg, 448K [photo] Click to view picture 40-Inch Puncture Test jpeg, 912K [photo] Click to view picture 30-Minute Pool Fire Test jpeg, 88K [photo] Click to view picture 8-Hour Immersion Test jpeg, 416K [photo] Click to view picture Graphics Unyielding Target jpeg, 144K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic Movies 30-Foot Free Drop Test AVI, 4.5 MB [movie] Click to view movie 1/3-Scale Puncture Test AVI, 3.3 MB [movie] Click to view movie 30-Minute

416

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Crush Comparison Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Comparison of the Free Drop Test to a Passenger Train and Semi-truck Trailer Collision Free Drop Test 3,000,000 lbs of force present in this package certification test. [DROP test] Click to view picture Real-life Accident Comparison 1,000,000 lbs of force present in this real-life accident. [DROP scenario] Click to view picture Real-life scenarios that are encompassed by the above test include: the package being struck by a train traveling 60 MPH the package falling off of a 30-foot high bridge onto solid rock or from a higher bridge onto a highway or railroad the package running into a bridge support or rock slope at 45 MPH. Packages are transported onboard trucks or rail cars, which absorb some of the impact energy, reducing the resulting damage to the packages from the accident. On May 2, 1995, an O&J Gordon Trucking Company truck consisting of a tractor and a lowbed semitrailer became lodged on a high-profile (hump) railroad grade crossing near Sycamore, South Carolina. About 35 minutes later, the truck was struck by southbound Amtrak train No. 81, Silver Star, en route from New York City to Tampa, Florida.

417

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

REGULATIONS & GUIDANCE SEARCH SITE MAP SITE MAP SAFE HOME Search Site RAM PACKAGES What are they? When are they used? How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record TESTING & CERTIFICATION How are packages certified? What are full-scale tests? What are scale-model tests? What is computer analysis? Package Certification Using Computer Analysis Engineering Principles Established by Three Early Scientists Engineering Principles Applied to Ancient Structures Description of Computer Model in Computer Analysis Engineered Structures Built WITHOUT the Use of Computer Analysis Structures Analyzed WITH the Use of Computer Analysis What are examples of severe testing? How do the certification tests compare to real-life accidents?

418

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Comparison of the Free Drop Test to a Mack Truck and Subaru Collision Crush Test 200,000 lbs of force present in this package certification test. [CRUSH test] Click to view picture Real-life Accident Comparison 60,000 lbs of force present in this real-life accident. [CRUSH scenario] Click to view picture Real-life scenarios that the above test* is designed to protect against include: the package being under a vehicle during a pile-up accident the package being pinned between two vehicles during a collision. The 55 gallon drum is an overpack for a smaller (6-inch diameter x 18-inch long, 1/4-inch thick stainless steel walled) package that is inside. Note*: This test is ONLY for packages weighing less than 500 kg (1100 lbs). On April 25, 1996, a Mack truck with a concrete mixer body, unable to stop, proceeded through an intersection at the bottom of an exit ramp. It collided with and overrode a Subaru passenger car near Plymouth Meeting, Pennsylvania.

419

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

What are examples of severe testing? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Purpose Background Results References Demonstrating Target Hardness between an Unyielding Target vs. Concrete Target During 30-foot Drop Tests. 30-foot 1/2 scale DHLW (Defense High-Level Waste) cask drop onto an unyielding target click to play, avi 4.7MB 30-foot 1/2 scale DHLW (Defense High-Level Waste) cask drop onto a 1/2 scale (5 1/2 inch) concrete pad click to play, avi 2.5MB 30-foot van drop onto an unyielding target click to play, avi 3.7MB 30-foot van drop onto an 11 inch concrete pad click to play, avi 3.4MB Purpose [ Back to top of page ] The purpose of this series of tests is to visually demonstrate the severity of the Type B Hypothetical Accident Condition impact test (10 CFR Part

420

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Immersion Comparison Demonstrating target hardness. Comparison of the Fire Test to a Gasoline Tanker and Sedan collision under an Overpass Fire Test [FIRE test] Click to view picture Real-life Accident Comparison [FIRE scenario] Click to view picture Real-life scenarios that the above test is designed to protect against include being involved in an accident with a gasoline tanker truck, causing the gasoline contents to burn the package. The amount of fuel being burned is approximately 5000 gallons in a pool 30 feet in diameter. During this test, the package is fully engulfed in the fire and is not protected by a transporting vehicle. On October 9, 1997, a truck tractor pulling a cargo tank semitrailer was going under an overpass of the New York State Thruway in Yonkers, New York when it was struck by a sedan. The car hit the right side of the cargo tank in the area of the tank's external loading/unloading lines, releasing the 8800 gallons of gasoline they contained.

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Emergency Responder Radioactive Material Quick Reference Sheet  

Broader source: Energy.gov [DOE]

This job aid is a quick reference to assist emergency responders in identifying preliminary safety precautions that should be taken during the initial response phase after arrival at the scene of...

422

Radioactive Materials Transportation and Incident Response  

Broader source: Energy.gov [DOE]

This booklet was written to answer questions most frequently asked by fire fighters, law enforcement officers, and emergency medical services personnel. The booklet is not intended as a substitute...

423

ETEC - Radioactive Handling Materials Facility (RMHF) Leachfield...  

Office of Environmental Management (EM)

of Plume (acres): 2 Plume Status: Plume expanding but not expected to migrate offsite Remedial Approach Remedy Name Status Start Date End Date Groundwater Use Exit Strategy...

424

Recovering Radioactive Materials with ORSP Team  

ScienceCinema (OSTI)

The National Nuclear Security Administration sponsors a program, executed by Los Alamos National Laboratory, to recover radioisotopes used by industry and academia and no longer needed. Called the "Offsite Source Recovery Program (OSRP), it has recovered more than 16,000 orphan sources as of 2008.

LANL

2009-09-01T23:59:59.000Z

425

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

National Nuclear Security Administration (NNSA)

established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible, identify, secure, remove andor...

426

Recovering Radioactive Materials with OSRP team  

ScienceCinema (OSTI)

The National Nuclear Security Administration sponsors a program, executed by Los Alamos National Laboratory, to recover radioisotopes used by industry and academia and no longer needed. Called the "Offsite Source Recovery Program (OSRP), it has recovered

None

2010-01-08T23:59:59.000Z

427

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Structures Analyzed WITH the Use of Computer Analysis Structures Analyzed WITH the Use of Computer Analysis What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Structural Analysis and Thermal Analysis of RAM Packaging Sandia National Laboratories jpeg, 24K Click to view picture AVI, 344K Click to view movie jpeg, 100K Click to view picture AVI, 1.5 MB Click to view movie C-1500 Truck Model Crash Analysis National Crash Analysis Center jpeg, 60K Click to view picture AVI, 616K Click to view movie AVI, 1.4 MB Click to view movie AVI, 368K Click to view movie Ship-to-Ship Collision Sandia National Laboratories Simulation Testing of Tire Designs Sandia National Laboratories jpeg, 72K Click to view picture AVI, 6.9 MB Click to view movie jpeg, 88K

428

DOE - Safety of Radioactive Material Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Biological Responses Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions [RAD Pie Chart] Exposure Source Average annual dose to an individual in the United States (millirem) Natural sources (including radon) - Ground, cosmic, and terrestrial - Internal radiation 200 mrem 100 mrem Occupational 0.9 mrem Nuclear Fuel Cycle 0.05 mrem Consumer Products - Tobacco - Other (i.e., smoke detectors, exit signs, luminous watch dials) Dose to lungs ~16,000 mrem 5 - 13 mrem Environmental Sources 0.06 mrem Medical - Diagnostic X-rays - Nuclear Medicine 39 mrem 14 mrem Approximate Annual Total 360 mrem [Radiation] Everyone in the world is continuously exposed to naturally-occuring background radiation. The average radiation dose received by the United

429

Used fuel disposition research and development roadmap - FY10 status.  

SciTech Connect (OSTI)

Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R&D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R&D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been made in the U.S. and other nations in understanding disposal concepts in different geologic media, but gaps in knowledge still exist. A principal aspect of concern to the UFDC as it considers the broad issues of siting a repository in different geologic media are the marked differences in the regulatory bases for assessing suitability and safety of a repository between the U.S. and other nations. Because the probability based - risked informed nature of the current U.S. regulations for high-level radioactive waste and spent nuclear fuel is sufficiently different from other regulations, information gained in previous studies, while useful, likely need to be supplemented to enable more convincing communication with the public, better defense of the numerical models, and stronger safety cases. Thus, it was recognized when the UFDC was established that there were readily identified disposal-related R&D opportunities to address knowledge gaps. An effort to document these research opportunities was a key component of Fiscal Year (FY) 2010 engineered system, natural system, and system-level modeling activities for a range of disposal environments. A principal contribution to identifying these gaps was a workshop held to gather perspectives from experts both within and external to the UFDC regarding R&D opportunities. In the planning for FY2010 it was expected that these activities would culminate with a UFDC research and development roadmap that would identify the knowledge gaps, discuss the R&D needed to fill these gaps, and prioritize the proposed R&D over both the near- and long-term. A number of knowledge gaps and needed R&D were identified and are discussed in this report. However, these preliminary R&D topics have not been evaluated in detail nor have they been prioritized to support future planning efforts. This will be completed in FY11 and the final UFDC Research and Development Roadmap will be completed. This report discusses proposed R&D topics in three areas related to repository siting, design, and performance: natural systems

Nutt, W. M. (Nuclear Engineering Division)

2010-10-01T23:59:59.000Z

430

Measurement of natural radioactivity from soil samples of Sind, Pakistan  

Science Journals Connector (OSTI)

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

S. A. Mujahid; S. Hussain

2011-06-01T23:59:59.000Z

431

Natural radioactivity in soil in the Baluchistan province of Pakistan  

Science Journals Connector (OSTI)

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

S. A. Mujahid; S. Hussain

2010-08-01T23:59:59.000Z

432

LANL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate the LA program. These modifications consist mostly of minor equipment upgrades. A commercial reactor operator has not been identified for the LA irradiation. Postirradiation examination (PIE) of the irradiated fuel will take place at either Oak Ridge National Laboratory or ANL-W. The only modifications required at either PIE site would be to accommodate full-length irradiated fuel rods. Results from this program are critical to the overall plutonium distribution schedule.

Fisher, S.E.; Holdaway, R.; Ludwig, S.B. [and others

1998-08-01T23:59:59.000Z

433

Hanford MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 1 facility. In all, a total of three LA MOX fuel fabrication options were identified by Hanford that could accommodate the program. In every case, only minor modification would be required to ready any of the facilities to accept the equipment necessary to accomplish the LA program.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

434

E-Print Network 3.0 - alpha contaminated material Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

possible. Radioactively Contaminated... consumption by removing levels of naturally occurring radioactive materials found in raw water supplies... . As large quantities of water...

435

Nonconforming Material Process  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

11 Nonconforming Material / Product Process 11_0304 Page 1 of 6 11 Nonconforming Material / Product Process 11_0304 Page 1 of 6 EOTA - Business Process Document Title: Nonconforming Material / Product Process Document Number: P-011 Rev. 11_0304 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: Q-001, Quality Manual Notify of Changes: EOTA Employees Referenced Document(s): F-015 Nonconformance Report, REG-003 Record Register, ISDP-002 Training Production Process P-011 Nonconforming Material / Product Process 11_0304 Page 2 of 6 Revision History: Rev. Description of Change A Initial Release 08_0416 Added verbiage CAR/PAR/IO to Step 2 P-011 Nonconforming Material / Product Process 11_0304 Page 3 of 6 I. Purpose To establish the process for nonconforming material to be identified, segregated and dispositioned to prevent its unintended

436

Sound propagation in urban areas: A periodic disposition of buildings  

Science Journals Connector (OSTI)

A numerical simulation of background noise propagation is performed for a network of hexagonal buildings. The obtained results suggest that the prediction of background noise in urban spaces is possible by means of a modified diffusion equation using two parameters: the diffusion coefficient that expresses the spreading out of noise resulting from diffuse scattering and multiple reflections by buildings, and an attenuation term accounting for the wall absorption, atmospheric attenuation, and absorption by the open top. The dependence of the diffusion coefficient with geometrical shapes and the diffusive nature of the buildings are investigated in the case of a periodic disposition of hexagonal buildings.

J. Picaut; J. Hardy; L. Simon

1999-10-01T23:59:59.000Z

437

Abstract 4241: Preclinical studies of brain/brain tumor disposition and antitumor efficacy of the aromatase inhibitor letrozole  

Science Journals Connector (OSTI)

...San Diego, CA Abstract 4241: Preclinical studies of brain/brain tumor disposition and antitumor efficacy of the aromatase...target for the treatment of CNS malignancies, as well as brain disposition and anti-tumor efficacy of letrozole, an...

Nimita Dave; Pankaj B. Desai; Gary A. Gudelsky; Kathleen LaSance; Lionel M.L. Chow; Xiaoyang Qi

2014-10-01T23:59:59.000Z

438

Neutron Assay System for Con?nement Vessel Disposition  

SciTech Connect (OSTI)

Waste will be removed from confinement vessels remaining from 1970s-era experiments. Los Alamos has 9+ spherical confinement vessels remaining from experiments. Each vessel contains {approx} 500 lbs of radioactive debris such as actinide metals and oxides, metals, powdered silica, graphite, and wires and hardware. In order to dispose of the vessels, debris and contamination must be removed. Neutron assay system was designed to assay vessels before and after cleanout. System requirements are: (1) Modular and moveable; (2) Capable of detecting {approx}100g {sup 239}Pu equivalent in a 2-inch thick steel sphere with 6 foot diameter; and (3) Capable of safeguards-quality assays. Initial design parameters arethe use of 4-atm {sup 3}He tubes with length of 6 feet, and {sup 3}He tubes embedded in polyethelene for moderation. This paper describes the calibration of the Confinement Vessel Assay System (CVAS) and quantification of its uncertainties. Assay uncertainty depends on five factors: (1) Statistical uncertainty in the assay measurement; (2) Statistical uncertainty in the background measurement; (3) Statistical uncertainty in the isotopics determination - This should be much smaller than the other uncertainties; (4) Systematic uncertainty due to position bias; and (5) Systematic uncertainty due to fluctuations in cosmic ray spallation. This one can be virtually eliminated by performing the background measurement with an empty vessel - but that may not be possible. We used modeling and experiments to quantify the systematic uncertainties. The calibration assumes a uniform distribution of material, but reality will be different. MCNPX modeling was used to quantify the positional bias. The model was benchmarked to build confidence in its results. Material at top of vessel is 44% greater than amount assayed, according to singles. Material near 19-tube detector is 38% less than amount assayed, according to singles. Cosmic ray spallation contributes significantly to the background. Comparing rates with and without a vessel showed that spallation adds an average of 27.27 singles/s and 5.45 doubles/s to background. Errors in the background rates were estimated at 20%.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

439

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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

1999-07-09T23:59:59.000Z

440

Implementation Guide for Surveillance and Maintenance during Facility Transition and Disposition  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

As DOE facilities complete mission operations and are declared excess, they pass into a transition phase that ultimately prepares them for disposition. The disposition phase of a facility's life cycle usually includes deactivation, decommissioning, and surveillance and maintenance (S&M) activities.

1999-09-29T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Fisetin disposition and metabolism in mice: Identification of geraldol as an active metabolite  

E-Print Network [OSTI]

1 Fisetin disposition and metabolism in mice: Identification of geraldol as an active metabolite title: Fisetin disposition and metabolism in mice ** Corresponding author: Dr. Guy G. Chabot, Chemical-yl)-3,5-diphenyltetrazolium; PBS, phosphate buffered saline. Keywords: flavonoid, fisetin

Paris-Sud XI, Université de

442

RADIOACTIVE ELEMENT REMOVAL FROM WATER USING GRAPHENE OXIDE (GO)  

E-Print Network [OSTI]

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

Concklin, Joshua Paul

2013-12-19T23:59:59.000Z

443

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final  

Broader source: Energy.gov (indexed) [DOE]

Idaho High-Level Waste and Facilities Disposition Final Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, DOE/EIS-0287 (September 2002)

444

EIS-0287: Idaho High-Level Waste & Facilities Disposition | Department of  

Broader source: Energy.gov (indexed) [DOE]

7: Idaho High-Level Waste & Facilities Disposition 7: Idaho High-Level Waste & Facilities Disposition EIS-0287: Idaho High-Level Waste & Facilities Disposition SUMMARY This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD January 12, 2010 EIS-0287: Amended Record of Decision Idaho High-Level Waste and Facilities Disposition January 4, 2010

445

Consent Order, Uranium Disposition Services, LLC - NCO-2010-01 | Department  

Broader source: Energy.gov (indexed) [DOE]

Uranium Disposition Services, LLC - NCO-2010-01 Uranium Disposition Services, LLC - NCO-2010-01 Consent Order, Uranium Disposition Services, LLC - NCO-2010-01 March 26, 2010 Consent Order issued to Uranium Disposition Services, LLC related to Construction Deficiencies at the DUF6 Conversion Buildings at the Portsmouth and Paducah Gaseous Diffusion Plants The Office of Health, Safety and Security's Office of Enforcement has completed its investigation into the facts and circumstances associated with construction deficiencies at the DUF6 Conversion Buildings located at the Portsmouth and Paducah Gaseous Diffusion Plants. The investigation reports, dated January 22, 2009, and April 23, 2009, were provided to Uranium Disposition Services, LLC (DDS), and addressed specific areas of potential noncompliance with DOE nuclear safety requirements established in

446

U.S. Natural Gas Monthly Supply and Disposition Balance  

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

Monthly Supply and Disposition Balance Monthly Supply and Disposition Balance (Billion Cubic Feet) Period: Monthly Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Data Series Apr-13 May-13 Jun-13 Jul-13 Aug-13 Sep-13 View History Gross Withdrawals 2,473 2,541 2,444 2,550 2,540 2,465 1973-2013 Marketed Production 2,086 2,166 2,097 2,188 2,188 2,105 1973-2013 NGPL Production, Gaseous Equivalent 107 110 107 113 117 116 1973-2013 Dry Production 1,979 2,056 1,990 2,076 2,071 1,989 1973-2013 Supplemental Gaseous Fuels 5 5 3 3 5 5 1973-2013 Net Imports 95 92 103 108 106 123 1973-2013 Net Storage Withdrawals -136 -418 -372 -275 -270 -355 1973-2013 Balancing Item 14 12 9 7 6 -5 2001-2013

447

Draft Environmental Assessment on the Remote-handled Waste Disposition  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment The U.S. Department of Energy invites the public to review and comment on a draft environmental assessment that the Department issued today, for a proposal to process approximately 327 cubic meters of remote-handled waste currently stored at the Idaho National Laboratory. An additional five cubic meters of waste stored at the Hanford Site near Richland, Washington is also evaluated since it is reasonably foreseeable that a decision may be made in the future to send that waste to Idaho for treatment. The project is necessary to prepare the waste for legally-required disposal. Under the Department�s preferred alternative, workers would use sealed rooms called hot cells at the Idaho Nuclear Technology and Engineering Center (INTEC) to process the waste, treat it as necessary and repackage it so that it is ready for disposal. The document describes the modifications necessary to hot cells to perform the work.

448

Innovative Resin Transfer and Disposition at Indian Point Unit 1  

SciTech Connect (OSTI)

A number of sites have both operating and shuttered nuclear facilities. Reducing dose to the caretakers can have beneficial effects for other site personnel who may work or pass near the shuttered facility. Furthermore, disposition of waste can have a positive effect on NRC required regular reporting of, and plans for the disposition of on-site wastes. Entergy's Indian Point Energy Center recently reduced the on-site curie load by working with RWE NUKEM and WMG, Inc. to innovatively free and ship nearly 1,000 cubic feet and nearly 600 curies of 30 year old resin and sludge from Unit 1. Old drawings, operations logs, were consulted and transfer lines were remotely checked. The tank selection sequence was primarily based on dose rates. System modifications to facilitate resin transfer were made on the lowest dose tanks first to gain current operating experience. Resin transfers were performed in accordance with the procedures developed, into waiting cask with appropriate waste containers. Decomposed resin of varying consistency could clog discharge lines and operational changes were made to mitigate against flow interruptions. Hydrogen buildup in the tanks was carefully addressed while solidified resin remains a challenge to be overcome. (authors)

Posivak, E.J.; Freitag, A.A.; Miller, R.J. [WMG, Inc., Peekskill, NY (United States)

2007-07-01T23:59:59.000Z

449

Major Risk Factors Integrated Facility Disposition Project - Oak Ridge  

Broader source: Energy.gov (indexed) [DOE]

O O O f f f f i i c c e e o o f f E E n n v v i i r r o o n n m m e e n n t t a a l l M M a a n n a a g g e e m m e e n n t t ( ( E E M M ) ) E E n n g g i i n n e e e e r r i i n n g g a a n n d d T T e e c c h h n n o o l l o o g g y y External Technical Review (ETR) Report Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN AUGUST 1, 2008 Acknowledgement The External Technical Review of the Integrated Facility Disposition Project was conducted simulta