National Library of Energy BETA

Sample records for materials handled radiological

  1. Handling and Packaging a Potentially Radiologically Contaminated...

    Office of Environmental Management (EM)

    Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is...

  2. Handling and Packaging a Potentially Radiologically Contaminated Patient

    Broader source: Energy.gov [DOE]

    The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients.

  3. Handling difficult materials: Textiles

    SciTech Connect (OSTI)

    Polk, T.

    1994-07-01

    As recyclable materials, textiles are a potentially valuable addition to community collection programs. They make up a fairly substantial fraction--about 4%--of the residential solid waste stream, a higher figure than corrugated cardboard or magazines. Textiles have well-established processing and marketing infrastructures, with annual sales of over $1 billion in the US And buyers are out there, willing to pay $40 to $100 per ton. There doesn't seem to be any cumbersome government regulations standing in the way, either. So why are so few municipalities and waste haulers currently attempting to recover textiles The answers can be found in the properties of the material itself and a lack of knowledge about the existing textile recycling industry. There are three main end markets that come from waste textiles. In descending order of market share, they are: used clothing, fiber for paper and re-processing, and industrial wiping and polishing cloths.

  4. Ergonomic material-handling device

    DOE Patents [OSTI]

    Barsnick, Lance E.; Zalk, David M.; Perry, Catherine M.; Biggs, Terry; Tageson, Robert E.

    2004-08-24

    A hand-held ergonomic material-handling device capable of moving heavy objects, such as large waste containers and other large objects requiring mechanical assistance. The ergonomic material-handling device can be used with neutral postures of the back, shoulders, wrists and knees, thereby reducing potential injury to the user. The device involves two key features: 1) gives the user the ability to adjust the height of the handles of the device to ergonomically fit the needs of the user's back, wrists and shoulders; and 2) has a rounded handlebar shape, as well as the size and configuration of the handles which keep the user's wrists in a neutral posture during manipulation of the device.

  5. Specialty Vehicles and Material Handling Equipment

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

    Industrial Power Efficient Simple Clean Today Industrial Power Efficient Simple Clean Today Specialty Vehicles and Material Handling Equipment Specialty Vehicles and Material Handling Equipment Specialty Vehicles and Material Handling Equipment Specialty Vehicles and Material Handling Equipment Matching Federal Government Energy Needs with Energy Efficient F Matching Federal Government Energy Needs with Energy Efficient F Matching Federal Government Energy Needs with Energy Efficient F Matching

  6. Hydrogen Fuel for Material Handling

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

    p Hydrogen Fuel for Hydrogen Fuel for Material Handling Tom Joseph © Air Products & Chemicals, Inc., 2009 7201 Hamilton Blvd Allentown PA 18195 7201 Hamilton Blvd., Allentown PA 18195 Fuel Cell Packs for MHE Form Fit and Function Battery Replacement Form, Fit and Function Battery Replacement © Air Products & Chemicals, Inc., 2009 Courtesy of Ballard Power Systems 31.1 x 13.2 x 31.6 LWH MHE Classes and Pack size 4kW 9kW 14kW 4kW 9kW 14kW CLASS 1 Forklift 32 x 38.6 x 22.7" LWH CLASS

  7. Operating Experience Level 3, Losing Control: Material Handling...

    Energy Savers [EERE]

    Losing Control: Material Handling Dangers Operating Experience Level 3, Losing Control: Material Handling Dangers October 23, 2014 OE-3 2014-05: Losing Control: Material Handling...

  8. Early Markets: Fuel Cells for Material Handling Equipment | Department...

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

    Material Handling Equipment Early Markets: Fuel Cells for Material Handling Equipment This fact sheet describes the use of hydrogen fuel cells to power material handling equipment ...

  9. Nuclear & Radiological Material Removal | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    & Radiological Material Removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  10. Hydrogen Fuel for Material Handling | Department of Energy

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

    for Material Handling Hydrogen Fuel for Material Handling Presented by Tom Joseph at the National Hydrogen Assocation Conference and Hydrogen Expo PDF icon josephinfrastructurefo...

  11. APPARATUS FOR HANDLING MIXTURES OF SOLID MATERIALS

    DOE Patents [OSTI]

    Hubbell, J.P.

    1959-08-25

    An apparatus is described for handling either a mixture of finely subdivided materials or a single material requiring a compacting action thereon preparatory to a chemical reducing process carried out in a crucible container. The apparatus is designed to deposit a mixture of dust-forming solid materials in a container while confining the materials against escape into the surrounding atmosphere. A movable filling tube, having a compacting member, is connected to the container and to a covered hopper receiving the mixture of materials. The filling tube is capable of reciprocating in the container and their relative positions are dependent upon the pressure established upon the material by the compacting member.

  12. DOE Hydrogen Storage Technical Performance Targets for Material Handling Equipment

    Broader source: Energy.gov [DOE]

    This table summarizes hydrogen storage technical performance targets for material handling equipment.

  13. GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material...

    National Nuclear Security Administration (NNSA)

    GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material May 29, 2014 GTRI's Remove Program works around the world to remove excess nuclear and radiological materials ...

  14. Bag-out material handling system

    DOE Patents [OSTI]

    Brak, Stephen B.; Milek, Henry F.

    1984-01-01

    A bagging device for transferring material from a first chamber through an pening in a wall to a second chamber includes an outer housing communicating with the opening and having proximal and distal ends relative to the wall. An inner housing having proximal and distal ends corresponding to those of the outer housing is mounted in a concentrically spaced, sealed manner with respect to the distal end of the outer housing. The inner and outer housings and mounting means therebetween define an annular chamber, closed at its distal end and open at its proximal end, in which a pliable tube is slidably positioned in sealed engagement with the housings. The pliable tube includes a sealed end positioned adjacent the proximal end of the inner housing so as to maintain isolation between the first and second chambers. Displacement of the material to be bagged from the first chamber along the inner housing so as to contact the sealed portion of the pliable bag allows the material to be positioned within the pliable bag in the second chamber. The bag is then sealed and severed between where the material is positioned therein and the wall in providing a sealed container for handling the material. The pliable tube when substantially depleted slides onto a narrow portion of the inner housing to allow a new pliable tube to be positioned over the old pliable tube. Remnants of the old pliable tube are then discharged into the new pliable tube with the bagging and removal of additional material.

  15. Bag-out material handling system

    DOE Patents [OSTI]

    Brak, Stephen B.

    1985-01-01

    A bagging device for transferring material from a first chamber through an opening in a wall to a second chamber includes an outer housing communicating with the opening and having proximal and distal ends relative to the wall. An inner housing having proximal and distal ends corresponding to those of the outer housing is mounted in a concentrically spaced, sealed manner with respect to the distal end of the outer housing. The inner and outer housings and mounting means therebetween define an annular chamber, closed at its distal end and open at its proximal end, in which a pliable tube is slidably positioned in sealed engagement with the housings. The pliable tube includes a sealed end positioned adjacent the proximal end of the inner housing so as to maintain isolation between the first and second chambers. Displacement of the material to be bagged from the first chamber along the inner housing so as to contact the sealed portion of the pliable bag allows the material to be positioned within the pliable bag in the second chamber. The bag is then sealed and severed between where the material is positioned therein and the wall in providing a sealed container for handling the material. The pliable tube when substantially depleted slides onto a narrow portion of the inner housing to allow a new pliable tube to be positioned over the old pliable tube. Remnants of the old pliable tube are then discharged into the new pliable tube with the bagging and removal of additional material.

  16. Webinar: Analysis Using Fuel Cell Material Handling Equipment for Shaving

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

    Peak Building Energy | Department of Energy Analysis Using Fuel Cell Material Handling Equipment for Shaving Peak Building Energy Webinar: Analysis Using Fuel Cell Material Handling Equipment for Shaving Peak Building Energy Access the recording and download the presentation slides from the Fuel Cell Technologies Office webinar "Analysis Using Fuel Cell Material Handling Equipment (MHE) for Shaving Peak Building Energy" held on August 11, 2015. Analysis Using Fuel Cell MHE for

  17. DOE Technical Targets for Hydrogen Storage Systems for Material Handling

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

    Equipment | Department of Energy Material Handling Equipment DOE Technical Targets for Hydrogen Storage Systems for Material Handling Equipment This table summarizes hydrogen storage technical performance targets for material handling equipment. These targets were developed with input to DOE through extensive communications with various stakeholders, industry developers, and end users, including through a 2012 request for information and workshops, as well as additional national lab

  18. Operating Experience Level 3, Losing Control: Material Handling Dangers

    Broader source: Energy.gov [DOE]

    This Operating Experience Level 3 (OE-3) document provides information about the dangers inherent in material handling and the role hazard analysis, work planning, and walkdowns can play in preventing injuries during heavy equipment moves. More than 200 material handling events reported to the Occurrence Reporting and Processing System (ORPS) from January 1, 2010, through August 31, 2014.

  19. Method and apparatus for in-cell vacuuming of radiologically contaminated materials

    DOE Patents [OSTI]

    Spadaro, Peter R.; Smith, Jay E.; Speer, Elmer L.; Cecconi, Arnold L.

    1987-01-01

    A vacuum air flow operated cyclone separator arrangement for collecting, handling and packaging loose contaminated material in accordance with acceptable radiological and criticality control requirements. The vacuum air flow system includes a specially designed fail-safe prefilter installed upstream of the vacuum air flow power supply. The fail-safe prefilter provides in-cell vacuum system flow visualization and automatically reduces or shuts off the vacuum air flow in the event of an upstream prefilter failure. The system is effective for collecting and handling highly contaminated radiological waste in the form of dust, dirt, fuel element fines, metal chips and similar loose material in accordance with radiological and criticality control requirements for disposal by means of shipment and burial.

  20. Method of preparing and handling chopped plant materials

    DOE Patents [OSTI]

    Bransby, David I.

    2002-11-26

    The method improves efficiency of harvesting, storage, transport, and feeding of dry plant material to animals, and is a more efficient method for harvesting, handling and transporting dry plant material for industrial purposes, such as for production of bioenergy, and composite panels.

  1. Duct Remediation Program: Material characterization and removal/handling

    SciTech Connect (OSTI)

    Beckman, T.d.; Davis, M.M.; Karas, T.M.

    1992-11-01

    Remediation efforts were successfully performed at Rocky Flats to locate, characterize, and remove plutonium holdup from process exhaust ducts. Non-Destructive Assay (NDA) techniques were used to determine holdup locations and quantities. Visual characterization using video probes helped determine the physical properties of the material, which were used for remediation planning. Assorted equipment types, such as vacuum systems, scoops, brushes, and a rotating removal system, were developed to remove specific material types. Personnel safety and material handling requirements were addressed throughout the project.

  2. Material Handling Fuel Cells for Building Electric Peak Shaving Applications

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

    Material Handling Fuel Cells for Building Electric Peak Shaving Applications U.S. Department of Energy Fuel Cell Technologies Office August 11, 2015 Presenter: Michael Penev of NREL DOE Host: Pete Devlin 2 Question and Answer * Please type your question into the question box hydrogenandfuelcells.energy.gov 3 Acknowledgments Fuel Cell Technologies Office, DOE EERE For providing funding for this project and for supporting sustainable hydrogen technology development through analysis, demonstration,

  3. Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | (NNSA) Insider Threat to Nuclear and Radiological Materials: Fact Sheet March 23, 2012 Almost all known cases of theft of nuclear material involved an insider. The threat of a nuclear facility insider, either individually or in collusion with an outsider, stealing fissile material or committing sabotage at a nuclear facility is a difficult one to accept and prevent. The skills, knowledge, access, and authority held by some insiders make the threat difficult

  4. Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste

    SciTech Connect (OSTI)

    R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

    2010-02-01

    This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

  5. RESCHEDULED: Webinar on Material Handling Fuel Cells for Building Electric Peak Shaving Applications

    Broader source: Energy.gov [DOE]

    The Fuel Cell Technologies Office will present a live webinar entitled "Material Handling Fuel Cells for Building Electric Peak Shaving Applications".

  6. NNSA Recovers Radiological Material from Mexico | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Recovers Radiological Material from Mexico July 28, 2015 The irradiators were loaded on the U.S. Air Force C-17 in Southern Mexico and flown back to a base in the United States. WASHINGTON, D.C. - The Department of Energy's (DOE) National Nuclear Security Administration (NNSA), in partnership with the Defense Threat Reduction Agency (DTRA), the U.S. Air Force (USAF), the U.S. Department of Agriculture (USDA), and the United Mexican States, has successfully completed

  7. Ross Hazardous and Toxic Materials Handling Facility: Environmental Assessment.

    SciTech Connect (OSTI)

    URS Consultants, Inc.

    1992-06-01

    The Bonneville Power Administration (BPA) owns a 200-acre facility in Washington State known as the Ross Complex. Activities at the Ross Complex routinely involve handling toxic substances such as oil-filled electrical equipment containing polychlorinated biphenyls (PCBs), organic and inorganic compounds for preserving wood transmission poles, and paints, solvents, waste oils, and pesticides and herbicides. Hazardous waste management is a common activity on-site, and hazardous and toxic substances are often generated from these and off-site activities. The subject of this environmental assessment (EA) concerns the consolidation of hazardous and toxic substances handling at the Complex. This environmental assessment has been developed to identify the potential environmental impacts of the construction and operation of the proposal. It has been prepared to meet the requirements of the National Environmental Policy Act (NEPA) to determine if the proposed action is likely to have a significant impact on the environment. In addition to the design elements included within the project, mitigation measures have been identified within various sections that are now incorporated within the project. This facility would be designed to improve the current waste handling practices and to assist BPA in meeting Federal and state regulations.

  8. ARRA Material Handling Equipment Composite Data Products: Data Through Quarter 4 of 2013

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Peters, M.

    2014-06-01

    This report includes 47 composite data products (CDPs) produced for American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment, with data through the fourth quarter of 2013.

  9. ARRA Material Handling Equipment Composite Data Products: Data Through Quarter 4 of 2012

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ainscough, C.; Saur, G.; Post, M.; Peters, M.; Ramsden, T.

    2013-05-01

    This presentation from the U.S. Department of Energy's National Renewable Energy Laboratory includes American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment composite data products for data through the fourth quarter of 2012.

  10. ARRA Material Handling Equipment Composite Data Products: Data through Quarter 2 of 2013

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ainscough, C.; Saur, G.; Post, M.; Peters, M.

    2013-11-01

    This report includes 47 composite data products (CDPs) produced for American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment, with data through the second quarter of 2013.

  11. Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated

    Broader source: Energy.gov [DOE]

    The purpose of this Model Procedure is to identify precautions and provide guidance to Medical Examiners/Coroners on the handling of a body or human remains that are potentially contaminated with...

  12. Hydrogen Fuel Cell Performance in the Key Early Markets of Material Handling Equipment and Backup Power (Presentation)

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ramsden, T.; Saur, G.; Ainscough, C.; Post, M.; Peters, M.

    2013-10-01

    This presentation summarizes the results of NREL's analysis of hydrogen fuel cell performance in the key early markets of material handling equipment (MHE) and backup power.

  13. TITLE III EVALUATION REPORT FOR THE MATERIAL AND PERSONNEL HANDLING SYSTEM

    SciTech Connect (OSTI)

    T. A. Misiak

    1998-05-21

    This Title III Evaluation Report (TER) provides the results of an evaluation that was conducted on the Material and Personnel Handling System. This TER has been written in accordance with the ''Technical Document Preparation Plan for the Mined Geologic Disposal System Title III Evaluation Reports'' (BA0000000-01717-4600-00005 REV 03). The objective of this evaluation is to provide recommendations to ensure consistency between the technical baseline requirements, baseline design, and the as-constructed Material and Personnel Handling System. Recommendations for resolving discrepancies between the as-constructed system, the technical baseline requirements, and the baseline design are included in this report. Cost and Schedule estimates are provided for all recommended modifications.

  14. Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment

    SciTech Connect (OSTI)

    Ramsden, T.

    2013-04-01

    This report discusses an analysis of the total cost of ownership of fuel cell-powered and traditional battery-powered material handling equipment (MHE, or more typically 'forklifts'). A number of fuel cell MHE deployments have received funding support from the federal government. Using data from these government co-funded deployments, DOE's National Renewable Energy Laboratory (NREL) has been evaluating the performance of fuel cells in material handling applications. NREL has assessed the total cost of ownership of fuel cell MHE and compared it to the cost of ownership of traditional battery-powered MHE. As part of its cost of ownership assessment, NREL looked at a range of costs associated with MHE operation, including the capital costs of battery and fuel cell systems, the cost of supporting infrastructure, maintenance costs, warehouse space costs, and labor costs. Considering all these costs, NREL found that fuel cell MHE can have a lower overall cost of ownership than comparable battery-powered MHE.

  15. An Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment

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

    An Evaluation of the Total Cost of Ownership of Fuel Cell- Powered Material Handling Equipment Todd Ramsden National Renewable Energy Laboratory Technical Report NREL/TP-5600-56408 April 2013 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 15013 Denver West Parkway Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No.

  16. ARRA Material Handling Equipment Composite Data Products: Data through Quarter 3 of 2014; NREL (National Renewable Energy Laboratory)

    SciTech Connect (OSTI)

    Ainscough, Chris; Kurtz, Jennifer

    2015-05-01

    This document includes 23 composite data products (CDPs) produced for American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment, with data through the third quarter of 2014.

  17. Material handling systems for use in glovebox lines: A survey of Department of Energy facility experience

    SciTech Connect (OSTI)

    Teese, G.D.; Randall, W.J.

    1992-12-31

    The Nuclear Weapons Complex Reconfiguration Study has recommended that a new manufacturing facility be constructed to replace the Rocky Flats Plant. In the new facility, use of an automated material handling system for movement of components would reduce both the cost and radiation exposure associated with production and maintenance operations. Contamination control would be improved between process steps through the use of airlocks and portals. Part damage associated with improper transport would be reduced, and accountability would be increased. In-process workpieces could be stored in a secure vault, awaiting a request for parts at a production station. However, all of these desirable features rely on the proper implementation of an automated material handling system. The Department of Energy Weapons Production Complex has experience with a variety of methods for transporting discrete parts in glovebox lines. The authors visited several sites to evaluate the existing technologies for their suitability for the application of plutonium manufacturing. Technologies reviewed were Linear motors, belt conveyors, roller conveyors, accumulating roller conveyors, pneumatic transport, and cart systems. The sites visited were The Idaho National Engineering laboratory, the Hanford Site, and the Rocky Flats Plant. Linear motors appear to be the most promising technology observed for the movement of discrete parts, and further investigation is recommended.

  18. Material handling systems for use in glovebox lines: A survey of Department of Energy facility experience

    SciTech Connect (OSTI)

    Teese, G.D.; Randall, W.J.

    1992-01-01

    The Nuclear Weapons Complex Reconfiguration Study has recommended that a new manufacturing facility be constructed to replace the Rocky Flats Plant. In the new facility, use of an automated material handling system for movement of components would reduce both the cost and radiation exposure associated with production and maintenance operations. Contamination control would be improved between process steps through the use of airlocks and portals. Part damage associated with improper transport would be reduced, and accountability would be increased. In-process workpieces could be stored in a secure vault, awaiting a request for parts at a production station. However, all of these desirable features rely on the proper implementation of an automated material handling system. The Department of Energy Weapons Production Complex has experience with a variety of methods for transporting discrete parts in glovebox lines. The authors visited several sites to evaluate the existing technologies for their suitability for the application of plutonium manufacturing. Technologies reviewed were Linear motors, belt conveyors, roller conveyors, accumulating roller conveyors, pneumatic transport, and cart systems. The sites visited were The Idaho National Engineering laboratory, the Hanford Site, and the Rocky Flats Plant. Linear motors appear to be the most promising technology observed for the movement of discrete parts, and further investigation is recommended.

  19. Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement

    SciTech Connect (OSTI)

    Seguin, Nicole R.

    2012-07-18

    Missions that the Radiological Laboratory, utility, Office Building (RLUOB) supports are: (1) Nuclear Materials Handling, Processing, and Fabrication; (2) Stockpile Management; (3) Materials and Manufacturing Technologies; (4) Nonproliferation Programs; (5) Waste Management Activities - Environmental Programs; and (6) Materials Disposition. The key capabilities are actinide analytical chemistry and material characterization.

  20. U.S. Department of Energy-Funded Performance Validation of Fuel Cell Material Handling Equipment (Presentation)

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ramsden, T.; Saur, G.; Ainscough, C.; Post, M.; Peters, M.

    2013-11-01

    This webinar presentation to the UK Hydrogen and Fuel Cell Association summarizes how the U.S. Department of Energy is enabling early fuel cell markets; describes objectives of the National Fuel Cell Technology Evaluation Center; and presents performance status of fuel cell material handling equipment.

  1. Multifunctional Metallic and Refractory Materials for Energy Efficient Handling of Molten Metals

    SciTech Connect (OSTI)

    Xingbo Liu; Ever Barbero; Bruce Kang; Bhaskaran Gopalakrishnan; James Headrick; Carl Irwin

    2009-02-06

    The goal of the project was to extend the lifetime of hardware submerged in molten metal by an order of magnitude and to improve energy efficiency of molten metal handling process. Assuming broad implementation of project results, energy savings in 2020 were projected to be 10 trillion BTU/year, with cost savings of approximately $100 million/year. The project team was comprised of materials research groups from West Virginia University and the Missouri University of Science and Technology formerly University of Missouri – Rolla, Oak Ridge National Laboratory, International Lead and Zinc Research Organization, Secat and Energy Industries of Ohio. Industry partners included six suppliers to the hot dip galvanizing industry, four end-user steel companies with hot-dip Galvanize and/or Galvalume lines, eight refractory suppliers, and seven refractory end-user companies. The results of the project included the development of: (1) New families of materials more resistant to degradation in hot-dip galvanizing bath conditions were developed; (2) Alloy 2020 weld overlay material and process were developed and applied to GI rolls; (3) New Alloys and dross-cleaning procedures were developed for Galvalume processes; (4) Two new refractory compositions, including new anti-wetting agents, were identified for use with liquid aluminum alloys; (5) A new thermal conductivity measurement technique was developed and validated at ORNL; (6) The Galvanizing Energy Profiler Decision Support System (GEPDSS)at WVU; Newly Developed CCW Laser Cladding Shows Better Resistance to Dross Buildup than 316L Stainless Steel; and (7) A novel method of measuring the corrosion behavior of bath hardware materials. Project in-line trials were conducted at Southwire Kentucky Rod and Cable Mill, Nucor-Crawfordsville, Nucor-Arkansas, Nucor-South Carolina, Wheeling Nisshin, California Steel, Energy Industries of Ohio, and Pennex Aluminum. Cost, energy, and environmental benefits resulting from the project

  2. Proposal for Construction/Demonstration/Implementation of A Material Handling System

    SciTech Connect (OSTI)

    Jim Jnatt

    2001-08-24

    Vortec Corporation, the United States Enrichment Corporation (USEC) and DOE/Paducah propose to complete the technology demonstration and the implementation of the Material Handling System developed under Contract Number DE-AC21-92MC29120. The demonstration testing and operational implementation will be done at the Paducah Gaseous Diffusion Plant. The scope of work, schedule and cost for the activities are included in this proposal. A description of the facility to be constructed and tested is provided in Exhibit 1, attached. The USEC proposal for implementation at Paducah is presented in Exhibit 2, and the commitment letters from the site are included in Exhibit 3. Under our agreements with USEC, Bechtel Jacobs Corporation and DOE/Paducah, Vortec will be responsible for the construction of the demonstration facility as documented in the engineering design package submitted under Phase 4 of this contract on August 9, 2001. USEC will have responsibility for the demonstration testing and commercial implementation of the plant. The demonstration testing and initial commercial implementation of the technology will be achieved by means of a USEC work authorization task with the Bechtel Jacobs Corporation. The initial processing activities will include the processing of approximately 4,250 drums of LLW. Subsequent processing of LLW and TSCA/LLW will be done under a separate contract or work authorization task. To meet the schedule for commercial implementation, it is important that the execution of the Phase 4 project option for construction of the demonstration system be executed as soon as possible. The schedule we have presented herein assumes initiation of the construction phase by the end of September 2001. Vortec proposes to complete construction of the demonstration test system for an estimated cost of $3,254,422. This price is based on the design submitted to DOE/NETL under the Phase 4 engineering design deliverable (9 august 2001). The cost is subject to the

  3. Radiological Modeling for Determination of Derived Concentration Levels of an Area with Uranium Residual Material - 13533

    SciTech Connect (OSTI)

    Perez-Sanchez, Danyl [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)] [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)

    2013-07-01

    As a result of a pilot project developed at the old Spanish 'Junta de Energia Nuclear' to extract uranium from ores, tailings materials were generated. Most of these residual materials were sent back to different uranium mines, but a small amount of it was mixed with conventional building materials and deposited near the old plant until the surrounding ground was flattened. The affected land is included in an area under institutional control and used as recreational area. At the time of processing, uranium isotopes were separated but other radionuclides of the uranium decay series as Th-230, Ra-226 and daughters remain in the residue. Recently, the analyses of samples taken at different ground's depths confirmed their presence. This paper presents the methodology used to calculate the derived concentration level to ensure that the reference dose level of 0.1 mSv y-1 used as radiological criteria. In this study, a radiological impact assessment was performed modeling the area as recreational scenario. The modelization study was carried out with the code RESRAD considering as exposure pathways, external irradiation, inadvertent ingestion of soil, inhalation of resuspended particles, and inhalation of radon (Rn-222). As result was concluded that, if the concentration of Ra-226 in the first 15 cm of soil is lower than, 0.34 Bq g{sup -1}, the dose would not exceed the reference dose. Applying this value as a derived concentration level and comparing with the results of measurements on the ground, some areas with a concentration of activity slightly higher than latter were found. In these zones the remediation proposal has been to cover with a layer of 15 cm of clean material. This action represents a reduction of 85% of the dose and ensures compliance with the reference dose. (authors)

  4. Resolving Radiological Classification and Release Issues for Many DOE Solid Wastes and Salvageable Materials

    SciTech Connect (OSTI)

    Hochel, R.C.

    1999-06-14

    The cost effective radiological classification and disposal of solid materials with potential volume contamination, in accordance with applicable U.S. Department of Energy (DOE) Orders, suffers from an inability to unambiguously distinguish among transuranic waste, low-level waste, and unconditional-release materials. Depending on the classification, disposal costs can vary by a hundred-fold. But in many cases, the issues can be easily resolved by a combination of process information, some simple measurements, and calculational predictions from a computer model for radiation shielding.The proper classification and disposal of many solid wastes requires a measurement regime that is able to show compliance with a variety of institutional and regulatory contamination limits. Although this is not possible for all solid wastes, there are many that do lend themselves to such measures. Several examples are discussed which demonstrate the possibilities, including one which was successfully applied to bulk contamination.The only barriers to such broader uses are the slow-to-change institutional perceptions and procedures. For many issues and materials, the measurement tools are available; they need only be applied.

  5. Asset Recovery of Hazardous Materials Beneficial Reuse of Radiologically Encumbered Lead Stocks ''Getting the Lead Out''

    SciTech Connect (OSTI)

    LLOYD, E.R.

    2003-01-23

    Underutilized and surplus lead stocks and leaded components are a common legacy environmental problem across much of the Department of Energy (DOE) Complex. While seeking to dispose of these items through its Environmental Management Program, DOE operational programs continue to pursue contemporary mission requirements such as managing and/or storing radioactive isotopes that require lead materials for shielding. This paradox was identified in late 1999 when DOES policies for managing scrap metal were assessed. In January 2000, the Secretary of Energy directed the National Center of Excellence for Materials Recycle (NMR) to develop and implement a comprehensive lead reuse program for all of DOE. Fluor Hanford, contractor for DOE Richland Operations, subsequently contacted NMR to pilot lead reclamation and reuse at the Hanford Site, This relationship resulted in the development of a beneficial reuse pathway for lead reclaimed from spent fuel transport railcars being stored at Hanford. The 1.3 million pounds of lead in the railcars is considered radiologically encumbered due to its prior use. Further, the material was considered a mixed Resource Conservation and Recovery Act (RCRA) low-level radioactive waste that would require expensive storage or macro encapsulation to meet land disposal restrictions prior to burial. Working closely with Flour Hanford and the Office of Air, Water, and Radiation (EH-412), NMR developed a directed reuse pathway for this and other radiologically encumbered lead When derived supplemental release limits were used, the lead recovered from these railcars became eligible for reuse in shielding products to support DOE and commercial nuclear industry operations. Using this disposition pathway has saved Hanford one third of the cost of disposing of the lead and the cost of acquiring additional lead for nuclear shielding applications. Furthermore, the environmental costs associated with mining and producing new lead for shielding products and

  6. Illicit Trafficking in Radiological and Nuclear Materials. Lack of Regulations and Attainable Disposal for Radioactive Materials Make Them More Vulnerable than Nuclear Materials

    SciTech Connect (OSTI)

    Balatsky, G.I.; Severe, W.R.; Leonard, L.

    2007-07-01

    Illicit trafficking in nuclear and radioactive materials is far from a new issue. Reports of nuclear materials offered for sale as well as mythical materials such as red mercury date back to the 1960's. While such reports were primarily scams, it illustrates the fact that from an early date there were criminal elements willing to sell nuclear materials, albeit mythical ones, to turn a quick profit. In that same time frame, information related to lost and abandoned radioactive sources began to be reported. Unlike reports on nuclear material of that era, these reports on abandoned sources were based in fact - occasionally associated with resulting injury and death. With the collapse of the Former Soviet Union, illicit trafficking turned from a relatively unnoticed issue to one of global concern. Reports of unsecured nuclear and radiological material in the states of the Former Soviet Union, along with actual seizures of such material in transit, gave the clear message that illicit trafficking was now a real and urgent problem. In 1995, the IAEA established an Illicit Trafficking Data Base to keep track of confirmed instances. Illicit Trafficking is deemed to include not only radioactive materials that have been offered for sale or crossed international boarders, but also such materials that are no longer under appropriate regulatory control. As an outcome of 9/11, the United States took a closer look at illicit nuclear trafficking as well as a reassessment of the safety and security of nuclear and other radioactive materials both in the United States and Globally. This reassessment launched heightened controls and security domestically and increased our efforts internationally to prevent illicit nuclear trafficking. This reassessment also brought about the Global Threat Reduction Initiative which aims to further reduce the threats of weapons usable nuclear materials as well those of radioactive sealed sources. This paper will focus on the issues related to a subset

  7. Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  8. The Department of Energy`s Rocky Flats Plant: A guide to record series useful for health related research. Volume 4: Production and materials handling

    SciTech Connect (OSTI)

    1995-08-01

    This is the fourth in a series of seven volumes which constitute a guide to records of the Rocky Flats Plant useful for conducting health-related research. The primary purpose of Volume 4 is to describe record series pertaining to production and materials handling activities at the Department of Energy`s (DOE) Rocky Flats Plant, now named the Rocky Flats Environmental Technology Site, near Denver, Colorado. History Associates Incorporated (HAI) prepared this guide as part of its work as the support services contractor for DOE`s Epidemiologic Records Inventory Project. This introduction briefly describes the Epidemiologic Records Inventory Project and HAI`s role in the project, provides a history of production and materials handling practices at Rocky Flats, and identifies organizations contributing to production and materials handling policies and activities. Other topics include the scope and arrangement of the guide and the organization to contact for access to these records.

  9. Office of Radiological Security

    National Nuclear Security Administration (NNSA)

    of physical security of radiological materials;

  10. Provision of mobile and man-portable radiation detection equipment;
  11. Regional cooperation on safeguards...

  12. Radiological Security Partnership | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Programs / Nonproliferation / Global Material Security / Radiological Security Radiological Security Partnership Radiological Security Partnership Secure Your Business, Your Community, and Your Country. Sign Up Today for Services Provided by the Radiological Security Partnership. RSP Logo Initiative of the Global Material Security Program Formerly the Global Threat Reduction Initiative RSP Registration RSP More Info Learn More Radiological Security Partnership

  13. Manufacturing Cost Analysis of 10 kW and 25 kW Direct Hydrogen Polymer Electrolyte Membrane (PEM) Fuel Cell for Material Handling Applications

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

    MANUFACTURING COST ANALYSIS OF 10 KW AND 25 KW DIRECT HYDROGEN POLYMER ELECTROLYTE MEMBRANE (PEM) FUEL CELL FOR MATERIAL HANDLING APPLICATIONS Prepared by: BATTELLE Battelle Memorial Institute 505 King Avenue Columbus, OH 43201 Prepared for: U.S. Department of Energy Golden Field Office Golden, CO DOE Contract No. DE-EE0005250 March 25, 2013 This report is a work prepared for the United States Government by Battelle. In no event shall either the United States Government or Battelle have any

  14. New radiological material detection technologies for nuclear forensics: Remote optical imaging and graphene-based sensors.

    SciTech Connect (OSTI)

    Harrison, Richard Karl; Martin, Jeffrey B.; Wiemann, Dora K.; Choi, Junoh; Howell, Stephen W.

    2015-09-01

    We developed new detector technologies to identify the presence of radioactive materials for nuclear forensics applications. First, we investigated an optical radiation detection technique based on imaging nitrogen fluorescence excited by ionizing radiation. We demonstrated optical detection in air under indoor and outdoor conditions for alpha particles and gamma radiation at distances up to 75 meters. We also contributed to the development of next generation systems and concepts that could enable remote detection at distances greater than 1 km, and originated a concept that could enable daytime operation of the technique. A second area of research was the development of room-temperature graphene-based sensors for radiation detection and measurement. In this project, we observed tunable optical and charged particle detection, and developed improved devices. With further development, the advancements described in this report could enable new capabilities for nuclear forensics applications.

  15. Air-Cooled Stack Freeze Tolerance Freeze Failure Modes and Freeze Tolerance Strategies for GenDriveTM Material Handling Application Systems and Stacks Final Scientific Report

    SciTech Connect (OSTI)

    Hancock, David, W.

    2012-02-14

    Air-cooled stack technology offers the potential for a simpler system architecture (versus liquid-cooled) for applications below 4 kilowatts. The combined cooling and cathode air allows for a reduction in part count and hence a lower cost solution. However, efficient heat rejection challenges escalate as power and ambient temperature increase. For applications in ambient temperatures below freezing, the air-cooled approach has additional challenges associated with not overcooling the fuel cell stack. The focus of this project was freeze tolerance while maintaining all other stack and system requirements. Through this project, Plug Power advanced the state of the art in technology for air-cooled PEM fuel cell stacks and related GenDrive material handling application fuel cell systems. This was accomplished through a collaborative work plan to improve freeze tolerance and mitigate freeze-thaw effect failure modes within innovative material handling equipment fuel cell systems designed for use in freezer forklift applications. Freeze tolerance remains an area where additional research and understanding can help fuel cells to become commercially viable. This project evaluated both stack level and system level solutions to improve fuel cell stack freeze tolerance. At this time, the most cost effective solutions are at the system level. The freeze mitigation strategies developed over the course of this project could be used to drive fuel cell commercialization. The fuel cell system studied in this project was Plug Power's commercially available GenDrive platform providing battery replacement for equipment in the material handling industry. The fuel cell stacks were Ballard's commercially available FCvelocity 9SSL (9SSL) liquid-cooled PEM fuel cell stack and FCvelocity 1020ACS (Mk1020) air-cooled PEM fuel cell stack.

  16. Radiological Impact Associated to Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) from Coal-Fired Power Plants Emissions - 13436

    SciTech Connect (OSTI)

    Dinis, Maria de Lurdes; Fiuza, Antonio; Soeiro de Carvalho, Jose; Gois, Joaquim; Meira Castro, Ana Cristina

    2013-07-01

    Certain materials used and produced in a wide range of non-nuclear industries contain enhanced activity concentrations of natural radionuclides. In particular, electricity production from coal is one of the major sources of increased human exposure to naturally occurring radioactive materials. A methodology was developed to assess the radiological impact due to natural radiation background. The developed research was applied to a specific case study, the Sines coal-fired power plant, located in the southwest coastline of Portugal. Gamma radiation measurements were carried out with two different instruments: a sodium iodide scintillation detector counter (SPP2 NF, Saphymo) and a gamma ray spectrometer with energy discrimination (Falcon 5000, Canberra). Two circular survey areas were defined within 20 km of the power plant. Forty relevant measurements points were established within the sampling area: 15 urban and 25 suburban locations. Additionally, ten more measurements points were defined, mostly at the 20-km area. The registered gamma radiation varies from 20 to 98.33 counts per seconds (c.p.s.) corresponding to an external gamma exposure rate variable between 87.70 and 431.19 nGy/h. The highest values were measured at locations near the power plant and those located in an area within the 6 and 20 km from the stacks. In situ gamma radiation measurements with energy discrimination identified natural emitting nuclides as well as their decay products (Pb-212, Pb-2142, Ra-226, Th-232, Ac-228, Th-234, Pa-234, U- 235, etc.). According to the results, an influence from the stacks emissions has been identified both qualitatively and quantitatively. The developed methodology accomplished the lack of data in what concerns to radiation rate in the vicinity of Sines coal-fired power plant and consequently the resulting exposure to the nearby population. (authors)

  17. EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York

    Broader source: Energy.gov [DOE]

    The Naval Nuclear Propulsion Program (NNPP) intent to prepare an Environmental Assessment for a radiological work and storage building at the Knolls Atomic Power Laboratory (Kesselring Site in West Milton, New York. A new facility is needed to streamline radioactive material handling and storage operations, permit demolition of aging facilities, and accommodate efficient maintenance of existing nuclear reactors.

  18. Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2012-October 31, 2013

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  19. Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2011-October 31, 2012

    SciTech Connect (OSTI)

    Mike lewis

    2013-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  20. Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: May 1, 2010-October 31, 2010

    SciTech Connect (OSTI)

    David B. Frederick

    2011-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (#LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  21. Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2010-October 31, 2011

    SciTech Connect (OSTI)

    David Frederick

    2012-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (No.LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  22. Accident Investigation Report- Radiological Release

    Broader source: Energy.gov [DOE]

    On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following the event, the investigation was broken into two phases. The Phase 1 report focused on how the radiological material was released into the atmosphere and Phase 2, performed once limited access to the underground was re‐established, focused on the source of the released radiological material.

  1. Technical evaluation of topsoil substitution practices and handling of potential acid/toxic-forming materials in Texas. Special study report

    SciTech Connect (OSTI)

    Not Available

    1985-09-01

    The Texas State program approved by the Office of Surface Mining (OSM) under the Surface Mining Control and Reclamation Act of 1977 (SMCRA) allows that selected overburden materials may, if justified, be substituted for topsoil in mined land reclamation. The report presents the Office of Surface Mining Reclamation and Enforcement's (OSM's) findings regarding the practice of topsoil substitution under the approved Texas program and related reclamation problems with potential minesoil acidification. The purpose of the study was not to determine whether the substitution of overburden for topsoil should be approved or disapproved on any specific mine or soil series in Texas. The report presents a summary of pertinent technical considerations that need to be addressed in permit approvals for surface coal mines which (1) may encounter potentially acid/toxic-forming materials during mining or (2) intend to substitute overburden for topsoil as a plant growth material. The report summarizes the results of a special study OSM conducted to evaluate the technical basis and justification for reclamation plans and the substitution of overburden for topsoil as a plant growth material suitable for the reclamation of coal mines.

  2. Tritium handling in vacuum systems

    SciTech Connect (OSTI)

    Gill, J.T. [Monsanto Research Corp., Miamisburg, OH (United States). Mound Facility; Coffin, D.O. [Los Alamos National Lab., NM (United States)

    1986-10-01

    This report provides a course in Tritium handling in vacuum systems. Topics presented are: Properties of Tritium; Tritium compatibility of materials; Tritium-compatible vacuum equipment; and Tritium waste treatment.

  3. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers’ Council

    2012-03-26

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

  4. Medical Examiner/Coroner on the Handling of a Body/Human Remains...

    Office of Environmental Management (EM)

    Medical ExaminerCoroner on the Handling of a BodyHuman Remains that are Potentially Radiologically Contaminated Medical ExaminerCoroner on the Handling of a BodyHuman Remains ...

  5. radiological. survey

    National Nuclear Security Administration (NNSA)

    7%2A en NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas http:nnsa.energy.govmediaroompressreleasesamsca

  6. Radiological Control

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

    2009-06-16

    The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs.

  7. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  8. Radiological Assessment Survey of the Vance road Facility Source Vault Building Materials, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    J. R. Morton

    2000-09-01

    From the 1950s, the Vance Road laboratory was the site of extensive nuclear medical research and involved the used of numerous radionuclides. These nuclides were stored in a source vault stored on the first floor of the facility. Nuclear medical research is no longer conducted in this facility, and the source vault was remediated in preparation for converting the area to office space and general use. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault and its associated miscellaneous building materials and laboratory equipment in preparation for the conversion to general use space.

  9. Bulk materials handling equipment roundup

    SciTech Connect (OSTI)

    Fiscor, S.

    2007-07-15

    The article reports recent product developments in belt conveyors. Flexco Steel Lancing Co. (Flexco) has a range of light, portable maintenance tools and offers training modules on procedures for belt conveyor maintenance on its website www.flexcosafe.com. Siemens recently fitted a 19 km long conveyor belt drive system at a Texan aluminium plant with five 556-kW Simovent Masterdrive VC drives. Voith recently launched the TPKL-T turbo coupling for users who want an alignment-free drive solution. Belt cleaners newly on the market include the RemaClean SGB brush and ASGCO Manufacturing's Razor-Back with Spray bar. Continental Conveyor has introduced a new line of dead-shaft pulleys offering increased bearing protection. 6 photos.

  10. Radiological Control

    National Nuclear Security Administration (NNSA)

    RADIOLOGICAL CONTROL U.S. Department of Energy SAFT Washington, D.C. 20585 DISTRIBUTION ... DOE-STD-1098-2008 ii This document is available on the Department of Energy Technical ...

  11. 2010 Manufacturing Readiness Assessment Update to the 2008 Report for Fuel Cell Stacks and Systems for the Backup Power and Materials Handling Equipment Markets

    SciTech Connect (OSTI)

    Wheeler, D.; Ulsh, M.

    2012-08-01

    In 2008, the National Renewable Energy Laboratory (NREL), under contract to the US Department of Energy (DOE), conducted a manufacturing readiness assessment (MRA) of fuel cell systems and fuel cell stacks for back-up power and material handling applications (MHE). To facilitate the MRA, manufacturing readiness levels (MRL) were defined that were based on the Technology Readiness Levels previously established by the US Department of Energy (DOE). NREL assessed the extensive existing hierarchy of MRLs developed by Department of Defense (DoD) and other Federal entities, and developed a MRL scale adapted to the needs of the Fuel Cell Technologies Program (FCTP) and to the status of the fuel cell industry. The MRL ranking of a fuel cell manufacturing facility increases as the manufacturing capability transitions from laboratory prototype development through Low Rate Initial Production to Full Rate Production. DOE can use MRLs to address the economic and institutional risks associated with a ramp-up in polymer electrolyte membrane (PEM) fuel cell production. In 2010, NREL updated this assessment, including additional manufacturers, an assessment of market developments since the original report, and a comparison of MRLs between 2008 and 2010.

  12. Radiological Security Partnership Information | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Programs / Nonproliferation / Global Material Security / Radiological Security / Radiological Security Partnership Radiological Security Partnership Information Radioactive sources play an important role in a number of commercial, medical, and research facilities. The benefits of these sources must be balanced with proper security. The Department of Energy's (DOE) National Nuclear Security Administration (NNSA) is working with the Nuclear Regulatory Commission and

  13. Radiological Control

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

    DOE-STD-1098-2008 October 2008 ------------------------------------- Change Notice 1 May 2009 DOE STANDARD RADIOLOGICAL CONTROL U.S. Department of Energy SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1098-2008 ii This document is available on the Department of Energy Technical Standards Program Website at http://www.standards.doe.gov/ iii DOE-STD-1098-2008 Change Notice 1: DOE-STD-1098-2008, Radiological Control Standard

  14. Radiological Control

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

    DOE-STD-1098-2008 October 2008 DOE STANDARD RADIOLOGICAL CONTROL U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ii DOE-STD-1098-2008 This document is available on the Department of Energy Technical Standards Program Website at http://www.standards.doe.gov/ DOE-STD-1098-2008 Radiological Control DOE Policy October 2008 iii Foreword The Department of Energy (DOE) has developed this Standard to assist

  15. Analysis of offsite emergency planning zones for the Rocky Flats Plant. Evaluation of radiological materials, Volume 1

    SciTech Connect (OSTI)

    Hodgin, C.R.; Daugherty, N.M.; Smith, M.L.; Bunch, D.; Toresdahl, J.; Verholek, M.G.

    1991-01-01

    The objective of this report is to fully document technical data and information that have been developed to support offsite emergency planning by the State of Colorado for potential accidents at the Rocky Flats Plant. Specifically, this report documents information and data that will assist the State of Colorado in upgrading its radiological emergency planning zones for Rocky Flats Plant. The Colorado Division of Disaster Emergency Services (DODES) and the Colorado Department of Health (CDH) represent the primary audience for this report. The secondary audience for this document includes the Rocky Flats Plant; federal, State, and local governmental agencies; the scientific community; and the interested public. Because the primary audience has a pre-existing background on the subject, this report assumes some exposure to emergency planning, health physics, and dispersion modeling on the part of the reader. The authors have limited their assumptions of background knowledge as much as possible, recognizing that the topics addressed in the report may be new to some secondary audiences.

  16. Radiological safety training for uranium facilities

    SciTech Connect (OSTI)

    1998-02-01

    This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

  17. RADIOLOGICAL SURWY

    Office of Legacy Management (LM)

    111 j -,~ ' - et- -*\. _(a v - r\lfs+8 plY 45+ c iill I r\l&; p) :;!I..; .: .. :,, ,m -,< :' - ' ec-. :-*% ". _(.*- ~ . . : : : ' .. : : : .. ..:, . . . :. : : ,, :;I;:~~:; :.:.!,;;y ' 1;: .: 1. .., ; ' . :. : c :...: .;: .: RADIOLOGICAL SURWY - RADIoL~BI~L.::.~~~y:- : ::: 1 ,: . . : : :: :. :..." - OFi~:,~~~~:poRTI~~~ 0J-g ,m_ ,. :. y.;,:. ,.:I; .:. F~~~~~~as~~~ ~~~~~~~:~~~~ :co~~~:~~~~~; ;, .. ; I : : ::.. :.. :. - ,B~~Lo,.~-~~~. ..; .:I ,,,, :--:.;:I:: ;' #I Y' i ' 11".

  18. RADRELAY RADIOLOGICAL DATA LINK DEVICE

    SciTech Connect (OSTI)

    Harpring, L; Frank Heckendorn, F

    2007-11-06

    The RadRelay effort developed small, field appropriate, portable prototype devices that allow radiological spectra to be downloaded from field radiological detectors, like the identiFINDER-U, and transmitted to land based experts. This communications capability was designed for the U. S. Coast Guard (USCG) but is also applicable to the Customs and Border Protection (CBP) personnel working in remote locations. USCG Level II personnel currently use the identiFINDER-U Hand-Held Radioisotope ID Devices (HHRIID) to detect radiological materials during specific boarding operations. These devices will detect not only radiological emissions but will also evaluate those emissions against a table of known radiological spectra. The RadRelay has been developed to significantly improve the functionality of HHRIID, by providing the capability to download radiological spectra and then transmit them using satellite or cell phone technology. This remote wireless data transfer reduces the current lengthy delay often encountered between the shipboard detection of unknown radiological material and the evaluation of that data by technical and command personnel. That delay is reduced from hours to minutes and allows the field located personnel to remain on station during the inspection and evaluation process.

  19. Radiological Security | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Nonproliferation / Global Material Security Radiological Security The program collaborates with domestic and international partners to address the threat of illicit use of high-priority radiological materials in the United States and abroad. The Radiological Security program accomplishes its mission by removing and disposing of excess or orphaned radioactive sources; promoting the replacement of radioactive sources with non-isotopic technologies, where feasible; and increasing security where

  20. ORISE: Radiological program assessment services

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

    Radiological program assessment services Minimizing the risk of human exposure to hazardous levels of radioactive materials requires designing a comprehensive safety program that ensures appropriate measures are taken to protect workers and the public. As a U.S. Department of Energy (DOE) institute, the Oak Ridge Institute for Science and Education (ORISE) understands the importance of having an effective safety program in place to assure stakeholders and regulators that your radiological

  1. DOE handbook: Tritium handling and safe storage

    SciTech Connect (OSTI)

    1999-03-01

    The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

  2. Radiological Control Technician Training

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

    DOE-HDBK-1122-2009 (Revised 2013) Module 2.03 Counting Errors and Statistics Student's Material Course Title: Radiological Control Technician Module Title: Counting Errors and Statistics Module Number: 2.03 Objectives: (This document, Study Material, is referred to as Study Guide in the Program Management Guide) 2.03.01. Identify five general types of errors that can occur when analyzing radioactive samples, and describe the effect of each source of error on sample measurements. 2.03.02. State

  3. Material Protection, Control, & Accounting | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Nonproliferation Nuclear and Radiological Material Security Material Protection, Control, & Accounting Material Protection, Control, & Accounting NNSA implements material...

  4. Radiological Control Technician Training

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

    ... of candidates for Radiological Control Technician (RCT) and for RCT Supervisor. ... OEBs as indicated in DOE's Radiological Control Standard (RCS) and the RCT Training ...

  5. Paint for detection of radiological or chemical agents

    DOE Patents [OSTI]

    Farmer, Joseph C.; Brunk, James L.; Day, Sumner Daniel

    2010-08-24

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  6. Unvented Drum Handling Plan

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    2000-08-01

    This drum-handling plan proposes a method to deal with unvented transuranic drums encountered during retrieval of drums. Finding unvented drums during retrieval activities was expected, as identified in the Transuranic (TRU) Phase I Retrieval Plan (HNF-4781). However, significant numbers of unvented drums were not expected until excavation of buried drums began. This plan represents accelerated planning for management of unvented drums. A plan is proposed that manages unvented drums differently based on three categories. The first category of drums is any that visually appear to be pressurized. These will be vented immediately, using either the Hanford Fire Department Hazardous Materials (Haz. Mat.) team, if such are encountered before the facilities' capabilities are established, or using internal capabilities, once established. To date, no drums have been retrieved that showed signs of pressurization. The second category consists of drums that contain a minimal amount of Pu isotopes. This minimal amount is typically less than 1 gram of Pu, but may be waste-stream dependent. Drums in this category are assayed to determine if they are low-level waste (LLW). LLW drums are typically disposed of without venting. Any unvented drums that assay as TRU will be staged for a future venting campaign, using appropriate safety precautions in their handling. The third category of drums is those for which records show larger amounts of Pu isotopes (typically greater than or equal to 1 gram of Pu). These are assumed to be TRU and are not assayed at this point, but are staged for a future venting campaign. Any of these drums that do not have a visible venting device will be staged awaiting venting, and will be managed under appropriate controls, including covering the drums to protect from direct solar exposure, minimizing of container movement, and placement of a barrier to restrict vehicle access. There are a number of equipment options available to perform the venting. The

  7. PRE-HOSPITAL PRACTICES FOR HANDLING A RADIOLOGICALLY CONTAMINATED...

    Office of Environmental Management (EM)

    ... or ERG, include: Medical problems take priority over ... Universal precautions protective clothing worn by emergency ... Training programs and planning tools are offered through the ...

  8. Pre-Hospital Practices for Handling a Radiologically Contaminated Patient

    Broader source: Energy.gov [DOE]

    The purpose of this User’s Guide is to provide instructors with an overview of the key points covered in the video.  The Student Handout portion of this Guide is designed to assist the instructor...

  9. INL@Work Radiological Search & Response Training

    ScienceCinema (OSTI)

    Turnage, Jennifer

    2013-05-28

    Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

  10. INL@Work Radiological Search & Response Training

    SciTech Connect (OSTI)

    Turnage, Jennifer

    2010-01-01

    Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

  11. Puck Handling Glovebox

    SciTech Connect (OSTI)

    Fiscus, J.B.

    2001-01-29

    This paper discusses development and testing of the robots and specialized automation involved in handling green pucks from the cold press through placing sintered pucks on the transfer trays.

  12. material recovery

    National Nuclear Security Administration (NNSA)

    dispose of dangerous nuclear and radiological material, and detect and control the proliferation of related WMD technology and expertise.

  13. NV/YMP radiological control manual, Revision 2

    SciTech Connect (OSTI)

    Gile, A.L.

    1996-11-01

    The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

  14. International Data on Radiological Sources

    SciTech Connect (OSTI)

    Martha Finck; Margaret Goldberg

    2010-07-01

    ABSTRACT The mission of radiological dispersal device (RDD) nuclear forensics is to identify the provenance of nuclear and radiological materials used in RDDs and to aid law enforcement in tracking nuclear materials and routes. The application of databases to radiological forensics is to match RDD source material to a source model in the database, provide guidance regarding a possible second device, and aid the FBI by providing a short list of manufacturers and distributors, and ultimately to the last legal owner of the source. The Argonne/Idaho National Laboratory RDD attribution database is a powerful technical tool in radiological forensics. The database (1267 unique vendors) includes all sealed sources and a device registered in the U.S., is complemented by data from the IAEA Catalogue, and is supported by rigorous in-lab characterization of selected sealed sources regarding physical form, radiochemical composition, and age-dating profiles. Close working relationships with global partners in the commercial sealed sources industry provide invaluable technical information and expertise in the development of signature profiles. These profiles are critical to the down-selection of potential candidates in either pre- or post- event RDD attribution. The down-selection process includes a match between an interdicted (or detonated) source and a model in the database linked to one or more manufacturers and distributors.

  15. Verification Survey of the Building 4059 Site (Phase B); Post Historical Site Assessment Sites, Block 1; and Radioactive Materials Handling Facility HOldup Pond (Site 4614), Santa Susana Field Laboratory, The Boeing Company, Ventura County, California

    SciTech Connect (OSTI)

    T.J. Vitkus

    2008-06-06

    Confirm that the final radiological conditions were accurately and adequately described in the FSS documentation, relative to the established release criteria.

  16. Radiological Control Technician Training

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

    Part 6 of 9 Radiological Control Technician Training Site Academic Training Study Guide Phase I Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 Radiological Control Technician Study Guide ii This page intentionally left blank DOE-HDBK-1122-2009 Radiological Control Technician Study Guide iii Table of Contents Page Module 2.01 Radiological Documentation

  17. Radiological Worker Training

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

    NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix A Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards

  18. Radiological Worker Training

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

    NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix C December 2008 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Safety Training for Radiation Producing (X-Ray) Devices U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management This

  19. Radiological Technician Training

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

    Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard ... . . . . . . . . 1 Phase I: RCT Academics Training . . . . . . . . . . . . . . . . . . . . ...

  20. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    L 2.10.13 State the requirements for removing or releasing materials from any radiological area. References: 1. 10 CFR 835, "Occupational Radiation Protection" (1998) 2. ...

  1. Solid waste handling

    SciTech Connect (OSTI)

    Parazin, R.J.

    1995-05-31

    This study presents estimates of the solid radioactive waste quantities that will be generated in the Separations, Low-Level Waste Vitrification and High-Level Waste Vitrification facilities, collectively called the Tank Waste Remediation System Treatment Complex, over the life of these facilities. This study then considers previous estimates from other 200 Area generators and compares alternative methods of handling (segregation, packaging, assaying, shipping, etc.).

  2. Uranium hexafluoride handling. Proceedings

    SciTech Connect (OSTI)

    Not Available

    1991-12-31

    The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF{sub 6} from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride. Selected papers were processed separately for inclusion in the Energy Science and Technology Database.

  3. Puck Handling Glovebox

    SciTech Connect (OSTI)

    Fiscus, J.B.

    2001-01-03

    The Plutonium Immobilization Project (PIP) is a joint venture between the Savannah River Site (SRS) and Lawrence Livermore National Laboratory (LLNL). This project will disposition excess weapons grade plutonium in a solid ceramic form. The plutonium, in oxide powder form, will be mixed with uranium oxide powder, ceramic precursors and binders. The combined powder mixture will be milled and possibly granulated; this processed powder will then be dispensed to a (dual action) cold press where it will be formed into green (unsintered) compacts. The compact will have the shape of a puck measuring approximately 3 1/2'' in diameter and 1 3/8'' thick. The green puck, once ejected from the press die, will be picked up by a robot and transferred into the Puck Handling Glovebox. Here the green puck will be inspected and then palletized onto furnace trays. The loaded furnace trays will be stacked/assembled and transported to the furnace where sintering operations will be performed. Finally the sintered pucks will be off loaded, inspected and transferred onto Transfer Trays which will carry the pucks from the Puck Handling Glovebox downstream to subsequent Bagless Transfer Can (BTC) operations. Due to contamination potential and high radiation rates, all Puck Handling Glovebox operations will be performed remotely using robots and specialized automation.

  4. Radiological Sites in Hawaii Complete NNSA Security Enhancements | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | (NNSA) Radiological Sites in Hawaii Complete NNSA Security Enhancements August 12, 2011 HONOLULU - The National Nuclear Security Administration (NNSA) today recognized the state of Hawaii and the city and county of Honolulu for completing security enhancements on all high priority radiological materials. The voluntary enhancements came with the assistance of NNSA's Global Threat Reduction Initiative (GTRI) and further improve radiological material security

  5. Flashback: Rapid scanning for radiological threats

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

    Flashback: Rapid scanning for radiological threats Flashback: Rapid scanning for radiological threats The ability to identify distinct material density enables the Multi-Mode Passive Detection System (MMPDS)to quickly detect unshielded to heavily shielded nuclear threats, as well as gamma rays, with near-zero false alarms. November 1, 2015 Decision Science Decision Science Decision Sciences' Multi-Mode Passive Detection System: Rapid scanning forradiological threats Click on headline to go to

  6. Solid handling valve

    DOE Patents [OSTI]

    Williams, William R.

    1979-01-01

    The present invention is directed to a solids handling valve for use in combination with lock hoppers utilized for conveying pulverized coal to a coal gasifier. The valve comprises a fluid-actuated flow control piston disposed within a housing and provided with a tapered primary seal having a recessed seat on the housing and a radially expandable fluid-actuated secondary seal. The valve seals are highly resistive to corrosion, erosion and abrasion by the solids, liquids, and gases associated with the gasification process so as to minimize valve failure.

  7. Current Trends in Gamma Ray Detection for Radiological Emergency Response

    SciTech Connect (OSTI)

    Mukhopadhyay, S., Guss, P., Maurer, R.

    2011-08-18

    Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies.

  8. Virtual Reality for Nuclear Material Handling

    Office of Energy Efficiency and Renewable Energy (EERE)

    AIKEN, S.C. – EM’s Savannah River National Laboratory (SRNL) is applying a high-tech solution to complex and dangerous workforce training: virtual reality.

  9. Specialty Vehicles and Material Handling Equipment

    Broader source: Energy.gov [DOE]

    This presentation by William Mitchell of Nuvera Fuel Cells was given at the Fuel Cell Meeting in April 2007.

  10. ETEC - Radioactive Handling Materials Facility (RMHF) Leachfield...

    Office of Environmental Management (EM)

    Environmental Indicators (EIs) Groundwater Migration Under Control? Yes Current Human Exposure Acceptable? Yes Confirmed by Lead Regulator? Yes Confirmed by Lead Regulator? Yes...

  11. Sectional device handling tool

    DOE Patents [OSTI]

    Candee, Clark B.

    1988-07-12

    Apparatus for remotely handling a device in an irradiated underwater environment includes a plurality of tubular sections interconnected end-to-end to form a handling structure, the bottom section being adapted for connection to the device. A support section is connected to the top tubular section and is adapted to be suspended from an overhead crane. Each section is flanged at its opposite ends. Axially retractable bolts in each bottom flange are threadedly engageable with holes in the top flange of an adjacent section, each bolt being biased to its retracted position and retained in place on the bottom flange. Guide pins on each top flange cooperate with mating holes on adjacent bottom flanges to guide movement of the parts to the proper interconnection orientation. Each section carries two hydraulic line segments provided with quick-connect/disconnect fittings at their opposite ends for connection to the segments of adjacent tubular sections upon interconnection thereof to form control lines which are connectable to the device and to an associated control console.

  12. Radiological Assistance Program

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

    1992-04-10

    To establish Department of Energy (DOE) policy, procedures, authorities, and responsibilities for its Radiological Assistance Program. Canceled by DOE O 153.1.

  13. Radiological Control Technician Training

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

    7of 9 Radiological Control Technician Training Practical Training Phase II Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy ...

  14. Radiological Control Technician Training

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

    HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG ... an implementation process for core training as recommended in chapter 14 to ...

  15. Radiological Control Technician Training

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

    Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of ...

  16. TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

    SciTech Connect (OSTI)

    Pfingston, M.; Arnish, J.; LePoire, D.; Chen, S.-Y.

    1998-10-14

    Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides.

  17. ORISE: Radiological program assessment services

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

    ORISE focuses its radiological audit and assessment services in these key areas: Nondestructive assay (NDA) Radiological control programs Environmental monitoring programs ...

  18. Surface with two paint strips for detection and warning of chemical warfare and radiological agents

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2013-04-02

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  19. Method for warning of radiological and chemical substances using detection paints on a vehicle surface

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2012-03-13

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  20. Paint for detection of corrosion and warning of chemical and radiological attack

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2010-08-24

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  1. Method for warning of radiological and chemical agents using detection paints on a vehicle surface

    DOE Patents [OSTI]

    Farmer, Joseph C.; Brunk, James L.; Day, S. Daniel

    2012-03-27

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  2. Aerial vehicle with paint for detection of radiological and chemical warfare agents

    DOE Patents [OSTI]

    Farmer, Joseph C.; Brunk, James L.; Day, S. Daniel

    2013-04-02

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  3. Tritium Handling and Safe Storage

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

    ... Individual mm Millimeter mrem Millirem NFPA National Fire Protection Association NP ... Handling of Tritium, published in 1991; and U.S. Department of Energy (DOE) publications. ...

  4. Tritium Handling and Safe Storage

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

    ... Level mm Millimeter mrem Millirem NFPA National Fire Protection Association NMMSS ... Safe Handling of Tritium, published in 1991, in addition to the French Nuclear Safety ...

  5. Tritium Handling and Safe Storage

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

    ... Individual mm Millimeters mrem Millirem NFPA National Fire Protection Association NPDWR ... "Safe Handling of Tritium," published in 1991; and U.S. Department of Energy (DOE) ...

  6. REMOTE HANDLING ARRANGEMENTS

    DOE Patents [OSTI]

    Ginns, D.W.

    1958-04-01

    A means for handling remotely a sample pellet to be irradiated in a nuclear reactor is proposed. It is comprised essentially of an inlet tube extending through the outer shield of the reactor and being inclined so that its outer end is at a higher elevation than its inner end, an outlet tube extending through the outer shield being inclined so that its inner end is at a higher elevation than its outer end, the inner ends of these two tubes being interconnected, and a straight tube extending through the outer shield and into the reactor core between the inlet and outlet tubes and passing through the juncture of said inner ends. A rod-like member is rotatably and slidely operated within the central straight tube and has a receptacle on its inner end for receiving a sample pellet from the inlet tube. The rod member is operated to pick up a sample pellet from the inlet tube, carry the sample pellet into the irradiating position within the core, and return to the receiving position where it is rotated to dump the irradiated pellet into the outlet tube by which it is conveyed by gravity to the outside of the reactor. Stop members are provided in the inlet tube, and electrical operating devices are provided to control the sequence of the operation automatically.

  7. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2010-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  8. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-04-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  9. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2009-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  10. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-08-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  11. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2010-05-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  12. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2015-03-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1C, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  13. A HUMAN RELIABILITY-CENTERED APPROACH TO THE DEVELOPMENT OF JOB AIDS FOR REVIEWERS OF MEDICAL DEVICES THAT USE RADIOLOGICAL BYPRODUCT MATERIALS.

    SciTech Connect (OSTI)

    COOPER, S.E.; BROWN, W.S.; WREATHALL, J.

    2005-02-02

    The U.S. Nuclear Regulatory Commission (NRC) is engaged in an initiative to risk-inform the regulation of byproduct materials. Operating experience indicates that human actions play a dominant role in most of the activities involving byproduct materials, which are radioactive materials other than those used in nuclear power plants or in weapons production, primarily for medical or industrial purposes. The overall risk of these activities is strongly influenced by human performance. Hence, an improved understanding of human error, its causes and contexts, and human reliability analysis (HRA) is important in risk-informing the regulation of these activities. The development of the human performance job aids was undertaken by stages, with frequent interaction with the prospective users. First, potentially risk significant human actions were identified based on reviews of available risk studies for byproduct material applications and of descriptions of events for byproduct materials applications that involved potentially significant human actions. Applications from the medical and the industrial domains were sampled. Next, the specific needs of the expected users of the human performance-related capabilities were determined. To do this, NRC headquarters and region staff were interviewed to identify the types of activities (e.g., license reviews, inspections, event assessments) that need HRA support and the form in which such support might best be offered. Because the range of byproduct uses regulated by NRC is so broad, it was decided that initial development of knowledge and tools would be undertaken in the context of a specific use of byproduct material, which was selected in consultation with NRC staff. Based on needs of NRC staff and the human performance related characteristics of the context chosen, knowledge resources were then compiled to support consideration of human performance issues related to the regulation of byproduct materials. Finally, with

  14. Radiological/biological/aerosol removal system

    DOE Patents [OSTI]

    Haslam, Jeffery J

    2015-03-17

    An air filter replacement system for existing buildings, vehicles, arenas, and other enclosed airspaces includes a replacement air filter for replacing a standard air filter. The replacement air filter has dimensions and air flow specifications that allow it to replace the standard air filter. The replacement air filter includes a filter material that removes radiological or biological or aerosol particles.

  15. Radiological Contamination Control Training for Laboratory Research

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

    2 of 3) Radiological Contamination Control Training for Laboratory Research Instructor's Guide Office of Environment, Safety & Health U.S. Department of Energy February 1997 DOE-HDBK-1106-97 ii This page intentionally left blank. DOE-HDBK-1106-97 iii Table of Contents Page DEPARTMENT OF ENERGY - Course/Lesson Plan.............................. 1 Standardized Core Course Materials................................................... 1 Course

  16. DOE standard: Radiological control

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

    The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs. DOE has established regulatory requirements for occupational radiation protection in Title 10 of the Code of Federal Regulations, Part 835 (10 CFR 835), ``Occupational Radiation Protection``. Failure to comply with these requirements may lead to appropriate enforcement actions as authorized under the Price Anderson Act Amendments (PAAA). While this Standard does not establish requirements, it does restate, paraphrase, or cite many (but not all) of the requirements of 10 CFR 835 and related documents (e.g., occupational safety and health, hazardous materials transportation, and environmental protection standards). Because of the wide range of activities undertaken by DOE and the varying requirements affecting these activities, DOE does not believe that it would be practical or useful to identify and reproduce the entire range of health and safety requirements in this Standard and therefore has not done so. In all cases, DOE cautions the user to review any underlying regulatory and contractual requirements and the primary guidance documents in their original context to ensure that the site program is adequate to ensure continuing compliance with the applicable requirements. To assist its operating entities in achieving and maintaining compliance with the requirements of 10 CFR 835, DOE has established its primary regulatory guidance in the DOE G 441.1 series of Guides. This Standard supplements the DOE G 441.1 series of Guides and serves as a secondary source of guidance for achieving compliance with 10 CFR 835.

  17. Contact-Handled and Remote-Handled Transuranic Waste Packaging

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

    2011-08-09

    Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. Does not cancel/supersede other directives.

  18. HAND TRUCK FOR HANDLING EQUIPMENT

    DOE Patents [OSTI]

    King, D.W.

    1959-02-24

    A truck is described for the handling of large and relatively heavy pieces of equipment and particularly for the handling of ion source units for use in calutrons. The truck includes a chassis and a frame pivoted to the chassis so as to be operable to swing in the manner of a boom. The frame has spaced members so arranged that the device to be handled can be suspended between or passed between these spaced members and also rotated with respect to the frame when the device is secured to the spaced members.

  19. Radiation Safety Training Materials

    Office of Energy Efficiency and Renewable Energy (EERE)

    The following Handbooks and Standard provide recommended hazard specific training material for radiological workers at DOE facilities and for various activities.

  20. Waste handling activities in glovebox dismantling facility

    SciTech Connect (OSTI)

    Kitamura, Akihiro; Okada, Takashi; Kashiro, Kashio; Yoshino, Masanori; Hirano, Hiroshi

    2007-07-01

    The Glovebox Dismantling Facility is a facility to decontaminate and size-reduce after-service gloveboxes in the Plutonium Fuel Production Facility, Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency. The wastes generated from these dismantling activities are simultaneously handled and packaged into drums in a bag-out manner. For future waste treatment and disposal, these wastes are separated into material categories. In this paper, we present the basic steps and analyzed data for the waste handling activities. The data were collected from dismantling activities for three gloveboxes (Grinding Pellet Glovebox, Visual Inspection Glovebox, Outer-diameter Screening Glovebox) conducted from 2001-2004. We also describe both current and near-future improvements. (authors)

  1. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014 April 2015 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release ...

  2. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    Phase 1 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014 April 2014 Radiological Release Event at the Waste Isolation Pilot Plant Radiological ...

  3. INTERNATIONAL COOPERATION ON RADIOLOGICAL THREAT REDUCTION PROGRAMS IN RUSSIA

    SciTech Connect (OSTI)

    Landers, Christopher C.; Tatyrek, Aaron P.

    2009-10-07

    Since its inception in 2004, the United States Department of Energy’s Global Threat Reduction Initiative (GTRI) has provided the Russian Federation with significant financial and technical assistance to secure its highly vulnerable and dangerous radiological material. The three program areas of this assistance are the removal of radioisotope thermoelectric generators (RTG), the physical protection of vulnerable in-use radiological material of concern, and the recovery of disused or abandoned radiological material of concern. Despite the many successes of the GTRI program in Russia, however, there is still a need for increased international cooperation in these efforts. Furthermore, concerns exist over how the Russian government will ensure that the security of its radiological materials provided through GTRI will be sustained. This paper addresses these issues and highlights the successes of GTRI efforts and ongoing activities.

  4. Radiological worker training

    SciTech Connect (OSTI)

    1998-10-01

    This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance.

  5. Radiological Worker Training - Radiological Control Training for Supervisors

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

    A December 2008 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at

  6. DOE Technical Targets for Hydrogen Storage Systems for Material...

    Office of Environmental Management (EM)

    Material Handling Equipment DOE Technical Targets for Hydrogen Storage Systems for Material Handling Equipment This table summarizes hydrogen storage technical performance targets ...

  7. 324 Building Baseline Radiological Characterization

    SciTech Connect (OSTI)

    R.J. Reeder, J.C. Cooper

    2010-06-24

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building.

  8. Property:TwitterHandle | Open Energy Information

    Open Energy Info (EERE)

    to: navigation, search Property Name TwitterHandle Property Type Text Description A Twitter handle in @Whatever format (not the full url) Pages using the property...

  9. Radiological Control Technician Training

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

    Part 7of 9 Radiological Control Technician Training Practical Training Phase II Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 Table of Contents Page Introduction.............................................................................. ......1 Development of Job Performance Measures (JPMs)............................ .....1 Conduct Job Performance Evaluation...................................................3

  10. Radiological Control Technician Training

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

    Part 8 of 9 Radiological Control Technician Training Oral Examination Boards Phase III Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 This page intentionally left blank ii DOE-HDBK-1122-2009 Table of Contents Page Introduction................................................................................................................................1 Purpose of Oral Examinations

  11. Radiological Control Technician Training

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

    9 of 9 Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 This page intentionally left blank ii DOE-HDBK-1122-2009 Table of Contents Page Introduction................................................................................................................................1 Facility Job Performance Measures

  12. Radiological Technician Training

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

    DOE-HDBK-1122-2009 Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 This page intentionally left blank. ii DOE-HDBK-1122-2009 Table of Contents Page Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 Purpose of Qualification Standard . . . . . . . . . . . . . . . . .

  13. NNSA Conducts International Radiological Response Training in...

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

    NNSA Conducts International Radiological Response Training in Vienna August 01, 2013 ... Radiological Assistance Program Training for Emergency Response Advanced ...

  14. Non-contact handling device

    DOE Patents [OSTI]

    Reece, Mark; Knorovsky, Gerald A.; MacCallum, Danny O.

    2007-05-15

    A pressurized fluid handling nozzle has a body with a first end and a second end, a fluid conduit and a recess at the second end. The first end is configured for connection to a pressurized fluid source. The fluid conduit has an inlet at the first end and an outlet at the recess. The nozzle uses the Bernoulli effect for lifting a part.

  15. Portable vacuum object handling device

    DOE Patents [OSTI]

    Anderson, Gordon H.

    1983-08-09

    The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuatable to apply the vacuum to lift the object.

  16. General Employee Radiological Training

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

    DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-HDBK-1131-2007 iii Foreword This Handbook describes an implementation process for core training as recommended in chapter 14,

  17. General Employee Radiological Training

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

    Not Measurement Sensitive DOE-HDBK-1131-2007 December 2007_______ Change Notice 1 Reaffirmed 2013 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The

  18. Radiological Worker Training

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

    98 October 1998 Change Notice No. 1 June 2001 Change Notice No. 2 December 2003 Reaffirmation with Errata May 2004 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-98 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information

  19. Radiological Worker Training - Radiological Contamination Control...

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

    ... for Laboratories Using Chemicals and NFPA 432, Code for the Storage of Organic Peroxides. ... Monitoring techniques for release of materials are addressed in DOECH-9401 (1993). ...

  20. Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014

    Broader source: Energy.gov [DOE]

    On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following the event, the investigation was broken into two phases. The Phase 1 report focused on how the radiological material was released into the atmosphere and Phase 2, performed once limited access to the underground was re?established, focused on the source of the released radiological material.

  1. Nuclear and Radiological Material Security | National Nuclear...

    National Nuclear Security Administration (NNSA)

    This includes NNSA's work to advance physical protection standards for nuclear facilities and to strengthen nuclear safeguards, which are criteria for the physical security and the ...

  2. Materials

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

    Materials Materials Access to Hopper Phase II (Cray XE6) If you are a current NERSC user, you are enabled to use Hopper Phase II. Use your SSH client to connect to Hopper II:...

  3. Materials

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

    Materials Materials Understanding and manipulating the most fundamental properties of materials can lead to major breakthroughs in solar power, reactor fuels, optical computing, telecommunications. News Releases Science Briefs Photos Picture of the Week Publications Social Media Videos Fact Sheets Yu Seung Kim (left) and Kwan-Soo Lee (right) New class of fuel cells offer increased flexibility, lower cost A new class of fuel cells based on a newly discovered polymer-based material could bridge

  4. Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

    SciTech Connect (OSTI)

    Mishima, J.; Sutter, S.L.; Hawley, K.A.; Jenkins, C.E.; Napier, B.A.

    1986-02-01

    The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Scenarios for operational accident and abnormal operational events are postulated, on the basis of the currently available information, for the application of the techniques employed for each waste class for each disposal alternative. From these scenarios, an upper-bound airborne release of radioactive material was postulated for each waste class and disposal alternative. Potential downwind radiologic impacts were calculated from these upper-bound events. In all three alternatives, the single postulated event with the largest calculated radiologic impact for any waste class is an explosion of a mixture of ferri/ferro cyanide precipitates during the mechanical retrieval or microwave drying of the salt cake in single shell waste tanks. The anticipated downwind dose (70-year dose commitment) to the maximally exposed individual is 3 rem with a total population dose of 7000 man-rem. The same individual would receive 7 rem from natural background radiation during the same time period, and the same population would receive 3,000,000 man-rem. Radiological impacts to the public from all other postulated accidents would be less than that from this accident; furthermore, the radiological impacts resulting from this accident would be less than one-half that from the natural background radiation dose.

  5. NNSA Receives Excellence Award for Radiological Security Enhancements in

    National Nuclear Security Administration (NNSA)

    Hawaii | National Nuclear Security Administration | (NNSA) Receives Excellence Award for Radiological Security Enhancements in Hawaii August 18, 2016 HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts to enhance the security of radioactive materials in the State of Hawaii.

  6. Portable vacuum object handling device

    DOE Patents [OSTI]

    Anderson, G.H.

    1983-08-09

    The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuatable to apply the vacuum to lift the object. 1 fig.

  7. Uranium hexafluoride: A manual of good handling practices. Revision 7

    SciTech Connect (OSTI)

    1995-01-01

    The United States Enrichment Corporation (USEC) is continuing the policy of the US Department of Energy (DOE) and its predecessor agencies in sharing with the nuclear industry their experience in the area of uranium hexafluoride (UF{sub 6}) shipping containers and handling procedures. The USEC has reviewed Revision 6 or ORO-651 and is issuing this new edition to assure that the document includes the most recent information on UF{sub 6} handling procedures and reflects the policies of the USEC. This manual updates the material contained in earlier issues. It covers the essential aspects of UF{sub 6} handling, cylinder filling and emptying, general principles of weighing and sampling, shipping, and the use of protective overpacks. The physical and chemical properties of UF{sub 6} are also described. The procedures and systems described for safe handling of UF{sub 6} presented in this document have been developed and evaluated during more than 40 years of handling vast quantities of UF{sub 6}. With proper consideration for its nuclear properties, UF{sub 6} may be safely handled in essentially the same manner as any other corrosive and/or toxic chemical.

  8. Smart Radiological Dosimeter

    DOE Patents [OSTI]

    Kosslow, William J.; Bandzuch, Gregory S.

    2004-07-20

    A radiation dosimeter providing an indication of the dose of radiation to which the radiation sensor has been exposed. The dosimeter contains features enabling the monitoring and evaluating of radiological risks so that a user can concentrate on the task at hand. The dosimeter provides an audible alarm indication that a predetermined time period has elapsed, an audible alarm indication reminding the user to check the dosimeter indication periodically, an audible alarm indicating that a predetermined accumulated dose has been prematurely reached, and an audible alarm indication prior or to reaching the 3/4 scale point.

  9. Radiological Assessor Training

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

    141-2001 April 2001 Change Notice No. 1 and Reaffirmation January 2007 DOE HANDBOOK Radiological Assessor Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823.

  10. Radiological Control Technician Training

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

    22-2009 February 2009_______ Change Notice 1 June 2009 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009 Original Change Part 3 1.05-1

  11. Radiological Control Technician Training

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

    Not Measurement Sensitive DOE-HDBK-1122-2009 February 2009 Change Notice No. 1 2009 Change Notice No. 2 2011 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009

  12. Radiological Worker Training

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

    8 December 2008 Change Notice 1 June 2009 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1130-2008 Original Change Part 2 Module 2 page 17 Medical

  13. Radiological Worker Training

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

    TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 December 2008 Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 2 DOE-HDBK-1130-2008 Original Change Throughout

  14. Material Safety Data Sheets

    Broader source: Energy.gov [DOE]

    Material Safety Data Sheets (MSDSs) provide workers and emergency personnel with ways for handling and working with a hazardous substance and other health and safety information.

  15. Radiological Worker Computer Based Training

    Energy Science and Technology Software Center (OSTI)

    2003-02-06

    Argonne National Laboratory has developed an interactive computer based training (CBT) version of the standardized DOE Radiological Worker training program. This CD-ROM based program utilizes graphics, animation, photographs, sound and video to train users in ten topical areas: radiological fundamentals, biological effects, dose limits, ALARA, personnel monitoring, controls and postings, emergency response, contamination controls, high radiation areas, and lessons learned.

  16. Standardized radiological dose evaluations

    SciTech Connect (OSTI)

    Peterson, V.L.; Stahlnecker, E.

    1996-05-01

    Following the end of the Cold War, the mission of Rocky Flats Environmental Technology Site changed from production of nuclear weapons to cleanup. Authorization baseis documents for the facilities, primarily the Final Safety Analysis Reports, are being replaced with new ones in which accident scenarios are sorted into coarse bins of consequence and frequency, similar to the approach of DOE-STD-3011-94. Because this binning does not require high precision, a standardized approach for radiological dose evaluations is taken for all the facilities at the site. This is done through a standard calculation ``template`` for use by all safety analysts preparing the new documents. This report describes this template and its use.

  17. Nuclear Radiological Threat Task Force Established | National...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task ...

  18. ORISE Resources: Radiological and Nuclear Terrorism: Medical...

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

    to mass casualties that may involve radiological injuries. The interactive, two-hour training, titled Radiological and Nuclear Terrorism: Medical Response to Mass Casualties...

  19. radiological consquence management | National Nuclear Security...

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

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home radiological consquence management radiological consquence management Fukushima: Five Years Later After the March 11, 2011, ...

  20. radiological response | National Nuclear Security Administration

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

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home radiological response radiological response Fukushima: Five Years Later After the March 11, 2011, Japan earthquake, tsunami, ...

  1. PIA - Radiological Work Permit | Department of Energy

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

    PIA - Radiological Work Permit PDF icon PIA - Radiological Work Permit More Documents & Publications PIA - Bonneville Power Adminstration Ethics Helpline Occupational Medical ...

  2. Radiological Weapons: How Great Is The Danger?

    SciTech Connect (OSTI)

    Moore, G M

    2003-06-01

    One of the underlying purposes of this paper is to provoke thinking about the interplay between the regulation of radioactive materials and the risk of their use in an radiological weapon (RW). Also considered in this paper are the types of RWs that a terrorist might use, the nature of the threat and danger posed by the various types of RWs, the essential elements that must be considered in responding to the terrorist use of an RW, and what steps may need to be taken a priori to minimize the consequences of the inevitable use of an RW. Because radiological dispersal devices (RDDs) have been the focus of so much recent concern and because RDDs are arguably the most likely of RWs to be used by a terrorist group, a major focus of this paper will be on RDDs. Radiological weapons are going to be used by some individual or group, if not this year then next year, or at some time in the foreseeable future. A policy of focusing resources solely on prevention of their use would leave any government open to significant economic disruption when the inevitable use occurs. Preplanning can limit the injuries, property damage, and economic losses that might result from the use of an RW. Moreover, a combination of efforts to prevent and to minimize the impact of RWs may significantly discourage potential users. The dangers from RWs can be dealt with while society continues to enjoy the benefits of nuclear technology that were promised under Atoms for Peace. However, some restructuring of our use of radioactive materials is necessary to ensure that the current and future uses of radioactive materials outweigh the potential disruption caused by misuse of the materials in RWs.

  3. Transfer Area Mechanical Handling Calculation

    SciTech Connect (OSTI)

    B. Dianda

    2004-06-23

    This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAX Company L.L. C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC28-01R W12101'' (Arthur, W.J., I11 2004). This correspondence was appended by further Correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC28-OIRW12101; TDL No. 04-024'' (BSC 2004a). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The purpose of this calculation is to establish preliminary bounding equipment envelopes and weights for the Fuel Handling Facility (FHF) transfer areas equipment. This calculation provides preliminary information only to support development of facility layouts and preliminary load calculations. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process. It is intended that this calculation is superseded as the design advances to reflect information necessary to support License Application. The design choices outlined within this calculation represent a demonstration of feasibility and may or may not be included in the completed design. This calculation provides preliminary weight, dimensional envelope, and equipment position in building for the purposes of defining interface variables. This calculation identifies and sizes major equipment and assemblies that dictate overall equipment dimensions and facility interfaces. Sizing of components is based on the selection of commercially available products, where applicable. This is not a specific recommendation for the future use of these components or their related

  4. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M.

    1989-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  5. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M.

    1990-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  6. Analytical methods for removing radiological constituents prior to organic analysis

    SciTech Connect (OSTI)

    Hakonson, K.; Monagle, M.; Cournoyer, M.

    1997-12-31

    Within the Department of Energy (DOE), there is a need to analyze mixed waste materials (i.e. materials that are contaminated with both radiological and hazardous components). As part of the technical support the Organic Analysis Group provides for programs within Los Alamos National Laboratory, methods are under development for radiologically contaminated oil samples being tested for polychlorinated biphenyls and other semivolatile constituents. Radionuclides are removed from oil samples by filtering the samples through a commercials available solid phase extraction cartridge. An aliquot of the eluent is then analyzed to quantitate the residual radioactivity.

  7. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    J.F. Beesley

    2005-04-21

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

  8. Enewetak radiological support project. Final report

    SciTech Connect (OSTI)

    Friesen, B.

    1982-09-01

    From 1972 through 1980, the Department of Energy acted in an advisory role to the Defense Nuclear Agency during planning for and execution of the cleanup of Enewetak Atoll. The Nevada Operations Office of the Department of Energy was responsible for the radiological characterization of the atoll and for certification of radiological condition of each island upon completion of the project. In-situ measurements of gamma rays emitted by americium-241 were utilized along with wet chemistry separation of plutonium from soil samples to identify and delineate surface areas requiring removal of soil. Military forces removed over 100,000 cubic yards of soil from the surface of five islands and deposited this material in a crater remaining from the nuclear testing period. Subsurface soil was excavated and removed from several locations where measurements indicated the presence of radionuclides above predetermined criteria. The methodologies of data acquisition, analysis and interpretation are described and detailed results are provided in text, figures and microfiche. The final radiological condition of each of 43 islets is reported.

  9. GIS Symbology for FRMAC/CMHT Radiological/Nuclear Products

    SciTech Connect (OSTI)

    Walker, H; Aluzzi, F; Foster, K; Pobanz, B; Sher, B

    2008-10-06

    This document is intended to codify, to the extent currently possible, the representation of map products produced for and by the Federal Radiological Monitoring and Assessment Center (FRMAC) and the Consequence Management Home Team (CHMT), particularly those that include model products from the National Atmospheric Release Advisory Capability (NARAC). This is to facilitate consistency between GIS products produced by different members of these teams, which should ease the task of interpreting these products by both team members and those outside the team who may need to use these products during a response. The aspects of symbology being considered are primarily isopleths levels (breakpoints) and colors used to plot NARAC modeled dose or deposition fields on mpas, although some comments will be made about the handling of legend and supporting textual information. Other aspects of symbolizing such products (e.g., transparency) are being left to the individual team members to allow them to adapt to particular organizational needs or requirements that develop during a particular a response or exercise. This document has been written in coordination with the creation of training material in Baskett, et al., 2008. It is not intended as an aid to NARAC product interpretation but to facilitate the work of GIS specialists who deal with these products in map design and in the development of supporting scripts and software that partially or completely automate the integration of NARAC model products with other GIS data. This work was completed as part of the NA-42 Technical Integration Project on GIS Automated Data Processing and Map Production in FY 2008. Other efforts that are part of this work include (a) updating the NARAC shapefile product representation to facilitate the automation work proceed at RSL as part of the same TI effort and (b) to ensure that the NARAC shapefile construct includes all of the necessary legend and other textual data to interpret dispersion

  10. Estimate Radiological Dose for Animals

    Energy Science and Technology Software Center (OSTI)

    1997-12-18

    Estimate Radiological dose for animals in ecological environment using open literature values for parameters such as body weight, plant and soil ingestion rate, rad. halflife, absorbed energy, biological halflife, gamma energy per decay, soil-to-plant transfer factor, ...etc

  11. Radiological cleanup of Enewetak Atoll

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

    For 8 years, from 1972 until 1980, the United States planned and carried out the radiological cleanup, rehabilitation, and resettlement of Enewetak Atoll in the Marshall Islands. This documentary records, from the perspective of DOD, the background, decisions, actions, and results of this major national and international effort. The documentary is designed: First, to provide a historical document which records with accuracy this major event in the history of Enewetak Atoll, the Marshall Islands, the Trust Territory of the Pacific Islands, Micronesia, the Pacific Basin, and the United States. Second, to provide a definitive record of the radiological contamination of the Atoll. Third, to provide a detailed record of the radiological exposure of the cleanup forces themselves. Fourth, to provide a useful guide for subsequent radiological cleanup efforts elsewhere.

  12. Radiological Worker Training

    Office of Environmental Management (EM)

    ... for Laboratories Using Chemicals and NFPA 432, Code for the Storage of Organic ... Monitoring techniques for release of materials are addressed in DOECH-9401 (1993). ...

  13. 327 Building liquid waste handling options modification project plan

    SciTech Connect (OSTI)

    Ham, J.E.

    1998-03-28

    This report evaluates the modification options for handling radiological liquid waste (RLW) generated during decontamination and cleanout of the 327 Building. The overall objective of the 327 Facility Stabilization Project is to establish a passively safe and environmentally secure configuration of the 327 Facility. The issue of handling of RLW from the 327 Facility (assuming the 34O Facility is not available to accept the RLW) has been conceptually examined in at least two earlier engineering studies (Parsons 1997a and Hobart l997). Each study identified a similar preferred alternative that included modifying the 327 Facility RLWS handling systems to provide a truck load-out station, either within the confines of the facility or exterior to the facility. The alternatives also maximized the use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes. An issue discussed in each study involved the anticipated volume of the RLW stream. Estimates ranged between 113,550 and 387,500 liters in the earlier studies. During the development of the 324/327 Building Stabilization/Deactivation Project Management Plan, the lower estimate of approximately 113,550 liters was confirmed and has been adopted as the baseline for the 327 Facility RLW stream. The goal of this engineering study is to reevaluate the existing preferred alternative and select a new preferred alternative, if appropriate. Based on the new or confirmed preferred alternative, this study will also provide a conceptual design and cost estimate for required modifications to the 327 Facility to allow removal of RLWS and treatment of the RLW generated during deactivation.

  14. Radiological Monitoring Continues at WIPP

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

    Radiological Monitoring Continues at WIPP CARLSBAD, N.M., February 19, 2014 - Radiological control personnel continue to collect surface and underground monitoring samples at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) after an underground air monitor detected airborne radiation around 11:30 p.m. (MT) on February 14. Recent laboratory analyses by Carlsbad Environmental Monitoring and Research Center (CEMRC) found some trace amounts of americium and plutonium from a

  15. Radiological training for tritium facilities

    SciTech Connect (OSTI)

    1996-12-01

    This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835.

  16. LANL responds to radiological incident

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

    LANL responds to radiological incident LANL responds to radiological incident Multiple tests indicate no health risks to public or employees. August 27, 2012 Aerial view of the Los Alamos Neutron Science Center(LANSCE). Aerial view of the Los Alamos Neutron Science Center (LANSCE). The contamination poses no danger to the public. The Laboratory is investigating the inadvertent spread of Technetium 99 by employees and contractors at the Lujan Neutron Scattering Center August 27, 2012-The

  17. Radiological Protection for DOE Activities

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

    1995-09-29

    Establishes radiological protection program requirements that, combined with 10 CFR 835 and its associated implementation guidance, form the basis for a comprehensive program for protection of individuals from the hazards of ionizing radiation in controlled areas. Extended by DOE N 441.3. Cancels DOE 5480.11, DOE 5480.15, DOE N 5400.13, DOE N 5480.11; please note: the DOE radiological control manual (DOE/EH-0256T)

  18. REM Handling Procedures | The Ames Laboratory

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

    REM Handling Procedures Below are recommended handling procedures for the Rare Earth Metals. Keep in mind that these procedures are intended for very high purity metals, and alternative procedures may exist or be better suited to your facilities' capabilities. Please consult with your safety officer(s) before employing any of these procedures. The procedures are grouped by element: La, Ce, Pr & Nd Sc, Y, Gd, Tb, Dy, Ho, Er, Tm and Lu Sm & Yb Eu RECOMMENDED HANDLING PROCEDURES FOR: La,

  19. Apparatus for remotely handling components

    DOE Patents [OSTI]

    Szkrybalo, Gregory A.; Griffin, Donald L.

    1994-01-01

    The inventive apparatus for remotely handling bar-like components which define a longitudinal direction includes a gripper mechanism for gripping the component including first and second gripper members longitudinally fixedly spaced from each other and oriented parallel to each other in planes transverse to the longitudinal direction. Each gripper member includes a jaw having at least one V-groove with opposing surfaces intersecting at a base and extending radially relative to the longitudinal direction for receiving the component in an open end between the opposing surfaces. The V-grooves on the jaw plate of the first and second gripper members are aligned in the longitudinal direction to support the component in the first and second gripper members. A jaw is rotatably mounted on and a part of each of the first and second gripper members for selectively assuming a retracted mode in which the open end of the V-groove is unobstructed and active mode in which the jaw spans the open end of the V-groove in the first and second gripper members. The jaw has a locking surface for contacting the component in the active mode to secure the component between the locking surface of the jaw and the opposing surfaces of the V-groove. The locking surface has a plurality of stepped portions, each defining a progressively decreasing radial distance between the base of the V-groove and the stepped portion opposing the base to accommodate varying sizes of components.

  20. Radiological assessment. A textbook on environmental dose analysis

    SciTech Connect (OSTI)

    Till, J.E.; Meyer, H.R.

    1983-09-01

    Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

  1. Feed Processing, Handling, and Gasification

    SciTech Connect (OSTI)

    2006-04-01

    Both current and future sugar biorefineries will generate a wide variety of residue streams that can be used as feedstocks for thermochemical processes, including corn stover, corn fiber, lignin-rich materials, and distillers dried grain and solubles.

  2. Radiological Control Technician Training

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

    ... Material Resolving Time Resolving time (or dead time) is the time interval which must ... In a non-paralyzable detector, an event happening during the dead time since the previous ...

  3. DOE - Office of Legacy Management -- U S Naval Radiological Defense

    Office of Legacy Management (LM)

    Laboratory - CA 0-06 Naval Radiological Defense Laboratory - CA 0-06 FUSRAP Considered Sites Site: U. S. NAVAL RADIOLOGICAL DEFENSE LABORATORY (CA.0-06) Eliminated from consideration under FUSRAP - Referred to the DoD Designated Name: Not Designated Alternate Name: None Location: San Francisco , California CA.0-06-1 Evaluation Year: 1987 CA.0-06-1 Site Operations: NRC licensed DoD facility which used small quantities of nuclear materials for R&D purposes and decontaminated ships.

  4. Legacy material work-off project

    SciTech Connect (OSTI)

    Sloan, T.J.; Baker, D.H. IV

    1999-01-25

    Los Alamos National Laboratory (LANL) and its subcontractors recently completed a nine-month legacy material clean-up effort. Legacy materials were defined as chemicals, hazardous, non-hazardous, and both hazardous and radioactive (mixed), that no longer served a programmatic use and had no identified individual owner within the Laboratory. Once personnel identified the legacy materials, the items were transferred to Solid Waste Operation`s (EM-SWO) control. Upon completing this process, the responsible division-level manager was required to certify that all non-radioactive hazardous and non-hazardous materials and acceptable mixed legacy materials had been identified and transferred to EM-SWO for proper handling or disposal. The major expense in this project was the cost of actual chemical and radiological analysis. This expense was the result of items not having an identified individual owner. The major benefit of this project is that LANL is now in an excellent position to implement its Integrated Safety Management (ISM) Plan, which requires the implementation of safe work practices, including requirements for removing unused items when vacating workspaces. Effective implementation of ISM will go a long way toward ensuring that legacy materials are no longer an issue at the Laboratory.

  5. Sensors & Materials | Argonne National Laboratory

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

    Sensors and Materials Argonne uses its materials and engineering expertise to develop, test, and deploy sensors and materials to detect nuclear and radiological materials, chemical and biological agents and explosives. Argonne uses its materials and engineering expertise to develop, test, and deploy sensors and materials to detect nuclear and radiological materials, chemical and biological agents and explosives. Our goal is to develop critical security technologies to prevent and manage events

  6. Radiological control manual. Revision 1

    SciTech Connect (OSTI)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

  7. A method for calculating the consequences of explosive radiological releases

    SciTech Connect (OSTI)

    Layman, B.J. )

    1991-01-01

    Radiological releases resulting from detonations are a primary concern of analysts when they are dealing with radiological sabotage. Calculating the consequences of these explosive releases is an integral part of the risk assessment process. This paper presents a method for relating the consequences of a release to the resultant doses by using the appropriate radiological guidelines. The doses are calculated as the product of dose conversion factors and building source terms. The uses of relative activities and committed dose equivalent factors, organ weighting factors, and meteorological data for calculating the dose conversion factors are discussed. Material at risk, release fractions, respirable fractions, and leak path factors, which are used to compute the building source terms, are also addressed.

  8. NNSA Provides Tajikistan Specialized Vehicles to Transport Radiological

    National Nuclear Security Administration (NNSA)

    Materials | National Nuclear Security Administration | (NNSA) Provides Tajikistan Specialized Vehicles to Transport Radiological Materials October 07, 2015 NNSA Program Manager Nick Cavellero, right, and NRSA Director of the Department of Information and International Relations Ilkhom Mirsaidov, left, with two specialized vehicles purchased by NNSA for Tajikistan. WASHINGTON - The Department of Energy's National Nuclear Security Administration (DOE/NNSA), the United States Embassy of

  9. Neutron Energy Measurements in Radiological Emergency Response Applications

    SciTech Connect (OSTI)

    Sanjoy Mukhopadhyay, Paul Guss, Michael Hornish, Scott Wilde, Tom Stampahar, Michael Reed

    2009-04-30

    We present significant results in recent advances in the determination of neutron energy. Neutron energy measurements are a small but very significant part of radiological emergency response applications. Mission critical information can be obtained by analyzing the neutron energy given off from radioactive materials. In the case of searching for special nuclear materials, neutron energy information from an unknown source can be of paramount importance.

  10. Oxygen Handling and Cooling Options in High Temperature Electrolysis Plants

    SciTech Connect (OSTI)

    Manohar S. Sohal; J. Stephen Herring

    2008-07-01

    Idaho National Laboratory is working on a project to generate hydrogen by high temperature electrolysis (HTE). In such an HTE system, safety precautions need to be taken to handle high temperature oxygen at ~830°C. This report is aimed at addressing oxygen handling in a HTE plant.. Though oxygen itself is not flammable, most engineering material, including many gases and liquids, will burn in the presence of oxygen under some favorable physicochemical conditions. At present, an absolute set of rules does not exist that can cover all aspects of oxygen system design, material selection, and operating practices to avoid subtle hazards related to oxygen. Because most materials, including metals, will burn in an oxygen-enriched environment, hazards are always present when using oxygen. Most materials will ignite in an oxygen-enriched environment at a temperature lower than that in air, and once ignited, combustion rates are greater in the oxygen-enriched environment. Even many metals, if ignited, burn violently in an oxygen-enriched environment. However, these hazards do not preclude the operations and systems involving oxygen. Oxygen can be safely handled and used if all the materials in a system are not flammable in the end-use environment or if ignition sources are identified and controlled. In fact, the incidence of oxygen system fires is reported to be low with a probability of about one in a million. This report is a practical guideline and tutorial for the safe operation and handling of gaseous oxygen in high temperature electrolysis system. The intent is to provide safe, practical guidance that permits the accomplishment of experimental operations at INL, while being restrictive enough to prevent personnel endangerment and to provide reasonable facility protection. Adequate guidelines are provided to govern various aspects of oxygen handling associated with high temperature electrolysis system to generate hydrogen. The intent here is to present acceptable

  11. Process Knowledge Summary Report for Advanced Test Reactor Complex Contact-Handled Transuranic Waste Drum TRA010029

    SciTech Connect (OSTI)

    B. R. Adams; R. P. Grant; P. R. Smith; J. L. Weisgerber

    2013-09-01

    This Process Knowledge Summary Report summarizes information collected to satisfy the transportation and waste acceptance requirements for the transfer of one drum containing contact-handled transuranic (TRU) actinide standards generated by the Idaho National Laboratory at the Advanced Test Reactor (ATR) Complex to the Advanced Mixed Waste Treatment Project (AMWTP) for storage and subsequent shipment to the Waste Isolation Pilot Plant for final disposal. The drum (i.e., Integrated Waste Tracking System Bar Code Number TRA010029) is currently stored at the Materials and Fuels Complex. The information collected includes documentation that addresses the requirements for AMWTP and applicable sections of their Resource Conservation and Recovery Act permits for receipt and disposal of this TRU waste generated from ATR. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for this TRU waste originating from ATR.

  12. How the NWC handles software as product

    SciTech Connect (OSTI)

    Vinson, D.

    1997-11-01

    This tutorial provides a hands-on view of how the Nuclear Weapons Complex project should be handling (or planning to handle) software as a product in response to Engineering Procedure 401099. The SQAS has published the document SQAS96-002, Guidelines for NWC Processes for Handling Software Product, that will be the basis for the tutorial. The primary scope of the tutorial is on software products that result from weapons and weapons-related projects, although the information presented is applicable to many software projects. Processes that involve the exchange, review, or evaluation of software product between or among NWC sites, DOE, and external customers will be described.

  13. Early Markets: Fuel Cells for Material Handling Equipment

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

    MHE can use Polymer Electrolyte Membrane (PEM) fuel cell systems, which can be fueled with hydrogen, or by using methanol in Direct Methanol Fuel Cells (DMFCs). The Case for Fuel ...

  14. Radiological Assistance Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | (NNSA) Radiological Assistance Program RAP Logo NNSA's Radiological Assistance Program (RAP) is the nation's premier first-response resource in assessing an emergency situation and advising decision-makers on further steps to take to evaluate and minimize the hazards of a radiological incident. RAP provides resources (trained personnel and equipment) to evaluate, assess, advise, isotopically identify, search for, and assist in the mitigation of actual or perceived nuclear or radiological

  15. Operational Guidelines/Radiological Emergency Response

    Broader source: Energy.gov [DOE]

    Operational Guidelines/Radiological Emergency Response. Provides information and resources concerning the development of Operational Guidelines as part of planning guidance for protection and recovery following Radiological Dispersal Device (RDD) and/or Improvised Nuclear Device (IND) incidents. Operational Guidelines Technical (OGT) Manual, 2009 RESRAD-RDD Complementing Software to OGT Manual EPA Protective Action Guidelines (2013), Interim Final Federal Radiological Monitoring and Assessment Center (FRMAC) Federal Radiological Preparedness Coordinating Committee (FRPCC)

  16. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    Department of Energy Office of Environmental Management Accident Investigation Report Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014 April 2015 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release Event at the Waste Isolation Pilot Plant Disclaimer On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. On March 4, 2014, an

  17. 2004 Biodiesel Handling and Use Guidelines (Revised)

    SciTech Connect (OSTI)

    Not Available

    2004-11-01

    This document is a guide for those who blend, distribute, and use biodiesel and biodiesel blends. It is intended to fleets and individual users, blenders, distributors, and those involved in related activities understand procedures for handling and using biodiesel.

  18. radiological | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological NNSA program strengthens national security from afar The Nuclear Smuggling Detection and Deterrence (NSDD) program is a key component of NNSA's core mission to reduce nuclear threats. The program, part of NNSA's Office of Defense Nuclear Nonproliferation, provides partners tools and training to deter, detect, and investigate smuggling of

  19. Departmental Radiological Emergency Response Assets

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

    2007-06-27

    The order establishes requirements and responsibilities for the DOE/NNSA national radiological emergency response assets and capabilities and Nuclear Emergency Support Team assets. Supersedes DOE O 5530.1A, DOE O 5530.2, DOE O 5530.3, DOE O 5530.4, and DOE O 5530.5.

  20. Nuclear and Radiological Forensics and Attribution Overview

    SciTech Connect (OSTI)

    Smith, D K; Niemeyer, S

    2005-11-04

    The goal of the U.S. Department of Homeland Security (DHS) Nuclear and Radiological Forensics and Attribution Program is to develop the technical capability for the nation to rapidly, accurately, and credibly attribute the origins and pathways of interdicted or collected materials, intact nuclear devices, and radiological dispersal devices. A robust attribution capability contributes to threat assessment, prevention, and deterrence of nuclear terrorism; it also supports the Federal Bureau of Investigation (FBI) in its investigative mission to prevent and respond to nuclear terrorism. Development of the capability involves two major elements: (1) the ability to collect evidence and make forensic measurements, and (2) the ability to interpret the forensic data. The Program leverages the existing capability throughout the U.S. Department of Energy (DOE) national laboratory complex in a way that meets the requirements of the FBI and other government users. At the same time the capability is being developed, the Program also conducts investigations for a variety of sponsors using the current capability. The combination of operations and R&D in one program helps to ensure a strong linkage between the needs of the user community and the scientific development.

  1. Storage/Handling | Department of Energy

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

    Storage/Handling Storage/Handling Records Management Procedures for Storage, Transfer & Retrieval of Records from the Washington National Records Center (WNRC) or Legacy Management Business Center RETIREMENT OF RECORDS: 1. The Program Office originates the Records Transmittal and Receipt Form SF-135 (PDF, 107KB), and sends it to IM-23 at doerm@hq.doe.gov for approval. 2. IM-23 reviews the SF-135 for completeness/correctness and coordinates with the originating office by email if more

  2. Large-Scale Liquid Hydrogen Handling Equipment

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

    8, 2007 Jerry Gillette Large-Scale Liquid Hydrogen Handling Equipment Hydrogen Delivery Analysis Meeting Argonne National Laboratory Some Delivery Pathways Will Necessitate the Use of Large- Scale Liquid Hydrogen Handling Equipment „ Potential Scenarios include: - Production plant shutdowns - Summer-peak storage „ Equipment Needs include: - Storage tanks - Liquid Pumps - Vaporizers - Ancillaries 2 1 Concern is that Scaling up from Small Units Could Significantly Underestimate Costs of Larger

  3. Reference Materials

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

    ID 412- 11/16/2012 - Page 1 Log No 2012-263 Reference Materials * Transporting Radioactive Waste to the Nevada National Security Site fact sheet (ww.nv.energy.gov/library/factsheets/DOENV_990.pdf) - Generators contract with commercial carriers - U.S. Department of Transportation regulations require carriers to select routes which minimize radiological risk * Drivers Route and Shipment Information Questionnaire completed by drivers to document routes taken to the NNSS upon entry into Nevada -

  4. TEPP Training - Modular Emergency Response Radiological Transportation

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

    Training (MERRTT) | Department of Energy Training - Modular Emergency Response Radiological Transportation Training (MERRTT) TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) Once the jurisdiction has completed an evaluation of their plans and procedures, they will need to address any gaps in training. To assist, TEPP has developed the Modular Emergency Response Radiological Transportation Training (MERRTT) program. MERRTT provides fundamental knowledge

  5. material | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    material NNSA Receives Excellence Award for Radiological Security Enhancements in Hawaii HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts

  6. Model Recovery Procedure for Response to a Radiological Transportation...

    Office of Environmental Management (EM)

    for Response to a Radiological Transportation Incident Model Recovery Procedure for Response to a Radiological Transportation Incident This Transportation Emergency...

  7. Current Trends in Gamma Radiation Detection for Radiological Emergency Response

    SciTech Connect (OSTI)

    Mukhopadhyay, S., Guss, P., Maurer, R.

    2011-09-01

    Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies. In recent years, since the establishment of the Domestic Nuclear Detection Office by the Department of Homeland Security, a tremendous amount of progress has been made in detection materials (scintillators, semiconductors), imaging techniques (Compton imaging, use of active masking and hybrid imaging), data acquisition systems with digital signal processing, field programmable gate arrays and embedded isotopic analysis software (viz. gamma detector response and analysis software [GADRAS]1), fast template matching, and data fusion (merging radiological data with geo-referenced maps, digital imagery to provide better situational awareness). In this stride to progress, a significant amount of interdisciplinary research and development has taken placetechniques and spin-offs from medical science (such as x-ray radiography and tomography), materials engineering (systematic planned studies on scintillators to optimize several qualities of a good scintillator, nanoparticle applications, quantum dots, and photonic crystals, just to name a few). No trend analysis of radiation detection systems would be complete without mentioning the unprecedented strategic position taken by the National Nuclear Security Administration (NNSA) to deter, detect, and interdict illicit trafficking in nuclear and other radioactive materials across international borders and through the global maritime transportationthe so-called second line of defense.

  8. Final remote-handled waste canister leaves Los Alamos National Laboratory

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

    Remote-handled waste canister leaves LANL Final remote-handled waste canister leaves Los Alamos National Laboratory The Laboratory began shipping the canisters exactly one month ago and averaged four shipments per week. July 2, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los

  9. V-217: Microsoft Windows NAT Driver ICMP Packet Handling Denial...

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

    7: Microsoft Windows NAT Driver ICMP Packet Handling Denial of Service Vulnerability V-217: Microsoft Windows NAT Driver ICMP Packet Handling Denial of Service Vulnerability August...

  10. Biodiesel Handling and Use Guide | Open Energy Information

    Open Energy Info (EERE)

    Handling and Use Guide Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Biodiesel Handling and Use Guide AgencyCompany Organization: National Renewable Energy...

  11. ETA-UTP007 - Road Course Handling Test

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

    Road Course Handling Test Prepared by Electric Transportation Applications Prepared by: ... Appendix A - Electric Vehicle Road Course Handling Test Data Sheet 13 Appendix B - Vehicle ...

  12. ETA-HITP07 - Road Course Handling Test

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

    Effective November 1, 2004 Road Course Handling Test Prepared by Electric Transportation ... Appendix A - Hydrogen Internal Combustion Vehicle Road Course Handling Test Data Sheet 6 ...

  13. Central Characterization Program (CCP) Contact-Handled (CH) TRU...

    Office of Environmental Management (EM)

    Contact-Handled (CH) TRU Waste Certification and Waste Information SystemWaste Data System (WWISWDS) Data Entry Central Characterization Program (CCP) Contact-Handled (CH) TRU...

  14. Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Danny Anderson

    2014-07-01

    and commercial disposal options exist for contact-handled LLW; however, offsite disposal options are either not currently available (i.e., commercial disposal facilities), practical, or cost-effective for all remote-handled LLW streams generated at INL. Offsite disposal of all INL and tenant-generated remote-handled waste is further complicated by issues associated with transporting highly radioactive waste in commerce; and infrastructure and processing changes at the generating facilities, specifically NRF, that would be required to support offsite disposal. The INL Remote-Handled LLW Disposal Project will develop a new remote handled LLW disposal facility to meet mission-critical, remote-handled LLW disposal needs. A formal DOE decision to proceed with the project has been made in accordance with the requirements of National Environmental Policy Act (42 USC§ 4321 et seq.). Remote-handled LLW is generated from nuclear programs conducted at INL, including spent nuclear fuel handling and operations at NRF and operations at the Advanced Test Reactor. Remote-handled LLW also will be generated by new INL programs and from segregation and treatment (as necessary) of remote handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex.

  15. Radiological Control Training for Supervisors

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

    3-2001 August 2001 Change Notice No 1. with Reaffirmation January 2007 DOE HANDBOOK Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax

  16. Radiological Training for Tritium Facilities

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

    DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology

  17. Understanding Mechanisms of Radiological Contamination

    SciTech Connect (OSTI)

    Rick Demmer; John Drake; Ryan James, PhD

    2014-03-01

    Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel, spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining these different types of contamination (and subsequent decontamination processes), which have included several different radionuclides and substrates, sheds light on contamination processes that occur throughout the nuclear industry and in the urban environment.

  18. Automated system for handling tritiated mixed waste

    SciTech Connect (OSTI)

    Dennison, D.K.; Merrill, R.D.; Reitz, T.C.

    1995-03-01

    Lawrence Livermore National Laboratory (LLNL) is developing a semi system for handling, characterizing, processing, sorting, and repackaging hazardous wastes containing tritium. The system combines an IBM-developed gantry robot with a special glove box enclosure designed to protect operators and minimize the potential release of tritium to the atmosphere. All hazardous waste handling and processing will be performed remotely, using the robot in a teleoperational mode for one-of-a-kind functions and in an autonomous mode for repetitive operations. Initially, this system will be used in conjunction with a portable gas system designed to capture any gaseous-phase tritium released into the glove box. This paper presents the objectives of this development program, provides background related to LLNL`s robotics and waste handling program, describes the major system components, outlines system operation, and discusses current status and plans.

  19. Plutonium stabilization and handling quality assurance program plan

    SciTech Connect (OSTI)

    Weiss, E.V.

    1998-04-22

    This Quality Assurance Program Plan (QAPP) identifies project quality assurance requirements for all contractors involved in the planning and execution of Hanford Site activities for design, procurement, construction, testing and inspection for Project W-460, Plutonium Stabilization and Handling. The project encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM.

  20. DOE - Office of Legacy Management -- Energy Technology Engineering...

    Office of Legacy Management (LM)

    Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site ... laboratory that tested components and systems for liquid metal cooled nuclear reactors. ...

  1. DOE - Office of Legacy Management -- WNI Split Rock Site - 043

    Office of Legacy Management (LM)

    Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Western Nuclear, Inc. (WNI) Split Rock site is a Uranium Mill ...

  2. DOE - Office of Legacy Management -- Oxnard Facility - 002

    Office of Legacy Management (LM)

    Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This facility was used to produce...

  3. Nuclear Materials: Reconsidering Wastes and Assets - 13193

    SciTech Connect (OSTI)

    Michalske, T.A.

    2013-07-01

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

  4. Nuclear / Radiological Advisory Team | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) / Radiological Advisory Team NRAT Logo NNSA's Nuclear / Radiological Advisory Team (NRAT) provides an emergency response capability for on-scene scientific and technical advice for both domestic and international nuclear or radiological incidents. It is led by a Senior Energy Official who runs the NNSA field operation and who coordinates NNSA follow-on assets as needed. The NRAT is composed of scientists and technicians who can provide advice or conduct limited

  5. Radiological Triage | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Radiological Triage Triage Logo NNSA's Triage is a non-deployable, secure, on-line capability that provides remote support to emergency responders in the event of a nuclear or radiological emergency. Triage has on-call scientists available 24 hours a day to analyze site-specific data and confirm radioisotope identification in the event of a radiological incident. The data is transmitted through the Triage website or provided over the telephone. Triage is an integrated system that is comprised of

  6. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    U.S. Department of Energy Office of Environmental Management Accident Investigation Report Phase 1 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014 April 2014 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release Event at the Waste Isolation Pilot Plant Disclaimer Phase 1 of this accident investigation report is an independent product of the Accident Investigation Board appointed by Matthew Moury, Deputy Assistant Secretary, Safety,

  7. Nuclear / Radiological Advisory Team | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Advisory Team (NRAT) provides an emergency response capability for on-scene scientific and technical advice for both domestic and international nuclear or ...

  8. Radiological Contamination Control Training for Laboratory Research

    Energy Savers [EERE]

    researchers. Course Description: This course illustrates and reinforces the skills and knowledge needed to assist personnel with radiological controls for laboratory research...

  9. Memorandum, Reporting of Radiological Sealed Sources Transactions...

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

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed ...

  10. Radiological Control - DOE Directives, Delegations, and Requirements

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

    98-2008, Change Notice 1, Radiological Control by Diane Johnson The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities...