Sample records for materials handled radiological

  1. MATERIAL HANDLING, STORAGE, AND DISPOSAL

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Materials shall be stored in a manner that allows easy identification and access to labels, identification entering storage areas. All persons shall be in a safe position while materials are being loadedEM 385-1-1 XX Jun 13 14-1 SECTION 14 MATERIAL HANDLING, STORAGE, AND DISPOSAL 14.A MATERIAL

  2. RESCHEDULED: Webinar on Material Handling Fuel Cells for Building...

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

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

  3. Guidance for use of Radiology Devices and Radioactive Materials in Research Protocols

    E-Print Network [OSTI]

    Puglisi, Joseph

    Guidance for use of Radiology Devices and Radioactive Materials in Research Protocols Definition preparation, handling, storage, administration, and waste disposal in sufficient detail to permit a radiological hazards evaluation of the proposal, including potential for radiation dose to other health care

  4. MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI SITE REMEDIATION

    E-Print Network [OSTI]

    MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI SITE REMEDIATION April 13, 2004 Prepared for. Wright Street Littleton, CO 80127 #12;MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI Site Remediation By: Date: Robert Krumberger Project Manager New Horizons Environmental Consultants, Inc. Approved By

  5. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP Project W-460

    SciTech Connect (OSTI)

    WEISS, E.V.

    2000-03-06T23:59:59.000Z

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

  6. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

    E-Print Network [OSTI]

    Weiss, E V

    2000-01-01T23:59:59.000Z

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

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

    DOE Patents [OSTI]

    Spadaro, Peter R. (Pittsburgh, PA); Smith, Jay E. (Pittsburgh, PA); Speer, Elmer L. (Ruffsdale, PA); Cecconi, Arnold L. (Clairton, PA)

    1987-01-01T23:59:59.000Z

    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.

  8. Method of preparing and handling chopped plant materials

    DOE Patents [OSTI]

    Bransby, David I. (2668 Wire Rd., Auburn, AL 36832)

    2002-11-26T23:59:59.000Z

    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.

  9. 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

    2010-02-01T23:59:59.000Z

    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.

  10. CARRIER PREPARATION BUILDING MATERIALS HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E.F. Loros

    2000-06-28T23:59:59.000Z

    The Carrier Preparation Building Materials Handling System receives rail and truck shipping casks from the Carrier/Cask Transport System, and inspects and prepares the shipping casks for return to the Carrier/Cask Transport System. Carrier preparation operations for carriers/casks received at the surface repository include performing a radiation survey of the carrier and cask, removing/retracting the personnel barrier, measuring the cask temperature, removing/retracting the impact limiters, removing the cask tie-downs (if any), and installing the cask trunnions (if any). The shipping operations for carriers/casks leaving the surface repository include removing the cask trunnions (if any), installing the cask tie-downs (if any), installing the impact limiters, performing a radiation survey of the cask, and installing the personnel barrier. There are four parallel carrier/cask preparation lines installed in the Carrier Preparation Building with two preparation bays in each line, each of which can accommodate carrier/cask shipping and receiving. The lines are operated concurrently to handle the waste shipping throughputs and to allow system maintenance operations. One remotely operated overhead bridge crane and one remotely operated manipulator is provided for each pair of carrier/cask preparation lines servicing four preparation bays. Remotely operated support equipment includes a manipulator and tooling and fixtures for removing and installing personnel barriers, impact limiters, cask trunnions, and cask tie-downs. Remote handling equipment is designed to facilitate maintenance, dose reduction, and replacement of interchangeable components where appropriate. Semi-automatic, manual, and backup control methods support normal, abnormal, and recovery operations. Laydown areas and equipment are included as required for transportation system components (e.g., personnel barriers and impact limiters), fixtures, and tooling to support abnormal and recovery operations. The Carrier Preparation Building Materials Handling System interfaces with the Cask/Carrier Transport System to move the carriers to and from the system. The Carrier Preparation Building System houses the equipment and provides the facility, utility, safety, communications, and auxiliary systems supporting operations and protecting personnel.

  11. Human error contribution to nuclear materials-handling events

    E-Print Network [OSTI]

    Sutton, Bradley (Bradley Jordan)

    2007-01-01T23:59:59.000Z

    This thesis analyzes a sample of 15 fuel-handling events from the past ten years at commercial nuclear reactors with significant human error contributions in order to detail the contribution of human error to fuel-handling ...

  12. Agent-based Control for Material Handling Systems in In-House Logistics

    E-Print Network [OSTI]

    Agent-based Control for Material Handling Systems in In-House Logistics Towards Cyber-Physical Systems in In-House-Logistics Utilizing Realsize Evaluation of Agent-based Material Handling Technology Werthmann Intelligent Production and Logistics Systems BIBA ­ Bremer Institut für Produktion und Logistik

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

    SciTech Connect (OSTI)

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

    2014-06-01T23:59:59.000Z

    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.

  14. 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.

    2013-11-01T23:59:59.000Z

    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.

  15. 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.

    2013-05-01T23:59:59.000Z

    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.

  16. ARRA Material Handling Equipment Composite Data Products: Data through Quarter 2 of 2012

    SciTech Connect (OSTI)

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

    2012-10-01T23:59:59.000Z

    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 second quarter of 2012.

  17. Hydrogen Fuel for Material Handling | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking of Blythe SolarContamination Detector WorkshopHydrogenEnergyfor Material

  18. Early Markets: Fuel Cells for Material Handling Equipment

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:RevisedAdvisory Board Contributions EMEMEnergy TaskEVERETTEagleMaterial

  19. 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.

    2013-10-01T23:59:59.000Z

    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.

  20. Methodology for performing measurements to release material from radiological control

    SciTech Connect (OSTI)

    Durham, J.S. [Pacific Northwest Lab., Richland, WA (United States); Gardner, D.L. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-09-01T23:59:59.000Z

    This report describes the existing and proposed methodologies for performing measurements of contamination prior to releasing material for uncontrolled use at the Hanford Site. The technical basis for the proposed methodology, a modification to the existing contamination survey protocol, is also described. The modified methodology, which includes a large-area swipe followed by a statistical survey, can be used to survey material that is unlikely to be contaminated for release to controlled and uncontrolled areas. The material evaluation procedure that is used to determine the likelihood of contamination is also described.

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

    SciTech Connect (OSTI)

    T. A. Misiak

    1998-05-21T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Ramsden, T.

    2013-04-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Seguin, Nicole R. [Los Alamos National Laboratory

    2012-07-18T23:59:59.000Z

    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.

  4. Analytical models to evaluate system performance measures for vehicle based material-handling systems under various dispatching policies

    E-Print Network [OSTI]

    Lee, Moonsu

    2005-08-29T23:59:59.000Z

    -route material-handling systems from two different perspectives: the workcenters?? point of view and the transporters?? point of view. The state-dependent nature of the transportation time is considered here for more accurate analytical approximation models...

  5. Guidelines for Laundering Laboratory Personal Protective Equipment Handling Potentially Contaminated Laundry

    E-Print Network [OSTI]

    Cui, Yan

    or radiological materials. The purpose of these guidelines is to provide guidance on how to handle your personal, chemical, radiological or mixed). Follow department specific procedures when available. Use minimal to be placed into a red bag. In-house laundry facility If your department does not utilize a vendor to clean

  6. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01T23:59:59.000Z

    radiological exposures may also present first to healthcare facilities.facility-based decontamination of victims exposed to chemical, biological, and radiologicalfacility-based decontamination of victims exposed to chemical, biological, and radiological

  7. 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.

    2013-11-01T23:59:59.000Z

    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.

  8. 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

    2009-02-06T23:59:59.000Z

    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 are due to: i) a reduced number of process shutdowns to change hardware or lining material, ii) reduced need to produce new hardware or lining material, iii) improved product quality leads to reduced need to remake product or manufacturing of new product, iv) reduction in contamination of melt from degradation of refractory and metallic components, v) elimination of worn hardware will increase efficiency of process, vi) reduced refractory lining deterioration or formation of a less insulating phase, would result in decreased heat loss through the walls. Projected 2015 benefits for the U.S. aluminum industry, assuming 21% market penetration of improved refractory materials, are energy savings of approximately 0.2 trillion BTU/year, cost savings of $2.3 billion/year and carbon reductions of approximately 1.4 billion tons/year. The carbon reduction benefit of the project for the hot-dip galvanize and aluminum industries combined is projected to be approximately 2.2 billion tons/year in 2015. Pathways from research to commercialization were based on structure of the project’s industrial partnerships. These partnerships included suppliers, industrial associations, and end users. All parties were involved in conducting the project including planning and critiquing the trials. Supplier companies such as Pyrotech Metaullics, Stoody, and Duraloy have commercialized products and processes developed on the project.

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

    SciTech Connect (OSTI)

    Jim Jnatt

    2001-08-24T23:59:59.000Z

    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 assumptions and conditions identified in Section 6 of this proposal.

  10. Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    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.

  11. Power-law distributions in events involving nuclear and radiological materials

    E-Print Network [OSTI]

    Chow, Jijun

    2009-01-01T23:59:59.000Z

    Nuclear and radiological events are large-impact, hard-to-predict rare events, whose associated probability is exceedingly low. They can exert monumental impacts and lead to grave environmental and economic consequences. ...

  12. Cefas contract report SLBA1 Marine material disposal Part II FEPA Radiological Assessment of

    E-Print Network [OSTI]

    of Dredging Application for Oldbury Power Station (2010) Cefas Environment Report RL 09/2010 Authors: K. S. Leonard and P. A. Smedley Issue date: October 2010 #12;#12;RADIOLOGICAL ASSESSMENT OF DREDGING APPLICATION to carry out a dredging program for a period of 3 years involving the disposal at sea of 59,900 m3

  13. Radiation dose assessments to support evaluations of radiological control levels for recycling or reuse of materials and equipment

    SciTech Connect (OSTI)

    Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

    1995-07-01T23:59:59.000Z

    Pacific Northwest Laboratory is providing Environmental Protection Support and Assistance to the USDOE, Office of Environmental Guidance. Air, Water, and Radiation Division. As part of this effort, PNL is collecting data and conducting technical evaluations to support DOE analyses of the feasibility of developing radiological control levels for recycling or reuse of metals, concrete, or equipment containing residual radioactive contamination from DOE operations. The radiological control levels will be risk-based, as developed through a radiation exposure scenario and pathway analysis. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and both health and non-health-related impacts. The main objective of this report is to develop a methodology for establishing radiological control levels for recycle or reuse. This report provides the results of the radiation exposure scenario and pathway analyses for 42 key radionuclides generated during DOE operations that may be contained in metals or equipment considered for either recycling or reuse. The scenarios and information developed by the IAEA. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities, are used as the initial basis for this study. The analyses were performed for both selected worker populations at metal smelters and for the public downwind of a smelter facility. Doses to the public downwind were estimated using the US (EPA) CAP88-PC computer code with generic data on atmospheric dispersion and population density. Potential non-health-related effects of residual activity on electronics and on film were also analyzed.

  14. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01T23:59:59.000Z

    contaminants, and management of contaminated materials andmanagement, triage, surveillance, decontamination procedures and materials,from the body, and management of contaminated materials and

  15. 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)

    NONE

    1995-08-01T23:59:59.000Z

    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.

  16. Correlation of injury occurrence data with estimated maximal aerobic capacity and body composition in a high frequency manual materials handling task

    E-Print Network [OSTI]

    Craig, Brian Nichols

    1995-01-01T23:59:59.000Z

    knowledge in the area of exercise physiology. I would also like to express my appreciation to the management of the manual materials handling company for their untiring assistance and organization. Credit must also be given to the manual materials..., Bicycle, and Step Tests Based on Oxygen Uptake Responses, Medicine and Science in Sports, 3, 149-154. National Institute of Occupational Safety and Health. (1981). A Work Practices Guide for Manual Lifting, Cincinnati, OH: US Department of Health...

  17. Radiological Threat Reduction | ornl.gov

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

    safely packaging and transporting those materials to a more stable state; and Protecting radiological materials at facilities that use or process such materials through facility...

  18. 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.

  19. Radiological Assistance Program, DOE Region 6 response plan

    SciTech Connect (OSTI)

    Jakubowski, F.M.

    1993-02-01T23:59:59.000Z

    This program plan meets all the requirements identified in DOE Order 5530.3, Radiological Assistance Program and supports those requirements leading to the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC) as required by DOE 5530-5. Requests for radiological assistance may come from other DOE facilities, Federal or state agencies, tribal officials, or from any private corporation or individual. Many of the requests will be handled by a telephone call, a conference or a letter, teletype or memorandum. Other requests for assistance may involve radioactive material in serious accidents, fire, personal injuries, contamination or possible hazards to the general public. Some occurrences may require the dispatch of trained personnel equipped with radiation monitoring instruments and related equipment necessary to evaluate, control and neutralize the hazard. The primary responsibility for incidents involving radioactive material always remains with the party having custody of the radioactive materials. In addition, the DOE recognizes that the assistance provided shall not in any way preempt state, tribal, or local authority and/or responsibility on state or tribal properties. Toward this end, DOE assistance for non-DOE radioactive materials, is limited to technical assistance, advice, measurement and other resources as deemed necessary by the local authorities but excludes DOE interface with the public media. This is a function handled by the local or state Incident Commander.

  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: November 1, 2010-October 31, 2011

    SciTech Connect (OSTI)

    David Frederick

    2012-02-01T23:59:59.000Z

    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.

  1. 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

    2011-02-01T23:59:59.000Z

    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.

  2. 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

    2014-02-01T23:59:59.000Z

    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.

  3. 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

    2013-02-01T23:59:59.000Z

    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.

  4. 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 [Geo-Environment and Resources Research Centre (CIGAR), Porto University, Faculty of Engineering - FEUP, Rua Dr. Roberto Frias, 4200-465 Porto (Portugal)] [Geo-Environment and Resources Research Centre (CIGAR), Porto University, Faculty of Engineering - FEUP, Rua Dr. Roberto Frias, 4200-465 Porto (Portugal); Meira Castro, Ana Cristina [School of Engineering Polytechnic of Porto - ISEP, Rua Dr. Antonio Bernardino de Almeida, 431, 4200-072, Porto (Portugal)] [School of Engineering Polytechnic of Porto - ISEP, Rua Dr. Antonio Bernardino de Almeida, 431, 4200-072, Porto (Portugal)

    2013-07-01T23:59:59.000Z

    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)

  5. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers’ Council

    2012-03-26T23:59:59.000Z

    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 low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

  6. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    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.

  7. 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.

    2012-02-14T23:59:59.000Z

    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.

  8. Road Materials and Pavement Design. Volume X No. X/2001, pages 1 to n Towards a novel framework for handling

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Road Materials and Pavement Design. Volume X ­ No. X/2001, pages 1 to n Towards a novel framework and Pavement Design. Volume X ­ No. X/2001 1. Introduction Nowadays, enterprises are outsourcing their business

  9. Radiological assessment of dredging application for

    E-Print Network [OSTI]

    Radiological assessment of dredging application for Oldbury power station (2009) Cefas Environment 14 /2009 RADIOLOGICAL ASSESSMENT OF DREDGING APPLICATION FOR OLDBURY POWER STATION (2009) The Centre material disposal ­ Part II FEPA #12;2 RADIOLOGICAL ASSESSMENT OF DREDGING APPLICATION FOR OLDBURY POWER

  10. Radiological assessment of dredging application for

    E-Print Network [OSTI]

    Radiological assessment of dredging application for the port of Lancaster (2008) Cefas Environment 21/2008 RADIOLOGICAL ASSESSMENT OF DREDGING APPLICATION FOR THE PORT OF LANCASTER (2008) The Centre Marine material disposal ­ Part II FEPA #12;2 RADIOLOGICAL ASSESSMENT OF DREDGING APPLICATION

  11. RESRAD-BUILD: A computer model for analyzing the radiological doses resulting from the remediation and occupancy of buildings contaminated with radioactive material

    SciTech Connect (OSTI)

    Yu, C.; LePoire, D.J.; Jones, L.G. [and others

    1994-11-01T23:59:59.000Z

    The RESRAD-BUILD computer code is a pathway analysis model designed to evaluate the potential radiological dose incurred by an individual who works or lives in a building contaminated with radioactive material. The transport of radioactive material inside the building from one compartment to another is calculated with an indoor air quality model. The air quality model considers the transport of radioactive dust particulates and radon progeny due to air exchange, deposition and resuspension, and radioactive decay and ingrowth. A single run of the RESRAD-BUILD code can model a building with up to: three compartments, 10 distinct source geometries, and 10 receptor locations. A shielding material can be specified between each source-receptor pair for external gamma dose calculations. Six exposure pathways are considered in the RESRAD-BUILD code: (1) external exposure directly from the source; (2) external exposure to materials deposited on the floor; (3) external exposure due to air submersion; (4) inhalation of airborne radioactive particulates; (5) inhalation of aerosol indoor radon progeny; and (6) inadvertent ingestion of radioactive material, either directly from the sources or from materials deposited on the surfaces of the building compartments. 4 refs., 23 figs., 4 tabs.

  12. Radiological safety training for uranium facilities

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    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.

  13. Trial operation of material protection, control, and accountability systems at two active nuclear material handling sites within the All-Russian Institute of Experimental Physics (VNIIEF)

    SciTech Connect (OSTI)

    Skripka, G.; Vatulin, V.; Yuferev, V. [VNIIEF, Sarov (Russian Federation)] [and others

    1997-11-01T23:59:59.000Z

    This paper discusses Russian Federal Nuclear Center (RFNC)-VNIIEF activities in the area of nuclear material protection, control, and accounting (MPC and A) procedures enhancement. The goal of such activities is the development of an automated systems for MPC and A at two of the active VNIIEF research sites: a research (reactor) site and a nuclear material production facility. The activities for MPC and A system enhancement at both sites are performed in the framework of a VNIIEF-Los Alamos National Laboratory contract with participation from Sandia National Laboratories, Lawrence Livermore National Laboratory, Brookhaven National Laboratory, Oak Ridge National Laboratory, Pacific Northwest National Laboratory, and PANTEX Plant in accordance with Russian programs supported by MinAtom. The American specialists took part in searching for possible improvement of technical solutions, ordering equipment, and delivering and testing the equipment that was provided by the Americans.

  14. 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.

    2012-08-01T23:59:59.000Z

    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.

  15. Bulk materials handling equipment roundup

    SciTech Connect (OSTI)

    Fiscor, S.

    2007-07-15T23:59:59.000Z

    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.

  16. Hydrogen Fuel for Material Handling

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(Fact Sheet), GeothermalGridHYDROGEND D e e& FuelInvitedinEnergyFuel Cellsp

  17. Paint for detection of radiological or chemical agents

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, Sumner Daniel (Danville, CA)

    2010-08-24T23:59:59.000Z

    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.

  18. INL@Work Radiological Search & Response Training

    ScienceCinema (OSTI)

    Turnage, Jennifer

    2013-05-28T23:59:59.000Z

    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.

  19. Digital radiology

    SciTech Connect (OSTI)

    Dallas, W.J. (Univ. of Arizona, Health Sciences Center, Tucson, AZ (US))

    1990-04-01T23:59:59.000Z

    Radiology is vital to the life-saving efforts of surgeons and other physicians, but precious time can be lost generating the images and transferring them to and from the operating room. Furthermore, hospitals are straining under the task of storing and managing the deluge of diagnostic films produced every year. A 300-bed hospital generates about 1 gigabyte (8 {times} 10{sup 9} bits) of picture information every day and is legally bound to hold it for three to seven years--30 years in the case of silicosis or black lung disease, illnesses that may have relevance to future lawsuits. Consequently, hospital warehouses are filling with x-ray film and written reports that are important for analysis of patient histories, for comparison between patients, and for analyzing the progress of disease. Yet only a fraction of the information's potential is being used because access is so complicated. What is more, films are easily lost, erasing valuable medical histories.

  20. DOE handbook: Tritium handling and safe storage

    SciTech Connect (OSTI)

    NONE

    1999-03-01T23:59:59.000Z

    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.

  1. Estimating radiological background using imaging spectroscopy

    SciTech Connect (OSTI)

    Bernacki, Bruce E.; Schweppe, John E.; Stave, Sean C.; Jordan, David V.; Kulisek, Jonathan A.; Stewart, Trevor N.; Seifert, Carolyn E.

    2014-06-13T23:59:59.000Z

    Optical imaging spectroscopy is investigated as a method to estimate radiological background by spectral identification of soils, sediments, rocks, minerals and building materials derived from natural materials and assigning tabulated radiological emission values to these materials. Radiological airborne surveys are undertaken by local, state and federal agencies to identify the presence of radiological materials out of regulatory compliance. Detection performance in such surveys is determined by (among other factors) the uncertainty in the radiation background; increased knowledge of the expected radiation background will improve the ability to detect low-activity radiological materials. Radiological background due to naturally occurring radiological materials (NORM) can be estimated by reference to previous survey results, use of global 40K, 238U, and 232Th (KUT) values, reference to existing USGS radiation background maps, or by a moving average of the data as it is acquired. Each of these methods has its drawbacks: previous survey results may not include recent changes, the global average provides only a zero-order estimate, the USGS background radiation map resolutions are coarse and are accurate only to 1 km – 25 km sampling intervals depending on locale, and a moving average may essentially low pass filter the data to obscure small changes in radiation counts. Imaging spectroscopy from airborne or spaceborne platforms can offer higher resolution identification of materials and background, as well as provide imaging context information. AVIRIS hyperspectral image data is analyzed using commercial exploitation software to determine the usefulness of imaging spectroscopy to identify qualitative radiological background emissions when compared to airborne radiological survey data.

  2. NV/YMP radiological control manual, Revision 2

    SciTech Connect (OSTI)

    Gile, A.L. [comp.] [comp.

    1996-11-01T23:59:59.000Z

    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.

  3. 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...

  4. International Data on Radiological Sources

    SciTech Connect (OSTI)

    Martha Finck; Margaret Goldberg

    2010-07-01T23:59:59.000Z

    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.

  5. Calculations of the radiological environment for handling of ISOLDE targets

    E-Print Network [OSTI]

    McDonald, Kirk

    Vehicle (AGV): Fully autonomous vehicle Integrated robot arm Robot mounted vision system for precise robot control Control + battery Shielded transport box Robot arm Vision system 4th High Power Targetry Workshop

  6. Handling and Packaging a Potentially Radiologically Contaminated Patient |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneralGuiding Documents and Linksl WHandbookDepartment

  7. Pre-Hospital Practices for Handling a Radiologically Contaminated Patient |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked QuestionsDepartmentGas and|Hours(5-Unit) AreaEnergyofN E R GAct

  8. Vacuum Vessel Remote Handling

    E-Print Network [OSTI]

    and Remote Handling 4 Vacuum vessel functions · Plasma vacuum environment · Primary tritium confinement, incl ports 65 tonnes - Weight of torus shielding 100 tonnes · Coolant - Normal Operation Water, Handling 12 Vessel octant subassembly fab. (3) · Octant-to-octant splice joint requires double wall weld

  9. Unvented Drum Handling Plan

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    2000-08-01T23:59:59.000Z

    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 preferred option is to use equipment provided by a commercial vendor during the first few years of retrieval and venting. This is based on a number of reasons. First, retrieval funding is uncertain. Using a commercial vendor will allow DOE-RL to avoid the investment and maintenance costs if retrieval is not funded. Second, when funding can be identified, retrieval will likely be performed with minimal initial throughput and intermittent operations. Again, costs can be saved by using contracted vendor services only as needed, rather than supporting Hanford equipment full time. When full-scale retrieval begins and the number of drums requiring venting increases significantly, then use of the Hanford container venting system (CVS) should be considered.

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

    SciTech Connect (OSTI)

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

    2011-08-18T23:59:59.000Z

    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.

  11. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Safety 3 C #12;Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2013-2014 Page 1

  12. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2012-2013 Page 1

  13. 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

    2008-06-06T23:59:59.000Z

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

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

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2012-03-13T23:59:59.000Z

    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.

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

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2013-04-02T23:59:59.000Z

    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.

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

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2010-08-24T23:59:59.000Z

    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.

  17. Radiological Assistance Program

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

    1992-04-10T23:59:59.000Z

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

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

    DOE Patents [OSTI]

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

    2013-04-02T23:59:59.000Z

    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.

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

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, S. Daniel (Danville, CA)

    2012-03-27T23:59:59.000Z

    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.

  20. Preconceptual design of a Long-Pulse Spallation Source (LPSS) at the LANSCE Facility: Target system, facility, and material handling considerations

    SciTech Connect (OSTI)

    Sommer, W.F. [comp.

    1995-12-01T23:59:59.000Z

    This report provides a summary of a preconceptual design study for the proposed Long-Pulse Spallation. Source (LPSS) at the Los Alamos Neutron Science Center (LANSCE). The LPSS will use a 0.8-MW proton beam to produce neutrons from a tungsten target. This study focuses on the design of the target station and changes to the existing building that would be made to accommodate the LPSS. The LPSS will provide fifteen flight paths to neutron scattering instruments. In addition, options for generating ultracold neutrons, pions, and muons will be available. Flight-energy, forward-scattered neutrons on the downstream side of the target will also be available for autoradiography studies. A Target Test Bed (TTB) is also proposed for full-beam tests of component materials and advanced spallation neutron sources. The design allows for separation of the experiment hall from the beam line, target, and flight paths. The target and moderator systems and the systems/components to be tested in the TTB will be emplaced and removed separately by remotely operated, shielded equipment. Irradiated materials will be transported to a hot cell adjacent to the target chamber for testing by remotely operated instruments. These tests will provide information about how materials properties are affected by proton and neutron beams.

  1. How to deal with radiologically contaminated vegetation

    SciTech Connect (OSTI)

    Wilde, E.W.; Murphy, C.E.; Lamar, R.T.; Larson, M.J.

    1996-12-31T23:59:59.000Z

    This report describes the findings from a literature review conducted as part of a Department of Energy, Office of Technology Development Biomass Remediation Task. The principal objective of this project is to develop a process or group of processes to treat radiologically contaminated vegetation in a manner that minimizes handling, processing, and treatment costs. Contaminated, woody vegetation growing on waste sites at SRS poses a problem to waste site closure technologies that are being considered for these sites. It is feared that large sections of woody vegetation (logs) can not be buried in waste sites where isolation of waste is accomplished by capping the site. Logs or large piles of woody debris have the potential of decaying and leaving voids under the cap. This could lead to cap failure and entrance of water into the waste. Large solid objects could also interfere with treatments like in situ mixing of soil with grout or other materials to encapsulate the contaminated sediments and soils in the waste sites. Optimal disposal of the wood includes considerations of volume reduction, treatment of the radioactive residue resulting from volume reduction, or confinement without volume reduction. Volume reduction consists primarily of removing the carbon, oxygen, and hydrogen in the wood, leaving an ash that would contain most of the contamination. The only contaminant that would be released by volume reduction would by small amounts of the radioactive isotope of hydrogen, tritium. The following sections will describe the waste sites at SRS which contain contaminated vegetation and are potential candidates for the technology developed under this proposal. The description will provide a context for the magnitude of the problem and the logistics of the alternative solutions that are evaluated later in the review. 76 refs.

  2. GUIDELINES FOR HANDLING HAZARDOUS CHEMICAL WASTE

    E-Print Network [OSTI]

    Tennessee, University of

    GUIDELINES FOR HANDLING HAZARDOUS CHEMICAL WASTE The proper management of hazardous waste and regulatory compliance are achieved: 1. Make sure that no hazardous materials are placed into regular solid in the departmental chemical hygiene plan (CHP) before you begin to use hazardous substances. 3. Make sure you know

  3. Waste Handling and Disposal Biological Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    plumbing services, EHS personnel wastewater treatment plant personnel, and the general public canWaste Handling and Disposal Biological Safety General Biosafety Practices (GBP) Why You Should Care on the next experiment. Are you working with r/sNA, biological toxins, human materials, needles, plasticware

  4. Enhanced radiological work planning

    SciTech Connect (OSTI)

    DECKER, W.A.

    1999-05-21T23:59:59.000Z

    The purpose of this standard is to provide Project Hanford Management Contractors (PHMC) with guidance for ensuring radiological considerations are adequately addressed throughout the work planning process. Incorporating radiological controls in the planning process is a requirement of the Hanford Site Radiological Control Manual (HSRCM-I), Chapter 3, Part 1. This standard is applicable to all PHMC contractors and subcontractors. The essential elements of this standard will be incorporated into the appropriate site level work control standard upon implementation of the anticipated revision of the PHMC Administration and Procedure System.

  5. Radiation Safety Training Materials

    Broader source: Energy.gov [DOE]

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

  6. Solid waste handling

    SciTech Connect (OSTI)

    Parazin, R.J.

    1995-05-31T23:59:59.000Z

    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.).

  7. Uranium hexafluoride handling. Proceedings

    SciTech Connect (OSTI)

    Not Available

    1991-12-31T23:59:59.000Z

    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.

  8. Status of ITER neutral beam cell remote handling system

    E-Print Network [OSTI]

    Sykes, N; Choi, C-H; Crofts, O; Crowe, R; Damiani, C; Delavalle, S; Meredith, L; Mindham, T; Raimbach, J; Tesini, A; Van Uffelen, M

    2013-01-01T23:59:59.000Z

    The ITER neutral beam cell will contain up to three heating neutral beams and one diagnostic neutral beam, and four upper ports. Though manual maintenance work is envisaged within the cell, when containment is breached, or the radiological protection is removed the maintenance must be conducted remotely. This maintenance constitutes the removal and replacement of line replaceable units, and their transport to and from a cask docked to the cell. A design of the remote handling system has been prepared to concept level which this paper describes including the development of a beam line transporter, beam source remote handling equipment, upper port remote handling equipment and equipment for the maintenance of the neutral shield. This equipment has been developed complete the planned maintenance tasks for the components of the neutral beam cell and to have inherent flexibility to enable as yet unforeseen tasks and recovery operations to be performed.

  9. NREL: Buildings Research - Webinar Rescheduled: Material Handling...

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

    attend this webinar. Printable Version Buildings Research Home Commercial Buildings Residential Buildings Facilities Working with Us Publications News Did you find what you...

  10. Specialty Vehicles and Material Handling Equipment

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

    Benefits Environmental Benefits "Well-to-Tank" Greenhouse Gas Factors Hydrogen fuel cell vehicles Hydrogen fuel cell vehicles Hydrogen fuel cell vehicles Hydrogen fuel cell...

  11. ETEC - Radioactive Handling Materials Facility (RMHF) Leachfield |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic Plan Department ofNotices |Notice The Crystal Cityof Energy

  12. DOE standard: Radiological control

    SciTech Connect (OSTI)

    Not Available

    1999-07-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-08-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-04-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Gary Mecham

    2010-10-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Gary Mecham

    2010-05-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Gary Mecham

    2009-10-01T23:59:59.000Z

    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.

  18. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 1 The Radiological Research Accelerator Facility for Radiological Research (CRR). Using the mi- crobeam facility, 10% of the cells were irradiated through particle beam as well as the first fo- cused microbeam in the new microbeam facility. · Another significant

  19. Radiological worker training

    SciTech Connect (OSTI)

    NONE

    1998-10-01T23:59:59.000Z

    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.

  20. 324 Building Baseline Radiological Characterization

    SciTech Connect (OSTI)

    R.J. Reeder, J.C. Cooper

    2010-06-24T23:59:59.000Z

    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.

  1. ORISE: Radiological program assessment services

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

    Environmental monitoring programs Operational environments Decontamination and decommissioning projects Compliance assessments Radiological release programs ORISE is actively...

  2. Detecting Illicit Nuclear Materials

    SciTech Connect (OSTI)

    Kouzes, Richard T.

    2005-09-01T23:59:59.000Z

    The threat that weapons of mass destruction might enter the United States has led to a number of efforts for the detection and interdiction of nuclear, radiological, chemical, and biological weapons at our borders. There have been multiple deployments of instrumentation to detect radiation signatures to interdict radiological material, including weapons and weapons material worldwide.

  3. 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.

    1986-02-01T23:59:59.000Z

    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.

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

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

    2011-08-09T23:59:59.000Z

    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 other directives.

  5. Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog technology; successfully completed the certification exam for the American Registry of Radiologic Technology

  6. Radiological Monitoring Continues at WIPP

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

    investigate this event. WIPP is developing a plan to safely re-enter the WIPP underground facility. Radiological professionals from other DOE locations and National Laboratories...

  7. Smart Radiological Dosimeter

    DOE Patents [OSTI]

    Kosslow, William J.; Bandzuch, Gregory S.

    2004-07-20T23:59:59.000Z

    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.

  8. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 71 The Radiological Research Accelerator Facility the irradiated cells. Both the microbeam and the track segment facilities continue to be utilized in various investigations of this phenomenon. The single- particle microbeam facility provides precise control of the number

  9. The Radiological Research Accelerator THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    The Radiological Research Accelerator Facility #12;84 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY Director: David J. Brenner, Ph.D., D.Sc., Manager: Stephen A. Marino, M.S. An NIH SupportedV/µm 4 He ions using the microbeam facility (Exp. 73) also continued. The transformation frequency

  10. Roadmap: Radiologic Imaging Sciences -Computed Tomography (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Computed Tomography (with AAS Radiologic Technology 34084 Computed Tomography and Magnetic Resonance Imaging Sectional Anatomy I 2 C RIS 44021 Patient Management in Computed Tomography (CT) 2 C RIS 44025 Computed Tomography (CT) Clinical Education I 3 C

  11. Roadmap: Radiologic Imaging Sciences -Computed Tomography (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Computed Tomography (with AAS Radiologic Technology] Note: Admission to the program is required to enroll in RIS courses RIS 34084 Computed Tomography and Magnetic Resonance Imaging Sectional Anatomy I 2 C RIS 44021 Patient Management in Computed Tomography 2

  12. Radiological Research Accelerator Facility Service Request Form

    E-Print Network [OSTI]

    Radiological Research Accelerator Facility Service Request Form National Institute of Biomedical Imaging and Bioengineering Radiological Research Accelerator Facility Service request form Estimate when(s) to control for this experiment (if more than one, please prioritize): Radiological Research Accelerator

  13. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    175 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY #12;176 #12;177 THE RADIOLOGICAL RESEARCH the microbeam and the track-segment facilities have been utilized in various investigations. Table 1 lists-segment facility. Samples are treated with graded doses of radical scavengers to observe changes in the cluster

  14. Radiological FIB/SEM (Quanta) | EMSL

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

    Radiological FIBSEM (Quanta) Radiological FIBSEM (Quanta) The environmental scanning electron microscope (ESEM) is a new-generation SEM that can image samples under controlled...

  15. Federal Radiological Monitoring and Assessment Center | National...

    National Nuclear Security Administration (NNSA)

    Mission The mission of the FRMAC is to coordinate and manage all federal radiological environmental monitoring and assessment Federal Radiological Monitoring and Assessment...

  16. Radiological Release Accident Investigation Report - Phase 1...

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

    Radiological Release Accident Investigation Report - Phase 1 Radiation Report Radiological Release Accident Investigation Report - Phase 1 Radiation Report Phase 1 of this accident...

  17. Radiological Work Planning and Procedures

    E-Print Network [OSTI]

    Kurtz, J E

    2000-01-01T23:59:59.000Z

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In add...

  18. Standardized radiological dose evaluations

    SciTech Connect (OSTI)

    Peterson, V.L.; Stahlnecker, E.

    1996-05-01T23:59:59.000Z

    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.

  19. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    1989-01-01T23:59:59.000Z

    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.

  20. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    1990-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2008-10-06T23:59:59.000Z

    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 and deposition patterns and related products correctly. This document is focusing on the products produced by the GIS Division of the Remove Sensing Laboratory (RSL) and by the National Atmospheric Release Advisory Center (NARAC), both separately and in combination. The expectation is that standard products produced by either group independently or in combination should use the same key attributes in displaying the same kinds of data so that products of a given type generally look similar in key aspects of the presentation, thereby minimizing any confusion of users when a variety of products from these groups may be needed. This document is dealing with the set of common standard products used in responding to radiological/nuclear releases. There are a number of less standard products that are used occasionally or in certain specific situations that are not addressed here. This includes special products that are occasionally produced by both NARAC and RSL in responses and major exercises to meet immediate and unanticipated requirements. At some future time, it may be appropriate to review the handling of such special products by both organizations to determine if there are any areas that would benefit from being integrated with the conventions described here. A particular area that should be addressed in the near-term is that of Derived Response Levels (DRLs) calculated by the Consequence Management Home Team (CMHT) or FRMAC Assessment Scientists. A new calculation is done for every event assigning contour levels, or break-points, based upon field measurements. These contour levels can be applied to deposition or dose rate NARAC calculations. Because these calculations are different every time, they can not be stored in a database.

  2. Radiological assessment. A textbook on environmental dose analysis

    SciTech Connect (OSTI)

    Till, J.E.; Meyer, H.R. (eds.)

    1983-09-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    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.

  4. Preliminary assessment of radiological doses in alternative waste management systems without an MRS facility

    SciTech Connect (OSTI)

    Schneider, K.J.; Pelto, P.J.; Daling, P.M.; Lavender, J.C.; Fecht, B.A.

    1986-06-01T23:59:59.000Z

    This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the reference study system, the radiological doses to the public and to the occupational workers are low, about 170 person-rem/1000 metric ton of uranium (MTU) handled with 70% of the fuel transported by rail and 30% by truck. The radiological doses to the public are almost entirely from transportation, whereas the doses to the occupational workers are highest at the reactors and the repository. Operating alternatives examined included using larger transportation casks, marshaling rail cars into multicar dedicated trains, consolidating spent fuel at the reactors, and wet or dry transfer options of spent fuel from dry storage casks. The largest contribution to radiological doses per unit of spent fuel for both the public and occupational workers would result from use of truck transportation casks, which are smaller than rail casks. Thus, reducing the number of shipments by increasing cask sizes and capacities (which also would reduce the number of casks to be handled at the terminals) would reduce the radiological doses in all cases. Consolidating spent fuel at the reactors would reduce the radiological doses to the public but would increase the doses to the occupational workers at the reactors.

  5. Radiological Release Accident Investigation Report (Phase II Report)

    Broader source: Energy.gov [DOE]

    In its Phase II Report, the Accident Investigation Board concludes that the Feb. 14, 2014 radiological release at the Waste Isolation Pilot Plant was caused by an exothermic reaction involving the mixture of organic materials and nitrate salts in one drum that was processed at the Los Alamos National Laboratory in December 2013.

  6. Radiological Protection for DOE Activities

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

    1995-09-29T23:59:59.000Z

    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)

  7. Materials

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDisposition | NationalMaterials

  8. Roadmap: Radiologic Technology Radiology Department Management Technology Associate of Technical Study

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Technology ­ Radiology Department Management Technology ­ Associate-Nov-13/LNHD This roadmap is a recommended semester-by-semester plan of study for this major. However

  9. Radiological Work Planning and Procedure

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-01-01T23:59:59.000Z

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD.

  10. Radiological control manual. Revision 1

    SciTech Connect (OSTI)

    Kloepping, R.

    1996-05-01T23:59:59.000Z

    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.

  11. U.S. Department of Energy Region 6 Radiological Assistance Program response plan. Revision 2

    SciTech Connect (OSTI)

    Jakubowski, F.M.

    1998-02-01T23:59:59.000Z

    Upon request, the DOE, through the Radiological Assistance Program (RAP), makes available and will provide radiological advice, monitoring, and assessment activities during radiological incidents where the release of radioactive materials is suspected or has occurred. Assistance will end when the need for such assistance is over, or if there are other resources available to adequately address the incident. The implementation of the RAP is usually accomplished through the recommendation of the DOE Regional Coordinating Office`s (RCO) on duty Regional Response Coordinator (RRC) with the approval of the Regional Coordinating Office Director (RCOD). The DOE Idaho Operations Office (DOE-ID) is the designated RCO for DOE Region 6 RAP. The purpose of this document is: to describe the mechanism for responding to any organization or private citizen requesting assistance to radiological incidents; to coordinate radiological assistance among participating federal agencies, states, and tribes in DOE Region 6; and to describe the RAP Scaled Response concept of operations.

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

    SciTech Connect (OSTI)

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

    2011-09-01T23:59:59.000Z

    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 place–techniques 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 transportation–the so-called second line of defense.

  13. Nuclear and Radiological Forensics and Attribution Overview

    SciTech Connect (OSTI)

    Smith, D K; Niemeyer, S

    2005-11-04T23:59:59.000Z

    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.

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

    National Nuclear Security Administration (NNSA)

    Radiological Threat Task Force Established | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

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

    National Nuclear Security Administration (NNSA)

    Radiological Advisory Team | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering...

  16. Radiological Assistance Program | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    Federal Radiological Monitoring and Assessment Center Emergency Response Accident Response Group Radiation Emergency Assistance Center Training Site National Atmospheric Release...

  17. Rice University Environmental Health and Safety Laboratory-Specific Radiological Safety Training Attendance Record

    E-Print Network [OSTI]

    Natelson, Douglas

    . [ ] Radioactive material waste segregation and disposal forms and inventory forms properly signed and dated. [ ] Review of written protocols involving radioactive material. [ ] Radiological safety considerations with the material. Such training shall include: 1. A brief discussion of the hazards of radiation and radioactive

  18. RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT

    E-Print Network [OSTI]

    Holland, Jeffrey

    RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT: Minors in Research Laboratories or Animal Facilities Page 1 of 4 PURPOSE: The purpose of this document is to provide guidance for Purdue sponsored programs which are designed for youth under the age of 15 and which have documented

  19. Departmental Radiological Emergency Response Assets

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

    2007-06-27T23:59:59.000Z

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

  20. Cask system design guidance for robotic handling

    SciTech Connect (OSTI)

    Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

    1990-10-01T23:59:59.000Z

    Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs.

  1. DOE, Westinghouse to Partner with NMJC To Train Radiological and Waste Handling Technicians

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power Administration wouldDECOMPOSITION OF CALCIUMCOSTDOENuclear EnergyMeetingMetricDOE,to Partner

  2. 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

    2013-09-01T23:59:59.000Z

    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.

  3. Laboratory Air Handling Unit System

    E-Print Network [OSTI]

    Cui, Y.; Liu, M.

    2001-01-01T23:59:59.000Z

    balance and moisture balance are given below for the entire building. iQ G26 + hQ G26 + hgQ G26 = rQ G26 + CQ G26 + eQ G26 + ehQ G26 + envQ G26 (1) Where Ge5 = = 2 1 , j jQQ G26 Ge5 = = 2 1 , j jQQ G26 Ge5 = = 2 1 , j jQQ G26 Ge5 = = 2 1 , j... jQQ G26 Ge5 = = 2 1 , j jQQ G26 Figure 1. Schematic diagram of air handling unit system for base system ehMMMM G26G26G26G26 ++= (2) Where Ge5 = = 2 1 , j jMM G26 Ge5 = = 2 1 , j jMM G26 ehWWWWWW G26G26G26G26...

  4. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    J.F. Beesley

    2005-04-21T23:59:59.000Z

    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.

  5. Handling of Multimedia Files in the Invenio Software

    E-Print Network [OSTI]

    Oltmanns, Björn; Schiefer, Bernhard

    Handling of multimedia files in the Invenio Software’ is motivated by the need for integration of multimedia files in the open-source, large-scale digital library software Invenio, developed and used at CERN, the European Organisation for Nuclear Research. In the last years, digital assets like pictures, presentations podcasts and videos became abundant in these systems and digital libraries have grown out of their classic role of only storing bibliographical metadata. The thesis focuses on digital video as a type of multimedia and covers the complete workflow of handling video material in the Invenio software: from the ingestion of digital video material to its processing on to the storage and preservation and finally the streaming and presentation of videos to the user. The potential technologies to realise a video submission workflow are discussed in-depth and evaluated towards system integration with Invenio. The focus is set on open and free technologies, which can be redistributed with the Inve...

  6. DOE - Office of Legacy Management -- St Louis Airport Site Vicinity...

    Office of Legacy Management (LM)

    Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: These properties are located in Hazelwood and Berkeley, Missouri,...

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

    Office of Legacy Management (LM)

    Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

  8. DOE - Office of Legacy Management -- Inhalation Toxicology Research...

    Office of Legacy Management (LM)

    Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

  9. DOE - Office of Legacy Management -- Fernald Environmental Management...

    Office of Legacy Management (LM)

    Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

  10. DOE - Office of Legacy Management -- Idaho National Engineering...

    Office of Legacy Management (LM)

    Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

  11. DOE - Office of Legacy Management -- Battelle Columbus Laboratories...

    Office of Legacy Management (LM)

    Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

  12. DOE - Office of Legacy Management -- Commercial (Burial) Disposal...

    Office of Legacy Management (LM)

    Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

  13. DOE - Office of Legacy Management -- Battelle Memorial Institute...

    Office of Legacy Management (LM)

    Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

  14. CARRIER/CASK HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E.F. Loros

    2000-06-23T23:59:59.000Z

    The Carrier/Cask Handling System receives casks on railcars and legal-weight trucks (LWTs) (transporters) that transport loaded casks and empty overpacks to the Monitored Geologic Repository (MGR) from the Carrier/Cask Transport System. Casks that come to the MGR on heavy-haul trucks (HHTs) are transferred onto railcars before being brought into the Carrier/Cask Handling System. The system is the interfacing system between the railcars and LWTs and the Assembly Transfer System (ATS) and Canister Transfer System (CTS). The Carrier/Cask Handling System removes loaded casks from the cask transporters and transfers the casks to a transfer cart for either the ATS or CTS, as appropriate, based on cask contents. The Carrier/Cask Handling System receives the returned empty casks from the ATS and CTS and mounts the casks back onto the transporters for reshipment. If necessary, the Carrier/Cask Handling System can also mount loaded casks back onto the transporters and remove empty casks from the transporters. The Carrier/Cask Handling System receives overpacks from the ATS loaded with canisters that have been cut open and emptied and mounts the overpacks back onto the transporters for disposal. If necessary, the Carrier/Cask Handling System can also mount empty overpacks back onto the transporters and remove loaded overpacks from them. The Carrier/Cask Handling System is located within the Carrier Bay of the Waste Handling Building System. The system consists of cranes, hoists, manipulators, and supporting equipment. The Carrier/Cask Handling System is designed with the tooling and fixtures necessary for handling a variety of casks. The Carrier/Cask Handling System performance and reliability are sufficient to support the shipping and emplacement schedules for the MGR. The Carrier/Cask Handling System interfaces with the Carrier/Cask Transport System, ATS, and CTS as noted above. The Carrier/Cask Handling System interfaces with the Waste Handling Building System for building structures and space allocations. The Carrier/Cask Handling System interfaces with the Waste Handling Building Electrical System for electrical power.

  15. Nuclear Materials: Reconsidering Wastes and Assets - 13193

    SciTech Connect (OSTI)

    Michalske, T.A. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

    2013-07-01T23:59:59.000Z

    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)

  16. Understanding Mechanisms of Radiological Contamination

    SciTech Connect (OSTI)

    Rick Demmer; John Drake; Ryan James, PhD

    2014-03-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Manohar S. Sohal; J. Stephen Herring

    2008-07-01T23:59:59.000Z

    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 oxygen standards and practices for minimum safety requirements. A summary of operational hazards, along with oxygen safety and emergency procedures, are provided.

  18. RadSTraM: Radiological Source Tracking and Monitoring, Phase II Final Report

    SciTech Connect (OSTI)

    Warren, Tracy A [ORNL; Walker, Randy M [ORNL; Hill, David E [ORNL; Gross, Ian G [ORNL; Smith, Cyrus M [ORNL; Abercrombie, Robert K [ORNL

    2008-12-01T23:59:59.000Z

    This report focuses on the technical information gained from the Radiological Source Tracking and Monitoring (RadSTraM) Phase II investigation and its implications. The intent of the RadSTraM project was to determine the feasibility of tracking radioactive materials in commerce, particularly International Atomic Energy Agency (IAEA) Category 3 and 4 materials. Specifically, Phase II of the project addressed tracking radiological medical isotopes in commerce. These categories of materials are susceptible to loss or theft but the problem is not being addressed by other agencies.

  19. DOE/NNSA Recovers One Millionth Curie of Radioactive Material...

    National Nuclear Security Administration (NNSA)

    were part of DOENNSA's global campaign to prevent terrorists from acquiring nuclear and radiological material. The radioactive source that achieved the millionth curie milestone...

  20. EHS-Net Tomato Handling Study EHS-Net Tomato Handling Study Protocol

    E-Print Network [OSTI]

    EHS-Net Tomato Handling Study 1 EHS-Net Tomato Handling Study Protocol I. Project Overview Title EHS-Net Tomato Handling Study Protocol Summary Few studies have examined in detail the nature Health Specialists Network (EHS-Net) special study. EHS- Net is a collaboration involving the Centers

  1. Radiological FIB/SEM (Quanta) | EMSL

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

    FIBSEM (Quanta) Radiological FIBSEM (Quanta) The environmental scanning electron microscope (ESEM) is a new-generation SEM that can image samples under controlled environments...

  2. Radiological Monitoring Continues at WIPP

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearch > TheNuclear Press Releases 2014 2013 2012Radiological Monitoring

  3. ORISE: Radiological program assessment services

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated CodesTransparencyDOENurse TriageInternationalRadiological program

  4. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    SciTech Connect (OSTI)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01T23:59:59.000Z

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  5. Specialty Vehicles and Material Handling EquipmentSpecialty Vehicles and Material Handling EquipmentSpecialty Vehicles and Material Handling EquipmentSpecialty Vehicles and Material Handling Equipment Matching Federal Government Energy Needs with Energy E

    E-Print Network [OSTI]

    ), producing hydrogensolar), producing hydrogen from natural gas at the stationfrom natural gas at the stationfrom natural gas at the stationfrom natural gas at the station has the lowest carbonhas the lowest Internal Combustion to Electric Conversion #12;#12;#12;Environmental Benefits Environmental Benefits

  6. automated material handling: Topics by E-print Network

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

    design and operation of an automated ac susceptibility set up using a closed cycle helium refrigerator. This set up is useful for measuring linear and nonlinear magnetic...

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the YouTube|6721 Federal Register / Vol.6: RecordJune- BatteryVehicles |DataEarly

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

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagementOPAM PolicyOfEnergy Online ClassifiedExplosives

  9. Virtual Reality for Nuclear Material Handling | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group current C3EDepartmentDepartment(GATE)

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:RevisedAdvisory Board Contributions EMEMEnergy

  11. Specialty Vehicles and Material Handling Equipment | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOriginEducationVideo »UsageSecretaryVideos Solid-State|Special Report:4-01Specialized

  12. RESCHEDULED: Webinar on Material Handling Fuel Cells for Building Electric

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin of ContaminationHubs+18, 2012 Qualified11 Connecticut Ave NW, Suite 600REQUEST FOR

  13. Radiation Sources and Radioactive Materials (Connecticut)

    Broader source: Energy.gov [DOE]

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

  14. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 75 RARAF - Table of Contents RARAF Professional FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2005 76 The Radiological Research Accelerator Facility AN NIH .................................................................................................................................................72 Development of Facilities

  15. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 65 RARAF - Table of Contents RARAF Professional FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2006 66 The Radiological Research Accelerator Facility AN NIH..................................................................................................................................................66 Development of facilities

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

    SciTech Connect (OSTI)

    Danny Anderson

    2014-07-01T23:59:59.000Z

    As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE 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.

  17. Handling uncertainty in DEX methodology Martin Znidarsic

    E-Print Network [OSTI]

    Bohanec, Marko

    URPDM2010 1 Handling uncertainty in DEX methodology Martin Znidarsic Jozef Stefan Institute, Jamova cesta 39, martin.znidarsic@ijs.si Marko Bohanec Jozef Stefan Institute, Jamova cesta 39, marko

  18. 2004 Biodiesel Handling and Use Guidelines (Revised)

    SciTech Connect (OSTI)

    Not Available

    2004-11-01T23:59:59.000Z

    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.

  19. Commercial Storage and Handling of Sorghum Grain.

    E-Print Network [OSTI]

    Brown, Charles W.; Moore, Clarence A.

    1963-01-01T23:59:59.000Z

    Summary Three areas that provide a cross section of physical and economic conditions under which sorghum grain is produced, handled and stored were selected for study of storage and handling facilities and practices by commercial grain storage...-60. Grain stocks in storage increased even more rapidly. Storage space in 1955 was 71 percent occupied on January 1, whereas the much greater space in 1960 was 82 percent occupied. Grain sorghum increased from less than half to almost three...

  20. Dairy Manure Handling Systems and Equipment.

    E-Print Network [OSTI]

    Sweeten, John M.

    1983-01-01T23:59:59.000Z

    The Texas A&M University System ? Texas Agricultural Extension Service Zerle L. Carpenter, Director College Station 8?1446 DAIRY MANURE HANDLING SYSTEMS AND EQUIPMENT DAIRY MANURE HANDLING SYSTEMS AND EQUIPMENT John M. Sweeten, Ph....D., P.E.* A manure management system for a modern dairy should be capable of controlling solid or liquid manure and wastewater from the open corrals (manure and rainfall runoff), free stall barn , feeding barn , holding lot or holding shed , milking...

  1. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council Nevada Test Site

    2010-02-09T23:59:59.000Z

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  2. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council - Nevada Test Site

    2009-10-01T23:59:59.000Z

    This document supersedes DOE/NV/11718--079, “NV/YMP Radiological Control Manual,” Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

  3. Federal Radiological Monitoring and Assessment Center

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

    1992-12-02T23:59:59.000Z

    To establish Department of Energy (DOE) policy, procedures, authorities, and requirements for the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC), as set forth in the Federal Radiological Emergency Response Plan (FRERP). This directive does not cancel another directive. Canceled by DOE O 153.1.

  4. Fifth Anniversary of Radiological Alarm Response Training for...

    National Nuclear Security Administration (NNSA)

    Office NPO News Releases Fifth Anniversary of Radiological Alarm Response Training ... Fifth Anniversary of Radiological Alarm Response Training for Local Law...

  5. Fifth Anniversary of Radiological Alarm Response Training for...

    National Nuclear Security Administration (NNSA)

    at NNSA Blog Home NNSA Blog Fifth Anniversary of Radiological Alarm Response Training ... Fifth Anniversary of Radiological Alarm Response Training for Local Law...

  6. LM Records Handling System-Fernald Historical Records System...

    Office of Environmental Management (EM)

    Fernald Historical Records System, Office of Legacy Management LM Records Handling System-Fernald Historical Records System, Office of Legacy Management LM Records Handling...

  7. Remote-Handled Transuranic Content Codes

    SciTech Connect (OSTI)

    Washington TRU Solutions

    2001-08-01T23:59:59.000Z

    The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document representsthe development of a uniform content code system for RH-TRU waste to be transported in the 72-Bcask. It will be used to convert existing waste form numbers, content codes, and site-specificidentification codes into a system that is uniform across the U.S. Department of Energy (DOE) sites.The existing waste codes at the sites can be grouped under uniform content codes without any lossof waste characterization information. The RH-TRUCON document provides an all-encompassing|description for each content code and compiles this information for all DOE sites. Compliance withwaste generation, processing, and certification procedures at the sites (outlined in this document foreach content code) ensures that prohibited waste forms are not present in the waste. The contentcode gives an overall description of the RH-TRU waste material in terms of processes and|packaging, as well as the generation location. This helps to provide cradle-to-grave traceability ofthe waste material so that the various actions required to assess its qualification as payload for the72-B cask can be performed. The content codes also impose restrictions and requirements on themanner in which a payload can be assembled.The RH-TRU Waste Authorized Methods for Payload Control (RH-TRAMPAC), Appendix 1.3.7of the 72-B Cask Safety Analysis Report (SAR), describes the current governing procedures|applicable for the qualification of waste as payload for the 72-B cask. The logic for this|classification is presented in the 72-B Cask SAR. Together, these documents (RH-TRUCON,|RH-TRAMPAC, and relevant sections of the 72-B Cask SAR) present the foundation and|justification for classifying RH-TRU waste into content codes. Only content codes described in thisdocument can be considered for transport in the 72-B cask. Revisions to this document will be madeas additional waste qualifies for transport. |Each content code uniquely identifies the generated waste and provides a system for tracking theprocess and packaging history. Each content code begins with a two-letter site abbreviation thatindicates the shipper of the RH-TRU waste. The site-specific letter designations for each of the|DOE sites are provided in Table 1. Not all of the sites listed in Table 1 have generated/stored RH-|TRU waste.

  8. New Developments in Storage and Handling of Biomass

    E-Print Network [OSTI]

    Bundalli, N.

    NEW DEVELOPMENTS IN STORAGE AND HA~DLING OF BIOMASS Nazmir Bunda1li, P.Eng., B.C. Research Vancouver, B.C., Canada ABSTRACT An extensive research project to derive guidelines for the design of a reliable bin-feeder system for biomass... hog fuel storage bins in pulp mills have been successfully modified, based on the new design. INTRODUCTION An important reqUirement for the use of biomass for ellergy is the need to handl e effi ci ently, large volumes of the material. A cOlill1...

  9. Plutonium stabilization and handling quality assurance program plan

    SciTech Connect (OSTI)

    Weiss, E.V.

    1998-04-22T23:59:59.000Z

    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.

  10. Understanding Contamination; Twenty Years of Simulating Radiological Contamination

    SciTech Connect (OSTI)

    Emily Snyder; John Drake; Ryan James

    2012-02-01T23:59:59.000Z

    A wide variety of simulated contamination methods have been developed by researchers to reproducibly test radiological decontamination methods. Some twenty years ago a method of non-radioactive contamination simulation was proposed at the Idaho National Laboratory (INL) that mimicked the character of radioactive cesium and zirconium contamination on stainless steel. It involved baking the contamination into the surface of the stainless steel in order to 'fix' it into a tenacious, tightly bound oxide layer. This type of contamination was particularly applicable to nuclear processing facilities (and nuclear reactors) where oxide growth and exchange of radioactive materials within the oxide layer became the predominant model for material/contaminant interaction. Additional simulation methods and their empirically derived basis (from a nuclear fuel reprocessing facility) are discussed. In the last ten years the INL, working with the Defense Advanced Research Projects Agency (DARPA) and the National Homeland Security Research Center (NHSRC), has continued to develop contamination simulation methodologies. The most notable of these newer methodologies was developed to compare the efficacy of different decontamination technologies against radiological dispersal device (RDD, 'dirty bomb') type of contamination. There are many different scenarios for how RDD contamination may be spread, but the most commonly used one at the INL involves the dispersal of an aqueous solution containing radioactive Cs-137. This method was chosen during the DARPA projects and has continued through the NHSRC series of decontamination trials and also gives a tenacious 'fixed' contamination. Much has been learned about the interaction of cesium contamination with building materials, particularly concrete, throughout these tests. The effects of porosity, cation-exchange capacity of the material and the amount of dirt and debris on the surface are very important factors. The interaction of the contaminant/substrate with the particular decontamination technology is also very important. Results of decontamination testing from hundreds of contaminated coupons have lead to certain conclusions about the contamination and the type of decontamination methods being deployed. A recent addition to the DARPA initiated methodology simulates the deposition of nuclear fallout. This contamination differs from previous tests in that it has been developed and validated purely to simulate a 'loose' type of contamination. This may represent the first time that a radiologically contaminated 'fallout' stimulant has been developed to reproducibly test decontamination methods. While no contaminant/methodology may serve as a complete example of all aspects that could be seen in the field, the study of this family of simulation methods provides insight into the nature of radiological contamination.

  11. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    Bzorgi, Fariborz M

    2014-10-07T23:59:59.000Z

    A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

  12. US Department of Energy Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1992-06-01T23:59:59.000Z

    This manual establishes practices for the conduct of radiological control activities. The Manual states DOE`s positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. (VC)

  13. US Department of Energy Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1992-06-01T23:59:59.000Z

    This manual establishes practices for the conduct of radiological control activities. The Manual states DOE's positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. (VC)

  14. USED NUCLEAR MATERIALS AT SAVANNAH RIVER SITE: ASSET OR WASTE?

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03T23:59:59.000Z

    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.

  15. Architecturing Conflict Handling of Pervasive Computing Resources

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Architecturing Conflict Handling of Pervasive Computing Resources Henner Jakob1 , Charles Consel1 to conflict in their usage of shared resources, e.g., controlling doors for security and fire evacuation computing resources. This approach covers the software devel- opment lifecycle and consists of enriching

  16. Easy Gardening.....Harvesting and Handling Vegetables

    E-Print Network [OSTI]

    Cotner, Sam; Masabni, Joseph; Wagner, Al

    2009-05-29T23:59:59.000Z

    Easy Gardening Joseph Masabni, Assistant Professor and Extension Horticulturist, The Texas A&M University System HARVESTING ? HANDLING ? STORING VEGETABLES -1- T ohelpensurethatthevegetables yougrowandprepareareofhigh quality.... Acknowledgments Thispublicationwasrevisedfromearlierversionswrittenby SamCotner,ProfessorEmeritusandformerExtension Horticulturist,andAlWagner,formerProfessorand ExtensionHorticulturist. -6- Produced by AgriLife Communications, The Texas A&M System Extension...

  17. Radiological Instrumentation Assessment for King County Wastewater Treatment Division

    SciTech Connect (OSTI)

    Strom, Daniel J.; McConn, Ronald J.; Brodzinski, Ronald L.

    2005-05-19T23:59:59.000Z

    The King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into its combined sanitary and storm sewer system. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material. Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. Volume 2 of PNNL-15163 assesses the radiological instrumentation needs for detection of radiological or nuclear terrorism, in support of decisions to treat contaminated wastewater or to bypass the West Point Treatment Plant (WPTP), and in support of radiation protection of the workforce, the public, and the infrastructure of the WPTP. Fixed radiation detection instrumentation should be deployed in a defense-in-depth system that provides 1) early warning of significant radioactive material on the way to the WPTP, including identification of the radionuclide(s) and estimates of the soluble concentrations, with a floating detector located in the wet well at the Interbay Pump Station and telemetered via the internet to all authorized locations; 2) monitoring at strategic locations within the plant, including 2a) the pipe beyond the hydraulic ram in the bar screen room; 2b) above the collection funnels in the fine grit facility; 2c) in the sampling tank in the raw sewage pump room; and 2d) downstream of the concentration facilities that produce 6% blended and concentrated biosolids. Engineering challenges exist for these applications. It is necessary to deploy both ultra-sensitive detectors to provide early warning and identification and detectors capable of functioning in high-dose rate environments that are likely under some scenarios, capable of functioning from 10 microrems per hour (background) up to 1000 rems per hour. Software supporting fixed spectroscopic detectors is needed to provide prompt, reliable, and simple interpretations of spectroscopic outputs that are of use to operators and decision-makers. Software to provide scientists and homeland security personnel with sufficient technical detail for identification, quantification, waste management decisions, and for the inevitable forensic and attribution needs must be developed. Computational modeling using MCNP software has demonstrated that useful detection capabilities can be deployed. In particular, any of the isotopes examined can be detected at levels between 0.01 and 0.1 ?Ci per gallon. General purpose instruments that can be used to determine the nature and extent of radioactive contamination and measure radiation levels for purposes of protecting personnel and members of the public should be available. One or more portable radioisotope identifiers (RIIDs) should be available to WTD personnel. Small, portable battery-powered personal radiation monitors should be widely available WTD personnel. The personal monitors can be used for personal and group radiation protection decisions, and to alert management to the need to get expert backup. All considerations of radiological instrumentation require considerations of training and periodic retraining of personnel, as well as periodic calibration and maintenance of instruments. Routine “innocent” alarms will occur due to medical radionuclides that are legally discharged into sanitary sewers on a daily basis.

  18. Letter Report - Verification Results for the Non-Real Property Radiological Release Program at the West Valley Demonstration Project, Ashford, New York

    SciTech Connect (OSTI)

    M.A. Buchholz

    2009-04-29T23:59:59.000Z

    The objective of the verification activities is to provide an independent review of the design, implementation, and performance of the radiological unrestricted release program for personal property, materials, and equipment (non-real property).

  19. November 28, 2006 Seismologists get handle on heat flow deep in earth

    E-Print Network [OSTI]

    Garnero, Ed

    November 28, 2006 Seismologists get handle on heat flow deep in earth Earth's interior placid inner Earth as a dynamic environment filled with exotic materials and substances roiling under that has an impact on what happens on our planet's surface. The latest evidence of this dynamic inner Earth

  20. Radiological survey results at 4400 Piehl Road, Ottawa Lake, Michigan

    SciTech Connect (OSTI)

    Foley, R.D.; Johnson, C.A.

    1993-04-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 4400 Piehl Road in Ottawa Lake, Michigan. The survey was performed in September, 1992. The purpose of the survey was to determine if materials containing uranium from work performed under government contract at the former Baker Brothers facility in Toledo, Ohio had been transported off-site to this neighboring area. The radiological survey included surface gamma scans indoors and outdoors, alpha and beta scans inside the house and attached garage, beta-gamma scans of the hard surfaces outside, and the collection of soil, water, and dust samples for radionuclide analyses. Results of the survey demonstrated that the majority of the measurements on the property were within DOE guidelines. However, the presence of isolated spots of uranium contamination were found in two areas where materials were allegedly transported to the property from the former Baker Brothers site. Uranium uptake by persons on the property by ingestion is fairly unlikely, but inhalation is a possibility. Based on these findings, it is recommended that the residential property at 4400 Piehl Road in Ottawa Lake, Michigan be considered for inclusion under FUSRAP.

  1. BNL ALARA Center's development of a computerized radiological assessment and design system (RADS)

    SciTech Connect (OSTI)

    Dionne, B.J. (Brookhaven National Lab., Upton, NY (United States)); Masciulli, S. (Vertechs Corp., Syracuse, NY (United States)); Connelly, J.M. (Dept. of Energy, Washington, DC (United States). Office of Health)

    1993-01-01T23:59:59.000Z

    The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation of DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of good-practice documents will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called Radiological Assessment and Design System (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analyses, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative rating of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results.

  2. BNL ALARA Center`s development of a computerized radiological assessment and design system (RADS)

    SciTech Connect (OSTI)

    Dionne, B.J. [Brookhaven National Lab., Upton, NY (United States); Masciulli, S. [Vertechs Corp., Syracuse, NY (US); Connelly, J.M. [Dept. of Energy, Washington, DC (US). Office of Health

    1993-07-01T23:59:59.000Z

    The US Department of Energy`s (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation of DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of good-practice documents will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called Radiological Assessment and Design System (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analyses, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative rating of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results.

  3. Viability of Existing INL Facilities for Dry Storage Cask Handling

    SciTech Connect (OSTI)

    Randy Bohachek; Charles Park; Bruce Wallace; Phil Winston; Steve Marschman

    2013-04-01T23:59:59.000Z

    This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

  4. Roadmap: Radiologic Imaging Sciences -Computed Tomography (with certification and ATS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Computed Tomography (with certification and ATS Radiologic 34084 Computed Tomography and Magnetic Resonance Imaging Sectional Anatomy I 2 C RIS 44021 Patient Management in Computed Tomography 2 C RIS 44025 Computed Tomography Clinical Education I 3 C RIS 44030

  5. Roadmap: Radiologic Imaging Sciences -Computed Tomography (with certification and ATS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Computed Tomography (with certification and ATS Radiologic 34084 Computed Tomography and Magnetic Resonance Imaging Sectional Anatomy I 2 C RIS 44021 Patient Management in Computed Tomography (CT) 2 C RIS 44025 Computed Tomography (CT) Clinical Education I 3 C

  6. Spent nuclear fuel retrieval system fuel handling development testing. Final report

    SciTech Connect (OSTI)

    Jackson, D.R.; Meeuwsen, P.V.

    1997-09-01T23:59:59.000Z

    Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin, clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge), remove the contents from the canisters and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. This report describes fuel handling development testing performed from May 1, 1997 through the end of August 1997. Testing during this period was mainly focused on performance of a Schilling Robotic Systems` Conan manipulator used to simulate a custom designed version, labeled Konan, being fabricated for K-Basin deployment. In addition to the manipulator, the camera viewing system, process table layout, and fuel handling processes were evaluated. The Conan test manipulator was installed and fully functional for testing in early 1997. Formal testing began May 1. The purposes of fuel handling development testing were to provide proof of concept and criteria, optimize equipment layout, initialize the process definition, and identify special needs/tools and required design changes to support development of the performance specification. The test program was set up to accomplish these objectives through cold (non-radiological) development testing using simulated and prototype equipment.

  7. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2004 RARAF -Table of Contents

    E-Print Network [OSTI]

    RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility AN NIHCENTER FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2004 RARAF - Table of Contents RARAF Staff ...................................................................................................................................................67 Development of Facilities

  8. Radiological Risk Assessment for King County Wastewater Treatment Division

    SciTech Connect (OSTI)

    Strom, Daniel J.

    2005-08-05T23:59:59.000Z

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document develops plausible and/or likely scenarios, including the identification of likely radioactive materials and quantities of those radioactive materials to be involved. These include 60Co, 90Sr, 137Cs, 192Ir, 226Ra, plutonium, and 241Am. Two broad categories of scenarios are considered. The first category includes events that may be suspected from the outset, such as an explosion of a "dirty bomb" in downtown Seattle. The explosion would most likely be heard, but the type of explosion (e.g., sewer methane gas or RDD) may not be immediately known. Emergency first responders must be able to quickly detect the radioisotopes previously listed, assess the situation, and deploy a response to contain and mitigate (if possible) detrimental effects resulting from the incident. In such scenarios, advance notice of about an hour or two might be available before any contaminated wastewater reaches a treatment plant. The second category includes events that could go initially undetected by emergency personnel. Examples of such a scenario would be the inadvertent or surreptitious introduction of radioactive material into the sewer system. Intact rogue radioactive sources from industrial radiography devices, well-logging apparatus, or moisture density gages may get into wastewater and be carried to a treatment plant. Other scenarios might include a terrorist deliberately putting a dispersible radioactive material into wastewater. Alternatively, a botched terrorism preparation of an RDD may result in radioactive material entering wastewater without anyone's knowledge. Drinking water supplies may also be contaminated, with the result that some or most of the radioactivity ends up in wastewater.

  9. GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTuba City, Arizona,SiteNational Nuclear Security AdministrationNational

  10. Improving Memory Error Handling Using Linux

    SciTech Connect (OSTI)

    Carlton, Michael Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Blanchard, Sean P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Debardeleben, Nathan A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-07-25T23:59:59.000Z

    As supercomputers continue to get faster and more powerful in the future, they will also have more nodes. If nothing is done, then the amount of memory in supercomputer clusters will soon grow large enough that memory failures will be unmanageable to deal with by manually replacing memory DIMMs. "Improving Memory Error Handling Using Linux" is a process oriented method to solve this problem by using the Linux kernel to disable (offline) faulty memory pages containing bad addresses, preventing them from being used again by a process. The process of offlining memory pages simplifies error handling and results in reducing both hardware and manpower costs required to run Los Alamos National Laboratory (LANL) clusters. This process will be necessary for the future of supercomputing to allow the development of exascale computers. It will not be feasible without memory error handling to manually replace the number of DIMMs that will fail daily on a machine consisting of 32-128 petabytes of memory. Testing reveals the process of offlining memory pages works and is relatively simple to use. As more and more testing is conducted, the entire process will be automated within the high-performance computing (HPC) monitoring software, Zenoss, at LANL.

  11. CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2005-04-07T23:59:59.000Z

    This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the CHF is included in the Q-List (BSC 2005 [DIRS 171190], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

  12. Interventional Radiology of Male Varicocele: Current Status

    SciTech Connect (OSTI)

    Iaccarino, Vittorio, E-mail: vittorio.iaccarino@unina.it; Venetucci, Pietro [University of Naples 'Federico II', Diagnostic Imaging Department-Cardiovascular and Interventional Radiology, School of Medicine (Italy)

    2012-12-15T23:59:59.000Z

    Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

  13. STUDENT ORGANIZATION FOOD/BEVERAGE HANDLING REQUEST FOR

    E-Print Network [OSTI]

    Oklahoma, University of

    STUDENT ORGANIZATION FOOD/BEVERAGE HANDLING REQUEST FOR HEALTH DEPARTMENT APPROVAL Please submit. PLEASE ALLOW AT LEAST 10 working days for approval. Student Organization: ___________________________________________________________ Student Responsible for Event/Food Handling: _______________________________________ Phone Number

  14. Advanced Neutron Source radiological design criteria

    SciTech Connect (OSTI)

    Westbrook, J.L.

    1995-08-01T23:59:59.000Z

    The operation of the proposed Advanced Neutron Source (ANS) facility will present a variety of radiological protection problems. Because it is desired to design and operate the ANS according to the applicable licensing standards of the Nuclear Regulatory Commission (NRC), it must be demonstrated that the ANS radiological design basis is consistent not only with state and Department of Energy (DOE) and other usual federal regulations, but also, so far as is practicable, with NRC regulations and with recommendations of such organizations as the Institute of Nuclear Power Operations (INPO) and the Electric Power Research Institute (EPRI). Also, the ANS radiological design basis is in general to be consistent with the recommendations of authoritative professional and scientific organizations, specifically the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP). As regards radiological protection, the principal goals of DOE regulations and guidance are to keep occupational doses ALARA [as low as (is) reasonably achievable], given the current state of technology, costs, and operations requirements; to control and monitor contained and released radioactivity during normal operation to keep public doses and releases to the environment ALARA; and to limit doses to workers and the public during accident conditions. Meeting these general design objectives requires that principles of dose reduction and of radioactivity control by employed in the design, operation, modification, and decommissioning of the ANS. The purpose of this document is to provide basic radiological criteria for incorporating these principles into the design of the ANS. Operations, modification, and decommissioning will be covered only as they are affected by design.

  15. Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

    2012-05-01T23:59:59.000Z

    This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

  16. Contamination surveys for release of material

    SciTech Connect (OSTI)

    Durham, J.S.; Johnson, M.L. [Pacific Northwest Lab., Richland, WA (United States); Gardner, D.L. [Westinghouse Hanford Co., Richland, WA (United States)

    1994-05-01T23:59:59.000Z

    This report describes, and presents the technical basis for, a methodology for performing instrument surveys to release material from radiological control, including release to controlled areas and release from radiological control. The methodology is based on a fast scan survey, a large-area wipe survey, and a series of statistical, fixed measurements. The methodology meets the requirements of the US Department of Energy Radiological Control Manual (RadCon Manual) (DOE 1994) and DOE Order 5400.5 (DOE 1990) for release of material in less time than is required by a conventional scan survey. Implementation of the proposed methodology with a confidence interval of 67% will meet the material release requirements. The material evaluation process will allow material that has not been exposed to contamination to be released from radiological control without a survey. For potential radioactive contaminants that are not reserved in DOE Order 5400.5, the methodology will allow material to be released from radiological control. For other radionuclides, with the exception of some difficult-to-detect radionuclides, material may be released for controlled use. Compared with current techniques, the proposed methodology will reduce the amount of time required to perform surveys.

  17. SOFTWARE AGENTS IN HANDLING ABNORMAL SITUATIONS IN INDUSTRIAL PLANTS

    E-Print Network [OSTI]

    SOFTWARE AGENTS IN HANDLING ABNORMAL SITUATIONS IN INDUSTRIAL PLANTS Sami Syrjälä and Seppo Kuikka. The abnormal situation handling in industrial plants is a challenging application area due to the complexity-model, abnormal situation handling, industrial plants 1. Introduction This paper is based on the work made

  18. On Exceptions, Exception Handling, Requirements and Software Lifecycle Alexander Romanovsky

    E-Print Network [OSTI]

    Southampton, University of

    On Exceptions, Exception Handling, Requirements and Software Lifecycle Alexander Romanovsky Notes. 32(2). 2007. [2] R. de Lemos, and A. Romanovsky. Exception handling in the software lifecycle. Castor Filho. Exception handling in the development of dependable component-based systems. Software

  19. RADIOACTIVE MATERIALS SENSORS

    SciTech Connect (OSTI)

    Mayo, Robert M.; Stephens, Daniel L.

    2009-09-15T23:59:59.000Z

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

  20. Nuclear and Radiological Engineering and Medical Physics Programs

    E-Print Network [OSTI]

    Weber, Rodney

    Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Year Enrollment - Fall Semester Undergraduate Graduate #12; Nuclear Power Industry Radiological Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants

  1. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 113 RARAF - Table of Contents RARAF Professional · ANNUAL REPORT 2007 114 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE CENTER................................................................................................................................................114 Development of Facilities

  2. Environmental Health and Safety Radiation Control and Radiological

    E-Print Network [OSTI]

    Slatton, Clint

    Environmental Health and Safety Radiation Control and Radiological Services #12;· Course focuses into six departments: 1) Facility and Fire Safety Pest Control and Fire Equipment Service Units 2) Radiation Control and Radiological Services University-wide radiation protection 3) Occupational

  3. Radiological Scoping Survey of the Scotia Depot, Scotia, NY

    SciTech Connect (OSTI)

    Bailey, E. N.

    2008-02-25T23:59:59.000Z

    The objectives of the radiological scoping survey were to collect adequate field data for use in evaluating the radiological condition of Scotia Depot land areas, warehouses, and support buildings.

  4. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents RARAF Professional Staff RESEARCH ANNUAL REPORT 2009 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE................................................................................................................................................101 Development of Facilities

  5. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 118 RARAF Table of Contents RARAF Professional ANNUAL REPORT 2008 119 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE CENTER................................................................................................................................................119 Development of Facilities

  6. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 117 RARAF - Table of Contents RARAF Professional RESEARCH · ANNUAL REPORT 2010 118 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE................................................................................................................................................117 Development of Facilities

  7. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    SciTech Connect (OSTI)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01T23:59:59.000Z

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC&FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate.

  8. Radiological Contingency Planning for the Mars Science Laboratory Launch

    SciTech Connect (OSTI)

    Paul Guss, Robert Augdahl, Bill Nickels, Cassandra Zellers

    2008-04-16T23:59:59.000Z

    This paper describes the contingency planning for the launch of the Mars Science Laboratory scheduled for the 21-day window beginning on September 15, 2009. National Security Technologies, LLC (NSTec), based in Las Vegas, Nevada, will support the U.S. Department of Energy (DOE) in its role for managing the overall radiological contingency planning support effort. This paper will focus on new technologies that NSTec’s Remote Sensing Laboratory (RSL) is developing to enhance the overall response capability that would be required for a highly unlikely anomaly. This paper presents recent advances in collecting and collating data transmitted from deployed teams and sensors. RSL is responsible to prepare the contingency planning for a range of areas from monitoring and assessment, sample collection and control, contaminated material release criteria, data management, reporting, recording, and even communications. The tools RSL has available to support these efforts will be reported. The data platform RSL will provide shall also be compatible with integration of assets and field data acquired with other DOE, National Aeronautics and Space Administration, state, and local resources, personnel, and equipment. This paper also outlines the organizational structure for response elements in radiological contingency planning.

  9. U.S., Peru Mark 10 Years of Nuclear and Radiological Security...

    National Nuclear Security Administration (NNSA)

    , Peru Mark 10 Years of Nuclear and Radiological Security Collaboration, Dedicate Secure Radiological Transportation Vehicle | National Nuclear Security Administration Facebook...

  10. Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant

    Broader source: Energy.gov [DOE]

    NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

  11. System for handling and storing radioactive waste

    DOE Patents [OSTI]

    Anderson, J.K.; Lindemann, P.E.

    1982-07-19T23:59:59.000Z

    A system and method are claimed for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

  12. System for handling and storing radioactive waste

    DOE Patents [OSTI]

    Anderson, John K. (San Diego, CA); Lindemann, Paul E. (Escondido, CA)

    1984-01-01T23:59:59.000Z

    A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

  13. REM Handling Procedures | The Ames Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70COMMUNITYResponses:December 11, 2014WD 05-2103 REM Handling

  14. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2001 RARAF Staff Photo

    E-Print Network [OSTI]

    RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 77 The Radiological Research Accelerator Facility AN NIHCENTER FOR RADIOLOGICAL RESEARCH ·ANNUAL REPORT 2001 76 RARAF Staff Photo RARAF staff (l-r): Dr and the track segment facilities continue to be utilized in various investigations of this phenomenon

  15. Radiological Control Manual Environment, Safety, Health, and Quality Division

    E-Print Network [OSTI]

    Wechsler, Risa H.

    ............................................................................................................................................8 128 Facility Modifications and Radiological Design ConsiderationsRadiological Control Manual Environment, Safety, Health, and Quality Division SLAC-I-720-0A05Z-001 and published by ESHQ Publishing Document Title: Radiological Control Manual Original Publication Date: 1

  16. Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations

    SciTech Connect (OSTI)

    Cowley, W.L.

    1996-04-25T23:59:59.000Z

    The analysis described in this report develops the Unit Liter Doses for use in the TWRS FSAR. The Unit Liter Doses provide a practical way to calculate conservative radiological consequences for a variety of potential accidents for the tank farms.

  17. Nuclear Engineering Catalog 2013 Radiological Concentration

    E-Print Network [OSTI]

    Tennessee, University of

    Nuclear Engineering Catalog 2013 Radiological Concentration Fall Math 141 or 147 (4) FA, SP, SU-approved by the department. Courses in Nuclear Engineering other than 500, 502 or 598 may also be used as technical electives on academic performance. Factors considered include overall grade point average, performance in selescted

  18. Material Recycling and Waste Disposal Document Control

    E-Print Network [OSTI]

    Guillas, Serge

    1 Material Recycling and Waste Disposal Procedure Document Control Document Created by 23, treatment, handling, transport and disposal of recyclable materials and residual wastes so as to maximise the opportunity and value for the recyclable materials and to minimise the quantity of residual materials

  19. Qualitative human reliability analysis for spent fuel handling

    SciTech Connect (OSTI)

    Brewer, J. D. [Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185-0748 (United States); Amico, P. [Science Applications International Corporation (United States); Cooper, S. E. [United Stated Nuclear Regulatory Commission (United States)

    2006-07-01T23:59:59.000Z

    Human reliability analysis (HRA) methods have been developed primarily to provide information for use in probabilistic risk assessments (PRAs) that analyze nuclear power plant (NPP) operations. Given the original emphasis of these methods, it is understandable that many HRAs have not ventured far from NPP control room applications. Despite this historical focus on the control room, there has been growing interest and discussion regarding the application of HRA methods to other NPP activities such as spent fuel handling (SFH) or operations in different types of facilities. One recently developed HRA method, 'A Technique for Human Event Analysis' (ATHEANA) has been proposed as a promising candidate for diverse applications due to its particular approach for systematically uncovering the dynamic, contextual conditions influencing human performance. This paper describes one successful test of this proposition by presenting portions of a recently completed project in which a scoping study was performed to accomplish the following goals: (1) investigate what should be included in a qualitative HRA for spent fuel and cask handling operations; and (2) demonstrate that the ATHEANA HRA technique can be usefully applied to these operations. The preliminary, scoping qualitative HRA examined, in a generic manner, how human performance of SFH and dry cask storage operations (DCSOs) can plausibly lead to radiological consequences that impact the public and the environment. The study involved the performance of typical, qualitative HRA tasks such as collecting relevant information and the preliminary identification of human failure events or unsafe actions, relevant influences (e.g., performance shaping factors, other contextual factors), event scenario development and categorization of human failure event (HFE) scenario groupings. Information from relevant literature sources was augmented with subject matter expert interviews and analysis of an edited video of selected operations. Elements of NUREG-1792, Good Practices for Implementing Human Reliability Analyses (HRA) and NUREG-1624, Rev. 1, Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA) formed critical parts of the technical basis for the preliminary analysis. Mis-loading of spent fuel into a cask and dropping of a loaded cask were the two human failure event groupings of primary interest, although all human performance aspects of DCSOs were considered to some extent. Of important note is that HRA is typically performed in the context of a plant-specific PRA study. This analysis was performed without the benefit of the context provided by a larger PRA study, nor was it plant specific, and so it investigated only generic HRA issues relevant to SFH. However, the improved understanding of human performance issues provided by the study will likely enhance the ability to carry out a detailed qualitative HRA for a specific NPP at some point in the future. Furthermore, support was obtained regarding the potential for applying ATHEANA beyond NPP settings. This paper provides a description of the process followed during the analysis, a description of the HFE scenario groupings, discussion regarding general human performance vulnerabilities, and a detailed examination of one HFE scenario developed in the study. (authors)

  20. HAZARDS OF THERMAL EXPANSION FOR RADIOLOGICAL CONTAINER ENGULFED IN FIRE

    SciTech Connect (OSTI)

    Donna Post Guillen

    2013-05-01T23:59:59.000Z

    Fire accidents pose a serious threat to nuclear facilities. It is imperative that transport casks or shielded containers designed to transport/contain radiological materials have the ability to withstand a hypothetical fire. A numerical simulation was performed for a shielded container constructed of stainless steel and lead engulfed in a hypothetical fire as outlined by 10 CFR §71.73. The purpose of this analysis was to determine the thermal response of the container during and after the fire. The thermal model shows that after 30 minutes of fire, the stainless steel will maintain its integrity and not melt. However, the lead shielding will melt since its temperature exceeds the melting point. Due to the method of construction of the container under consideration, ample void space must be provided to allow for thermal expansion of the lead upon heating and melting, so as to not overstress the weldment.

  1. Time cycle analysis and simulation of material flow in MOX process layout

    SciTech Connect (OSTI)

    Chakraborty, S.; Saraswat, A.; Danny, K.M.; Somayajulu, P.S.; Kumar, A. [Nuclear Fuels Group, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085 (India)

    2013-07-01T23:59:59.000Z

    The (U,Pu)O{sub 2} MOX fuel is the driver fuel for the upcoming PFBR (Prototype Fast Breeder Reactor). The fuel has around 30% PuO{sub 2}. The presence of high percentages of reprocessed PuO{sub 2} necessitates the design of optimized fuel fabrication process line which will address both production need as well as meet regulatory norms regarding radiological safety criteria. The powder pellet route has highly unbalanced time cycle. This difficulty can be overcome by optimizing process layout in terms of equipment redundancy and scheduling of input powder batches. Different schemes are tested before implementing in the process line with the help of a software. This software simulates the material movement through the optimized process layout. The different material processing schemes have been devised and validity of the schemes are tested with the software. Schemes in which production batches are meeting at any glove box location are considered invalid. A valid scheme ensures adequate spacing between the production batches and at the same time it meets the production target. This software can be further improved by accurately calculating material movement time through glove box train. One important factor is considering material handling time with automation systems in place.

  2. Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego

    2009-06-01T23:59:59.000Z

    The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new 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. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.

  3. Fuel handling system for a nuclear reactor

    DOE Patents [OSTI]

    Saiveau, James G. (Hickory Hills, IL); Kann, William J. (Park Ridge, IL); Burelbach, James P. (Glen Ellyn, IL)

    1986-01-01T23:59:59.000Z

    A pool type nuclear fission reactor has a core, with a plurality of core elements and a redan which confines coolant as a hot pool at a first end of the core separated from a cold pool at a second end of the core by the redan. A fuel handling system for use with such reactors comprises a core element storage basket located outside of the redan in the cold pool. An access passage is formed in the redan with a gate for opening and closing the passage to maintain the temperature differential between the hot pool and the cold pool. A mechanism is provided for opening and closing the gate. A lifting arm is also provided for manipulating the fuel core elements through the access passage between the storage basket and the core when the redan gate is open.

  4. Primer on tritium safe handling practices

    SciTech Connect (OSTI)

    Not Available

    1994-12-01T23:59:59.000Z

    This Primer is designed for use by operations and maintenance personnel to improve their knowledge of tritium safe handling practices. It is applicable to many job classifications and can be used as a reference for classroom work or for self-study. It is presented in general terms for use throughout the DOE Complex. After reading it, one should be able to: describe methods of measuring airborne tritium concentration; list types of protective clothing effective against tritium uptake from surface and airborne contamination; name two methods of reducing the body dose after a tritium uptake; describe the most common method for determining amount of tritium uptake in the body; describe steps to take following an accidental release of airborne tritium; describe the damage to metals that results from absorption of tritium; explain how washing hands or showering in cold water helps reduce tritium uptake; and describe how tritium exchanges with normal hydrogen in water and hydrocarbons.

  5. Error handling strategies in multiphase inverse modeling

    SciTech Connect (OSTI)

    Finsterle, S.; Zhang, Y.

    2010-12-01T23:59:59.000Z

    Parameter estimation by inverse modeling involves the repeated evaluation of a function of residuals. These residuals represent both errors in the model and errors in the data. In practical applications of inverse modeling of multiphase flow and transport, the error structure of the final residuals often significantly deviates from the statistical assumptions that underlie standard maximum likelihood estimation using the least-squares method. Large random or systematic errors are likely to lead to convergence problems, biased parameter estimates, misleading uncertainty measures, or poor predictive capabilities of the calibrated model. The multiphase inverse modeling code iTOUGH2 supports strategies that identify and mitigate the impact of systematic or non-normal error structures. We discuss these approaches and provide an overview of the error handling features implemented in iTOUGH2.

  6. Overview on Hydrate Coring, Handling and Analysis

    SciTech Connect (OSTI)

    Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

    2003-06-30T23:59:59.000Z

    Gas hydrates are crystalline, ice-like compounds of gas and water molecules that are formed under certain thermodynamic conditions. Hydrate deposits occur naturally within ocean sediments just below the sea floor at temperatures and pressures existing below about 500 meters water depth. Gas hydrate is also stable in conjunction with the permafrost in the Arctic. Most marine gas hydrate is formed of microbially generated gas. It binds huge amounts of methane into the sediments. Worldwide, gas hydrate is estimated to hold about 1016 kg of organic carbon in the form of methane (Kvenvolden et al., 1993). Gas hydrate is one of the fossil fuel resources that is yet untapped, but may play a major role in meeting the energy challenge of this century. In June 2002, Westport Technology Center was requested by the Department of Energy (DOE) to prepare a ''Best Practices Manual on Gas Hydrate Coring, Handling and Analysis'' under Award No. DE-FC26-02NT41327. The scope of the task was specifically targeted for coring sediments with hydrates in Alaska, the Gulf of Mexico (GOM) and from the present Ocean Drilling Program (ODP) drillship. The specific subjects under this scope were defined in 3 stages as follows: Stage 1: Collect information on coring sediments with hydrates, core handling, core preservation, sample transportation, analysis of the core, and long term preservation. Stage 2: Provide copies of the first draft to a list of experts and stakeholders designated by DOE. Stage 3: Produce a second draft of the manual with benefit of input from external review for delivery. The manual provides an overview of existing information available in the published literature and reports on coring, analysis, preservation and transport of gas hydrates for laboratory analysis as of June 2003. The manual was delivered as draft version 3 to the DOE Project Manager for distribution in July 2003. This Final Report is provided for records purposes.

  7. Gamma radiological surveys of the Oak Ridge Reservation, Paducah Gaseous Diffusion Plant, and Portsmouth Gaseous Diffusion Plant, 1990-1993, and overview of data processing and analysis by the Environmental Restoration Remote Sensing Program, Fiscal Year 1995

    SciTech Connect (OSTI)

    Smyre, J.L.; Moll, B.W.; King, A.L.

    1996-06-01T23:59:59.000Z

    Three gamma radiological surveys have been conducted under auspices of the ER Remote Sensing Program: (1) Oak Ridge Reservation (ORR) (1992), (2) Clinch River (1992), and (3) Portsmouth Gaseous Diffusion Plant (PORTS) (1993). In addition, the Remote Sensing Program has acquired the results of earlier surveys at Paducah Gaseous Diffusion Plant (PGDP) (1990) and PORTS (1990). These radiological surveys provide data for characterization and long-term monitoring of U.S. Department of Energy (DOE) contamination areas since many of the radioactive materials processed or handled on the ORR, PGDP, and PORTS are direct gamma radiation emitters or have gamma emitting daughter radionuclides. High resolution airborne gamma radiation surveys require a helicopter outfitted with one or two detector pods, a computer-based data acquisition system, and an accurate navigational positioning system for relating collected data to ground location. Sensors measure the ground-level gamma energy spectrum in the 38 to 3,026 KeV range. Analysis can provide gamma emission strength in counts per second for either gross or total man-made gamma emissions. Gross count gamma radiation includes natural background radiation from terrestrial sources (radionuclides present in small amounts in the earth`s soil and bedrock), from radon gas, and from cosmic rays from outer space as well as radiation from man-made radionuclides. Man-made count gamma data include only the portion of the gross count that can be directly attributed to gamma rays from man-made radionuclides. Interpretation of the gamma energy spectra can make possible the determination of which specific radioisotopes contribute to the observed man-made gamma radiation, either as direct or as indirect (i.e., daughter) gamma energy from specific radionuclides (e.g., cesium-137, cobalt-60, uranium-238).

  8. NV/YMP RADIOLOGICAL CONTROL MANUAL

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

    2004-11-01T23:59:59.000Z

    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), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

  9. Remote Handling Equipment for a High-Level Waste Waste Package Closure System

    SciTech Connect (OSTI)

    Kevin M. Croft; Scott M. Allen; Mark W. Borland

    2006-04-01T23:59:59.000Z

    High-level waste will be placed in sealed waste packages inside a shielded closure cell. The Idaho National Laboratory (INL) has designed a system for closing the waste packages including all cell interior equipment and support systems. This paper discusses the material handling aspects of the equipment used and operations that will take place as part of the waste package closure operations. Prior to construction, the cell and support system will be assembled in a full-scale mockup at INL.

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

    E-Print Network [OSTI]

    of radioactive material. In order to work within 3410 facility radiological limits, potential users must provide can evaluate whether it will meet our facility limits. Note that while the EMSL Radiochemistry Annex

  11. Fixation of Radiological Contamination; International Collaborative Development

    SciTech Connect (OSTI)

    Rick Demmer

    2013-03-01T23:59:59.000Z

    A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdom’s National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

  12. Radiological Threat Reduction | ornl.gov

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection Radiation Protection Regulations:Radiological Threat Reduction SHARE

  13. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    SciTech Connect (OSTI)

    KOZLOWSKI, S.D.

    2007-05-30T23:59:59.000Z

    This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.

  14. Handbook for Handling, Storing, and Dispensing E85

    SciTech Connect (OSTI)

    Not Available

    2008-04-01T23:59:59.000Z

    Guidebook contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

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

    Office of Environmental Management (EM)

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

  16. LM Records Handling System (LMRHS01) - Energy Employees Occupational...

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

    Energy Employees Occupational Illness Compensation Program Act, Office of Legacy Management LM Records Handling System (LMRHS01) - Energy Employees Occupational Illness...

  17. LM Records Handling System (LMRHS01) - Electronic Records Keeping...

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

    System (LMRHS01) - Electronic Records Keeping System, Office of Legacy Management, LM Records Handling System (LMRHS01) - Electronic Records Keeping System, Office of Legacy...

  18. LM Records Handling System (LMRHS01) - Rocky Flats Environmental...

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

    Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy...

  19. Biodiesel Handling and Use Guide: Fourth Edition (Revised)

    SciTech Connect (OSTI)

    Not Available

    2009-01-01T23:59:59.000Z

    Intended for those who blend, distribute, and use biodiesel and its blends, this guide contains procedures for handling and using these fuels.

  20. Radiological re-survey results at 146 West Central Avenue, Maywood, New Jersey (MJ034)

    SciTech Connect (OSTI)

    Murray, M.E.; Johnson, C.A.

    1994-05-01T23:59:59.000Z

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE) designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 146 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, Oak Ridge National Laboratory (ORNL) conducted a radiological survey on this property. A report describing this survey was published in 1989. A second radiological survey by ORNL was conducted on this property in May 1993 at the request of DOE after an ad hoc radiological survey, requested by the property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the second ORNL survey was to determine whether radioactive materials from the old MCW were present on the property, and if so, if radioactive materials present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological re-survey. The re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses. Results of this survey demonstrated that although elevated residual thorium-232 contamination was present in a few isolated spots on the southern end of the backyard, it did not exceed DOE guidelines.

  1. An aerial radiological survey of the Nevada Test Site

    SciTech Connect (OSTI)

    Hendricks, T J; Riedhauser, S R

    1999-12-01T23:59:59.000Z

    A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the US Department of Energy's Nevada Test Site including three neighboring areas during August and September 1994. The survey team measured the terrestrial gamma radiation at the Nevada Test Site to determine the levels of natural and man-made radiation. This survey included the areas covered by previous surveys conducted from 1962 through 1993. The results of the aerial survey showed a terrestrial background exposure rate that varied from less than 6 microroentgens per hour (mR/h) to 50 mR/h plus a cosmic-ray contribution that varied from 4.5 mR/h at an elevation of 900 meters (3,000 feet) to 8.5 mR/h at 2,400 meters (8,000 feet). In addition to the principal gamma-emitting, naturally occurring isotopes (potassium-40, thallium-208, bismuth-214, and actinium-228), the man-made radioactive isotopes found in this survey were cobalt-60, cesium-137, europium-152, protactinium-234m an indicator of depleted uranium, and americium-241, which are due to human actions in the survey area. Individual, site-wide plots of gross terrestrial exposure rate, man-made exposure rate, and americium-241 activity (approximating the distribution of all transuranic material) are presented. In addition, expanded plots of individual areas exhibiting these man-made contaminations are given. A comparison is made between the data from this survey and previous aerial radiological surveys of the Nevada Test Site. Some previous ground-based measurements are discussed and related to the aerial data. In regions away from man-made activity, the exposure rates inferred from the gamma-ray measurements collected during this survey agreed very well with the exposure rates inferred from previous aerial surveys.

  2. Comparison of potential radiological consequences from a spent-fuel repository and natural uranium deposits

    SciTech Connect (OSTI)

    Wick, O.J.; Cloninger, M.O.

    1980-09-01T23:59:59.000Z

    A general criterion has been suggested for deep geological repositories containing spent fuel - the repositories should impose no greater radiological risk than due to naturally occurring uranium deposits. The following analysis investigates the rationale of that suggestion and determines whether current expectations of spent-fuel repository performance are consistent with such a criterion. In this study, reference spent-fuel repositories were compared to natural uranium-ore deposits. Comparisons were based on intrinsic characteristics, such as radionuclide inventory, depth, proximity to aquifers, and regional distribution, and actual and potential radiological consequences that are now occurring from some ore deposits and that may eventually occur from repositories and other ore deposits. The comparison results show that the repositories are quite comparable to the natural ore deposits and, in some cases, present less radiological hazard than their natural counterparts. On the basis of the first comparison, placing spent fuel in a deep geologic repository apparently reduces the hazard from natural radioactive materials occurring in the earth's crust by locating the waste in impermeable strata without access to oxidizing conditions. On the basis of the second comparison, a repository constructed within reasonable constraints presents no greater hazard than a large ore deposit. It is recommended that if the naturally radioactive environment is to be used as a basis for a criterion regarding repositories, then this criterion should be carefully constructed. The criterion should be based on the radiological quality of the waters in the immediate region of a specific repository, and it should be in terms of an acceptable potential increase in the radiological content of those waters due to the existence of the repository.

  3. Radiological Assessment of Steam Generator Removal and Replacement: Update and Revision

    SciTech Connect (OSTI)

    Hoenes, G. R.; Mueller, M. A.; McCormack, W. D.

    1980-12-01T23:59:59.000Z

    A previous analysis of the radiological impact of removing and replacing corroded steam generators has been updated based on experience gained during steam generator repairs at Surry Unit 2. Some estimates of occupational doses involved in the operation have been revised but are not significantly different from the earlier estimates. Estimates of occupational doses and radioactive effluents for new tasks have been added. Health physics concerns that arose at Surry included the number of persons involved in the operation, tne training of workers, the handling of quantitites.of low-level waste, and the application of the ALARA principle. A review of these problem areas may help in the planning of other similar operations. A variety of processes could be used to decontaminate steam generators. Research is needed to assess these techniques and their associated occupational doses and waste volumes. Contaminated steam generators can be stored or disposed of after removal without significant radiological problems. Onsite storage and intact shipment have the least impact. In-placing retubing, an alternative to steam generator removal, results in occupational doses and effluents similar to those from removal, but prior decontamination of the channel head is needed. The retubing option should be assessed further.

  4. Handling Radioactive Waste from the Proton Accelerator Facility at the Paul Scherrer Institut (PSI) - Always Surprising? - 13320

    SciTech Connect (OSTI)

    Mueth, Joachim [Paul Scherrer Institute, CH-5232 Villigen (Switzerland)] [Paul Scherrer Institute, CH-5232 Villigen (Switzerland)

    2013-07-01T23:59:59.000Z

    The Paul Scherrer Institut (PSI) is the largest national research centre in Switzerland. Its multidisciplinary research is dedicated to a wide field in natural science and technology as well as particle physics. In this context, PSI is operating, amongst others, a large proton accelerator facility since more than 30 years. In two cyclotrons, protons are accelerated to high speeds and then guided along roughly 100 m of beam line to three different target stations to produce secondary particles like mesons and neutrons for experiments and a separately beam line for UCN. The protons induce spallation processes in the target materials, and also at other beam loss points along the way, with emission of protons, neutrons, hydrogen, tritium, helium, heavier fragments and fission processes. In particular the produced neutrons, due to their large penetration depth, will then interact also with the surrounding materials. These interactions of radiation with matter lead to activation and partly to contamination of machine components and the surrounding infrastructures. Maintenance, operation and decommissioning of installations generate inevitably substantial amounts of radioactive operational and dismantling waste like targets, magnets, collimators, shielding (concrete, steel) and of course secondary waste. To achieve an optimal waste management strategy for interim storage or final disposal, radioactive waste has to be characterized, sorted and treated. This strategy is based on radiation protection demands, raw waste properties (size, material, etc.), and requirements to reduce the volume of waste, mainly for legal and economical reasons. In addition, the radiological limitations for transportation of the waste packages to a future disposal site have to be taken into account, as well as special regulatory demands. The characterization is a task of the waste producer. The conditioning processes and quality checks for radioactive waste packages are part of an accredited waste management process of PSI, especially of the Section Dismantling and Waste Management. Strictly proven and accepted methods needed to be developed and enhanced for safe treatment, transport, conditioning and storage. But in the field of waste from research activities, individual and new solutions have to be found in an increasingly growing administrative environment. Furthermore, a wide variety of components, with a really large inventory of radioactive nuclides, has to be handled. And there are always surprising challenges concerning the unusual materials or the nuclide inventory. In case of the operational and dismantling radioactive accelerator waste, the existing conditioning methods are in the process of a continuous enhancement - technically and administratively. The existing authorized specifications of conditioning processes have to be extended to optimize and fully describe the treatment of the inevitably occurring radioactive waste from the accelerator facility. Additional challenges are the changes with time concerning the legal and regulatory requirements - or do we have to consider it as business as usual? This paper gives an overview of the current practices in radioactive waste management and decommissioning of the existing operational accelerator waste. (authors)

  5. Gas Cylinder Storage and Handling Serious accidents can result from the misuse, abuse, or mishandling of compressed gas

    E-Print Network [OSTI]

    de Lijser, Peter

    Gas Cylinder Storage and Handling Serious accidents can result from the misuse, abuse, or mishandling of compressed gas cylinders. Safe procedures for their use are as follows: · All compressed gas combustible material. · Keep cylinders out of the direct sun and do not allow them to be overheated. · Gas

  6. EXHIBITION INSTALLATION AND DISMANTLING Item Handling and Housing

    E-Print Network [OSTI]

    Mathis, Wayne N.

    EXHIBITION INSTALLATION AND DISMANTLING Item Handling and Housing A. For general handling's and Don'ts. B. For examples of housing options and alternatives for paper artifacts, see Housing and Environment Options for Display, Housing and Environment Options for Storage, or consult a conservator. 1. All

  7. Measurement of Exception-Handling Code: An Exploratory Study

    E-Print Network [OSTI]

    Power, James

    Measurement of Exception-Handling Code: An Exploratory Study Keith ´O D´ulaigh, James F. Power Dept of exception- handling constructs, and study their change as the systems evolve through several versions the level of exception-related code in a system? · What kinds of graphs are most useful for visualising

  8. MVAPACK: A Complete Data Handling Package for NMR Metabolomics

    E-Print Network [OSTI]

    Powers, Robert

    in MVAPACK span the following general categories: data loading, preprocessing, pretreatment, modelingMVAPACK: A Complete Data Handling Package for NMR Metabolomics Bradley Worley and Robert Powers Supporting Information ABSTRACT: Data handling in the field of NMR metabolomics has historically been reliant

  9. Waxy crude oil handling in Nigeria; Practices, problems, and prospects

    SciTech Connect (OSTI)

    Ajienka, J.A.; Ikoku, C.U. (Dept. of Petroleum Engineering, Univ. of Port Harcourt, Choba, Port Harcourt (NG))

    1990-01-01T23:59:59.000Z

    With case studies, the practices, problems, and prospects of handling waxy crude oils in Nigeria are discussed. Using a rotational viscometer, the temperature dependence of rheological properties and thixotropy of these crudes were determined. Suggestions are given on how to improve handling practices. These suggestions include adequate screening and ranking of wax inhibitors, taking into account pour-point depression, viscosity, and yield value.

  10. HANDLING FRESH FISH REFRIGERATION OF FISH -PART 2

    E-Print Network [OSTI]

    HANDLING FRESH FISH REFRIGERATION OF FISH - PART 2 UNITED STATES DEPARTMENT OF THE INTERIOR FISH 428 Washington 25, D, C. December 1956 REFRIGERATION OF FISH - PART TWO HANDLING FRESH FISH By Charles in a series of five on "Refrigeration of Fish." Titles of the other four leaflets are: - 38 - 84 Part 1

  11. Automatic Continuous Commissioning of Measurement Instruments in Air Handling Units 

    E-Print Network [OSTI]

    Xiao, F.; Wang, S.

    2006-01-01T23:59:59.000Z

    component analysis (PCA), is adopted and modified to monitor the air handling process. Two PCA models are built corresponding to the heat balance and pressure-flow balance of the air-handling process. Sensor faults can be detected and isolated using the Q...

  12. H dli dHandling and Safety Training

    E-Print Network [OSTI]

    Farritor, Shane

    HendershotPam Hendershot Praxair Distribution Inc. Praxair Distribution Inc., Quality Department .Copyright © 2000, Praxair Technology, Inc. All rights reserved. .Rev. Date 04/24/2006-A 1 #12;Safe Handling Dangers Proper PPEp Proper Handling and Transporting of cryogen liquidscryogen liquids Praxair

  13. Mining API Error-Handling Specifications from Source Code

    E-Print Network [OSTI]

    Xie, Tao

    Mining API Error-Handling Specifications from Source Code Mithun Acharya and Tao Xie Department it difficult to mine error-handling specifications through manual inspection of source code. In this paper, we, without any user in- put. In our framework, we adapt a trace generation technique to distinguish

  14. Model Annex for Preparedness and Response to Radiological Transportati...

    Office of Environmental Management (EM)

    Response to Radiological Transportation Incidents.docx More Documents & Publications TEPP Model Needs Assessment Document First Responder Initial Response Procedure Hazardous...

  15. Review of the Hanford Tank Farms Radiological Controls Activity...

    Energy Savers [EERE]

    Independent Oversight Review of the Hanford Tank Farms Radiological Controls Activity-Level Implementation May 2011 December 2012 Office of Safety and Emergency Management...

  16. Nuclear and Radiological Field Training Center | Y-12 National...

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

    during the Manhattan Project is now the Y-12 National Security Complex's Nuclear and Radiological Field Training Center - the only facility of its kind in the world. The...

  17. Recent Developments in Field Response for Mitigation of Radiological...

    Energy Savers [EERE]

    of Radiological Incidents Carlos Corredor*, Department of Energy; Charley Yu, Argonne National Labs Abstract: Since September 11, 2001, there has been a large effort by...

  18. Combining Radiography and Passive Measurements for Radiological Threat Detection in Cargo

    SciTech Connect (OSTI)

    Miller, Erin A.; White, Timothy A.; Jarman, Kenneth D.; Kouzes, Richard T.; Kulisek, Jonathan A.; Robinson, Sean M.; Scherrer, Charles; Wittman, Richard S.

    2012-12-01T23:59:59.000Z

    Abstract Radiography is widely understood to provide information complimentary to passive detection: while not directly sensitive to radiological materials, radiography can reveal highly shielded regions which may mask a passive radiological signal. We present a method for combining radiographic and passive data which uses the radiograph to provide an estimate of scatter and attenuation for possible sources. This approach allows quantitative use of radiographic images without relying on image interpretation, and results in a probabilistic description of likely source locations and strengths. We present first results for this method for a simple modeled test case of a cargo container driving through a PVT portal. With this inversion approach, we address criteria for an integrated passive and radiographic screening system and how detection of SNM threats might be improved in such a system.

  19. An aerial radiological survey of the Central Savannah River Site, Aiken, South Carolina

    SciTech Connect (OSTI)

    Feimster, E.L.

    1991-09-01T23:59:59.000Z

    An aerial radiological survey was conducted over a 194-square- kilometer (75-square-mile) area encompassing the central portion of the Savannah River Site (SRS). The survey was flown during February 10--27, 1987. These radiological measurements were used as baseline data for the central area and for determining the extent of man-made radionuclide distribution. Previous SRS surveys included small portions of the area; the 1987 survey was covered during the site- wide survey conducted in 1979. Man-made radionuclides (including cobalt-60, cesium-137, protactinium-234m, and elevated levels of uranium-238 progeny) that were detected during the survey were typical of those produced by the reactor operations and material processing activities being conducted in the area. The natural terrestrial radiation levels were consistent with those measured during prior surveys of other SRS areas. 1 refs., 4 figs.

  20. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    SciTech Connect (OSTI)

    Barnett, J. M.; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Ted M.; Rhoads, Kathleen

    2010-05-25T23:59:59.000Z

    This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs. Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. Radiological emissions at the PNNL Site result from Physical Sciences Facility (PSF) major emissions units. A team was established to determine how the PNNL Site would meet federal regulations and address guidelines developed to monitor and estimate offsite air emissions of radioactive materials. The result is a program that monitors the impact to the public from the PNNL Site.

  1. Assessment of Chemical and Radiological Vulnerabilities

    SciTech Connect (OSTI)

    SETH, S.S.

    2000-05-17T23:59:59.000Z

    Following the May 14, 1997 chemical explosion at Hanford's Plutonium Reclamation Facility, the Department of Energy Richland Operations Office and its prime contractor, Fluor Hanford, Inc., completed an extensive assessment to identify and address chemical and radiological safety vulnerabilities at all facilities under the Project Hanford Management Contract. This was a challenging undertaking because of the immense size of the problem, unique technical issues, and competing priorities. This paper focuses on the assessment process, including the criteria and methodology for data collection, evaluation, and risk-based scoring. It does not provide details on the facility-specific results and corrective actions, but discusses the approach taken to address the identified vulnerabilities.

  2. ORISE: Radiological Assessment and Monitoring System (RAMS)

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated CodesTransparencyDOENurse TriageInternational TrainingRadiological

  3. ALARA Center of Technology promotes good radiological work practices at Hanford

    SciTech Connect (OSTI)

    Waggoner, L.O., Westinghouse Hanford, Richland, WA

    1997-10-31T23:59:59.000Z

    The central Radiological Control Organization, originally under the previous Management and Operations contractor (Westinghouse Hanford Company) decided that a significant improvement in ALARA implementation would result if examples of engineered controls used for radiological work were assembled in one location to provide a ``showcase`` for workers and managers. The facility would be named the ALARA Center of Technology (ACT) and would include the latest technologies used to accomplish radiological work, as well as proven techniques, tools, and equipment. A location for the Center was selected in the 200 East Area of Hanford in a central location to be easily accessible to all facilities and contractors. Since there was little money available for this project, a decision was made to contact several vendors and request loans of their tools, equipment, and materials. In return, the center would help market products on site and assist with product demonstrations when the vendors visited Hanford. Out of 28 vendors originally contacted, 16 responded with offers to loan products. This included a containment tent, several glove bags, BEPA filtered vacuum cleaners, portable ventilation systems, fixatives, temporary shielding, pumps, and several special tools. Vendors who could not provide products sent videos and brochures. Westinghouse Hanford Company began using the ACT in June 1996. Fluor Daniel Hanford, Inc., the present Management and Integrating Contractor for the Hanford Site, held the formal opening ceremony of the ALARA Center of Technology on October 1, 1996. The Center now has about 1200 ft{sup 2} of floor space fi Iled with tools, equipment and material used to perform radiological work.

  4. Infrastructure to support ultra high throughput biodosimetry screening after a radiological event

    E-Print Network [OSTI]

    Brenner, David Jonathan

    GUY GARTY1 , ANDREW KARAM2 , & DAVID J. BRENNER3 1 Radiological Research Accelerator Facility, Radiological Research Accelerator Facility, Nevis Laboratories, Columbia UniverInfrastructure to support ultra high throughput biodosimetry screening after a radiological event

  5. Intelligent Sensor Management in Nuclear Searches and Radiological Surveys A.V. Klimenko1

    E-Print Network [OSTI]

    Tanner, Herbert G.

    Intelligent Sensor Management in Nuclear Searches and Radiological Surveys A.V. Klimenko1 , W developed intelligent sensor management strategies for nuclear search and radiological surveys positives. RADIATION FIELD MODEL The present approach to the radiological survey and nuclear search

  6. Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering

    E-Print Network [OSTI]

    Ma, Yi

    Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering University of Illinois at Urbana-Champaign The Department of Nuclear, Plasma, and Radiological Engineering-qualified candidates with background in areas related to reactor power engineering and other nuclear applications

  7. Cefas contract report MLA/2012/00454 Radiological Assessment of

    E-Print Network [OSTI]

    Cefas contract report MLA/2012/00454 Radiological Assessment of Dredging Application for Heysham. Smedley Issue date: February 2013 #12; #12; RADIOLOGICAL ASSESSMENT OF DREDGING APPLICATION a MCAA licensing application to carry out a dredging program involving the disposal at sea of 198

  8. FRMAC Interactions During a Radiological or Nuclear Event

    SciTech Connect (OSTI)

    Wong, C T

    2011-01-27T23:59:59.000Z

    During a radiological or nuclear event of national significance the Federal Radiological Emergency Monitoring and Assessment Center (FRMAC) assists federal, state, tribal, and local authorities by providing timely, high-quality predictions, measurements, analyses and assessments to promote efficient and effective emergency response for protection of the public and the environment from the consequences of such an event.

  9. APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES 1998 SITE ENVIRONMENTAL REPORTB-1

    E-Print Network [OSTI]

    APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES 1998 SITE ENVIRONMENTAL REPORTB-1 APPENDIX B Radiological Data Methodologies 1. DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY Dispersion of airborne and distance. Facility-specific radionuclide release rates (in Ci per year) were also used. All annual site

  10. C-1 2003 SITE ENVIRONMENTAL REPORT Radiological Data Methodologies

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2003 SITE ENVIRONMENTAL REPORT APPENDIX C Radiological Data Methodologies DOSE CALCULATION to calculate annual disper- sions for the midpoint of a given sector and distance. Facility Protection Agency Exposure Factors Handbook (EPA 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur

  11. healthcare.utah.edu/radiology What is Nuclear Medicine?

    E-Print Network [OSTI]

    Feschotte, Cedric

    expensive diagnostic tests or surgery. Tissues such as intestines, muscles, and blood vessels are difficulthealthcare.utah.edu/radiology Radiology What is Nuclear Medicine? Nuclear Medicine is a specialized to visualize on a standard X-ray. In Nuclear Medicine, a radioactive tracer is used so the tissue is seen more

  12. Studies and research concerning BNFP: cask handling equipment standardization

    SciTech Connect (OSTI)

    McCreery, Paul N.

    1980-10-01T23:59:59.000Z

    This report covers the activities of one of the sub-tasks within the Spent LWR Fuel Transportation Receiving, Handling, and Storage program. The sub-task is identified as Cask Handling Equipment Standardization. The objective of the sub-task specifies: investigate and identify opportunities for standardization of cask interface equipment. This study will examine the potential benefits of standardized yokes, decontamination barriers and special tools, and, to the extent feasible, standardized methods and software for handling the variety of casks presently available in the US fleet. The result of the investigations is a compilation of reports that are related by their common goal of reducing cask turnaround time.

  13. Handling effluent from nuclear thermal propulsion system ground tests

    SciTech Connect (OSTI)

    Shipers, L.R.; Allen, G.C.

    1992-09-09T23:59:59.000Z

    A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the different methods to handle effluent from nuclear thermal propulsion system ground tests.

  14. Nondestructive assay and nondestructive examination of remote-handled transuranic waste at the ORNL waste handling and packaging plant

    SciTech Connect (OSTI)

    Schultz, F.J.; Caldwell, J.T. (Oak Ridge National Lab., TN (USA); Pajarito Scientific Corp. (USA))

    1989-01-01T23:59:59.000Z

    The purpose of this investigation is to examine the use of an electron linear accelerator (LINAC) in the performance of nondestructive assay (NDA) and nondestructive examination (NDE) measurements of remote-handled transuranic wastes. The system will be used to perform waste characterization and certification activities at the Oak Ridge National Laboratory's proposed Waste Handling and Packaging Plant. The NDA and NDE technologies which were developed for contact-handled wastes are inadequate to perform such measurements on high gamma and neutron dose-rate wastes. A single LINAC will provide the interrogating fluxes required for both NDA and NDE measurements of the wastes. 11 refs., 6 figs.

  15. An Integrated Air Handling Unit System for Large Commercial Buildings

    E-Print Network [OSTI]

    Song, L.; Liu, M.

    2001-01-01T23:59:59.000Z

    This paper presents an integrated air handling unit system (OAHU) for large commercial buildings. The system introduces outside air into the interior section and circulates the return air to the exterior section. Detailed analytical models...

  16. Thermal decomposition study of hydroxylamine nitrate during storage and handling 

    E-Print Network [OSTI]

    Zhang, Chuanji

    2007-09-17T23:59:59.000Z

    decomposition behavior under various conditions and proposed isothermal aging testing and kinetic-based simulation to determine safety boundaries for HAN storage and handling. Specifically, HAN decomposition in the presence of glass, titanium, stainless steel...

  17. air handling unit: Topics by E-print Network

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

    case of fans, or indirectly, in the case of heat exchangers, which impose loads on the chiller and boiler plant. Air-handling units can comprise a myriad of subsystems (fans,...

  18. air handling units: Topics by E-print Network

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

    case of fans, or indirectly, in the case of heat exchangers, which impose loads on the chiller and boiler plant. Air-handling units can comprise a myriad of subsystems (fans,...

  19. T-625: Opera Frameset Handling Memory Corruption Vulnerability

    Broader source: Energy.gov [DOE]

    The vulnerability is caused due to an error when handling certain frameset constructs during page unloading and can be exploited to corrupt memory via a specially crafted web page.

  20. Microsoft Word - remote handled waste comment extension.doc

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

    extends public comment period on the Remote-handled Waste Disposition Project Environmental Assessment Jan. 26, 2009 Media contact: Brad Bugger, (208) 526-0833 In response to a...

  1. Thermal decomposition study of hydroxylamine nitrate during storage and handling

    E-Print Network [OSTI]

    Zhang, Chuanji

    2007-09-17T23:59:59.000Z

    Hydroxylamine nitrate (HAN), an important agent for the nuclear industry and the U.S. Army, has been involved in several costly incidents. To prevent similar incidents, the study of HAN safe storage and handling boundary has become extremely...

  2. HANDLING UNCERTAINTY IN PRODUCTION ACTIVITY CONTROL USING PROACTIVE SIMULATION

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    HANDLING UNCERTAINTY IN PRODUCTION ACTIVITY CONTROL USING PROACTIVE SIMULATION Olivier CARDIN, Production Control, Manufacturing Systems, Proactive, Real-time. 1. INTRODUCTION In today's complex of a product. Real-word planning and scheduling problems are generally complex, constrained and multi

  3. WIPP Remote Handled Waste Facility: Performance Dry Run Operations

    SciTech Connect (OSTI)

    Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

    2003-02-24T23:59:59.000Z

    The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

  4. Radiological assessments for the National Ignition Facility

    SciTech Connect (OSTI)

    Hong, Kou-John; Lazaro, M.A.

    1996-08-01T23:59:59.000Z

    The potential radiological impacts of the National Ignition Facility (NIF), a proposed facility for fusion ignition and high energy density experiments, were assessed for five candidate sites to assist in site selection. The GENII computer program was used to model releases of radionuclides during normal NIF operations and a postulated accident and to calculate radiation doses to the public. Health risks were estimated by converting the estimated doses into health effects using a standard cancer fatality risk factor. The greatest calculated radiation dose was less than one thousandth of a percent of the dose received from natural background radiation; no cancer fatalities would be expected to occur in the public as the result of normal operations. The highest dose conservatively estimated to result from a postulated accident could lead to one in one million risk of cancer.

  5. Recovery from chemical, biological, and radiological incidents :

    SciTech Connect (OSTI)

    Franco, David Oliver; Yang, Lynn I.; Hammer, Ann E.

    2012-06-01T23:59:59.000Z

    To restore regional lifeline services and economic activity as quickly as possible after a chemical, biological or radiological incident, emergency planners and managers will need to prioritize critical infrastructure across many sectors for restoration. In parallel, state and local governments will need to identify and implement measures to promote reoccupation and economy recovery in the region. This document provides guidance on predisaster planning for two of the National Disaster Recovery Framework Recovery Support Functions: Infrastructure Systems and Economic Recovery. It identifies key considerations for infrastructure restoration, outlines a process for prioritizing critical infrastructure for restoration, and identifies critical considerations for promoting regional economic recovery following a widearea disaster. Its goal is to equip members of the emergency preparedness community to systematically prioritize critical infrastructure for restoration, and to develop effective economic recovery plans in preparation for a widearea CBR disaster.

  6. Southern State Radiological Transportation Emergency Response Training Course Summary

    SciTech Connect (OSTI)

    Not Available

    1990-09-01T23:59:59.000Z

    The Southern States Energy Board (SSEB) is an interstate compact organization that serves 16 states and the commonwealth of Puerto Rico with information and analysis in energy and environmental matters. Nuclear waste management is a topic that has garnered considerable attention in the SSEB region in the last several years. Since 1985, SSEB has received support from the US Department of Energy for the regional analysis of high-level radioactive waste transportation issues. In the performance of its work in this area, SSEB formed the Advisory Committee on High-Level Radioactive Materials Transportation, which comprises representatives from impacted states and tribes. SSEB meets with the committee semi-annually to provide issue updates to members and to solicit their views on activities impacting their respective states. Among the waste transportation issues considered by SSEB and the committee are shipment routing, the impacts of monitored retrievable storage, state liability in the event of an accident and emergency preparedness and response. This document addresses the latter by describing the radiological emergency response training courses and programs of the southern states, as well as federal courses available outside the southern region.

  7. Plutonium stabilization and handling (PuSH)

    SciTech Connect (OSTI)

    Weiss, E.V.

    1997-01-23T23:59:59.000Z

    This Functional Design Criteria (FDC) addresses construction 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 for up to fifty years. The major sections of the project are: site preparation; SPS Procurement, Installation, and Testing; storage vault modification; and characterization equipment additions. The SPS will be procured as part of a Department of Energy nationwide common procurement. Specific design crit1460eria for the SPS have been extracted from that contract and are contained in an appendix to this document.

  8. Recycling issues facing target and RTL materials of inertial fusion designs L. El-Guebaly, P. Wilson, M. Sawan, D. Henderson, A. Varuttamaseni,

    E-Print Network [OSTI]

    radiation environment at the target/RTL fabrication facility. In this study, we estimated the target hohlraum wall and RTL materials, explored the radiological issues of the recycled materials, evaluated and Z-pinch recycling processes. The next section addresses the radiological criteria that have been

  9. Conceptual design report, plutonium stabilization and handling,project W-460

    SciTech Connect (OSTI)

    Weiss, E.V.

    1997-03-06T23:59:59.000Z

    Project W-460, Plutonium Stabilization and Handling, 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 for up to fifty years. This Conceptual Design Report (CDR) provides conceptual design details for the vault modification, site preparation and site interface with the purchased SPS. Two concepts are described for vault configuration; acceleration of this phase of the project did not allow completion of analysis which would clearly identify a preferred approach.

  10. Porous Materials Porous Materials

    E-Print Network [OSTI]

    Berlin,Technische Universität

    1 Porous Materials x Porous Materials · Physical properties * Characteristic impedance p = p 0 e -jk xa- = vej[ ] p x - j ; Zc= p ve = c ka 0k = c 1-j #12;2 Porous Materials · Specific acoustic impedance Porous Materials · Finite thickness ­ blocked p e + -jk (x-d)a p e - jk (x-d)a d x #12

  11. Atmospheric dispersion and the radiological consequences of normal airborne effluents from a nuclear power plant

    SciTech Connect (OSTI)

    Fang, D.; Yang, L. [Tsinghua Univ., Beijing (China); Sun, C.Z. [Suhou Nuclear Research Inst., Suzhou (China)

    1995-01-01T23:59:59.000Z

    The relationship between the consequences of the normal exhaust of radioactive materials in air from nuclear power plants and atmospheric dispersion is studied. Because the source terms of the exhaust from a nuclear power plant are relatively low and their radiological consequences are far less than the corresponding authoritative limits, the atmospheric dispersion models, their various modifications, and selections of relevant parameters have few effects on those consequences. In the environmental assessment and siting, the emphasis should not be placed on the consequence evaluation of routine exhaust of nuclear power plants, and the calculation of consequences of the exhaust and atmospheric field measurements should be appropriately, simplified. 12 refs., 5 figs., 7 tabs.

  12. Results of the radiological survey at Two Mile Creek, Tonawanda, New York (TNY002)

    SciTech Connect (OSTI)

    Murray, M.E.; Rodriguez, R.E.; Uziel, M.S.

    1997-08-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Two Mile Creek, Tonawanda, New York. The survey was performed in November 1991 and May 1996. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been transported into the creek. The survey included a surface gamma scan in accessible areas near the creek and the collection of soil, sediment, and core samples for radionuclide analyses. Survey results indicate that no significant material originating at the Linde plant is presently in the creek. Three of the 1991 soil sample locations on the creek bank and one near the lake contained slightly elevated concentrations of {sup 238}U with radionuclide distributions similar to that found in materials resulting from former processing activities at the Linde site.

  13. Results of radiological measurements taken in the Niagara Falls, New York, area (NF002)

    SciTech Connect (OSTI)

    Williams, J.K.; Berven, B.A.

    1986-11-01T23:59:59.000Z

    The results of a radiological survey of 100 elevated gamma radiation anomalies in the Niagara Falls, New York, area are presented. These radiation anomalies were identified by a mobile gamma scanning survey during the period October 3-16, 1984, and were recommended for an onsite survey to determine if the elevated levels of radiation may be related to the transportation of radioactive waste material to the Lake Ontario Ordnance Works for storage. In this survey, radiological measurements included outdoor gamma exposure rates at 1 m above the surface; outdoor gamma exposure rates at the surface, range of gamma exposure rates during scan; and uranium, radium, and thorium concentrations in biased surface soil samples. The results show 38 anomalies (35 located along Pletcher Road and 3 associated with other unreleated locations) were found to exceed Formerly Utilized Sites Remedial Action Program (FUSRAP) remedial action guidelines and were recommended for formal characterization surveys. (Since the time of this survey, remedial actions have been conducted on the 38 anomalies identified as exceeding FUSRAP guidelines, and the radioactive material above guidelines has been removed.) The remaining 62 anomalies are associated with asphalt driveways and parking lots, which used a phosphate slag material (previously identified as cyclowollastonite, synthetic CaSiO/sub 3/). This rocky-slag waste material was used for bedding under asphalt surfaces and in general gravel applications. Most of the contaminated soil and rock samples collected at the latter anomalies had approximately equal concentrations of /sup 226/Ra and /sup 238/U and, therefore, are not related to materials connected with the Niagara Falls Storage Site (NFSS), including material that was transported to the NFSS. 13 refs., 7 figs., 14 tabs.

  14. 618-10 Burial Ground USRADS radiological surveys

    SciTech Connect (OSTI)

    Wendling, M.

    1994-05-26T23:59:59.000Z

    This report summarizes and documents the results of the radiological surveys conducted from February 11 through February 17 and March 30, 1993 over the 618-10 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-10 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-10 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil.

  15. 618-11 Burial Ground USRADS radiological surveys

    SciTech Connect (OSTI)

    Wendling, M.A.

    1994-05-26T23:59:59.000Z

    This report summarizes and documents the results of the radiological surveys conducted from February 4 through February 10, 1993 over the 618-11 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-11 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-11 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil.

  16. Radiological Assistance Program | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    remains with the owner of the radioactive material. RAP team member surveying a vehicle Additionally, RAP provides emergency response training assistance to federal, state,...

  17. Arrival condition of spent fuel after storage, handling, and transportation

    SciTech Connect (OSTI)

    Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

    1982-11-01T23:59:59.000Z

    This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

  18. Great Lakes ports coal handling capacity and export coal potential

    SciTech Connect (OSTI)

    Ames, A.H. Jr.

    1981-02-01T23:59:59.000Z

    This study was developed to determine the competitive position of the Great Lakes Region coal-loading ports in relation to other US coastal ranges. Due to the congestion at some US Atlantic coastal ports US coal producers have indicated a need for alternative export routes, including the Great Lakes-St. Lawrence Seaway System. The study assesses the regions coal handling capacity and price competitiveness along with the opportunity for increased US flag vessel service. A number of appendices are included showing major coal producers, railroad marketing representatives, US vessel operators, and port handling capacities and throughput. A rate analysis is provided including coal price at the mine, rail rate to port, port handling charges, water transportation rates to western Europe, Great Lakes route versus the US Atlantic Coast ports.

  19. Remote-Handled Low Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2010-10-01T23:59:59.000Z

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  20. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, Aed M. (Augusta, GA); Wagner, David G. (Augusta, GA); Teese, Gregory D. (Aiken, SC)

    1994-01-01T23:59:59.000Z

    An apparatus for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm.

  1. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, A.M.; Wagner, D.G.; Teese, G.D.

    1994-06-28T23:59:59.000Z

    An apparatus is described for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm. 5 figures.

  2. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, A.M.; Ward, C.R.; Jones, J.D.; Mallet, W.R.; Harpring, L.J.; Collins, M.X.; Anderson, E.K.

    1999-08-10T23:59:59.000Z

    A mobile robotic system is described that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console. 4 figs.

  3. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, Aed M. (Dearborn, MI); Ward, Clyde R. (Aiken, SC); Jones, Joel D. (Aiken, SC); Mallet, William R. (Cowichan Bay, CA); Harpring, Larry J. (North Augusta, SC); Collins, Montenius X. (Blackville, SC); Anderson, Erin K. (Pleasanton, CA)

    1999-01-01T23:59:59.000Z

    A mobile robotic system that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console.

  4. A review of the radiological treatment

    SciTech Connect (OSTI)

    Mueller, C.J.; Folga, S.; Nabelssi, B.; Kohout, E.

    1996-07-01T23:59:59.000Z

    The Draft Waste Management Programmatic Environmental Impact Statement (WM PEIS) was released by the U.S. Department of Energy (DOE) for public comment on September 22, 1995. Prepared in accordance with the National Environmental Policy Act (NEPA), the Final WM PEIS is currently scheduled for release in late summer 1996. The Draft WM PEIS was published after about 3 years of effort to select and evaluated the best alternatives for treating, storing, and disposing of the 50-year legacy of radioactive and chemically hazardous wastes existing within the DOE complex. The evaluation examined the potential health and environmental impacts of integrated waste management alternatives for five categories of waste types at 54 DOE sites. A primary consideration as a potential source of human health impacts at all sites is that of radiological releases resulting from postulated accidents involving facilities used to treat radioactive wastes. This paper first provides a brief, updated summary of the approach used to define and perform treatment facility accident analyses in the Draft WM PEIS. It reviews the selection of dominant sequences for the major sites most affected by the preferred waste management alternatives and highlights the salient accident analysis results. Finally, it summarizes and addresses key public and state and federal agency comments relating to accident analysis that were received in the public comment process.

  5. Remote Handling Experiments with the MASCOT IV Servomanipulator at JET and Prospects of Enhancements

    E-Print Network [OSTI]

    Remote Handling Experiments with the MASCOT IV Servomanipulator at JET and Prospects of Enhancements

  6. Certification document for newly generated contact-handled transuranic waste

    SciTech Connect (OSTI)

    Box, W.D.; Setaro, J.

    1984-01-01T23:59:59.000Z

    The US Department of Energy has requested that all national laboratories handling defense waste develop and augment a program whereby all newly generated contact-handled transuranic (TRU) waste be contained, stored, and then shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in WIPP-DOE-114. The program described in this report delineates how Oak Ridge National Laboratory intends to comply with these requirements and lists the procedures used by each generator to ensure that their TRU wastes are certifiable for shipment to WIPP.

  7. METHODS FOR THE SAFE STORAGE, HANDLING, AND DISPOSAL OF PYROPHORIC LIQUIDS AND SOLIDS IN THE LABORATORY

    SciTech Connect (OSTI)

    Simmons, F.; Kuntamukkula, M.; Alnajjar, M.; Quigley, D.; Freshwater, D.; Bigger, S.

    2010-02-02T23:59:59.000Z

    Pyrophoric reagents represent an important class of reactants because they can participate in many different types of reactions. They are very useful in organic synthesis and in industrial applications. The Occupational Safety and Health Administration (OSHA) and the National Fire Protection Association (NFPA) define Pyrophorics as substances that will self-ignite in air at temperatures of 130 F (54.4 C) or less. However, the U.S. Department of Transportation (DOT) uses criteria different from the auto-ignition temperature criterion. The DOT defines a pyrophoric material as a liquid or solid that, even in small quantities and without an external ignition source, can ignite within five minutes after coming in contact with air when tested according to the United Nations Manual of Tests and Criteria. The Environmental Protection Agency has adopted the DOT definition. Regardless of which definition is used, oxidation of the pyrophoric reagents by oxygen or exothermic reactions with moisture in the air (resulting in the generation of a flammable gas such as hydrogen) is so rapid that ignition occurs spontaneously. Due to the inherent nature of pyrophoric substances to ignite spontaneously upon exposure to air, special precautions must be taken to ensure their safe handling and use. Pyrophoric gases (such as diborane, dichloroborane, phosphine, etc.) are typically the easiest class of pyrophoric substances to handle since the gas can be plumbed directly to the application and used remotely. Pyrophoric solids and liquids, however, require the user to physically manipulate them when transferring them from one container to another. Failure to follow proper safety precautions could result in serious injury or unintended consequences to laboratory personnel. Because of this danger, pyrophorics should be handled only by experienced personnel. Users with limited experience must be trained on how to handle pyrophoric reagents and consult with a knowledgeable staff member prior to performing the experimental task. The purpose of this article is three fold: (1) to provide guidelines and general safety precautions to avoid accidents, (2) describe proper techniques on how to successfully handle, store, and dispose of pyrophoric liquids and solids, and (3) illustrate best practices for working with this class of reactants in a laboratory environment.

  8. Radiological and Clinical Pneumonitis After Stereotactic Lung Radiotherapy: A Matched Analysis of Three-Dimensional Conformal and Volumetric-modulated Arc Therapy Techniques

    SciTech Connect (OSTI)

    Palma, David A., E-mail: d.palma@vumc.n [Department of Radiation Oncology, VU Medical Center, Amsterdam (Netherlands); Senan, Suresh; Haasbeek, Cornelis J.A.; Verbakel, Wilko F.A.R. [Department of Radiation Oncology, VU Medical Center, Amsterdam (Netherlands); Vincent, Andrew [Department of Biometrics, Netherlands Cancer Institute, Amsterdam (Netherlands); Lagerwaard, Frank [Department of Radiation Oncology, VU Medical Center, Amsterdam (Netherlands)

    2011-06-01T23:59:59.000Z

    Purpose: Lung fibrosis is common after stereotactic body radiotherapy (SBRT) for lung tumors, but the influence of treatment technique on rates of clinical and radiological pneumonitis is not well described. After implementing volumetric modulated arc therapy (RapidArc [RA]; Varian Medical Systems, Palo Alto, CA) for SBRT, we scored the early pulmonary changes seen with arc and conventional three-dimensional SBRT (3D-CRT). Methods and Materials: Twenty-five SBRT patients treated with RA were matched 1:2 with 50 SBRT patients treated with 3D-CRT. Dose fractionations were based on a risk-adapted strategy. Clinical pneumonitis was scored using Common Terminology Criteria for Adverse Events version 3.0. Acute radiological changes 3 months posttreatment were scored by three blinded observers. Relationships among treatment type, baseline factors, and outcomes were assessed using Spearman's correlation, Cochran-Mantel-Haenszel tests, and logistic regression. Results: The RA and 3D-CRT groups were well matched. Forty-three patients (57%) had radiological pneumonitis 3 months after treatment. Twenty-eight patients (37%) had computed tomography (CT) findings of patchy or diffuse consolidation, and 15 patients (20%) had ground-glass opacities only. Clinical pneumonitis was uncommon, and no differences were seen between 3D-CRT vs. RA patients in rates of grade 2/3 clinical pneumonitis (6% vs. 4%, respectively; p = 0.99), moderate/severe radiological changes (24% vs. 36%, respectively, p = 0.28), or patterns of CT changes (p = 0.47). Radiological severity scores were associated with larger planning target volumes (p = 0.09) and extended fractionation (p = 0.03). Conclusions: Radiological changes after lung SBRT are common with both approaches, but no differences in early clinical or radiological findings were observed after RA. Longer follow-up will be required to exclude late changes.

  9. Design package for fuel retrieval system fuel handling tool modification

    SciTech Connect (OSTI)

    TEDESCHI, D.J.

    1998-11-09T23:59:59.000Z

    This is a design package that contains the details for a modification to a tool used for moving fuel elements during loading of MCO Fuel Baskets for the Fuel Retrieval System. The tool is called the fuel handling tool (or stinger). This document contains requirements, development design information, tests, and test reports.

  10. Design package for fuel retrieval system fuel handling tool modification

    SciTech Connect (OSTI)

    TEDESCHI, D.J.

    1999-03-17T23:59:59.000Z

    This is a design package that contains the details for a modification to a tool used for moving fuel elements during loading of MCO Fuel Baskets for the Fuel Retrieval System. The tool is called the fuel handling tool (or stinger). This document contains requirements, development design information, tests, and test reports.

  11. Design Package for Fuel Retrieval System Fuel Handling Tool Modification

    SciTech Connect (OSTI)

    TEDESCHI, D.J.

    2000-03-27T23:59:59.000Z

    This is a design package that contains the details for a modification to a tool used for moving fuel elements during loading of MCO Fuel Baskets for the Fuel Retrieval System. The tool is called the fuel handling tool (or stinger). This document contains requirements, development design information, tests, and test reports.

  12. Sample handling for kinetics and molecular assembly in flow cytometry

    SciTech Connect (OSTI)

    Sklar, L.A. [Los Alamos National Lab., NM (United States). National Flow Cytometry Resource]|[Univ. of New Mexico, Albuquerque, NM (United States). School of Medicine; Seamer, L.C.; Kuckuck, F.; Prossnitz, E.; Edwards, B. [Univ. of New Mexico, Albuquerque, NM (United States). School of Medicine; Posner, G. [Northern Arizona Univ., Flagstaff, AZ (United States). Dept. of Chemistry

    1998-07-01T23:59:59.000Z

    Flow cytometry discriminates particle associated fluorescence from the fluorescence of the surrounding medium. It permits assemblies of macromolecular complexes on beads or cells to be detected in real-time with precision and specificity. The authors have investigated two types of robust sample handling systems which provide sub-second resolution and high throughput: (1) mixers which use stepper-motor driven syringes to initiate chemical reactions in msec time frames; and (2) flow injection controllers with valves and automated syringes used in chemical process control. In the former system, the authors used fast valves to overcome the disparity between mixing 100 {micro}ls of sample in 100 msecs and delivering sample to a flow cytometer at 1 {micro}l/sec. Particles were detected within 100 msec after mixing, but turbulence was created which lasted for 1 sec after injection of the sample into the flow cytometer. They used optical criteria to discriminate particles which were out of alignment due to the turbulent flow. Complex sample handling protocols involving multiple mixing steps and sample dilution have also been achieved. With the latter system they were able to automate sample handling and delivery with intervals of a few seconds. The authors used a fluidic approach to defeat turbulence caused by sample introduction. By controlling both sheath and sample with individual syringes, the period of turbulence was reduced to {approximately} 200 msecs. Automated sample handling and sub-second resolution should permit broad analytical and diagnostic applications of flow cytometry.

  13. Certification Plan, low-level waste Hazardous Waste Handling Facility

    SciTech Connect (OSTI)

    Albert, R.

    1992-06-30T23:59:59.000Z

    The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

  14. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    SciTech Connect (OSTI)

    Mertz, G.

    1999-12-16T23:59:59.000Z

    This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

  15. South Carolina Farm Auditing Good Agricultural Practices and Good Handling

    E-Print Network [OSTI]

    Duchowski, Andrew T.

    South Carolina Farm Auditing Program Good Agricultural Practices and Good Handling Practices Audit of charts #12;Additional Requirements Signs must be in English and Spanish Good hygiene practices Water Verification Program Jack Dantzler Director of Inspections and Grading South Carolina Department of Agriculture

  16. STABILIZING LINEAR MPC WITH EFFICIENT PRIORITIZED INFEASIBILITY HANDLING

    E-Print Network [OSTI]

    Foss, Bjarne A.

    is illustrated on a simulated distillation column, and we present a novel stability result for this infeasibilitySTABILIZING LINEAR MPC WITH EFFICIENT PRIORITIZED INFEASIBILITY HANDLING Jostein Vada Olav predictive controller fails to compute a control input, all practical MPC implementations should havea means

  17. Challenges of Handling Storm Water Runoff Through Municipal Sewer Systems

    E-Print Network [OSTI]

    Illinois at Urbana-Champaign, University of

    cleaned and retained as a Best Management Practice (BMP). Receives only non-industrial storm water on storm water are leading municipalities to change permitting practices. As a result, facilitiesChallenges of Handling Storm Water Runoff Through Municipal Sewer Systems A South Carolina Case

  18. SOLIS Data Handling Christoph Keller, Steve Wampler, Carl Henney

    E-Print Network [OSTI]

    SOLIS Data Handling Christoph Keller, Steve Wampler, Carl Henney National Solar Observatory #12;May, 2003 FASR Data System Workshop 3 Science What causes the solar cycle? How is energy stored and released in the solar atmosphere? How does the solar radiative and non- radiative output vary? Vector

  19. Summary of the radiological assessment of the fuel cycle for a thorium-uranium carbide-fueled fast breeder reactor

    SciTech Connect (OSTI)

    Tennery, V.J.; Bomar, E.S.; Bond, W.D.; Meyer, H.R.; Morse, L.E.; Till, J.E.; Yalcintas, M.G.

    1980-01-01T23:59:59.000Z

    A large fraction of the potential fuel for nuclear power reactors employing fissionable materials exists as ores of thorium. In addition, certain characteristics of a fuel system based on breeding of the fissionable isotope {sup 233}U from thorium offer the possibility of a greater resistance to the diversion of fissionable material for the fabrication of nuclear weapons. This report consolidates into a single source the principal content of two previous reports which assess the radiological environmental impact of mining and milling of thorium ore and of the reprocessing and refabrication of spent FBR thorium-uranium carbide fuel.

  20. Radiological assessment of residues from uranium and other ore mining and processing - A precondition for decisions on remedial measures

    SciTech Connect (OSTI)

    Ettenhuber, E; Roehnsch, W. [Bundesamt fuer Strahlenschutz, Berlin (Germany); Biesold, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Colonge (Germany)

    1994-12-31T23:59:59.000Z

    In certain parts of Eastern Germany relics of uranium mining and milling as well as of traditional ore mining and processing may contribute to the environmental contamination and the radiation exposure of the public. Systematic investigations of the situation are the indispensable prerequisite for decisions upon the radiological relevance and remedial actions. In view of the large number and scattering of relics under consideration, a stepwise procedure with increasing intensity of investigation was developed to solve the task effectively and in an appropriate time. For the radiological evaluation following the steps of investigation generic criteria were derived. They are based on a primary reference dose of level (1 mSv/year) and on measureable radioactivity quantities recommend by the German Commission on Radiological Protection for unrestricted/restricted release of contaminated grounds. Applying the criteria established for the verification (gamma dose rate, volume of disposed material, area affected by waste materials) the investigations led to the result that no more than 30% of the objects of former mining have to be classified as {open_quotes}possibly relevant{close_quotes} and have to be investigated further on.

  1. Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

    SciTech Connect (OSTI)

    Not Available

    1993-10-01T23:59:59.000Z

    The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 [Public Law (PL) 95-6041]. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. The remedial action at the processing site will be conducted to remove the tailings and contaminated materials to meet the EPA bulk soil cleanup standards for surface and subsurface soils. The site areas disturbed by remedial action excavation will be either contoured or backfilled with radiologically uncontaminated soil and contoured to restore the site. The final contours will produce a final surface grade that will create positive drainage from the site.

  2. Unwanted Materials and Equipment All unwanted materials and equipment must go through Salvage (x2329) for disposal or reuse.

    E-Print Network [OSTI]

    Wechsler, Risa H.

    Unwanted Materials and Equipment All unwanted materials and equipment must go through Salvage (x.stanford.edu/main/propertyforms.asp) Some items may require a Radiation Survey or handling by Waste Management. Follow the directions with collecting empty moving boxes, and taking materials to trash or recycling containers. Submit a Service

  3. ASPECT Emergency Response Chemical and Radiological Mapping

    ScienceCinema (OSTI)

    LANL

    2009-09-01T23:59:59.000Z

    A unique airborne emergency response tool, ASPECT is a Los Alamos/U.S. Environmental Protection Agency project that can put chemical and radiological mapping tools in the air over an accident scene. The name ASPECT is an acronym for Airborne Spectral Photometric Environmental Collection Technology. Update, Sept. 19, 2008: Flying over storm-damaged refineries and chemical factories, a twin-engine plane carrying the ASPECT (Airborne Spectral Photometric Environmental Collection Technology) system has been on duty throughout the recent hurricanes that have swept the Florida and Gulf Coast areas. ASPECT is a project of the U.S. U.S. Environmental Protection Agencys National Decontamination Team. Los Alamos National Laboratory leads a science and technology program supporting the EPA and the ASPECT aircraft. Casting about with a combination of airborne photography and infrared spectroscopy, the highly instrumented plane provides emergency responders on the ground with a clear concept of where danger lies, and the nature of the sometimes-invisible plumes that could otherwise kill them. ASPECT is the nations only 24/7 emergency response aircraft with chemical plume mapping capability. Bob Kroutil of Bioscience Division is the project leader, and while he said the team has put in long hours, both on the ground and in the air, its a worthwhile effort. The plane flew over 320 targeted sites in four days, he noted. Prior to the deployment to the Gulf Coast, the plane had been monitoring the Democratic National Convention in Denver, Colorado. Los Alamos National Laboratory Divisions that are supporting ASPECT include, in addition to B-Division, CTN-5: Networking Engineering and IRM-CAS: Communication, Arts, and Services. Leslie Mansell, CTN-5, and Marilyn Pruitt, IRM-CAS, were recognized the the U.S. EPA for their outstanding support to the hurricane response of Gustav in Louisiana and Ike in Texas. The information from the data collected in the most recent event, Hurricane Ike, was sent to the EPA Region 6 Rapid Needs Assessment and the State of Texas Joint Field Office in Austin, Texas. It appears that though there is considerable damage in Galveston and Texas City, there are fewer chemical leaks than during either hurricanes Katrina or Rita. Specific information gathered from the data was reported out to the U.S. Environmental Protection Agency Headquarters, the Federal Emergency Management Agency, the Department of Homeland Security, and the State of Texas Emergency Management Agency.

  4. Hanford Radiological Protection Support Services Annual Report for 2000

    SciTech Connect (OSTI)

    Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A.; Piper, Roman K.

    2001-05-07T23:59:59.000Z

    During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.

  5. Test plan for K-Basin fuel handling tools

    SciTech Connect (OSTI)

    Bridges, A.E.

    1995-02-08T23:59:59.000Z

    The purpose of this document is to provide the test plan and procedures for the acceptance testing of the handling tools enveloped for the removal of an N-Reactor fuel element from its storage canister in the K-Basins storage pool and insertion into the Single fuel Element Can for subsequent shipment to a Hot Cell for examination. Examination of these N-Reactor fuel elements is part of the overall characterization effort. New hand tools were required since previous fuel movement has involved grasping the fuel in a horizontal position. The 305 Building Cold Test Facility will be used to conduct the acceptance testing of the Fuel Handling Tools. Upon completion of this acceptance testing and any subsequent training of operators, the tools will be transferred to the 105 KW Basin for installation and use.

  6. Fiber glass pipe effective for offshore water handling

    SciTech Connect (OSTI)

    Turnipseed, S.P. [Chevron Research and Technology Co., Richmond, CA (United States)

    1995-07-03T23:59:59.000Z

    Excellent corrosion resistance, weight savings, ease of construction, and reduced maintenance make fiber glass pipe attractive for water-handling service on offshore platforms. This article covers guidelines for fiber glass pipe installations and presents a number of case histories from the industry and Chevron Corp. Applications include seawater treatment, water injection, sewage and drains, deluge fire water systems, hose reel fire water, seawater cooling, produced water, and potable water. The paper gives usage guidelines.

  7. Health physics considerations in UF{sub 6} handling

    SciTech Connect (OSTI)

    Bailey, J.C. [Norway Assoicates, Inc., Oak Ridge, TN (United States)

    1991-12-31T23:59:59.000Z

    Uranium is a radioactive substance that emits alpha particles and very small amounts of gamma radiation. Its daughter products emit beta and gamma radiation. In uranium handling operations these are the radiations one must consider. This presentation will review the characteristics of the radiations, the isotopes from which they originate, the growth and decay of the uranium daughter products, and some specific health physics practices dictated by these factors.

  8. Liquid class predictor for liquid handling of complex mixtures

    DOE Patents [OSTI]

    Seglke, Brent W. (San Ramon, CA); Lekin, Timothy P. (Livermore, CA)

    2008-12-09T23:59:59.000Z

    A method of establishing liquid classes of complex mixtures for liquid handling equipment. The mixtures are composed of components and the equipment has equipment parameters. The first step comprises preparing a response curve for the components. The next step comprises using the response curve to prepare a response indicator for the mixtures. The next step comprises deriving a model that relates the components and the mixtures to establish the liquid classes.

  9. Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141

    SciTech Connect (OSTI)

    Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M. [VUJE, Inc., Okruzna 5, 918 64 Trnava (Slovakia); Michal, V. [IAEA, Wagramer Strasse 5, P.O.Box 100, A-1400 Vienna (Austria); Vargovcik, L. [ZTS VVU Kosice, Inc., Juzna Trieda 95, 041 24 Kosice (Slovakia)

    2012-07-01T23:59:59.000Z

    The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementation of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design of manipulator, their operation and control systems as well as tools of manipulators. Precise planning of decontamination and dismantling tasks is necessary for its successful performance by remotely controlled manipulator. The example of the heavy water evaporator demonstrates typical procedure for decommissioning of contaminated technological equipment by remotely controlled manipulators - planning of decommissioning tasks, preparatory tasks, modification of applied tools and design of specific supporting constructions for manipulator and finally decontamination and dismantling themselves. Due to the particularly demanding conditions in highly contaminated A1 NPP, a team of experts with special know-how in the field of decommissioning has grown up, and unique technological equipment enabling effective and safe work in environment with a high radiation level has been developed. (authors)

  10. Tonopah Test Range Air Monitoring: CY2012 Meteorological, Radiological, and Airborne Particulate Observations

    SciTech Connect (OSTI)

    Mizell, Steve A; Nikolich, George; Shadel, Craig; McCurdy, Greg; Miller, Julianne J

    2013-07-01T23:59:59.000Z

    In 1963, the Atomic Energy Commission (AEC), predecessor to the US Department of Energy (DOE), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range (NAFR)). Operation Roller Coaster consisted of four tests in which chemical explosions were detonated in the presence of nuclear devices to assess the dispersal of radionuclides and evaluate the effectiveness of storage structures to contain the ejected radionuclides. These tests resulted in dispersal of plutonium over the ground surface downwind of the test ground zero. Three tests, Clean Slate 1, 2, and 3, were conducted on the TTR in Cactus Flat; the fourth, Double Tracks, was conducted in Stonewall Flat on the NTTR. DOE is working to clean up and close all four sites. Substantial cleaned up has been accomplished at Double Tracks and Clean Slate 1. Cleanup of Clean Slate 2 and 3 is on the DOE planning horizon for some time in the next several years. The Desert Research Institute installed two monitoring stations, number 400 at the Sandia National Laboratories Range Operations Center and number 401 at Clean Slate 3, in 2008 and a third monitoring station, number 402 at Clean Slate 1, in 2011 to measure radiological, meteorological, and dust conditions. The primary objectives of the data collection and analysis effort are to (1) monitor the concentration of radiological parameters in dust particles suspended in air, (2) determine whether winds are re-distributing radionuclides or contaminated soil material, (3) evaluate the controlling meteorological conditions if wind transport is occurring, and (4) measure ancillary radiological, meteorological, and environmental parameters that might provide insight to the above assessments. The following observations are based on data collected during CY2012. The mean annual concentration of gross alpha and gross beta is highest at Station 400 and lowest at Station 401. This difference may be the result of using filter media at Station 400 with a smaller pore size than the media used at the other two stations. Average annual gamma exposure at Station 401 is slightly greater than at Station 400 and 402. Average annual gamma exposure at all three TTR stations are in the upper range to slightly higher than values reported for the CEMP stations surrounding the TTR. At higher wind speeds, the saltation counts are greater at Station 401 than at Station 402 while the suspended particulate concentrations are greater at Station 402 than at Statin 401. Although these observations seem counterintuitive, they are likely the result of differences in the soil material present at the two sites. Station 401 is located on an interfluve elevated above two adjacent drainage channels where the soil surface is likely to be composed of coarser material. Station 402 is located in finer sediments at the playa edge and is also subject to dust from a dirt road only 500 m to the north. During prolonged high wind events, suspended dust concentrations at Station 401 peaked with the initial winds then decreased whereas dust concentrations at Station 402 peaked with each peak in the wind speed. This likely reflects a limited PM10 source that is quickly expended at Station 401 relative to an abundant PM10 source at Station 402. In CY2013, to facilitate comparisons between radiological analyses of collected dust, the filter media at all three stations will be standardized. In addition, a sequence of samples will be collected at Station 400 using both types of filter media to enable development of a mathematical relationship between the results derived from the two filter types. Additionally, having acquired approximately four years of observations at Stations 400 and 401 and a year of observations at Station 402, a period-of-record analysis of the radiological and airborne dust conditions will be undertaken.

  11. C-1 2001 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2001 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES DOSE CALCULATION sector and distance. Facility-specificradionuclidereleaserates(incuries per year [Ci/yr]) were also used 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur in a random fashion

  12. West Valley facility spent fuel handling, storage, and shipping experience

    SciTech Connect (OSTI)

    Bailey, W.J.

    1990-11-01T23:59:59.000Z

    The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs.

  13. An analysis of repository waste-handling operations

    SciTech Connect (OSTI)

    Dennis, A.W.

    1990-09-01T23:59:59.000Z

    This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs.

  14. A Smartphone Controlled Handheld Microfluidic Liquid Handling System

    E-Print Network [OSTI]

    Li, Baichen; Guan, Allan; Dong, Quan; Ruan, Kangcheng; Hu, Ronggui; Li, Zhenyu

    2014-01-01T23:59:59.000Z

    Microfluidics and lab-on-a-chip technologies have made it possible to manipulate small volume liquids with unprecedented resolution, automation and integration. However, most current microfluidic systems still rely on bulky off-chip infrastructures such as compressed pressure sources, syringe pumps and computers to achieve complex liquid manipulation functions. Here, we present a handheld automated microfluidic liquid handling system controlled by a smartphone, which is enabled by combining elastomeric on-chip valves and a compact pneumatic system. As a demonstration, we show that the system can automatically perform all the liquid handling steps of a bead-based sandwich immunoassay on a multi-layer PDMS chip without any human intervention. The footprint of the system is 6 by 10.5 by 16.5cm, and the total weight is 829g including battery. Powered by a 12.8V 1500mAh Li battery, the system consumed 2.2W on average during the immunoassay and lasted for 8.7 hrs. This handheld microfluidic liquid handling platform...

  15. Radiological Survey Results for the Niagara Mohawk Right-of-Way, Tonawanda, New York (TNY004)

    SciTech Connect (OSTI)

    McKenzie, S.P.; Uziel, M.S.

    1998-11-01T23:59:59.000Z

    At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of a small portion of the Niagara Mohawk Power Corporation right-of-way in Tonawanda, New York. The purpose of the survey was to determine if radioactive residuals had migrated from or been redistributed onto the Niagara Mohawk right-of-way from the former Linde property to the west. The Linde Air Products Division of Union Carbide Corporation, Tonawanda New York, had used radioactive materials at that location for work performed under government contract from 1942 through 1948. The survey was performed in May 1996 in response to Formerly Utilized Sites Remedial Action Program (FUSRAP) requirements. These requirements dictate that the radiological status of certain vicinity properties shall be assessed and documented according to prescribed procedures prior to certification of the property for release for unrestricted use. Such release can only be granted if the property is found to be within current applicable authorized limits. The survey included a gamma scan of accessible areas and the collection and radionuclide analysis of soil samples from the portion of right-of-way located east of the former Linde plant site and north of the railway spur entrance gate. Results of the survey indicate that radioactive material probably originating from the Linde plant is located on the Niagara Mohawk right-of-way in the area surveyed. Surface gamma exposure rates were elevated above typical background levels. Four scattered surface soil samples exceeded DOE guideline values for {sup 238}U, and 8 of 13 surface soil samples exceeded DOE guideline values for {sup 226}Ra. The radionuclide distribution in these samples was similar to that found in materials resulting from former processing activities at the Linde site. It is recommended that the property be designated for remedial action by DOE.

  16. Radiological verification survey results at 14 Peck Ave., Pequannock, New Jersey (PJ001V)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Johnson, C.A.

    1995-05-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W. R. Grace facility. The property at 14 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil and debris samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 14 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

  17. Radiological verification survey results at 7 Peck Ave., Pequannock, New Jersey (PJ003V)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Johnson, C.A.

    1995-05-01T23:59:59.000Z

    The US Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W.R. Grace facility. The property at 7 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 7 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

  18. Radiological Survey Results for the R.P. Adams Company Property, Tonawanda, New York (TNY003)

    SciTech Connect (OSTI)

    Carrier, R.F.; McKenzie, S.P.; Uziel, M.S.

    1998-11-01T23:59:59.000Z

    At the request of the U.S. Department of Energy (DOE), a team horn Oak Ridge National Laboratory conducted a radiological survey of property belonging to the R P. Adarns Company, Inc., Tonawanda, New York. The survqy was performed in November 1995 and May and July 1996. The P-e of tie SUIWY was to determine if radioactive residuals had migrated, or been re&stribu@ from the former Linde property to the south onto the R P. Adams property. The Linde Air Products Division of Union Carbide Corporation, Toni~w~da, New York, had used radioactive materials at that location for work performed under government contract born 1942 through 1948. The survey was performed in response to Formerly Utilized Sites Remedial Action Program (FUSRAP) requirements. These requirements dictate that the radiological status of certain vicinity properties shall be assessed and docw.nented according to prescribed procedures prior to certification of the property for release for unrestricted use. Such release can only be granted if the property is found to be within current applicable authorized limits. The survey included a gamma scan of accessible areas in both the developed and the undeveloped portions of the property and the collection and radionuclide analysis of soil samples. A comparison of these data to the current DOE guidelines shows that all radionuclide concentrations and radioactivity levels found on the property are below the current guidelines. Therefore, this property should not be included in the FUSRAP program for remediation. xi

  19. Results of the radiological survey at 142 West Central Avenue, Maywood, New Jersey (MJ041)

    SciTech Connect (OSTI)

    Foley, R.D.; Crutcher, J.W.

    1989-06-01T23:59:59.000Z

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 142 West Central Avenue, Maywood, New Jersey (MJ041), was conducted during 1988. Results of the survey indicated scattered radiation or ''shine'' from a storage pile, located off the property, containing residual radioactive material. Lead-shielded measurements showed radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 4 refs., 8 figs., 3 tabs.

  20. Radiological considerations in the operation of the low-energy undulator test line (LEUTL).

    SciTech Connect (OSTI)

    Moe, H.J.

    1998-11-11T23:59:59.000Z

    The Low-Energy Undulator Test Line (LEUTL) is a facility that uses the existing APS linac to accelerate electrons up to an energy of 700 MeV. These electrons are transported through the Pm into a portion of the booster synchrotrons and on into the LEUTL main enclosure (MIL 97). Figure 1 shows the layout of the LEUTL building, which consists of an earth-benned concrete enclosure and an end-station building. The concrete enclosure houses the electron beamline, test undulator, and beam dump. This facility is about 51 m long and 3.66 m wide. Technical components and diagnostics for characterizing the undulator light are found in the end station. This building has about 111 m{sup 2} of floor space. This note deals with the radiological considerations of operations using electrons up to 700 MeV and at power levels up to the safety envelope of 1 kW. Previous radiological considerations for electron and positron operations in the linac, PAR, and synchrotrons have been addressed else-where (MOE 93a, 93b, and 93c). Much of the methodology discussed in the previous writeups, as well as in MOE 94, has been used in the computations in this note. The radiological aspects that are addressed include the following: prompt secondary radiation (bremsstrahlung, giant resonance neutrons, medium- and high-energy neutrons) produced by electrons interacting in a beam stop or in component structures; skyshine radiation, which produces a radiation field in nearby areas and at the nearest off-site location; radioactive gases produced by neutron irradiation of air in the vicinity of a particle loss site; noxious gases (ozone and others) produced in air by the escaping bremsstrahlung radiation that results from absorbing particles in the components; activation of the LEUTL components that results in a residual radiation field in the vicinity of these materials following shutdown; potential activation of water used for cooling the magnets and other purposes in the tunnel; and evaluation of the radiation fields due to escaping gas bremsstrahlung. Estimated dose rates have been computed or scaled (in the case of 400 MeV electrons) outside of the bermed tunnel, in Building 412, and in the Klystron Gallery for several modes of operation, including potential safety envelope beam power, normal beam power and MCI (maximum credible incident) conditions. Radiological aspects of shielding changes to the synchrotrons and their effect upon operations are addressed in MOE 97. No change in the safety envelope for synchrotrons operation was warranted.

  1. DEVELOPMENT OF A TAMPER RESISTANT/INDICATING AEROSOL COLLECTION SYSTEM FOR ENVIRONMENTAL SAMPLING AT BULK HANDLING FACILITIES

    SciTech Connect (OSTI)

    Sexton, L.

    2012-06-06T23:59:59.000Z

    Environmental sampling has become a key component of International Atomic Energy Agency (IAEA) safeguards approaches since its approval for use in 1996. Environmental sampling supports the IAEA's mission of drawing conclusions concerning the absence of undeclared nuclear material or nuclear activities in a Nation State. Swipe sampling is the most commonly used method for the collection of environmental samples from bulk handling facilities. However, augmenting swipe samples with an air monitoring system, which could continuously draw samples from the environment of bulk handling facilities, could improve the possibility of the detection of undeclared activities. Continuous sampling offers the opportunity to collect airborne materials before they settle onto surfaces which can be decontaminated, taken into existing duct work, filtered by plant ventilation, or escape via alternate pathways (i.e. drains, doors). Researchers at the Savannah River National Laboratory and Oak Ridge National Laboratory have been working to further develop an aerosol collection technology that could be installed at IAEA safeguarded bulk handling facilities. The addition of this technology may reduce the number of IAEA inspector visits required to effectively collect samples. The principal sample collection device is a patented Aerosol Contaminant Extractor (ACE) which utilizes electrostatic precipitation principles to deposit particulates onto selected substrates. Recent work has focused on comparing traditional swipe sampling to samples collected via an ACE system, and incorporating tamper resistant and tamper indicating (TRI) technologies into the ACE system. Development of a TRI-ACE system would allow collection of samples at uranium/plutonium bulk handling facilities in a manner that ensures sample integrity and could be an important addition to the international nuclear safeguards inspector's toolkit. This work was supported by the Next Generation Safeguards Initiative (NGSI), Office of Nonproliferation and International Security (NIS), National Nuclear Security Administration (NNSA).

  2. Anticipated dose to workers for Plutonium Stabilization and Handling at PFP Project W-460

    SciTech Connect (OSTI)

    LILLY, J.T.

    1999-11-30T23:59:59.000Z

    Report provides estimates of expected whole body and extremity radiological dose to workers conducting planned Pu stabilization and packaging operations at PFP.

  3. Algorithms and Automated Material Handling Systems Design for Stacking 3D Irregular Stone Pieces 

    E-Print Network [OSTI]

    Ko, Ming-Cheng

    2011-10-21T23:59:59.000Z

    one is based on the approximated weight of the stone. An automatic real-time stacking system including pneumatic devices, sensors, relays, a conveyor, a programmable logic controller, a robotic arm, and a vision system was developed for this study...

  4. Algorithms and Automated Material Handling Systems Design for Stacking 3D Irregular Stone Pieces

    E-Print Network [OSTI]

    Ko, Ming-Cheng

    2011-10-21T23:59:59.000Z

    , but also minimizes the irregular boundary in the unused container, and thus 6 helps for further application. In addition, the authors also make a comparison with Jakobs [11], whose heuristic and genetic algorithm does not consider placing...

  5. NFS File Handle Security Avishay Traeger, Abhishek Rai, Charles P. Wright, and Erez Zadok

    E-Print Network [OSTI]

    Zadok, Erez

    a file han- dle. When an NFS client performs an operation, it passes the file handle to the server, which decodes the file han- dle to determine what object the file handle refers to. Since NFS is a stateless

  6. Evaluation and improvement on external-hazard proof of JSFR fuel handling system

    SciTech Connect (OSTI)

    Katoh, A.; Chikazawa, Y. [Japan Atomic Energy Agency, 4002 Narita, O-arai-machi, Ibaraki-ken, 311-1393 (Japan); Uzawa, M. [Mitsubishi FBR Systems Inc. MFBR, 34-17, Jingumae 2-chome, Shibuya-ku, Tokyo 150-0001 (Japan)

    2012-07-01T23:59:59.000Z

    Responding to the the Fukushima Dai-ichi nuclear power plant (1F-NPP) accident, the earthquake and the tsunami proof of the fuel handling system (FHS) in Japan sodium-cooled fast reactor (JSFR) is studied. In the earthquake proof estimation, the margin of seismic resistance against the earthquake of the 1F-envelop condition and the sloshing behavior in the EVST is estimated. In terms of the tsunami proof, the scenario to lead fuel subassemblies into the stable cooling state and the potential of the cooling system is introduced in case of loss of the emergency power supply. As a result, it is clear that JSFR FHS originally could already be prepared to have the potential to prevent the release of radioactive material. (authors)

  7. Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1 DRAFT The radiological dose assessment assures stakeholders that BNL facilities and operations are in compliance with federal, state, and local regulations and the public is protected. The potential radiological dose to members of the public

  8. Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and BNL operations are in compliance with federal, state, and local regulations, and that the public is protected. The potential radiological dose

  9. Radiological Dose Assessment 8 2012 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2012 SITE ENVIRONMENTAL REPORT8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and BNL operations are in compliance with federal, state, and local regulations, and that the public is protected. The potential radiological dose

  10. Radiological Dose Assessment 8 2011 Site environmental report8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2011 Site environmental report8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and operations are in compliance with federal, state and local regulations, and that the public is protected. The potential radiological dose to members

  11. The RABiT: A Rapid Automated Biodosimetry Tool for radiological triage. II. Technological developments

    E-Print Network [OSTI]

    Yao, Y. Lawrence

    , & DAVID J. BRENNER3 1 Radiological Research Accelerator Facility, 2 Department of Mechanical EngineeringThe RABiT: A Rapid Automated Biodosimetry Tool for radiological triage. II. Technological, and 3 Center for Radiological Research, Columbia University, New York, NY, USA (Received 14 September

  12. RADTRAN3. Radioactive Material Transport Risk

    SciTech Connect (OSTI)

    Madsen, M.M.; Taylor, J.M.; Ostmeyer, R.M.; Reardon, P.C. [Sandia National Labs., Albuquerque, NM (United States)

    1986-02-01T23:59:59.000Z

    RADTRAN3 is a flexible analytical tool for calculating both the incident-free and accident impacts of transporting radioactive materials. The consequences from incident-free shipments are apportioned among eight population subgroups and can be calculated for several transport modes. The radiological accident risk (probability times consequence summed over all postulated accidents) is calculated in terms of early fatalities, early morbidities, latent cancer fatalities, genetic effects, and economic impacts. Groundshine, ingestion, inhalation, direct exposure, resuspension, and cloudshine dose pathways are modeled to calculate the radiological health risks from accidents. Economic impacts are evaluated based on costs for emergency response, cleanup, evacuation, income loss, and land use. RADTRAN3 can be applied to specific scenario evaluations (individual transport modes or specified combinations), to compare alternative modes or to evaluate generic radioactive material shipments. Unit-risk factors can easily be evaluated to aid in performing generic analyses when several options must be compared with the amount of travel as the only variable.

  13. An evaluation of current hazardous material management procedures for the Texas Department of Transportation 

    E-Print Network [OSTI]

    Lovell, Cheryl Alane

    1993-01-01T23:59:59.000Z

    with used motor oil, old asphalt, spent 26 solvents, abandoned materials on the right-of-way, and occasional spill materials. The district offices handle these same hazardous wastes, as well as, leftover paint, old batteries, and old or unused materials... of the state. A copy of this survey is included in Appendix A. Questions were asked concerning handling, storage, collection, and disposal procedures, as well as, questions concerning inventories, report filing, and spill response actions. The answers from...

  14. Dr. Thad M. Adams Materials Technology Section

    E-Print Network [OSTI]

    Dr. Thad M. Adams Materials Technology Section Savannah River National Laboratory DOE Hydrogen extraction/handling/separation/storage operations · Applied R&D provided by Savannah River National for Hydrogen Service #12;Hydrogen Technology at the SavannahHydrogen Technology at the Savannah River SiteRiver

  15. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Vakni, David

    . Carbon dioxide, dry chemical powder, or appropriate foam. FIREFIGHTING Protective Equipment: Wear self. Incompatible Materials: Absorbs carbon dioxide from air. SPECIAL REQUIREMENTS Handle and store under inert gas/Chemical Properties Appearance Physical State: Solid Color: White Form: Fine Property Value At Temperature or Pressure

  16. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2011 Research Using RARAF

    E-Print Network [OSTI]

    CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2011 1 Research Using RARAF For over a decade, many cell membrane contact. Both the Microbeam and the Track Segment Facilities continue to be utilized involved in radiation-induced bystander responses (Exp. 110). Using the Microbeam Facility, they observed

  17. Biological Treatment of Petroleum in Radiologically Contaminated Soil

    SciTech Connect (OSTI)

    BERRY, CHRISTOPHER

    2005-11-14T23:59:59.000Z

    This chapter describes ex situ bioremediation of the petroleum portion of radiologically co-contaminated soils using microorganisms isolated from a waste site and innovative bioreactor technology. Microorganisms first isolated and screened in the laboratory for bioremediation of petroleum were eventually used to treat soils in a bioreactor. The bioreactor treated soils contaminated with over 20,000 mg/kg total petroleum hydrocarbon and reduced the levels to less than 100 mg/kg in 22 months. After treatment, the soils were permanently disposed as low-level radiological waste. The petroleum and radiologically contaminated soil (PRCS) bioreactor operated using bioventing to control the supply of oxygen (air) to the soil being treated. The system treated 3.67 tons of PCRS amended with weathered compost, ammonium nitrate, fertilizer, and water. In addition, a consortium of microbes (patent pending) isolated at the Savannah River National Laboratory from a petroleum-contaminated site was added to the PRCS system. During operation, degradation of petroleum waste was accounted for through monitoring of carbon dioxide levels in the system effluent. The project demonstrated that co-contaminated soils could be successfully treated through bioventing and bioaugmentation to remove petroleum contamination to levels below 100 mg/kg while protecting workers and the environment from radiological contamination.

  18. Radiology utilizing a gas multiwire detector with resolution enhancement

    DOE Patents [OSTI]

    Majewski, Stanislaw (Grafton, VA); Majewski, Lucasz A. (Grafton, VA)

    1999-09-28T23:59:59.000Z

    This invention relates to a process and apparatus for obtaining filmless, radiological, digital images utilizing a gas multiwire detector. Resolution is enhanced through projection geometry. This invention further relates to imaging systems for X-ray examination of patients or objects, and is particularly suited for mammography.

  19. DOE Radiological Calibrations Intercomparison Program: Results of fiscal year 1987

    SciTech Connect (OSTI)

    Cummings, F.M.; McDonald, J.C.

    1988-06-01T23:59:59.000Z

    This report presents the FY 1987 results of the radiological calibrations intercomparison program. The intercomparison operation is discussed, and the equipment is described, particularly the instrument set, the beta source set, and relevant calculations. Solutions to problems and improvements in the program are suggested, and conclusions are then introduced. 9 refs., 3 figs., 8 tabs.

  20. www.medscape.com From Medscape Radiology > Viewpoints

    E-Print Network [OSTI]

    Jadvar, Hossein

    www.medscape.com From Medscape Radiology > Viewpoints Chest CT and Whole-Body 18F-FDG PET Are Cost study was to assess the cost-effectiveness of whole-body 18F- fluorodeoxyglucose positron emission California that involved 270 PET/CT scans, the incidence of metastatic disease occurring below the neck

  1. www.medscape.com From Medscape Radiology > Viewpoints

    E-Print Network [OSTI]

    Jadvar, Hossein

    www.medscape.com From Medscape Radiology > Viewpoints 18F-FDG PET/CT Findings and Circulating Tumor in 55 women who were undergoing systemic therapies for bone metastases from breast cancer. FDG PET/CT no relevant financial relationships. FDG PET/CT: A Role in Monitoring Bone Metastases in Breast Cancer

  2. COMMENTARY/COMMENTAIRE The radiological consequences of the Chernobyl

    E-Print Network [OSTI]

    Shlyakhter, Ilya

    COMMENTARY/COMMENTAIRE The radiological consequences of the Chernobyl accident The First­22 March 1996 Eric Voice Abstract: The human health consequences of the Chernobyl accident in 1986 have are discussed with particular focus on thyroid cancers and exposures to iodine-131. Key words: Chernobyl

  3. EA-1919: Recycle of Scrap Metals Originating from Radiological Areas

    Broader source: Energy.gov [DOE]

    This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.)

  4. Results of the radiological and beryllium verification survey at the Sacandaga Site, Glenville, New York (SY002V)

    SciTech Connect (OSTI)

    Foley, R.D.; Cottrell, W.D.; Johnson, C.A.

    1994-09-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent verification radiological and non-radioactive beryllium survey at the Sacandaga Site, located on Sacandaga Road, Glenville, New York following limited remediation of the site by Allwash of Syracuse, Inc. At the time of this survey, only building P was still standing. A small concrete structure at the east of the property had been demolished and the debris hauled away, leaving only a pit. The purpose of the survey, conducted between April and August 1993, was to confirm the success of the remedial actions performed to remove any beryllium concentrations or radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter indoors and outdoors, alpha and beta scans inside building P, and the collection of soil, dust and debris samples and smears for radionuclide and beryllium analyses. Results of the survey demonstrated that all radiological and beryllium measurements on the property were within applicable DOE guidelines. Based on all data collected. the Sacandaga Site, Glenville, New York, conforms to all applicable radiological and non-radioactive beryllium guidelines established for this site by DOE and approved by the State of New York.

  5. Results of the radiological and beryllium verification survey at the Peek Street Site, Schenectady, New York (SY001V)

    SciTech Connect (OSTI)

    Foley, R.D.; Johnson, C.A.; Carrier, R.F.; Allred, J.F.

    1994-10-01T23:59:59.000Z

    At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent verification radiological and non-radioactive beryllium survey at the Peek Street site, located at 425 Peek Street, Schenectady, New York. The purpose of the survey, conducted during 1993 and continuing through January 1994, was to confirm the success of the remedial actions performed to remove any beryllium concentrations or radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at one meter indoors and outdoors, alpha and beta scans inside the structure, and the collection of soil, dust and debris samples and smears for radionuclide and beryllium analyses. Results of the survey demonstrated that all radiological and beryllium measurements on the property were within applicable DOE guidelines. Based on all data collected, the industrial property at 425 Peek Street and the adjacent state-owned bike path in Schenectady, New York, conforms to all applicable radiological and non-radioactive beryllium guidelines established for this site by DOE and approved by the State of New York.

  6. Results of the radiological verification survey of the partial remediation at 90 Avenue C, Lodi, New Jersey (LJ079V)

    SciTech Connect (OSTI)

    Foley, R.D.; Johnson, C.A.

    1994-02-01T23:59:59.000Z

    The property at 90 Avenue C, Lodi, New Jersey is one of the vicinity properties of the former Maywood Chemical Works, Maywood, New Jersey designated for remedial action by the US Department of Energy (DOE). In July 1991, Bechtel National, Inc. performed a partial remedial action on this property. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey in July, 1991 at this site. The purpose of the verification survey was to ensure the effectiveness of remedial actions performed within FUSRAP and to confirm the site`s compliance with DOE guidelines. The radiological survey included surface gamma scans indoors and outdoors, ground-level beta-gamma measurements, and systematic and biased soil and material sampling. Results of the verification survey demonstrated that all radiological measurements on the portions of the property that had been remediated were within DOE guidelines. However, there still remains a portion of the property to be remediated that is not covered by this verification survey.

  7. Characteristics of fuel crud and its impact on storage, handling, and shipment of spent fuel. [Fuel crud

    SciTech Connect (OSTI)

    Hazelton, R.F.

    1987-09-01T23:59:59.000Z

    Corrosion products, called ''crud,'' form on out-of-reactor surfaces of nuclear reactor systems and are transported by reactor coolant to the core, where they deposit on external fuel-rod cladding surfaces and are activated by nuclear reactions. After discharge of spent fuel from a reactor, spallation of radioactive crud from the fuel rods could impact wet or dry storage operations, handling (including rod consolidation), and shipping. It is the purpose of this report to review earlier (1970s) and more recent (1980s) literature relating to crud, its characteristics, and any impact it has had on actual operations. Crud characteristics vary from reactor type to reactor type, reactor to reactor, fuel assembly to fuel assembly in a reactor, circumferentially and axially in an assembly, and from cycle to cycle for a specific facility. To characterize crud of pressurized-water (PWRs) and boiling-water reactors (BWRs), published information was reviewed on appearance, chemical composition, areal density and thickness, structure, adhesive strength, particle size, and radioactivity. Information was also collected on experience with crud during spent fuel wet storage, rod consolidation, transportation, and dry storage. From experience with wet storage, rod consolidation, transportation, and dry storage, it appears crud spallation can be managed effectively, posing no significant radiological problems. 44 refs., 11 figs.

  8. Results of the radiological survey of the Excelsior Steel Ball Company, Tonawanda, New York (TNY005)

    SciTech Connect (OSTI)

    McKenzie, S.P.; Brown, K.S.

    1998-07-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted two radiological surveys of property belonging to the Excelsior Steel Ball Company, which is surrounded on three sides by the former site of the Linde Uranium Refinery, Tonawanda, New York. The surveys were performed in September 1997 and February 1998. The purpose of the first survey was to determine if radioactive residuals were present from previous activities at the former Linde site. The Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had used radioactive materials at that location for work performed under government contract from 1942 through 1948. The purpose of the second survey was to collect additional biased samples from an area of the site where biased sample results showed slightly elevated levels of thorium-232.

  9. Remote-handled transuranic system assessment. Volume 1

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    This document identifies the necessary actions for addressing current questions concerning the safe and efficient disposal of remote-handled transuranic wastes that have been generated through Department of Energy activities. In addition, this document presents summaries of existing information and analyses regarding the potential alternatives for disposing of remote-handled (RH) transuranic (TRU) waste at the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP). A further discussion of DOE`s approach for addressing RH-TRU issues is contained in the document, Waste Isolation Pilot Plant Remote-Handled Transuranic Waste Disposal Strategy, DOE/WIPP-95-1090 (DOE, 1995a). Of this stored and projected inventory, approximately 30% can be characterized with current technology and subsequently certified to meet the waste acceptance criteria for disposal at WIPP; characterization of the remaining 70% will require the use of alternative techniques. At most of the generator sites, characterization equipment and facilities need to be procured in order for the sites to certify waste for shipment either to WIPP or to an interim site. If surface dose rates are too high, the use of non-invasive techniques such as non-destructive examination (NDE) and non-destructive assay (NDA) may be precluded. Characterization methods using NDA can be effectively used on RH-TRU wastes with surface dose rates of less than 1.0 rem/hr (neutron); NDE methods are effective on waste with surface dose rates of less than 10 rem/hr (gamma). The ability to use current NDE technology on waste with surface dose rates above 10 rem/hr will need to be demonstrated. Alternate characterization techniques, such as examination within a hot cell, could be used for the remaining waste; however, such techniques are labor intensive and would require additional effort to gather assay data. Improvements in characterization capabilities are being pursued through future technology development initiatives.

  10. SR-30 Soluble Support Material Safety Data Sheet 108454-0002

    E-Print Network [OSTI]

    Rollins, Andrew M.

    . HANDLING & STORAGE Handling Use good industrial hygiene practices. Provide adequate ventilation. Storage-irritating to skin. Ingestion No hazard in normal industrial use. Skin Absorption No absorption hazard in normal industrial use. 2011-04-27 Page 1 of 5 #12;SR-30 Soluble Support Material Safety Data Sheet 108454-0002 4

  11. Methods and Cost of Handling Texas Citrus, 1946-51.

    E-Print Network [OSTI]

    Sorensen, H. B.; Baker, C. K.

    1953-01-01T23:59:59.000Z

    Methods and Costs of Handling Texas Citrus TEXAS AGRICULTURAL EXPERIMENT STAT10 R. D. LEWIS. DIRECTOR, COLLEGE STATION. TEXAS DIGEST The citrus industry in Texas underwent considerable change during the 1946-51 period. 7 of production dropped... changes during this period although trends in the use of containers for fresh citrus showed the rise in popularity of consumer-size mesh bags. The increase in proportion of these bags was from 2 percent of the total to 13 percent for grapefruit and from...

  12. Fusion Potentials for G_k and Handle Squashing

    E-Print Network [OSTI]

    Michael Crescimanno

    1991-10-22T23:59:59.000Z

    Using Chern-Simons gauge theory, we show that the fusion ring of the conformal field theory G_k is isomorphic to P(u)/(\\del V), where V is a polynomial in u and (\\del V) is the ideal generated by the conditions \\del V=0. We also derive a residue-like formula for the correlation functions in the Chern-Simons theory thus providing a RCFT version of the residue formula for the TLG models. An operator that acts like the measure in the residue formula has the ionterpretation of a handle squashing operator and an explicit formula for this operator is given.

  13. Handbook for Handling, Storing, and Dispensing E85 | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are8COaBulkTransmissionSitingProcess.pdfGetec AG| OpenInformation Handbook for Handling, Storing, and Dispensing

  14. Laboratory to demolish excavation enclosures at Material Disposal Area B

    E-Print Network [OSTI]

    to hazardous and radiological contamination while excavating and packaging contaminated debris and soil from of a highly successful environmental cleanup project at Material Disposal Area B," said Ed Worth, federal project manager #12;- 2 - with the National Nuclear Security Administration's Los Alamos Site Office. "We

  15. The LINAC Coherent Light Source and Radiological Issues During the Commissioning

    SciTech Connect (OSTI)

    Mao, X.S.; Leitner, M.Santana; Vollaire, J.; /SLAC

    2010-08-26T23:59:59.000Z

    The Linac Coherent Light Source (LCLS) at SLAC National Accelerator Laboratory is the world's first X-ray free electron laser (XFEL). Pulses of x-ray laser light from LCLS will be many orders of magnitude brighter and several orders of magnitude shorter than what can be produced by other x-ray sources available in the world. These characteristics will enable frontier new science in many areas. This paper describes the LCLS beam parameters and lay-out. The general radiological issues during commissioning are presented, such as radiation dose rates and integrated doses outside the enclosure. Also, specific radiological issues related to X-ray free electron lasers are discussed. XFEL with high peak power will burn through high-Z materials. The X-ray beam needs to be blocked by stoppers when the downstream areas are occupied. LCLS stoppers feature a piece of boron carbide (B{sub 4}C), 10 mm thick. B{sub 4}C is one of the best materials since it has a low absorption coefficient for X-rays and a high melting temperature. Theoretical calculations indicate that the unfocused fluence of the LCLS XFEL beam should be about one order of magnitude below the damage threshold for bulk B{sub 4}C, for 830 eV FEL radiation. However, these calculations have not been tested experimentally and cannot be validated until LCLS begins providing 830 eV XFEL pulses. This paper describes the test plan for using the initial LCLS radiation to evaluate the survivability of B{sub 4}C and reports the preliminary results. Another major issue for LCLS is the potential radiation damage to the LCLS undulator magnets during operation. TLD dosimeters were installed along the LCLS undulators for each period of two or three weeks. This paper reports the integrated doses along the undulators with and without XFEL generation.

  16. Radiological surveys of properties in the Middlesex, New Jersey area. Final report

    SciTech Connect (OSTI)

    Leggett, R W; Haywood, F.F. Cottrell, W.D.

    1981-03-01T23:59:59.000Z

    Results of the radiological surveys conducted at three properties in the Middlesex, New Jersey area as well as one additional location downstream from the Middlesex Sampling Plant (Willow Lake), are presented. The survey revealed that the yard around the church rectory on Harris Avenue is contaminated with a /sup 226/Ra-bearing material, probably pitchblende ore from the former Middlesex Sampling Plant. The elevated /sup 226/Ra concentrations around and, to a lesser extent, underneath the rectory are leading to elevated /sup 222/Rn concentrations in air in the rectory and elevated alpha contamination levels (from radon daughters) on surfaces inside the rectory. External gamma radiation levels in the rectory yard are well above background levels, and beta-gamma dose rates at many points in the yard are above federal guidelines for the release of property for unrestricted use. The radiological survey of a parking lot at the Union Carbide plant in Bound Brook, New Jersey revealed that a nearly circular region of 50-ft diam in the lot showed above-background external gamma radiation levels. Two isolated spots within this region showed concentrations of uranium in soil above the licensable level stated in 10 CFR 40. Soil samples taken in the area of elevated gamma radiation levels generally showed nearly equal activities of /sup 226/Ra and /sup 238/U. The survey at the residences on William Street in Piscataway, revealed that the front yeard is generally contaminated from near the surface to a depth of 1.5 to 2.5 ft with /sup 226/Ra-bearing material, possibly pitchblende ore. The remainder of the yard shows scattered contaminaion. External gamma radiation levels inside the house are above the background level near some outside walls.

  17. Supplementary radiological and beryllium characterization of the facility at 425 Peek Street, Schenectady, New York

    SciTech Connect (OSTI)

    Foley, R.D.; Allred, J.F.; Carrier, R.F.

    1994-10-01T23:59:59.000Z

    At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a radiological survey of the Peek Street industrial facility, the adjacent state-owned bike path, and two nearby residential properties was conducted by Oak Ridge National Laboratory (ORNL) in November 1989. The results indicated small isolated areas that exceeded DOE guidelines. These areas totaled approximately 0.2 m{sup 2} of floor area and approximately 3 m{sup 2} of wall area inside the building, and two small areas totaling approximately 5 m{sup 2} outside the building. A small section of one of these areas extended beyond the fence on the east side of the industrial property onto the state-owned property. No residual radioactive material or elevated radiation levels were detected on any portion of the paved section of the bike path or the residential properties adjacent to the site. Because the elevated radiation levels were localized and limited in extent, any credible use scenario, including current use conditions, indicated that no significant radiation exposures would accrue to individuals frequenting the area. Samples were also analyzed for elemental beryllium since that material had formerly been used at the site. In conjunction with the planned remediation at the facility, a supplementary characterization survey was performed to further define the areas containing beryllium in excess of the identified guidelines. Additional radiological characterization of Ra-226, Th-232, and U-238 was also performed in areas that were largely inaccessible prior to the remediation efforts.

  18. Handling of Highly Radioactive Radiation Sources in a Hot Cell Using a Mechanically Driven Cell Crane - 13452

    SciTech Connect (OSTI)

    Klute, Stefan; Huber, Wolfgang-Bruno [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany)] [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany); Meyer, Franz [Nuclear Engineering Seibersdorf GmbH, 2444 Seibersdorf (Austria)] [Nuclear Engineering Seibersdorf GmbH, 2444 Seibersdorf (Austria)

    2013-07-01T23:59:59.000Z

    In 2010, Siempelkamp Nukleartechnik GmbH was awarded the contract for design and erection of a Hot Cell for handling and storage of highly radioactive radiation sources. This Hot Cell is part of a new hot cell laboratory, constructed for the NHZ (Neues Handhabungszentrum = New Handling Center) of the Nuclear Engineering Seibersdorf GmbH (NES). All incurring radioactive materials from Austria are collected in the NHZ, where they are safely conditioned and stored temporarily until their final storage. The main tasks of the NES include, apart from the collection, conditioning and storage of radioactive waste, also the reprocessing and the decontamination of facilities and laboratories originating from 45 years of research and development at the Seibersdorf site as well as the operation of the Hot Cell Laboratory [1]. The new Hot Cell Laboratory inside the NHZ consists of the following room areas: - One hot cell, placed in the center, for remote controlled, radiation protected handling of radioactive materials, including an integrated floor storage for the long-term temporary storage of highly radioactive radiation sources; - An anteroom for the loading and unloading of the hot cell; - One control room for the remote controlling of the hot cell equipment; - One floor storage, placed laterally to the hot cell, for burial, interim storage and removal of fissionable radioactive material in leak-proof packed units in 100 l drums. The specific design activity of the hot cell of 1.85 Pbq relating to 1-Me-Radiator including the integrated floor storage influences realization and design of the components used in the cell significantly. (authors)

  19. A Loop Material Flow System Design for Automated Guided Vehicles

    E-Print Network [OSTI]

    Dessouky, Maged

    A Loop Material Flow System Design for Automated Guided Vehicles Ardavan Asef-Vaziri 1 Maged load automated guided vehicles. The model simultaneously determines both the design are attributed to material handling (Tompkins et al., 1996). Automated guided vehicles (AGVs) are among

  20. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-12-29T23:59:59.000Z

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source documents from the U.S. Nuclear RegulatoryCommission (NRC) and the New Mexico Environment Department (NMED) for acomprehensive and detailed listing of the requirements.This CH-WAC does not address the subject of waste characterization relating to adetermination of whether the waste is hazardous; rather, the sites are referred to theWaste Analysis Plan (WAP) contained in the WIPP Hazardous Waste Facility Permit fordetails of the sampling and analysis protocols to be used in determining compliance withthe required physical and chemical properties of the waste. Requirements andassociated criteria pertaining to a determination of the radiological properties of thewaste, however, are addressed in appendix A of this document. The collectiveinformation obtained from waste characterization records and acceptable knowledge(AK) serves as the basis for sites to certify that their CH-TRU waste satisfies the WIPPwaste acceptance criteria listed herein.

  1. The Role of Interventional Radiology in Obstetric Hemorrhage

    SciTech Connect (OSTI)

    Gonsalves, M., E-mail: michael.gonsalves@stgeorges.nhs.uk; Belli, A., E-mail: Anna.Belli@stgeorges.nhs.u [St. Georges Hospital, Radiology Department (United Kingdom)

    2010-10-15T23:59:59.000Z

    Obstetric hemorrhage remains a major cause of maternal morbidity and mortality worldwide. Traditionally, in cases of obstetric hemorrhage refractory to conservative treatment, obstetricians have resorted to major surgery with the associated risks of general anesthesia, laparotomy, and, in the case of hysterectomy, loss of fertility. Over the past two decades, the role of pelvic arterial embolization has evolved from a novel treatment option to playing a key role in the management of obstetric hemorrhage. To date, interventional radiology offers a minimally invasive, fertility-preserving alternative to conventional surgical treatment. We review current literature regarding the role of interventional radiology in postpartum hemorrhage, abnormal placentation, abortion, and cervical ectopic pregnancy. We discuss techniques, success rates, and complications.

  2. Hanford radiological protection support services annual report for 1988

    SciTech Connect (OSTI)

    Lyon, M.; Fix, J.J.; Kenoyer, J.L.; Leonowich, J.A.; Palmer, H.E.; Sula, M.J.

    1989-06-01T23:59:59.000Z

    The report documents the performance of certain radiological protection sitewide services during calendar year (CY) 1988 by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy-Richland Operations Office (DOE-RL) and contractor activities on the Hanford Site. The routine program for each service is discussed along with any significant program changes and tasks, investigations, and studies performed in support of each program. Other related activities such as publications, presentations, and memberships on standard or industry committees are also listed. The programs covered provide services in the areas of (1) internal dosimetry, (2) in vivo measurements, (3) external dosimetry, (4) instrument calibration and evaluation, (5) calibration of radiation sources traceable to the National Institute of Standards and Technology (NIST) (formerly the National Bureau of Standards), and (6) radiological records. 23 refs., 15 figs., 15 tabs.

  3. US Department of Energy radiological control manual. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-04-01T23:59:59.000Z

    This manual establishes practices for the conduct of Department of Energy radiological control activities. The Manual states DOE`s positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. This Manual is not a substitute for Regulations; it is intended to be consistent with all relevant statutory and regulatory requirements and shall be revised whenever necessary to ensure such consistency. Some of the Manual provisions, however, challenge the user to go well beyond minimum requirements. Following the course of action delineated in the Manual will result in achieving and surpassing related statutory or regulatory requirements.

  4. ENVIRONMENTAL SAMPLING USING LOCATION SPECIFIC AIR MONITORING IN BULK HANDLING FACILITIES

    SciTech Connect (OSTI)

    Sexton, L.; Hanks, D.; Degange, J.; Brant, H.; Hall, G.; Cable-Dunlap, P.; Anderson, B.

    2011-06-07T23:59:59.000Z

    Since the introduction of safeguards strengthening measures approved by the International Atomic Energy Agency (IAEA) Board of Governors (1992-1997), international nuclear safeguards inspectors have been able to utilize environmental sampling (ES) (e.g. deposited particulates, air, water, vegetation, sediments, soil and biota) in their safeguarding approaches at bulk uranium/plutonium handling facilities. Enhancements of environmental sampling techniques used by the IAEA in drawing conclusions concerning the absence of undeclared nuclear materials or activities will soon be able to take advantage of a recent step change improvement in the gathering and analysis of air samples at these facilities. Location specific air monitoring feasibility tests have been performed with excellent results in determining attribute and isotopic composition of chemical elements present in an actual test-bed sample. Isotopic analysis of collected particles from an Aerosol Contaminant Extractor (ACE) collection, was performed with the standard bulk sampling protocol used throughout the IAEA network of analytical laboratories (NWAL). The results yielded bulk isotopic values expected for the operations. Advanced designs of air monitoring instruments such as the ACE may be used in gas centrifuge enrichment plants (GCEP) to detect the production of highly enriched uranium (HEU) or enrichments not declared by a State. Researchers at Savannah River National Laboratory in collaboration with Oak Ridge National Laboratory are developing the next generation of ES equipment for air grab and constant samples that could become an important addition to the international nuclear safeguards inspector's toolkit. Location specific air monitoring to be used to establish a baseline environmental signature of a particular facility employed for comparison of consistencies in declared operations will be described in this paper. Implementation of air monitoring will be contrasted against the use of smear ES when used during unannounced inspections, design information verification, limited frequency unannounced access, and complementary access visits at bulk handling facilities. Analysis of technical features required for tamper indication and resistance will demonstrate the viability of successful application of the system in taking ES within a bulk handling location. Further exploration of putting this technology into practice is planned to include mapping uranium enrichment facilities for the identification of optimal for installation of air monitoring devices.

  5. Material Disposal Areas

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

    Permit in its next request for permit modification. MDA V MDA V is categorized as a radiological facility. It consists of three historic wastewater absorption beds that...

  6. Radiological survey results at Beverly Harbor, Beverly, Massachusetts (VB025)

    SciTech Connect (OSTI)

    Foley, R.D.; Johnson, C.A.

    1992-08-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Beverly Harbor, Beverly, Massachusetts. The survey was performed in may 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to the harbor and neighboring areas. The survey included a surface gamma scan and the collection of soil and biological samples for radionuclide analyses.

  7. Radiological survey results for the Peek Street site properties, Schenectady, New York

    SciTech Connect (OSTI)

    Foley, R.D.; Cottrell, W.D.; Carrier, R.F.

    1992-08-01T23:59:59.000Z

    The Peek Street Industrial Facility, located at 425 Peek Street, Schenectady, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1955. A variety of operations using radioactive materials were conducted at the site, but the main activities were to design an intermediate breeder reactor and to develop a chemical process for the recovery of uranium and plutonium from spent reactor fuel. Nonradioactive beryllium metal was machined on the site for breeder reactor application. The 4.5-acre site was decommissioned and released in October 1955. A radiological survey was conducted by Oak Ridge National Laboratory in November 1989. The survey included scan and grid point measurements of direct radiation levels outdoors on the five properties and inside the factory building, and radionuclide analysis of samples collected from each property. Radionuclide concentrations were determined in outdoor surface and subsurface soil samples from each property and in dust, debris, and structural materials from inside the factory building. Auger holes were logged to assess location and extent of possible subsurface residual soil radioactivity. Radionuclide concentrations were deter-mined in both indoor and outdoor water samples and in selected samples of vegetation. The presence of fixed and transferable surface residual radioactivity was investigated inside the factory building and on discarded materials outdoors on the property. High-volume air samples as well as additional selected indoor and outdoor soil samples were analyzed to determine levels of elemental beryllium.

  8. Reducing the Risks. In the aftermath of a terrorist attack, wastewater utilities may have to contend with decontamination water containing chemical, biological, or radiological substances

    SciTech Connect (OSTI)

    Warren, Linda P.; Hornback, Chris; Strom, Daniel J.

    2006-08-01T23:59:59.000Z

    In the aftermath of a chemical, biological, or radiological (CBR) attack, decontamination of people and infrastructure will be needed. Decontamination inevitably produces wastewater, and wastewater treatment plants (WTPs) need to know how to handle decontamination wastewater. This article describes CBR substances; planning, coordinating, and communicating responses across agencies; planning within a utility; coordination with local emergency managers and first responders; mitigating effects of decontamination wastewater; and mitigating effects on utility personnel. Planning for Decontamination Wastewater: A Guide for Utilities, the document on which this article is based, was developed under a cooperative agreement from the U.S. Environmental Protection Agency by the National Association of Clean Water Agencies (NACWA) and its contractor, CH2MHILL, Inc.

  9. Covetic Materials

    Energy Savers [EERE]

    Can re-melt, dilute, alloy... Fabrication of Covetic Materials - Nanocarbon Infusion 3 4 Technical Approach Unusual Characteristics of Covetic Materials ("covalent" &...

  10. Automated cassette-to-cassette substrate handling system

    DOE Patents [OSTI]

    Kraus, Joseph Arthur; Boyer, Jeremy James; Mack, Joseph; DeChellis, Michael; Koo, Michael

    2014-03-18T23:59:59.000Z

    An automated cassette-to-cassette substrate handling system includes a cassette storage module for storing a plurality of substrates in cassettes before and after processing. A substrate carrier storage module stores a plurality of substrate carriers. A substrate carrier loading/unloading module loads substrates from the cassette storage module onto the plurality of substrate carriers and unloads substrates from the plurality of substrate carriers to the cassette storage module. A transport mechanism transports the plurality of substrates between the cassette storage module and the plurality of substrate carriers and transports the plurality of substrate carriers between the substrate carrier loading/unloading module and a processing chamber. A vision system recognizes recesses in the plurality of substrate carriers corresponding to empty substrate positions in the substrate carrier. A processor receives data from the vision system and instructs the transport mechanism to transport substrates to positions on the substrate carrier in response to the received data.

  11. A Scintillator Purification Plant and Fluid Handling System for SNO+

    E-Print Network [OSTI]

    Ford, Richard J

    2015-01-01T23:59:59.000Z

    A large capacity purification plant and fluid handling system has been constructed for the SNO+ neutrino and double-beta decay experiment, located 6800 feet underground at SNOLAB, Canada. SNO+ is a refurbishment of the SNO detector to fill the acrylic vessel with liquid scintillator based on Linear Alkylbenzene (LAB) and 2 g/L PPO, and also has a phase to load natural tellurium into the scintillator for a double-beta decay experiment with 130Te. The plant includes processes multi-stage dual-stream distillation, column water extraction, steam stripping, and functionalized silica gel adsorption columns. The plant also includes systems for preparing the scintillator with PPO and metal-loading the scintillator for double-beta decay exposure. We review the basis of design, the purification principles, specifications for the plant, and the construction and installations. The construction and commissioning status is updated.

  12. A Scintillator Purification Plant and Fluid Handling System for SNO+

    E-Print Network [OSTI]

    Richard J. Ford; for the SNO+ Collaboration

    2015-06-29T23:59:59.000Z

    A large capacity purification plant and fluid handling system has been constructed for the SNO+ neutrino and double-beta decay experiment, located 6800 feet underground at SNOLAB, Canada. SNO+ is a refurbishment of the SNO detector to fill the acrylic vessel with liquid scintillator based on Linear Alkylbenzene (LAB) and 2 g/L PPO, and also has a phase to load natural tellurium into the scintillator for a double-beta decay experiment with 130Te. The plant includes processes multi-stage dual-stream distillation, column water extraction, steam stripping, and functionalized silica gel adsorption columns. The plant also includes systems for preparing the scintillator with PPO and metal-loading the scintillator for double-beta decay exposure. We review the basis of design, the purification principles, specifications for the plant, and the construction and installations. The construction and commissioning status is updated.

  13. Test reports for K Basins vertical fuel handling tools

    SciTech Connect (OSTI)

    Meling, T.A.

    1995-02-01T23:59:59.000Z

    The vertical fuel handling tools, for moving N Reactor fuel elements, were tested in the 305 Building Cold Test Facility (CTF) in the 300 Area. After fabrication was complete, the tools were functionally tested in the CTF using simulated N Reactor fuel rods (inner and outer elements). The tools were successful in picking up the simulated N Reactor fuel rods. These tools were also load tested using a 62 pound dummy to test the structural integrity of each assembly. The tools passed each of these tests, based on the performance objectives. Finally, the tools were subjected to an operations acceptance test where K Basins Operations personnel operated the tool to determine its durability and usefulness. Operations personnel were satisfied with the tools. Identified open items included the absence of a float during testing, and documentation required prior to actual use of the tools in the 100 K fuel storage basin.

  14. The combustion and handling properties of several heavy bitumen emulsions

    SciTech Connect (OSTI)

    Whaley, H.; Wong, J.K.L.; Banks, G.N.; Lee, S.W.

    1995-12-31T23:59:59.000Z

    A research program was undertaken by ACT/CANMET to compare the combustion and heat transfer characteristics of a number of bitumen-based water emulsions with those of heavy fuel oil. The addition of water gives some advantage in the areas of fuel handling, atomization and emissions. These studies showed that the emulsions burn and transfer heat in a manner similar to commercial heavy fuel oils and make excellent fuels for boiler and process combustors. However, if the heavy bitumen is partially upgraded, the emulsion made from these residues can sometimes give rise to combustion and emissions related concerns. Particular attention must be paid to the burner/atomization system in order to avoid combustion problems resulting in unacceptably high levels of soot deposition and emissions.

  15. Results of the radiological survey at 9 Redstone Lane, Lodi, New Jersey (LJ069)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1989-07-01T23:59:59.000Z

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process waste and residues associated with the production and refining of thorium and thorium compounds from monozite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Areas residents used the sandlike waste from this thorium extraction process mixed with teas and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigate radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 9 Redstone Lane, Lodi, New Jersey (LJ069), was conducted during 1987. Measurements at the private property located at 9 Redstone Lane indicate slightly elevated gamma exposure rates in association with cinder-like material observed in logging holes. These elevated levels result from naturally occurring radioactivity present in such substances as ashes and cinders. They are not related to the deposit of residues from processing operations at the MCW site. All other radiological findings conform to the guidelines established by the DOE for the Maywood, New Jersey, area remedial action plan. 4 refs., 3 figs., 3 tabs.

  16. Preliminary results of the radiological survey at the former Dow Chemical Company site, Madison, Illinois

    SciTech Connect (OSTI)

    Cottrell, W.D.; Williams, J.K.

    1990-12-01T23:59:59.000Z

    During the late 1950s and early 1960s, the former Dow Chemical Company plant, now owned and operated by Spectrulite Consortium Inc., supplied materials and provided services for the Atomic Energy Commission (AEC) under purchase orders issued by the Mallinckrodt Chemical Company, a primary AEC contractor. Information indicates that research and development work involving gamma-phase extrusion of uranium metal was conducted at the Dow Chemical plant. Because documentation establishing the current radiological condition of the property was unavailable, a radiological survey was conducted by members of the Measurement Applications and Development Group of the Oak Ridge National Laboratory in March 1989. The survey included: measurement of indoor gamma exposure rates; collection and radionuclide analysis of dust and debris samples; and measurements to determine alpha and beta-gamma surface contamination. The results of the survey demonstrate that Building 6, the area uranium extrusion and rod-straightening work occurred, is generally free of radioactive residuals originating from former DOE-sponsored activities. However, {sup 238}U- and {sup 232}Th-contaminated dust was found on overhead beams at the south end of Building 6. These findings suggest that past DOE-supported operations were responsible for uranium-contaminated beam dust in excess of guidelines in Building 6. However, the contamination is localized and limited in extent, rendering it highly unlikely that under present use an individual working in or frequenting these remote areas would receive a significant radiation exposure. We recommend that additional scoping survey measurements and sampling be performed to further define the extent of indoor uranium contamination southward to include Building 4 and northward throughout Building 6. 5 refs., 11 figs., 4 tabs.

  17. Materials Scientist

    Broader source: Energy.gov [DOE]

    Alternate Title(s):Materials Research Engineer; Metallurgical/Chemical Engineer; Product Development Manager;

  18. Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2010-10-01T23:59:59.000Z

    The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

  19. LM Records Handling System-Freedom of Information/Privacy Act...

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

    Freedom of InformationPrivacy Act, Office of Legacy management LM Records Handling System-Freedom of InformationPrivacy Act, Office of Legacy management More Documents &...

  20. Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study

    SciTech Connect (OSTI)

    Napier, Bruce A. (BATTELLE (PACIFIC NW LAB))

    1999-01-01T23:59:59.000Z

    This is a review of the book ''Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study.''

  1. Cefas contract report MLA/2012/00027 Marine material disposal Part II FEPA Radiological Assessment of

    E-Print Network [OSTI]

    Assessment of Dredging Application for Silloth Docks, Cumbria (2012) Cefas Environment Report RL 10 OF DREDGING APPLICATION FOR SILLOTH DOCKS (2012) Summary In 2012, Associated British Ports Holdings Limited lodged a FEPA licensing application to carry out a 3 year dredging program, involving the disposal at sea

  2. Nuclear, Plasma, and Radiological Engineering Center for Plasma-Material Interactions

    E-Print Network [OSTI]

    MIT (Lithium/Metal Infused Trenches) Concept Feb. 16, 2011 VLT Conference Call David N. Ruzic, Wenyu Xu, Vijay

  3. Forward model calculations for determining isotopic compositions of materials used in a radiological dispersal device

    E-Print Network [OSTI]

    Burk, David Edward

    2005-08-29T23:59:59.000Z

    -standard lattice assemblies. The measured isotopic concentrations from all three of the reactors showed good agreement with the calculated values....

  4. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01T23:59:59.000Z

    care facility-based decontamination of victims exposed tofirst undergoing field decontamination. This article reviewsfacility-based decontamination, including regulatory

  5. Results of the radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York (TNY001)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Murray, M.E.; Uziel, M.S.

    1992-10-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York. The survey was performed in September 1991. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been deposited in the landfill. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey suggest that material originating at the Linde plant may have been deposited in the landfill. Soil samples S54 and B12 contained technologically enhanced levels of {sup 238}U not unlike the product formerly produced by the Linde plant. In contrast, samples B4A, B5A and B7B, containing elevated concentrations of {sup 226}Ra and {sup 230}Th with much lower concentrations of {sup 238}U, were similar to the residue or byproduct of the refinery operation conducted at the Linde plant. In 24 instances, soil samples from the Town of Tonawanda Landfill exceeded DOE guideline values for {sup 238}U, {sup 226}Ra, and/or {sup 230}Th in surface or subsurface soil. Nine of these samples contained radionuclide concentrations more than 30 times the guideline value.

  6. Results of the radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York (TNY001)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Murray, M.E.; Uziel, M.S.

    1992-10-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York. The survey was performed in September 1991. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been deposited in the landfill. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey suggest that material originating at the Linde plant may have been deposited in the landfill. Soil samples S54 and B12 contained technologically enhanced levels of [sup 238]U not unlike the product formerly produced by the Linde plant. In contrast, samples B4A, B5A and B7B, containing elevated concentrations of [sup 226]Ra and [sup 230]Th with much lower concentrations of [sup 238]U, were similar to the residue or byproduct of the refinery operation conducted at the Linde plant. In 24 instances, soil samples from the Town of Tonawanda Landfill exceeded DOE guideline values for [sup 238]U, [sup 226]Ra, and/or [sup 230]Th in surface or subsurface soil. Nine of these samples contained radionuclide concentrations more than 30 times the guideline value.

  7. Results of the independent radiological verification survey of the lower Sheffield Brook floodplain, Wayne, New Jersey

    SciTech Connect (OSTI)

    Yalcintas, M.G.; Carrier, R.F.

    1989-05-01T23:59:59.000Z

    Prior to 1971, the W.R. Grace Company processed and stored radioactive materials at Wayne, New Jersey, under license to the Atomic Energy Commission. Decontamination of structures and storage of waste materials on the property at the Wayne Interim Storage Site (WISS) took place in 1974. Surveys by the State of New Jersey Department of Environmental Protection and by Oak Ridge Associated Universities for the NRC in 1982 indicated that properties adjacent to the WISS contained surface contamination by radioactive residuals in amounts exceeding those acceptable under US Department of Energy (DOE) remedial action guidelines. At the request of DOE, remedial actions have been conducted by Bechtel National, Inc., to remove radioactive residuals from properties adjacent to the site. It is the policy of DOE to assign an independent verification contractor to ensure the effectiveness of remedial actions performed within the Formerly Utilized Sites Remedial Action Program. This report describes the methods and results of those studies that were conducted by the Measurement Applications and Development Group of the Oak Ridge National Laboratory for the lower Sheffield Brook floodplain west of the WISS. Based upon post-remedial action and verification survey data, it was concluded that residual soil concentrations and gamma levels following excavation and backfilling of the area are within the limits prescribed by DOE radiological guidelines. 12 refs., 6 figs., 8 tabs.

  8. Guide of good practices for occupational radiological protection in plutonium facilities

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    This Technical Standard (TS) does not contain any new requirements. Its purpose is to provide guides to good practice, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. the technical rationale is given to allow US Department of Energy (DOE) health physicists to adapt the recommendations to similar situations throughout the DOE complex. Generally, DOE contractor health physicists will be responsible to implement radiation protection activities at DOE facilities and DOE health physicists will be responsible for oversight of those activities. This guidance is meant to be useful for both efforts. This TS replaces PNL-6534, Health Physics Manual of Good Practices for Plutonium Facilities, by providing more complete and current information and by emphasizing the situations that are typical of DOE`s current plutonium operations; safe storage, decontamination, and decommissioning (environmental restoration); and weapons disassembly.

  9. A radiological assessment of nuclear power and propulsion operations near Space Station Freedom. Contract report, January 1988-January 1990

    SciTech Connect (OSTI)

    Bolch, W.E.; Thomas, J.K.; Peddicord, K.L.; Nelson, P.; Marshall, D.T.; Busche, D.M.

    1990-03-01T23:59:59.000Z

    Scenarios were identified which involve the use of nuclear power systems in the vicinity of Space Station Freedom (SSF) and their radiological impact on the SSF crew was quantified. Several of the developed scenarios relate to the use of SSF as an evolutionary transportation node for lunar and Mars missions. In particular, radiation doses delivered to SSF crew were calculated for both the launch and subsequent return of a Nuclear Electric Propulsion (NEP) cargo vehicle and a Nuclear Thermal Rocket (NTR) personnel vehicle to low earth orbit. The use of nuclear power on co-orbiting platforms and the storage and handling issues associated with radioisotope power systems were also explored as they relate to SSF. A central philosophy in these analyses was the utilization of a radiation dose budget, defined as the difference between recommended dose limits from all radiation sources and estimated doses received by crew members from natural space radiations. Consequently, for each scenario examined, the dose budget concept was used to identify and quantify constraints on operational parameters such as launch separation distances, returned vehicle parking distances, and reactor shutdown times prior to vehicle approach. The results indicate that realistic scenarios do not exist which would preclude the use of nuclear power sources in the vicinity of SSF. The radiation dose to the SSF crew can be maintained at safe levels solely by implementing proper and reasonable operating procedures.

  10. Nearest Neighbor Averaging and its Effect on the Critical Level and Minimum Detectable Concentration for Scanning Radiological Survey Instruments that Perform Facility Release Surveys.

    SciTech Connect (OSTI)

    Fournier, Sean Donovan; Beall, Patrick S [Sandia National Laboratories, Livermore, CA; Miller, Mark L.

    2014-08-01T23:59:59.000Z

    Through the SNL New Mexico Small Business Assistance (NMSBA) program, several Sandia engineers worked with the Environmental Restoration Group (ERG) Inc. to verify and validate a novel algorithm used to determine the scanning Critical Level (L c ) and Minimum Detectable Concentration (MDC) (or Minimum Detectable Areal Activity) for the 102F scanning system. Through the use of Monte Carlo statistical simulations the algorithm mathematically demonstrates accuracy in determining the L c and MDC when a nearest-neighbor averaging (NNA) technique was used. To empirically validate this approach, SNL prepared several spiked sources and ran a test with the ERG 102F instrument on a bare concrete floor known to have no radiological contamination other than background naturally occurring radioactive material (NORM). The tests conclude that the NNA technique increases the sensitivity (decreases the L c and MDC) for high-density data maps that are obtained by scanning radiological survey instruments.

  11. Hanford Radiological Protection Support Services annual report for 1992

    SciTech Connect (OSTI)

    Lyon, M; Bihl, D E; Fix, J J; Piper, R K; Froelich, T J; Lynch, T P

    1993-07-01T23:59:59.000Z

    Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Field Office and Hanford contractors are described in this annual report of calendar year 1992. These activities include internal dosimetry measurements and evaluations, in vivo measurements, external dosimetry measurements and evaluations, instrument calibration and evaluation, radiation source calibration, and radiological record keeping. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

  12. Hanford radiological protection support services annual report for 1996

    SciTech Connect (OSTI)

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Froelich, T.J.; Piper, R.K.; Schulze, S.A.

    1997-06-01T23:59:59.000Z

    Various Hanford Site radiation protection services provided by the Pacific Northwest National Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1996. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological exposure record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

  13. Compact cyclone filter train for radiological and hazardous environments

    DOE Patents [OSTI]

    Bench, T.R.

    1998-04-28T23:59:59.000Z

    A compact cyclone filter train is disclosed for the removal of hazardous and radiological particles from a gaseous fluid medium. This filter train permits a small cyclone separator to be used in a very small space envelope due to the arrangement of the filter housing adjacent to the separator with the cyclone separator and the filters mounted on a plate. The entire unit will have a hoist connection at the center of gravity so that the entire unit including the separator, the filters, and the base can be lifted and repositioned as desired. 3 figs.

  14. Federal Radiological Monitoring and Assessment Center Health and Safety Manual

    SciTech Connect (OSTI)

    FRMAC Health and Safety Working Group

    2012-03-20T23:59:59.000Z

    This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

  15. Energy deposition and radiological studies for the LBNF Hadron Absorber

    E-Print Network [OSTI]

    Rakhno, I L; Tropin, I S; Eidelman, Y I

    2015-01-01T23:59:59.000Z

    Results of detailed Monte Carlo energy deposition and radiological studies performed for the LBNF hadron absorber with the MARS15 code are described. The model of the entire facility, that includes a pion-production target, focusing horns, target chase, decay channel, hadron absorber system - all with corresponding radiation shielding - was developed using the recently implemented ROOT-based geometry option in the MARS15 code. Both normal operation and accidental conditions were studied. Results of detailed thermal calculations with the ANSYS code helped to select the most viable design options.

  16. Compact cyclone filter train for radiological and hazardous environments

    DOE Patents [OSTI]

    Bench, Thomas R. (Pittsburgh, PA)

    1998-01-01T23:59:59.000Z

    A compact cyclone filter train for the removal of hazardous and radiologi particles from a gaseous fluid medium which permits a small cyclone separator to be used in a very small space envelope due to the arrangement of the filter housing adjacent to the separator with the cyclone separator and the filters mounted on a plate. The entire unit will have a hoist connection at the center of gravity so that the entire unit including the separator, the filters, and the base can be lifted and repositioned as desired.

  17. Hanford radiological protection support services annual report for 1991

    SciTech Connect (OSTI)

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Piper, R.K.; Froelich, T.J.; Leonwich, J.A.; Lynch, T.P.

    1992-07-01T23:59:59.000Z

    Various Hanford sitewide radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy, Richland Field Office and Hanford contractors are described In this annual report for calendar year 1991. These activities include internal dosimetry measurements and evaluations, in vivo measurements, external dosimetry measurements and evaluations, instrument calibration and evaluation, radiation source calibration, and radiological records keeping. For each of these activities, the routine program, program changes and enhancements, associated tasks, investigations and studies, and related publications, presentations, and other staff professional activities are discussed as applicable.

  18. Hanford radiological protection support services annual report for 1994

    SciTech Connect (OSTI)

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Piper, R.K.; Froelich, T.J.; Olsen, P.C.

    1995-06-01T23:59:59.000Z

    Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for the calendar year 1994. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program- related publications, presentations, and other staff professional activities are also described.

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician Air

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician Air

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician Air

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician Air

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control Technician

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control TechnicianStudy

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control TechnicianStudy

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological Control

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological ControlStudy Guide

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological ControlStudy GuideStudy

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological ControlStudy

  15. DOE-HDBK-1122-99; Radiological Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological ControlStudy5 of 9

  16. DOE-HDBK-1131-98; General Employee Radiological Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological ControlStudy5

  17. DOE-HDBK-1141-2001; Radiological Assessor Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological32-99 April0-200141-2001

  18. DOE-HDBK-1141-2001; Radiological Assessor Training, Overheads

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological32-994-1 DEPARTMENT56.1

  19. DOE-HDBK-1141-2001; Radiological Assessor Training, Overheads

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No Significant Impact6 of 9 Radiological32-994-1

  20. DRAFT - Design of Radiological Survey and Sampling to Support Title Transfer or Lease of Property on the Department of Energy Oak Ridge Reservation

    SciTech Connect (OSTI)

    Cusick L.T.

    2002-09-25T23:59:59.000Z

    The U.S. Department of Energy (DOE) owns, operates, and manages the buildings and land areas on the Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee. As land and buildings are declared excess or underutilized, it is the intent of DOE to either transfer the title of or lease suitable property to the Community Reuse Organization of East Tennessee (CROET) or other entities for public use. It is DOE's responsibility, in coordination with the U.S. Environmental Protection Agency (EPA), Region 4, and the Tennessee Department of Environment and Conservation (TDEC), to ensure that the land, facilities, and personal property that are to have the title transferred or are to be leased are suitable for public use. Release of personal property must also meet site requirements and be approved by the DOE contractor responsible for site radiological control. The terms title transfer and lease in this document have unique meanings. Title transfer will result in release of ownership without any restriction or further control by DOE. Under lease conditions, the government retains ownership of the property along with the responsibility to oversee property utilization. This includes involvement in the lessee's health, safety, and radiological control plans and conduct of site inspections. It may also entail lease restrictions, such as limiting access to certain areas or prohibiting digging, drilling, or disturbing material under surface coatings. Survey and sampling requirements are generally more rigorous for title transfer than for lease. Because of the accelerated clean up process, there is an increasing emphasis on title transfers of facilities and land. The purpose of this document is to describe the radiological survey and sampling protocols that are being used for assessing the radiological conditions and characteristics of building and land areas on the Oak Ridge Reservation that contain space potentially available for title transfer or lease. After necessary surveys and sampling and laboratory analyses are completed, the data are analyzed and included in an Environmental Baseline Summary (EBS) report for title transfer or in a Baseline Environmental Analysis Report (BEAR) for lease. The data from the BEAR is then used in a Screening-Level Human Health Risk Assessment (SHHRA) or a risk calculation (RC) to assess the potential risks to future owners/occupants. If title is to be transferred, release criteria in the form of specific activity concentrations called Derived Concentration Guideline Levels (DCGLs) will be developed for the each property. The DCGLs are based on the risk model and are used with the data in the EBS to determine, with statistical confidence, that the release criteria for the property have been met. The goal of the survey and sampling efforts is to (1) document the baseline conditions of the property (real or personal) prior to title transfer or lease, (2) obtain enough information that an evaluation of radiological risks can be made, and (3) collect sufftcient data so that areas that contain minimal residual levels of radioactivity can be identified and, following radiological control procedures, be released from radiological control. (It should be noted that release from radiological control does not necessarily mean free release because DOE may maintain institutional control of the site after it is released from radiological control). To meet the goals of this document, a Data Quality Objective (DQO) process will be used to enhance data collection efficiency and assist with decision-making. The steps of the DQO process involve stating the problem, identifying the decision, identifying inputs to the decision, developing study boundaries, developing the decision rule, and optimizing the design. This document describes the DQOs chosen for surveys and sampling efforts performed for the purposes listed above. The previous version to this document focused on the requirements for radiological survey and sampling protocols that are be used for leasing. Because the primary focus at this time is on title transfer, th

  1. Self-actuating mechanical grapple for lifting and handling objects

    DOE Patents [OSTI]

    Hovis, Gregory L. (North Augusta, SC); Etheredge, Jr., Carl T. (Tuscaloosa, AL)

    2001-01-01T23:59:59.000Z

    A self-actuating mechanical grapple for lifting and handling an object includes a support housing with upper and lower portions and defining an internal recess. The lower portion of the housing includes a bottom opening which communicates with the recess. Preferably, two or three grapple jaws are provided, the first end portions of which are connected to the housing and the second end portions thereof remain free for engaging an object. The grapple jaws are pivotable between open and closed positions. An actuator member is slidably positioned in the recess for opening and closing the jaws, and includes a cam portion in operative engagement with the first end portions of the jaws in a manner to pivot the jaws when the actuator member moves axially relative to the housing. The actuator member includes a rotatable member with at least one contact member. A locking member or logic ring includes grooves defining open and closed positions of the jaws and is fixedly mounted to the internal surface of the housing and cooperates with the rotatable member. A plunger member is axially movable in the housing for contacting an object and includes at least one stud member for immovably engaging the contact member.

  2. Removable pellicle for lithographic mask protection and handling

    DOE Patents [OSTI]

    Klebanoff, Leonard E. (Dublin, CA); Rader, Daniel J. (Albuquerque, NM); Hector, Scott D. (Oakland, CA); Nguyen, Khanh B. (Sunnyvale, CA); Stulen, Richard H. (Livermore, CA)

    2002-01-01T23:59:59.000Z

    A removable pellicle for a lithographic mask that provides active and robust particle protection, and which utilizes a traditional pellicle and two deployments of thermophoretic protection to keep particles off the mask. The removable pellicle is removably attached via a retaining structure to the mask substrate by magnetic attraction with either contacting or non-contacting magnetic capture mechanisms. The pellicle retaining structural is composed of an anchor piece secured to the mask substrate and a frame member containing a pellicle. The anchor piece and the frame member are in removable contact or non-contact by the magnetic capture or latching mechanism. In one embodiment, the frame member is retained in a floating (non-contact) relation to the anchor piece by magnetic levitation. The frame member and the anchor piece are provided with thermophoretic fins which are interdigitated to prevent particles from reaching the patterned area of the mask. Also, the anchor piece and mask are maintained at a higher temperature than the frame member and pellicle which also prevents particles from reaching the patterned mask area by thermophoresis. The pellicle can be positioned over the mask to provide particle protection during mask handling, inspection, and pumpdown, but which can be removed manually or robotically for lithographic use of the mask.

  3. B cell remote-handled waste shipment cask alternatives study

    SciTech Connect (OSTI)

    RIDDELLE, J.G.

    1999-05-26T23:59:59.000Z

    The decommissioning of the 324 Facility B Cell includes the onsite transport of grouted remote-handled radioactive waste from the 324 Facility to the 200 Areas for disposal. The grouted waste has been transported in the leased ATG Nuclear Services 3-82B Radioactive Waste Shipping Cask (3-82B cask). Because the 3-82B cask is a U.S. Nuclear Regulatory Commission (NRC)-certified Type B shipping cask, the lease cost is high, and the cask operations in the onsite environment may not be optimal. An alternatives study has been performed to develop cost and schedule information on alternative waste transportation systems to assist in determining which system should be used in the future. Five alternatives were identified for evaluation. These included continued lease of the 3-82B cask, fabrication of a new 3-82B cask, development and fabrication of an onsite cask, modification of the existing U.S. Department of Energy-owned cask (OH-142), and the lease of a different commercially available cask. Each alternative was compared to acceptance criteria for use in the B Cell as an initial screening. Only continued leasing of the 3-82B cask, fabrication of a new 3-82B cask, and the development and fabrication of an onsite cask were found to meet all of the B Cell acceptance criteria.

  4. Urenco`s experience of UF{sub 6} handling

    SciTech Connect (OSTI)

    Saelmans, F. [Urenco Almelo (Netherlands); Scane, C. [Urenco Capenhurst (United Kingdom); Christofzik, J. [Urenco Gronau (Germany)

    1991-12-31T23:59:59.000Z

    Urenco operates enrichment plants at three sites, Almelo (Netherlands), Capenhurst (United Kingdom) and Gronau (Germany). Current installed separative work capacity is 2,500 tSWpa. Since 1971, when the first pilot plants were built, enrichment production has totalled 18,000 tSW. During this last 20 years over 3,500 48 containers of UF{sub 6} have been fed to the plants, over 3,700 30 containers have been filled with product and delivered successfully to Urenco`s customers worldwide and over 3,000 48 containers of depleted tails have been filled and have either been returned to customers or retained for long term storage on site. The paper gives a brief outline of Urenco`s experience in handling UF{sub 6}: the equipment and methods used in receiving, feeding, filling, blending, liquid sampling, storing, moving on site and despatching of UF{sub 6} containers. Some of the difficulties experienced with UF{sub 6} containers are appended.

  5. Missing Data Handling for Meter Data Management System Ru-Sen Jeng1

    E-Print Network [OSTI]

    Chen, Ling-Jyh

    Applications]: Types of Systems-- Decision support (e.g., MIS) Keywords Missing data, Smart meter, MDMS 1-scale deployments. As a consequence, conventional missing data handling methods are not applicable to smart meterMissing Data Handling for Meter Data Management System Ru-Sen Jeng1 , Chien-Yu Kuo1 , Yao-hua Ho1

  6. From Modelica Models to Fault Diagnosis in Air Handling Units Raymond Sterling1

    E-Print Network [OSTI]

    Cengarle, María Victoria

    From Modelica Models to Fault Diagnosis in Air Handling Units Raymond Sterling1 , Peter Struss2 Handling Unit (AHU). This solution is derived from a general first-principle Modelica model and exploits 4 presents the modelica models and its calibration. In section 5 an example of the complete tool

  7. Towards Architecture-Level Middleware-Enabled Exception Handling of Component-based Systems

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Towards Architecture-Level Middleware-Enabled Exception Handling of Component-based Systems Gang of Electronics Engineering and Computer Science, Peking University, Beijing, 100871, China huanggang@sei.pku.edu.cn Abstract Exception handling is a practical and important way to improve the availability and reliability

  8. GUIDELINES FOR DESIGN AND SAFE HANDLING OF CURVED I-SHAPED STEEL GIRDERS

    E-Print Network [OSTI]

    Texas at Austin, University of

    0-5574-P1 GUIDELINES FOR DESIGN AND SAFE HANDLING OF CURVED I-SHAPED STEEL GIRDERS Authors: Jason FOR DESIGN AND SAFE HANDLING OF CURVED I-SHAPED STEEL GIRDERS PURPOSE: The purpose of this set of guidelines-sixth #12;2 (Eq. 6.10.2.2-2). However, TxDOT's Preferred Practices for Steel Bridge Design, Fabrication

  9. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-02-01T23:59:59.000Z

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  10. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-05-01T23:59:59.000Z

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  11. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-10-01T23:59:59.000Z

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  12. HADEGA: A Novel MPLS-based Mitigation Solution to Handle Network Attacks

    E-Print Network [OSTI]

    Garcia-Alfaro, Joaquin

    in order to evaluate the efficiency of our approach. Results are presented. Index Terms--Network SecurityHADEGA: A Novel MPLS-based Mitigation Solution to Handle Network Attacks Nabil Hachem, Herve Debar are controlled and properly handled inside the core network of service providers. We conducted simulations

  13. Palliative Airway Stenting Performed Under Radiological Guidance and Local Anesthesia

    SciTech Connect (OSTI)

    Profili, Stefano; Manca, Antonio [University of Sassari, Department of Radiology (Italy); Feo, Claudio F. [Istituto di Clinica Chirurgica, University of Sassari, Department of Surgery (Italy)], E-mail: cffeo@uniss.it; Padua, Guglielmo [University of Sassari, Department of Anesthesiology (Italy); Ortu, Riccardo [SS Annunziata Hospital, Service of Pneumology (Italy); Canalis, Giulio C.; Meloni, Giovanni B. [University of Sassari, Department of Radiology (Italy)

    2007-02-15T23:59:59.000Z

    Purpose. To assess the effectiveness of airway stenting performed exclusively under radiological guidance for the palliation of malignant tracheobronchial strictures. Methods. We report our experience in 16 patients with malignant tracheobronchial stricture treated by insertion of 20 Ultraflex self-expandable metal stents performed under fluoroscopic guidance only. Three patients presented dysphagia grade IV due to esophageal malignant infiltration; they therefore underwent combined airway and esophageal stenting. All the procedures were performed under conscious sedation in the radiological room; average procedure time was around 10 min, but the airway impediment never lasted more than 40 sec. Results. We obtained an overall technical success in 16 cases (100%) and clinical success in 14 patients (88%). All prostheses were successfully placed without procedural complications. Rapid clinical improvement with symptom relief and normalization of respiratory function was obtained in 14 cases. Two patients died within 48 hr from causes unrelated to stent placement. Two cases (13%) of migration were observed; they were successfully treated with another stent. Tumor overgrowth developed in other 2 patients (13%); however, no further treatment was possible because of extensive laryngeal infiltration. Conclusions. Tracheobronchial recanalization with self-expandable metal stents is a safe and effective palliative treatment for malignant strictures. Airway stenting performed exclusively under fluoroscopic view was rapid and well tolerated.

  14. Safe handling of potential peroxide forming compounds and their corresponding peroxide yielded derivatives.

    SciTech Connect (OSTI)

    Sears, Jeremiah Matthew; Boyle, Timothy J.; Dean, Christopher J.

    2013-06-01T23:59:59.000Z

    This report addresses recent developments concerning the identification and handling of potential peroxide forming (PPF) and peroxide yielded derivative (PYD) chemicals. PPF chemicals are described in terms of labeling, shelf lives, and safe handling requirements as required at SNL. The general peroxide chemistry concerning formation, prevention, and identification is cursorily presented to give some perspective to the generation of peroxides. The procedure for determining peroxide concentrations and the proper disposal methods established by the Hazardous Waste Handling Facility are also provided. Techniques such as neutralization and dilution are provided for the safe handling of any PYD chemicals to allow for safe handling. The appendices are a collection of all available SNL documentation pertaining to PPF/PYD chemicals to serve as a single reference.

  15. Cefas contract report C5078 (MCU1245 and MCU1258) Radiological Assessment of

    E-Print Network [OSTI]

    Cefas contract report C5078 (MCU1245 and MCU1258) Radiological Assessment of Dredging Application. A. Smedley and S.M. Cogan Issue date: April 2013 #12;#12;RADIOLOGICAL ASSESSMENT OF DREDGING licensing application to carry out a variety of dredging scenarios, within which dredging and disposal could

  16. 2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01T23:59:59.000Z

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  17. 2013 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01T23:59:59.000Z

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  18. C-1 SITE ENVIRONMENTAL REPORT 2000 APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 SITE ENVIRONMENTAL REPORT 2000 APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES APPENDIX C: Radiological Data Methodologies DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY The effective dose equivalent. Facility-specific radionu- clide release rates (in curies per year [Ci/yr]) were also used. All annual site

  19. 2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    mike lewis

    2011-02-01T23:59:59.000Z

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  20. B-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    B-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES APPENDIX B: DOSE to calculate annual dispersions for the midpoint of a given sector and distance. Facility specific radionuclide Handbook (EPA 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur in a random fashion

  1. 2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2012-02-01T23:59:59.000Z

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  2. C-1 2002 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2002 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES APPENDIX C Radiological Data Methodologies DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY The effective dose equivalent. Facility-specificradionuclidereleaserates(incu- ries per year [Ci/yr]) were also used.All annual site

  3. TECHNOLOGY DEVELOPMENT AND DEPLOYMENT OF SYSTEMS FOR THE RETRIEVAL AND PROCESSING OF REMOTE-HANDLED SLUDGE FROM HANFORD K-WEST FUEL STORAGE BASIN

    SciTech Connect (OSTI)

    RAYMOND RE

    2011-12-27T23:59:59.000Z

    In 2011, significant progress was made in developing and deploying technologies to remove, transport, and interim store remote-handled sludge from the 105-K West Fuel Storage Basin on the Hanford Site in south-central Washington State. The sludge in the 105-K West Basin is an accumulation of degraded spent nuclear fuel and other debris that collected during long-term underwater storage of the spent fuel. In 2010, an innovative, remotely operated retrieval system was used to successfully retrieve over 99.7% of the radioactive sludge from 10 submerged temporary storage containers in the K West Basin. In 2011, a full-scale prototype facility was completed for use in technology development, design qualification testing, and operator training on systems used to retrieve, transport, and store highly radioactive K Basin sludge. In this facility, three separate systems for characterizing, retrieving, pretreating, and processing remote-handled sludge were developed. Two of these systems were successfully deployed in 2011. One of these systems was used to pretreat knockout pot sludge as part of the 105-K West Basin cleanup. Knockout pot sludge contains pieces of degraded uranium fuel ranging in size from 600 {mu}m to 6350 {mu}m mixed with pieces of inert material, such as aluminum wire and graphite, in the same size range. The 2011 pretreatment campaign successfully removed most of the inert material from the sludge stream and significantly reduced the remaining volume of knockout pot product material. Removing the inert material significantly minimized the waste stream and reduced costs by reducing the number of transportation and storage containers. Removing the inert material also improved worker safety by reducing the number of remote-handled shipments. Also in 2011, technology development and final design were completed on the system to remove knockout pot material from the basin and transport the material to an onsite facility for interim storage. This system is scheduled for deployment in 2012. The prototype facility also was used to develop technology for systems to retrieve remote-handled transuranic sludge smaller than 6350 {mu}m being stored in underwater containers. After retrieving the sludge, the system will be used to load and transport the sludge for interim storage. During 2011, full-scale prototype systems were developed and tested to a Technology Readiness Level 6 as defined by U.S. Department of Energy standards. This system is scheduled for deployment in 2013. Operations also are scheduled for completion in 2014.

  4. Radiological Assessment System for Consequence Analysis (RASCAL) Version 3.0

    SciTech Connect (OSTI)

    Athey, G.F.; Fosmire, C.; Mohseni, A.; Ramsdell, J.V., Jr.; Sjoreen, A.

    1999-09-13T23:59:59.000Z

    The Radiological Assessment System for Consequence AnaLysis, Version 3.0 (RASCAL 3.0) is the U.S. Nuclear Regulatory Commission?s (NRC) main computational tool for use during radiological emergencies. RASCAL estimates doses from radiological accidents for comparison with Protective Action Guides and acute health effects thresholds. It includes six computational tools: ST-Dose, FM-Dose, Decay, BackCalc, UF6Plume, and MetProc. ST-Dose computes time-dependent nuclide release rates, atmospheric transport, radiological decay, and doses. FM-Dose computes doses from environmental concentrations of nuclides. Decay computes radiological decay and daughter in-growth. BackCalc estimates a distribution of possible release rates from field measurements. UF6Plume computes uranium exposures and HF concentrations from a UF6 release. MetProc prepares meteorological data for use by ST-Dose and UF6Plume.

  5. Predicting error in detecting mammographic masses among radiology trainees using statistical models based on BI-RADS features

    SciTech Connect (OSTI)

    Grimm, Lars J., E-mail: Lars.grimm@duke.edu; Ghate, Sujata V.; Yoon, Sora C.; Kim, Connie [Department of Radiology, Duke University Medical Center, Box 3808, Durham, North Carolina 27710 (United States)] [Department of Radiology, Duke University Medical Center, Box 3808, Durham, North Carolina 27710 (United States); Kuzmiak, Cherie M. [Department of Radiology, University of North Carolina School of Medicine, 2006 Old Clinic, CB No. 7510, Chapel Hill, North Carolina 27599 (United States)] [Department of Radiology, University of North Carolina School of Medicine, 2006 Old Clinic, CB No. 7510, Chapel Hill, North Carolina 27599 (United States); Mazurowski, Maciej A. [Duke University Medical Center, Box 2731 Medical Center, Durham, North Carolina 27710 (United States)] [Duke University Medical Center, Box 2731 Medical Center, Durham, North Carolina 27710 (United States)

    2014-03-15T23:59:59.000Z

    Purpose: The purpose of this study is to explore Breast Imaging-Reporting and Data System (BI-RADS) features as predictors of individual errors made by trainees when detecting masses in mammograms. Methods: Ten radiology trainees and three expert breast imagers reviewed 100 mammograms comprised of bilateral medial lateral oblique and craniocaudal views on a research workstation. The cases consisted of normal and biopsy proven benign and malignant masses. For cases with actionable abnormalities, the experts recorded breast (density and axillary lymph nodes) and mass (shape, margin, and density) features according to the BI-RADS lexicon, as well as the abnormality location (depth and clock face). For each trainee, a user-specific multivariate model was constructed to predict the trainee's likelihood of error based on BI-RADS features. The performance of the models was assessed using area under the receive operating characteristic curves (AUC). Results: Despite the variability in errors between different trainees, the individual models were able to predict the likelihood of error for the trainees with a mean AUC of 0.611 (range: 0.502–0.739, 95% Confidence Interval: 0.543–0.680,p < 0.002). Conclusions: Patterns in detection errors for mammographic masses made by radiology trainees can be modeled using BI-RADS features. These findings may have potential implications for the development of future educational materials that are personalized to individual trainees.

  6. On-Line Educational Means on Radiological Protection and Accelerator General Safety Policy in Radiotherapy and Industrial Sterilization Facilities

    E-Print Network [OSTI]

    Spyropoulos, B

    1999-01-01T23:59:59.000Z

    On-Line Educational Means on Radiological Protection and Accelerator General Safety Policy in Radiotherapy and Industrial Sterilization Facilities

  7. Skyshine And Groundshine Phenomena And Related Radiological quantities evaluated For The Environment Of A High Current Spallation Facility

    E-Print Network [OSTI]

    Zazula, J M; Cloth, P

    1987-01-01T23:59:59.000Z

    Skyshine And Groundshine Phenomena And Related Radiological quantities evaluated For The Environment Of A High Current Spallation Facility

  8. Safe Handling of Dry Ice During a Power Outage

    E-Print Network [OSTI]

    is an affirmative-action equal-opportunity institution. Michigan State University Extension programs and materials.S. Department of Agriculture. Thomas Coon, Extension director, Michigan State University, E. Lansing, MI 48824-800-332-4010 United States Food Safety Web Site www.foodsafety.gov The Food Domain. Michigan State University www

  9. Compilation of Requirements for Safe Handling of Fluorine and Fluorine-Containing Products of Uranium Hexafluoride Conversion

    SciTech Connect (OSTI)

    Ferrada, J.J.

    2000-04-03T23:59:59.000Z

    Public Law (PL) 105-204 requires the U.S. Department of Energy to develop a plan for inclusion in the fiscal year 2000 budget for conversion of the Department's stockpile of depleted uranium hexafluoride (DUF{sub 6}) to a more stable form over an extended period. The conversion process into a more stable form will produce fluorine compounds (e.g., elemental fluorine or hydrofluoric acid) that need to be handled safely. This document compiles the requirements necessary to handle these materials within health and safety standards, which may apply in order to ensure protection of the environment and the safety and health of workers and the public. Fluorine is a pale-yellow gas with a pungent, irritating odor. It is the most reactive nonmetal and will react vigorously with most oxidizable substances at room temperature, frequently with ignition. Fluorine is a severe irritant of the eyes, mucous membranes, skin, and lungs. In humans, the inhalation of high concentrations causes laryngeal spasm and broncospasms, followed by the delayed onset of pulmonary edema. At sublethal levels, severe local irritation and laryngeal spasm will preclude voluntary exposure to high concentrations, unless the individual is trapped or incapacitated. A blast of fluorine gas on the shaved skin of a rabbit causes a second degree burn. Lower concentrations cause severe burns of insidious onset, resulting in ulceration, similar to the effects produced by hydrogen fluoride. Hydrofluoric acid is a colorless, fuming liquid or gas with a pungent odor. It is soluble in water with release of heat. Ingestion of an estimated 1.5 grams produced sudden death without gross pathological damage. Repeated ingestion of small amounts resulted in moderately advanced hardening of the bones. Contact of skin with anhydrous liquid produces severe burns. Inhalation of AHA or aqueous hydrofluoric acid mist or vapors can cause severe respiratory tract irritation that may be fatal. Based on the extreme chemical properties of these chemicals as noted above, fluorine or fluorine compounds must be handled appropriately within the boundaries of many safety requirements for the protection of the environment and the public. This report analyzes the safety requirements that regulatory agencies have issued to handle fluorine or fluorine compounds and lists them in Table 1. Table 1 lists the source of the requirements, the specific section of the source document, and a brief description of the requirements.

  10. Radioactive material in the West Lake Landfill: Summary report

    SciTech Connect (OSTI)

    none,

    1988-06-01T23:59:59.000Z

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

  11. Scintillator material

    DOE Patents [OSTI]

    Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

    1994-01-01T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

  12. Scintillator material

    DOE Patents [OSTI]

    Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

    1992-01-01T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

  13. Scintillator material

    DOE Patents [OSTI]

    Anderson, D.F.; Kross, B.J.

    1992-07-28T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

  14. Scintillator material

    DOE Patents [OSTI]

    Anderson, D.F.; Kross, B.J.

    1994-06-07T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

  15. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-02-01T23:59:59.000Z

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  16. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Timothy Solack; Carol Mason

    2012-03-01T23:59:59.000Z

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  17. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-05-01T23:59:59.000Z

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  18. Critical Materials:

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

    lighting. 14 (bottom) Criticality ratings of shortlisted raw 76 materials. 15 77 2. Technology Assessment and Potential 78 This section reviews the major trends within...

  19. How to Translate a Material Safety Data Sheet (MSDS)

    E-Print Network [OSTI]

    Sherrill, David

    ­ Section 6- Health Hazards ­ Section 7- Storage and Handling Procedures ­ Section 8- Emergency First Aid = 1, Propane =1.6, Hydrogen = 0.1, Gasoline = 3.0 - 4.0 Vapor Density is Important Because If # > 1, the material will sink Examples: Water = 1, Gasoline = 0.8 #12;Specific Gravity is Important

  20. Status of ion sources at National Institute of Radiological Sciences

    SciTech Connect (OSTI)

    Kitagawa, A.; Fujita, T.; Goto, A.; Hattori, T.; Hamano, T.; Hojo, S.; Honma, T.; Imaseki, H.; Katagiri, K.; Muramatsu, M.; Sakamoto, Y.; Sekiguchi, M.; Suda, M.; Sugiura, A.; Suya, N. [National Institute of Radiological Sciences (NIRS), 4-9-1 Anagawa, Inage, Chiba 263-8555 (Japan)

    2012-02-15T23:59:59.000Z

    The National Institute of Radiological Sciences (NIRS) maintains various ion accelerators in order to study the effects of radiation of the human body and medical uses of radiation. Two electrostatic tandem accelerators and three cyclotrons delivered by commercial companies have offered various life science tools; these include proton-induced x-ray emission analysis (PIXE), micro beam irradiation, neutron exposure, and radioisotope tracers and probes. A duoplasmatron, a multicusp ion source, a penning ion source (PIG), and an electron cyclotron resonance ion source (ECRIS) are in operation for these purposes. The Heavy-Ion Medical Accelerator in Chiba (HIMAC) is an accelerator complex for heavy-ion radiotherapy, fully developed by NIRS. HIMAC is utilized not only for daily treatment with the carbon beam but also for fundamental experiments. Several ECRISs and a PIG at HIMAC satisfy various research and clinical requirements.