National Library of Energy BETA

Sample records for materials handled radiological

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

    Office of Environmental Management (EM)

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

  2. Handling and Packaging a Potentially Radiologically Contaminated Patient

    Broader source: Energy.gov [DOE]

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

  3. Handling difficult materials: Textiles

    SciTech Connect (OSTI)

    Polk, T.

    1994-07-01

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

  4. Ergonomic material-handling device

    DOE Patents [OSTI]

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

    2004-08-24

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

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

    Energy Savers [EERE]

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

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

    National Nuclear Security Administration (NNSA)

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

  7. Hydrogen Fuel for Material Handling | Department of Energy

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

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

  8. APPARATUS FOR HANDLING MIXTURES OF SOLID MATERIALS

    DOE Patents [OSTI]

    Hubbell, J.P.

    1959-08-25

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

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

    Broader source: Energy.gov [DOE]

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

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

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

    Energy Material Handling Equipment Early Markets: Fuel Cells for Material Handling Equipment This fact sheet describes the use of hydrogen fuel cells to power material handling equipment (MHE) and includes cost and performance comparisons for fuel cell-powered and battery-powered MHE. PDF icon Early Markets: Fuel Cells for Material Handling Equipment More Documents & Publications An Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment Market

  11. 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)

    to Partner with NMJC To Train Radiological and Waste Handling Technicians Hobbs, NM, December 5, 2001 -- Representatives of the Waste Isolation Pilot Plant (WIPP) yesterday presented a check for $70,000 to New Mexico Junior College (NMJC) to initiate a new program to train and certify radiological and waste handling technicians. Dr. Steve McCleery, President of NMJC, accepted the check from Dr. Chuan-Fu Wu, Senior Technical Advisor for the U.S. Department of Energy's Carlsbad Field Office, and

  12. Bag-out material handling system

    DOE Patents [OSTI]

    Brak, Stephen B.

    1985-01-01

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

  13. Bag-out material handling system

    DOE Patents [OSTI]

    Brak, Stephen B.; Milek, Henry F.

    1984-01-01

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

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

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

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

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

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

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

  16. Material Handling Fuel Cells for Building Electric Peak Shaving...

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

    Time ---> Power ---> Grid power Power from FCEV Building demand Time ---> Power ---> DC bus Class I, II, III material handling equipment (MHE) On-site refueling available Forklift ...

  17. Early Markets: Fuel Cells for Material Handling Equipment

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

    Material Handling Equipment Overview Fuel cells can be used to produce power for many ... natural gas, or biogas to electricity, fuel cells can effciently provide power while ...

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

    Broader source: Energy.gov [DOE]

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

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

    DOE Patents [OSTI]

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

    1987-01-01

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

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

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material May 29, 2014 GTRI's Remove Program works around the world to remove excess nuclear and radiological materials that could be used for a nuclear weapon or radiological dispersal device (RDD), or "dirty bomb". Mission In 2004 NNSA established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible, identify,

  1. Method of preparing and handling chopped plant materials

    DOE Patents [OSTI]

    Bransby, David I.

    2002-11-26

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

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

    SciTech Connect (OSTI)

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

    1992-11-01

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

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

    SciTech Connect (OSTI)

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

    2010-02-01

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

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

    National Nuclear Security Administration (NNSA)

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

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

    Broader source: Energy.gov [DOE]

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

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

    National Nuclear Security Administration (NNSA)

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

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

    SciTech Connect (OSTI)

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

    2013-11-01

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

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

    SciTech Connect (OSTI)

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

    2014-06-01

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

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

    SciTech Connect (OSTI)

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

    2013-05-01

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

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

    SciTech Connect (OSTI)

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

    2013-10-01

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

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

    SciTech Connect (OSTI)

    T. A. Misiak

    1998-05-21

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

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

    SciTech Connect (OSTI)

    Ramsden, T.

    2013-04-01

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

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

    SciTech Connect (OSTI)

    Ainscough, Chris; Kurtz, Jennifer

    2015-05-01

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

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

    SciTech Connect (OSTI)

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

    1992-01-01

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

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

    SciTech Connect (OSTI)

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

    1992-12-31

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

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

    SciTech Connect (OSTI)

    Seguin, Nicole R.

    2012-07-18

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

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

    SciTech Connect (OSTI)

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

    2013-11-01

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

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

    SciTech Connect (OSTI)

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

    2009-02-06

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

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

    Broader source: Energy.gov [DOE]

    This report provides cost estimates for the manufacture of 10 kW and 25 kW PEM fuel cells designed for material handling applications.

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

    SciTech Connect (OSTI)

    Jim Jnatt

    2001-08-24

    Vortec Corporation, the United States Enrichment Corporation (USEC) and DOE/Paducah propose to complete the technology demonstration and the implementation of the Material Handling System developed under Contract Number DE-AC21-92MC29120. The demonstration testing and operational implementation will be done at the Paducah Gaseous Diffusion Plant. The scope of work, schedule and cost for the activities are included in this proposal. A description of the facility to be constructed and tested is provided in Exhibit 1, attached. The USEC proposal for implementation at Paducah is presented in Exhibit 2, and the commitment letters from the site are included in Exhibit 3. Under our agreements with USEC, Bechtel Jacobs Corporation and DOE/Paducah, Vortec will be responsible for the construction of the demonstration facility as documented in the engineering design package submitted under Phase 4 of this contract on August 9, 2001. USEC will have responsibility for the demonstration testing and commercial implementation of the plant. The demonstration testing and initial commercial implementation of the technology will be achieved by means of a USEC work authorization task with the Bechtel Jacobs Corporation. The initial processing activities will include the processing of approximately 4,250 drums of LLW. Subsequent processing of LLW and TSCA/LLW will be done under a separate contract or work authorization task. To meet the schedule for commercial implementation, it is important that the execution of the Phase 4 project option for construction of the demonstration system be executed as soon as possible. The schedule we have presented herein assumes initiation of the construction phase by the end of September 2001. Vortec proposes to complete construction of the demonstration test system for an estimated cost of $3,254,422. This price is based on the design submitted to DOE/NETL under the Phase 4 engineering design deliverable (9 august 2001). The cost is subject to the assumptions and conditions identified in Section 6 of this proposal.

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

    SciTech Connect (OSTI)

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

    2007-07-01

    Illicit trafficking in nuclear and radioactive materials is far from a new issue. Reports of nuclear materials offered for sale as well as mythical materials such as red mercury date back to the 1960's. While such reports were primarily scams, it illustrates the fact that from an early date there were criminal elements willing to sell nuclear materials, albeit mythical ones, to turn a quick profit. In that same time frame, information related to lost and abandoned radioactive sources began to be reported. Unlike reports on nuclear material of that era, these reports on abandoned sources were based in fact - occasionally associated with resulting injury and death. With the collapse of the Former Soviet Union, illicit trafficking turned from a relatively unnoticed issue to one of global concern. Reports of unsecured nuclear and radiological material in the states of the Former Soviet Union, along with actual seizures of such material in transit, gave the clear message that illicit trafficking was now a real and urgent problem. In 1995, the IAEA established an Illicit Trafficking Data Base to keep track of confirmed instances. Illicit Trafficking is deemed to include not only radioactive materials that have been offered for sale or crossed international boarders, but also such materials that are no longer under appropriate regulatory control. As an outcome of 9/11, the United States took a closer look at illicit nuclear trafficking as well as a reassessment of the safety and security of nuclear and other radioactive materials both in the United States and Globally. This reassessment launched heightened controls and security domestically and increased our efforts internationally to prevent illicit nuclear trafficking. This reassessment also brought about the Global Threat Reduction Initiative which aims to further reduce the threats of weapons usable nuclear materials as well those of radioactive sealed sources. This paper will focus on the issues related to a subset of the materials involved in illicit trafficking in nuclear and radioactive materials, that of radioactive sealed sources. The focus on radioactive sealed sources is based on our belief that insufficient attention has been paid to trafficking incidents involving such sources which constitute the majority of trafficking cases. According to the IAEA's Illicit Trafficking Data Base, as of December 31 2005 there were 827 confirmed cases reporting by the participating states, including 250 incidents (or 30%) involved nuclear and other radioactive materials and 566 (or 68%) involved other radioactive materials, mostly radioactive sources, and radioactively contaminated materials. Experts in the Lugar Survey on Proliferation Threat and Response (June 2005) agreed that an attack with a Radiological Dispersion Device (RDD) was the most probable form of nuclear terrorism the world could expect over the next decade. At the same time radiological materials are used in wide a variety of applications, located in virtually every country and in general, radiological materials are far easier to access than nuclear materials. It has become increasingly obvious that the lack of a cradle-to-grave approach for sealed radioactive sources that have reached the end of their useful life is the main reason that sources are abandoned. It appears that the questions will ultimately become whether industry will impose additional regulations upon itself and become self-regulating with respect to repatriating radioactive material at the end of service life, or whether national authorities at some point will take actions and regulate the industry. Argentina, which is one of the most advanced countries regarding control of radiological sources adopted additional measures to safeguard its radiological materials to a level comparable to that proscribed for nuclear materials. This approach, while highly successful, has led to some minor unforeseen consequences, namely insufficient funds to implement all regulations in full and a lack of inspectors and appropriate equipment to assure compliance This

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

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

    SciTech Connect (OSTI)

    Hochel, R.C.

    1999-06-14

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

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

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

    ARRA Material Handling Equipment Composite Data Products Data through Quarter 3 of 2014 Chris Ainscough, Jennifer Kurtz May 2015 NREL/PR-5400-64362 2 CDP-MHE-102 Fuel Cell System Operation Hours 3 CDP-MHE-103 Fueling Events by Quarter 4 CDP-MHE-104 Hydrogen Dispensed by Quarter 5 CDP-MHE-105 Refueling Time of Day 6 CDP-MHE-106 Histogram of Fueling Times 7 CDP-MHE-107 Tank Pressure Level at Fueling 8 CDP-MHE-108 Operation Time between Fueling 9 CDP-MHE-109 Histogram of Fueling Rates 10

  5. Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

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

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

    SciTech Connect (OSTI)

    1995-08-01

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

  7. Office of Radiological Security

    National Nuclear Security Administration (NNSA)

    of physical security of radiological materials;

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

  10. Radiological Security Partnership | National Nuclear Security

    National Nuclear Security Administration (NNSA)

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

  11. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    the physical, chemical, and radiological hazards created by these agents and materials. ... The physical, chemical, and radiological properties of special tritium compounds may ...

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

    SciTech Connect (OSTI)

    Hancock, David, W.

    2012-02-14

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

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

    SciTech Connect (OSTI)

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

    2015-09-01

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

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

  15. 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.

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

    SciTech Connect (OSTI)

    David B. Frederick

    2011-02-01

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

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

    SciTech Connect (OSTI)

    Mike lewis

    2013-02-01

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

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

    SciTech Connect (OSTI)

    David Frederick

    2012-02-01

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

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

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

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

  20. Radiological Security Partnership | Y-12 National Security Complex

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

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

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

    SciTech Connect (OSTI)

    Not Available

    1985-09-01

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

  22. Tritium handling in vacuum systems

    SciTech Connect (OSTI)

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

    1986-10-01

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

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

    Office of Environmental Management (EM)

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

  2. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers’ Council

    2012-03-26

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

  3. Radiological Control

    Office of Environmental Management (EM)

    ... starts at the worker level and broadens as it ... releases as low as reasonably achievable. Radiological design criteria should ... with regard to integrated safety management (ISM). ...

  4. radiological. survey

    National Nuclear Security Administration (NNSA)

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

  5. Radiological Control

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

    2009-06-16

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

  6. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

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

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

    SciTech Connect (OSTI)

    J. R. Morton

    2000-09-01

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

  8. Bulk materials handling equipment roundup

    SciTech Connect (OSTI)

    Fiscor, S.

    2007-07-15

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

  9. Hydrogen Fuel for Material Handling

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

    CLASS 3 Forklift Value to the MHE Market z Trend has been toward electric - Indoor air quality issues z Early adopter of fuel cell technology technology - Fleet market - ...

  10. 2010 Manufacturing Readiness Assessment Update to the 2008 Report for Fuel Cell Stacks and Systems for the Backup Power and Materials Handling Equipment Markets

    SciTech Connect (OSTI)

    Wheeler, D.; Ulsh, M.

    2012-08-01

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

  11. Radiological Control

    National Nuclear Security Administration (NNSA)

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

  12. Radiological Security Partnership Information | National Nuclear Security

    National Nuclear Security Administration (NNSA)

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

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

    SciTech Connect (OSTI)

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

    1991-01-01

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

  14. Radiological safety training for uranium facilities

    SciTech Connect (OSTI)

    1998-02-01

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

  15. Radiological Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

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

  16. DOE handbook: Tritium handling and safe storage

    SciTech Connect (OSTI)

    1999-03-01

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

  17. ORISE: Radiological program assessment services

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

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

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

    National Nuclear Security Administration (NNSA)

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

  19. Radiological Control Technician Training

    Energy Savers [EERE]

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

  20. Paint for detection of radiological or chemical agents

    DOE Patents [OSTI]

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

    2010-08-24

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

  1. Unvented Drum Handling Plan

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    2000-08-01

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

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

    Office of Environmental Management (EM)

    Design Competition | Department of Energy Prairie View A&M Tops 2016 U.S. Department of Energy Race to Zero Student Design Competition Prairie View A&M Tops 2016 U.S. Department of Energy Race to Zero Student Design Competition April 22, 2016 - 3:00pm Addthis As part of the Obama Administration's commitment to helping families across the United States save money by saving energy, the U.S. Department of Energy announced winners of its third annual Race to Zero Student Design

  3. PRE-HOSPITAL PRACTICES FOR HANDLING A RADIOLOGICALLY CONTAMINATED PATIENT

    Office of Environmental Management (EM)

    IMPERIAL IRRIGATION DISTRICT ORDER NO. PP-174 I. BACKGROUND The Office of Fossil Energy (FE) of the Department of Energy (DOE) has the responsibility for implementing Executive Order (EO) 10485, as amended by EO 12038, which requires the issuance of Presidential permits for the construction, connection, operation, and maintenance of electric transmission facilities at the United States international border. In an application

  4. Puck Handling Glovebox

    SciTech Connect (OSTI)

    Fiscus, J.B.

    2001-01-29

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

  5. INL@Work Radiological Search & Response Training

    SciTech Connect (OSTI)

    Turnage, Jennifer

    2010-01-01

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

  6. INL@Work Radiological Search & Response Training

    ScienceCinema (OSTI)

    Turnage, Jennifer

    2013-05-28

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

  7. material recovery

    National Nuclear Security Administration (NNSA)

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

  8. Handling and characterization of glow-discharge polymer samples...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Handling and characterization of glow-discharge polymer samples for the ... Subject: 71 CLASSICAL AND QUANTUMM MECHANICS, GENERAL PHYSICS; 36 MATERIALS SCIENCE; 37 ...

  9. NV/YMP radiological control manual, Revision 2

    SciTech Connect (OSTI)

    Gile, A.L.

    1996-11-01

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

  10. Accident Investigation Report - Radiological Release | Department of Energy

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

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

  11. International Data on Radiological Sources

    SciTech Connect (OSTI)

    Martha Finck; Margaret Goldberg

    2010-07-01

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

  12. Radiological Control Technician Training

    Energy Savers [EERE]

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

  13. Solid waste handling

    SciTech Connect (OSTI)

    Parazin, R.J.

    1995-05-31

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

  14. Uranium hexafluoride handling. Proceedings

    SciTech Connect (OSTI)

    Not Available

    1991-12-31

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

  15. Puck Handling Glovebox

    SciTech Connect (OSTI)

    Fiscus, J.B.

    2001-01-03

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

  16. Solid handling valve

    DOE Patents [OSTI]

    Williams, William R.

    1979-01-01

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

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

    Office of Environmental Management (EM)

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

  18. Virtual Reality for Nuclear Material Handling

    Broader source: Energy.gov [DOE]

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

  19. Specialty Vehicles and Material Handling Equipment

    Broader source: Energy.gov [DOE]

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

  20. DOE Issues WIPP Radiological Release Investigation Report

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

    4, 2014 DOE Issues WIPP Radiological Release Investigation Report Today, the Department of Energy's (DOE) Office of Environmental Management (EM) released the initial accident investigation report related to the February 14 radiological release at the Waste Isolation Pilot Plant (WIPP). The report's initial investigation focused on the reaction to the radioactive material release, including related exposure to aboveground workers and the response actions. After the entry teams determine the

  1. Flashback: Rapid scanning for radiological threats

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

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

  2. Sectional device handling tool

    DOE Patents [OSTI]

    Candee, Clark B.

    1988-07-12

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

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

    SciTech Connect (OSTI)

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

    2011-08-18

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

  4. Radiological Worker Training

    Office of Environmental Management (EM)

    ... for Evaluation of Nuclear Facility Training Programs." ... the Radiological Safety Training for ... affect photon energy and power. 6. Explain how X-rays ...

  5. Radiological Worker Training

    Office of Environmental Management (EM)

    ... is to provide a high level of knowledge and skills in ... Reduction Radioactive Waste Minimization Personnel ... Radiological Worker Training Program Management Monitor ...

  6. Radiological Assistance Program

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

    1992-04-10

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

  7. Biomass Engineering: Transportation & Handling

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

    ... * Updated results show materials have similar particles sizes and shapes. * Microscopy indicates that flowability at low compressive stresses depends primarily upon ...

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

    SciTech Connect (OSTI)

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

    1998-10-14

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

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

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2012-03-13

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

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

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2013-04-02

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

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

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2010-08-24

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

  12. ORISE: Radiological program assessment services

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

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

  13. ORISE: REAC/TS Radiological Incident Medical Consultation

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

    Radiological Incident Medical Consultation Radiological Incident Medical Consultation The Oak Ridge Institute for Science and Education (ORISE) provides the U.S. Department of Energy (DOE) with a comprehensive capability to respond effectively to medical emergencies involving radiological or nuclear materials. Through the management of the Radiation Emergency Assistance Center/Training Site (REAC/TS), ORISE provides advice and consultation to emergency personnel responsible for the medical

  14. REMOTE HANDLING ARRANGEMENTS

    DOE Patents [OSTI]

    Ginns, D.W.

    1958-04-01

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

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

    DOE Patents [OSTI]

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

    2012-03-27

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

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

    DOE Patents [OSTI]

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

    2013-04-02

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

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

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-04-01

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

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

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-08-01

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

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

    SciTech Connect (OSTI)

    Gary Mecham

    2010-05-01

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

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

    SciTech Connect (OSTI)

    Gary Mecham

    2010-10-01

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

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

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2015-03-01

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

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

    SciTech Connect (OSTI)

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

    2005-02-02

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

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

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

    2011-08-09

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

  4. HAND TRUCK FOR HANDLING EQUIPMENT

    DOE Patents [OSTI]

    King, D.W.

    1959-02-24

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

  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. Radiological/biological/aerosol removal system

    DOE Patents [OSTI]

    Haslam, Jeffery J

    2015-03-17

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

  7. DOE standard: Radiological control

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

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

  8. Waste handling activities in glovebox dismantling facility

    SciTech Connect (OSTI)

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

    2007-07-01

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

  9. INTERNATIONAL COOPERATION ON RADIOLOGICAL THREAT REDUCTION PROGRAMS IN RUSSIA

    SciTech Connect (OSTI)

    Landers, Christopher C.; Tatyrek, Aaron P.

    2009-10-07

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

  10. Radiological worker training

    SciTech Connect (OSTI)

    1998-10-01

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

  11. Property:TwitterHandle | Open Energy Information

    Open Energy Info (EERE)

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

  12. 324 Building Baseline Radiological Characterization

    SciTech Connect (OSTI)

    R.J. Reeder, J.C. Cooper

    2010-06-24

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

  13. Radiological Control Technician Training

    Energy Savers [EERE]

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

  14. Radiological Control Technician Training

    Energy Savers [EERE]

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

  15. Radiological Technician Training

    Energy Savers [EERE]

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

  16. Radiological Worker Training - Radiological Contamination Control...

    Energy Savers [EERE]

    ... Program Management 15 Materials Checklist The following ... 23 V. RADIOACTIVE WASTE MANAGEMENT......gamma emitters near low background counting ...

  17. Tritium Handling and Safe Storage

    Energy Savers [EERE]

    NOT MEASUREMENT SENSITIVE DOE-STD-1129-2015 September 2015 DOE STANDARD TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-STD-1129-2015 ii TABLE OF CONTENTS FOREWORD ............................................................................................................................................. 1 ACRONYMS

  18. Portable vacuum object handling device

    DOE Patents [OSTI]

    Anderson, Gordon H.

    1983-08-09

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

  19. Non-contact handling device

    DOE Patents [OSTI]

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

    2007-05-15

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

  20. Materials

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

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

  1. General Employee Radiological Training

    Energy Savers [EERE]

    _______ Change Notice 1 June 2009 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The average annual radiation dose to a

  2. General Employee Radiological Training

    Energy Savers [EERE]

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

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

    National Nuclear Security Administration (NNSA)

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

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

    Broader source: Energy.gov [DOE]

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

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

    SciTech Connect (OSTI)

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

    1986-02-01

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

  6. Tritium Handling and Safe Storage

    Energy Savers [EERE]

    DOE-HDBK-1129-2008 December 2008 DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-HDBK-1129-2008 ii This page is intentionally blank. DOE-HDBK-1129-2008 iii TABLE OF CONTENTS SECTION PAGE FOREWORD................................................................................................................................ ix ACRONYMS

  7. Tritium Handling and Safe Storage

    Energy Savers [EERE]

    SENSITIVE DOE-HDBK-1129-2007 March 2007 ____________________ DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1129-2007 ii This page is intentionally blank. DOE-HDBK-1129-2007 iii TABLE OF CONTENTS SECTION PAGE FOREWORD............................................................................................................................... vii

  8. Portable vacuum object handling device

    DOE Patents [OSTI]

    Anderson, G.H.

    1983-08-09

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

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

    SciTech Connect (OSTI)

    1995-01-01

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

  10. Material Safety Data Sheets

    Broader source: Energy.gov [DOE]

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

  11. I COMPREHENSIVE RADIOLOGICAL SURVEY I

    Office of Legacy Management (LM)

    im I COMPREHENSIVE RADIOLOGICAL SURVEY I Prepared by Oak Ridge Associated Universities Prprd* OFF-SITE PROPERTY H' | Prepared for Office of Operational FORMER LAKE ONTARIO ORDNANCE WORKS SITE Safety U.S. Department LEWISTON, NEW YORK I of Energy i J.D. BERGER i Radiological Site Assessment Program Manpower Education, Research, and Training Division I l*~~~~~~ ~~~~DRAFT REPORT January 1983 I I I ------- COMPREHENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY H' FORMER LAKE ONTARIO ORDNANCE WORKS SITE

  12. Smart Radiological Dosimeter

    DOE Patents [OSTI]

    Kosslow, William J.; Bandzuch, Gregory S.

    2004-07-20

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

  13. ORNL-5680 Radiological Surveys

    Office of Legacy Management (LM)

    DOVEV-0005/l (Supplement) ORNL-5680 Radiological Surveys of Properties in the Middlesex, New Jersey, Area R. W. Leggett D. L. Anderson F. F. Haywood D. J. Christian W. D. Cottrell R. W. Doane D. J. Crawford W. H. Shinpaugh E. B. Wagner T. E. Myrick W. A. Goldsmith Printed in the United States of America. Available from National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road, Springfield, Virginia 22161 NTIS price codes-Printed Copy: A07 Microfiche ,401 I I This

  14. Radiological Control Technician Training

    Energy Savers [EERE]

    _______ Change Notice 1 June 2009 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009 Original Change Part 3 1.05-1 NCRP Report No. 93

  15. Radiological Control Technician Training

    Energy Savers [EERE]

    Change Notice No. 1 2009 Change Notice No. 2 2011 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009 Original Change Part 3 1.05-1 NCRP

  16. Radiological Worker Computer Based Training

    Energy Science and Technology Software Center (OSTI)

    2003-02-06

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

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

    National Nuclear Security Administration (NNSA)

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

  18. PIA - Radiological Work Permit | Department of Energy

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

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

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

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

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

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

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

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

  1. radiological response | National Nuclear Security Administration

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

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

  2. Standardized radiological dose evaluations

    SciTech Connect (OSTI)

    Peterson, V.L.; Stahlnecker, E.

    1996-05-01

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

  3. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    J.F. Beesley

    2005-04-21

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

  4. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M.

    1990-01-01

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

  5. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M.

    1989-01-01

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

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

    SciTech Connect (OSTI)

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

    1997-12-31

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

  7. Enewetak radiological support project. Final report

    SciTech Connect (OSTI)

    Friesen, B.

    1982-09-01

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

  8. 327 Building liquid waste handling options modification project plan

    SciTech Connect (OSTI)

    Ham, J.E.

    1998-03-28

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

  9. Apparatus for remotely handling components

    DOE Patents [OSTI]

    Szkrybalo, Gregory A.; Griffin, Donald L.

    1994-01-01

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

  10. Radiological cleanup of Enewetak Atoll

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

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

  11. Estimate Radiological Dose for Animals

    Energy Science and Technology Software Center (OSTI)

    1997-12-18

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

  12. Radiological Worker Training

    Office of Environmental Management (EM)

    ... DOE-HDBK-1130-2008 Program Management Materials Checklist The following ... V. RADIOACTIVE WASTE MANAGEMENT......gamma emitters near low background counting ...

  13. Radiological Monitoring Continues at WIPP

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

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

  14. LANL responds to radiological incident

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

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

  15. Radiological training for tritium facilities

    SciTech Connect (OSTI)

    1996-12-01

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

  16. Radiological Protection for DOE Activities

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

    1995-09-29

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

  17. Feed Processing, Handling, and Gasification

    SciTech Connect (OSTI)

    2006-04-01

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

  18. Radiological assessment. A textbook on environmental dose analysis

    SciTech Connect (OSTI)

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

    1983-09-01

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

  19. Radiological Control Technician Training

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

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

  20. Sensors & Materials | Argonne National Laboratory

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

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

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

    SciTech Connect (OSTI)

    Manohar S. Sohal; J. Stephen Herring

    2008-07-01

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

  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

    2013-09-01

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

  3. Radiological control manual. Revision 1

    SciTech Connect (OSTI)

    Kloepping, R.

    1996-05-01

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

  4. Neutron Energy Measurements in Radiological Emergency Response Applications

    SciTech Connect (OSTI)

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

    2009-04-30

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

  5. NNSA Provides Tajikistan Specialized Vehicles to Transport Radiological

    National Nuclear Security Administration (NNSA)

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

  6. Reference Materials

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

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

  7. 2004 Biodiesel Handling and Use Guidelines (Revised)

    SciTech Connect (OSTI)

    Not Available

    2004-11-01

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

  8. Storage/Handling | Department of Energy

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

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

  9. Departmental Radiological Emergency Response Assets

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

    2007-06-27

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

  10. Nuclear and Radiological Forensics and Attribution Overview

    SciTech Connect (OSTI)

    Smith, D K; Niemeyer, S

    2005-11-04

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

  11. TEPP Training - Modular Emergency Response Radiological Transportation

    Energy Savers [EERE]

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

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

    Office of Environmental Management (EM)

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

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

    SciTech Connect (OSTI)

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

    2011-09-01

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

  14. Biodiesel Handling and Use Guide | Open Energy Information

    Open Energy Info (EERE)

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

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

    Office of Environmental Management (EM)

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

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

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

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

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

    SciTech Connect (OSTI)

    Danny Anderson

    2014-07-01

    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.

  18. Automated system for handling tritiated mixed waste

    SciTech Connect (OSTI)

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

    1995-03-01

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

  19. Understanding Mechanisms of Radiological Contamination

    SciTech Connect (OSTI)

    Rick Demmer; John Drake; Ryan James, PhD

    2014-03-01

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

  20. DOE - Office of Legacy Management -- Reactor Site - Fort Belvoir...

    Office of Legacy Management (LM)

    VA.0-02-1 Site Disposition: Eliminated - Referred to DOD VA.0-02-1 Radioactive Materials Handled: Reactor fuel Primary Radioactive Materials Handled: Reactor Fuel Radiological ...

  1. DOE - Office of Legacy Management -- Petrolite Corp - MO 08

    Office of Legacy Management (LM)

    Materials Handled: Yes Primary Radioactive Materials Handled: Uranium Flouride & Thorium Oxide MO.08-2 Radiological Survey(s): None Indicated Site Status: Eliminated from ...

  2. Nuclear Materials: Reconsidering Wastes and Assets - 13193

    SciTech Connect (OSTI)

    Michalske, T.A.

    2013-07-01

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

  3. Global Material Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Nonproliferation Global Material Security The mission of the Office of Global Material Security (GMS) is to help partner countries secure and account for nuclear weapons, weapons-useable nuclear and radiological materials, as well as to build capacity to deter, detect and interdict the illicit trafficking of such materials. GMS achieves its mission through three subprograms: International Nuclear Security Radiological Security Nuclear Smuggling Detection and Deterrence (formerly Second Line of

  4. Nuclear / Radiological Advisory Team | National Nuclear Security

    National Nuclear Security Administration (NNSA)

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

  5. Radiological Assistance Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

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

  6. Radiological Triage | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

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

  7. Environmental/Radiological Assistance Directory (ERAD) | Department...

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

    The Environmental Radiological Assistance Directory or ERAD, developed by AU-22, serves as an assistance tool to the DOE complex for protection of the public and environment from ...

  8. Cardiovascular and Interventional Radiological Society of Europe...

    Office of Scientific and Technical Information (OSTI)

    Springer Science+Business Media New York and the Cardiovascular and Interventional Radiological Society of Europe (CIRSE); http:www.springer-ny.com; Country of ...

  9. NEVADA TEST SITE RADIOLOGICAL CONTROL MANUAL

    Office of Scientific and Technical Information (OSTI)

    ... in both normal and changing radiological conditions. ... to ensure that RCTs meet the standards for education. ... Personnel Monitoring: Systematic and periodic estimates of ...

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

    National Nuclear Security Administration (NNSA)

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

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

    National Nuclear Security Administration (NNSA)

    ... System (AMS), and the Radiation Emergency Assistance CenterTraining Site (REACTS). ... radiological analysis and data assessments; and medical advice for radiation injuries. ...

  12. Radiological Contamination Control Training for Laboratory Research

    Energy Savers [EERE]

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

  13. RADIOLOGICAL ASSESSMENT OF BALLOD AND ASSOCIATES PROPERTY

    Office of Legacy Management (LM)

    RADIOLOGICAL ASSESSMENT OF BALLOD AND ASSOCIATES PROPERTY (STEPAN CHEMICAL COMPANY) ... BALLOD A:D ASSSOCIATES PROPERTY (STEPAN CHEMICAL COMPANY) MAYWOOD, NEW JERSEY ...

  14. radiological. survey | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    survey NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas A U.S. Department of Energy National Nuclear Security...

  15. Radiological Assistance Program Flight Planning Tool

    SciTech Connect (OSTI)

    2011-12-19

    The Radiological Assitance Program (RAP) is the National Nuclear Security Administration's (NNSA) first responder to radiological emergencies. RAP's mission is to identify and minimize radiological hazards, as well as provide radiological emergency response and technical advice to decision makers. One tool commonly used is aerial radiation detection equipment. During a response getting this equipment in the right place quickly is critical. The RAP Flight Planning Tool (a ArcGIS 10 Desktop addin) helps minimize this response time and provides specific customizable flight path information to the flight staff including maps, coordinates, and azimuths.

  16. Radiological Assistance Program Flight Planning Tool

    Energy Science and Technology Software Center (OSTI)

    2011-12-19

    The Radiological Assitance Program (RAP) is the National Nuclear Security Administration's (NNSA) first responder to radiological emergencies. RAP's mission is to identify and minimize radiological hazards, as well as provide radiological emergency response and technical advice to decision makers. One tool commonly used is aerial radiation detection equipment. During a response getting this equipment in the right place quickly is critical. The RAP Flight Planning Tool (a ArcGIS 10 Desktop addin) helps minimize this responsemore » time and provides specific customizable flight path information to the flight staff including maps, coordinates, and azimuths.« less

  17. Radiological Contamination Control Training for Laboratory Research

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

    Available to DOE and DOE contractors from ES&H Technical ......... 13 Course Description......outlined in the DOE Radiological Control (RadCon) Standard. ...

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

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

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

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

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

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

  20. Operating Experience Level 3: Radiologically Contaminated Respirators...

    Energy Savers [EERE]

    Experience Level 3 provides information on a safety concern related to radiological contamination of launderedreconditioned respirators and parts that have been certified as...

  1. Progress Continues on Mitigation of Radiological Contamination

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

    August 13, 2015 Progress Continues on Mitigation of Radiological Contamination This week, WIPP personnel will complete the installation of the brattice cloth and salt barrier on a...

  2. Radiological Training for Tritium Facilities

    Energy Savers [EERE]

    Change Notice No. 2 May 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of

  3. Radiological Worker Training - Radiological Safety Training for Radiation Producing (X-Ray) Devices

    Energy Savers [EERE]

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

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

    SciTech Connect (OSTI)

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

    2008-12-01

    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.

  5. DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E. F. Loros

    2000-06-30

    The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

  6. 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)

    2014-07-25

    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.

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

    SciTech Connect (OSTI)

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

    2013-04-01

    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.

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

    SciTech Connect (OSTI)

    Bohachek, Randy; Wallace, Bruce; Winston, Phil; Marschman, Steve

    2013-04-30

    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.

  9. CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2005-04-07

    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].

  10. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council - Nevada Test Site

    2009-10-01

    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.

  11. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council Nevada Test Site

    2010-02-09

    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.

  12. Federal Radiological Monitoring and Assessment Center

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

    1992-12-02

    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.

  13. Memorandum, Reporting of Radiological Sealed Sources Transactions

    Broader source: Energy.gov [DOE]

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed Sources. The data reported in accordance with DOE N 234.1 are maintained in the DOE Radiological Source Registry and Tracking (RSRT) database by the Office of Information Management, within the Office of Environment, Health, Safety and Security.

  14. System for detecting special nuclear materials

    DOE Patents [OSTI]

    Jandel, Marian; Rusev, Gencho Yordanov; Taddeucci, Terry Nicholas

    2015-07-14

    The present disclosure includes a radiological material detector having a convertor material that emits one or more photons in response to a capture of a neutron emitted by a radiological material; a photon detector arranged around the convertor material and that produces an electrical signal in response to a receipt of a photon; and a processor connected to the photon detector, the processor configured to determine the presence of a radiological material in response to a predetermined signature of the electrical signal produced at the photon detector. One or more detectors described herein can be integrated into a detection system that is suited for use in port monitoring, treaty compliance, and radiological material management activities.

  15. 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.

    2005-08-01

    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.

  16. Office of Radiological Security | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    Gallery Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home Office of Radiological Security Office of Radiological Security NNSA Provides Tajikistan...

  17. Office of Radiological Security | Y-12 National Security Complex

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

    Office of Radiological ... Office of Radiological Security Read more about Y-12's contributions of the Global Threat Reduction Initiative to secure the world's most vulnerable...

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

    Office of Environmental Management (EM)

    Annex for Preparedness and Response to Radiological Transportation Incidents Model Annex for Preparedness and Response to Radiological Transportation Incidents This part should...

  19. MODARIA: Modelling and Data for Radiological Impact Assessment...

    Office of Environmental Management (EM)

    MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview Presentation...

  20. Hawaii Department of Health Indoor and Radiological Health Branch...

    Open Energy Info (EERE)

    Indoor and Radiological Health Branch Jump to: navigation, search Name: Hawaii Department of Health Indoor and Radiological Health Branch From Open Energy Information Address: 591...

  1. Los Alamos National Security Corrective Action Plan - Radiological...

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

    Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security ...

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

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

    Course Number: Radiological Control Technicians Module ... Module 2.15 Radiological Considerations for First Aid ... want to remove the machine from the room ASAP. 2) ...

  3. Innovative methods for corn stover collecting, handling, storing and transporting

    SciTech Connect (OSTI)

    Atchison, J. E.; Hettenhaus, J. R.

    2004-04-01

    Investigation of innovative methods for collecting, handling, storing, and transporting corn stover for potential use for production of cellulosic ethanol.

  4. System for handling and storing radioactive waste

    DOE Patents [OSTI]

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

    1982-07-19

    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.

  5. System for handling and storing radioactive waste

    DOE Patents [OSTI]

    Anderson, John K.; Lindemann, Paul E.

    1984-01-01

    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.

  6. Materials Videos

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

    Materials Videos Materials

  7. Contact-Handled Transuranic Waste Authorized Methods for Payload...

    Office of Environmental Management (EM)

    This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the ...

  8. Radiological Training for Tritium Facilities

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

    ... personnel. - Evaluate training program effectiveness. - Modify training materials based on evaluation of training program. *Stein, F. Instructor Competencies: The Standards. ...

  9. DOE - Office of Legacy Management -- Exxon Ray Point Site - 032

    Office of Legacy Management (LM)

    Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This site is a Uranium Mill Tailings Rmedial Action (UMTRA) title II site located in Texas. ...

  10. 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

    2012-05-01

    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

  11. Nuclear Radiological Threat Task Force Established | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Radiological Threat Task Force Established Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task Force (NRTRTF) to combat the threats posed by radiological dispersion devices or "dirty bombs."

  12. Understanding Contamination; Twenty Years of Simulating Radiological Contamination

    SciTech Connect (OSTI)

    Emily Snyder; John Drake; Ryan James

    2012-02-01

    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.

  13. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    Bzorgi, Fariborz M

    2014-10-07

    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.

  14. OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL

    Office of Legacy Management (LM)

    - Field Survey Supervisor Survey Team Members E. T. Loy R. S. Ray C. N. Smith R. R. Smith Work performed as part of the RADIOLOGICAL SURVEY ACTIVITIES PROGRAM Prepared by ...

  15. DOE Issues WIPP Radiological Release Investigation Report

    Broader source: Energy.gov [DOE]

    Today, the Department of Energy’s Office of Environmental Management (EM) released the initial accident investigation report related to the Feb. 14 radiological release at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico.

  16. Error handling strategies in multiphase inverse modeling

    SciTech Connect (OSTI)

    Finsterle, S.; Zhang, Y.

    2010-12-01

    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.

  17. Experiences with decontaminating tritium-handling apparatus

    SciTech Connect (OSTI)

    Maienschein, J.L.; Garcia, F.; Garza, R.G.; Kanna, R.L.; Mayhugh, S.R.; Taylor, D.T. )

    1992-03-01

    Tritium-handling apparatus has been decontaminated as part of the downsizing of the LLNL Tritium Facility. Two stainless-steel glove boxes that had been used to process lithium deuteride-tritide (LiDT) slat were decontaminated using the Portable Cleanup System so that they could be flushed with room air through the facility ventilation system. In this paper the details on the decontamination operation are provided. A series of metal (palladium and vanadium) hydride storage beds have been drained of tritium and flushed with deuterium, in order to remove as much tritium as possible. The bed draining and flushing procedure is described, and a calculational method is presented which allows estimation of the tritium remaining in a bed after it has been drained and flushed. Data on specific bed draining and flushing are given.

  18. Primer on tritium safe handling practices

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    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.

  19. Method and system rapid piece handling

    DOE Patents [OSTI]

    Spletzer, Barry L.

    1996-01-01

    The advent of high-speed fabric cutters has made necessary the development of automated techniques for the collection and sorting of garment pieces into collated piles of pieces ready for assembly. The present invention enables a new method for such handling and sorting of garment parts, and to apparatus capable of carrying out this new method. The common thread is the application of computer-controlled shuttling bins, capable of picking up a desired piece of fabric and dropping it in collated order for assembly. Such apparatus with appropriate computer control relieves the bottleneck now presented by the sorting and collation procedure, thus greatly increasing the overall rate at which garments can be assembled.

  20. Fuel handling system for a nuclear reactor

    DOE Patents [OSTI]

    Saiveau, James G.; Kann, William J.; Burelbach, James P.

    1986-01-01

    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.

  1. Environmental Management Headquarters Corrective Action Plan - Radiological

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

    Release Phase I | Department of Energy I Environmental Management Headquarters Corrective Action Plan - Radiological Release Phase I The purpose of this Corrective Action Plan (CAP) is to specify U.S. Department of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 1: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified 31

  2. Environmental Management Headquarters Corrective Action Plan - Radiological

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

    Release Phase II | Department of Energy II Environmental Management Headquarters Corrective Action Plan - Radiological Release Phase II The purpose ofthis Corrective Action Plan (CAP) is to specify U.S. Department of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 2: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified

  3. Radiological Primer Common Understanding of Terms

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

    Radiological Primer Understanding Radiological Terms Richard Bloom and Dr. Antone Brooks Health Safety Environmental Protection Committee Hanford Advisory Board Tom Rogers and Crystal Mathey Washington State Department of Health Radioactivity vs. Radiation  What is radioactivity?  Property exhibited by certain types of matter of emitting radiation spontaneously.  What is radiation?  Process by which energy is emitted from a source  Forms of ionizing radiation  Gamma (photons)

  4. Overview on Hydrate Coring, Handling and Analysis

    SciTech Connect (OSTI)

    Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

    2003-06-30

    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.

  5. Computer Model Buildings Contaminated with Radioactive Material

    Energy Science and Technology Software Center (OSTI)

    1998-05-19

    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.

  6. Radiological risk assessment of environmental radon

    SciTech Connect (OSTI)

    Khalid, Norafatin; Majid, Amran Ab; Yahaya, Redzuwan; Yasir, Muhammad Samudi

    2013-11-27

    Measurements of radon gas ({sup 222}Rn) in the environmental are important to assess indoor air quality and to study the potential risk to human health. Generally known that exposure to radon is considered the second leading cause of lung cancer after smoking. The environmental radon concentration depends on the {sup 226}Ra concentration, indoor atmosphere, cracking on rocks and building materials. This study was carried out to determine the indoor radon concentration from selected samples of tin tailings (amang) and building materials in an airtight sealed homemade radon chamber. The radiological risk assessment for radon gas was also calculated based on the annual exposure dose, effective dose equivalent, radon exhalation rates and fatal cancer risk. The continuous radon monitor Sun Nuclear model 1029 was used to measure the radon concentration emanates from selected samples for 96 hours. Five types of tin tailings collected from Kampar, Perak and four samples of building materials commonly used in Malaysia dwellings or building constructions were analysed for radon concentration. The indoor radon concentration determined in ilmenite, monazite, struverite, xenotime and zircon samples varies from 219.6 76.8 Bq m{sup ?3} to 571.1 251.4 Bq m{sup ?3}, 101.0 41.0 Bq m{sup ?3} to 245.3 100.2 Bq m{sup ?3}, 53.1 7.5 Bq m{sup ?3} to 181.8 9.7 Bq m{sup ?3}, 256.1 59.3 Bq m{sup ?3} to 652.2 222.2 Bq m{sup ?3} and 164.5 75.9 Bq m{sup ?3} to 653.3 240.0 Bq m{sup ?3}, respectively. Whereas, in the building materials, the radon concentration from cement brick, red-clay brick, gravel aggregate and cement showed 396.3 194.3 Bq m{sup ?3}, 192.1 75.4 Bq m{sup ?3}, 176.1 85.9 Bq m{sup ?3} and 28.4 5.7 Bq m{sup ?3}, respectively. The radon concentration in tin tailings and building materials were found to be much higher in xenotime and cement brick samples than others. All samples in tin tailings were exceeded the action level for radon gas of 148 Bq m{sup ?3} proposed by EPA except monazite 0.15 kg, struverite 0.15 kg and 0.25 kg. Whereas, all building material samples have exceeded the radon concentration in concrete and building materials of 3 to 7 Bq m{sup ?3} estimated by ICRP. The annual effective dose, effective dose equivalent, and radon exhalation rates in tin tailings were calculated to be in the range of 2.47 to 11.46 mSv, 5.94 to 1090.56 mSv y{sup ?1}, and 0.23 to 1.18 mBq kg{sup ?1} h{sup ?1}. For building materials, the calculated risk assessment of the annual effective dose, effective dose equivalent, radon exhalation rates and fatal cancer risk were 0.72 to 10.00 mSv, 1.73 to 24.00 mSv y{sup ?1}, 0.010 to 0.06 mBq kg{sup ?1} h{sup ?1} and 40 to 550 chances of persons will suffer the cancer per million (1 10{sup 6}), respectively.

  7. Los Alamos National Security Corrective Action Plan - Radiological Release

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

    Phase II | Department of Energy Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II PDF icon Los Alamos National Security Corrective Action Plan - Radiological Release Phase II More Documents & Publications Environmental Management Los Alamos Field Office Corrective Action Plan - Radiological Release Phase II

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

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03

    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.

  9. Remote-Handled Transuranic Content Codes

    SciTech Connect (OSTI)

    Washington TRU Solutions

    2006-12-01

    The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is 3. The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code.

  10. Radiological Instrumentation Assessment for King County Wastewater Treatment Division

    SciTech Connect (OSTI)

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

    2005-05-19

    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 μCi 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.

  11. LM Records Handling System (LMRHS01) - Electronic Records Keeping System,

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

    Office of Legacy Management, | Department of Energy System (LMRHS01) - Electronic Records Keeping System, Office of Legacy Management, LM Records Handling System (LMRHS01) - Electronic Records Keeping System, Office of Legacy Management, LM Records Handling System (LMRHS01) - Electronic Records Keeping System, Office of Legacy Management, PDF icon LM Records Handling System (LMRHS01) - Electronic Records Keeping System, Office of Legacy Management, More Documents & Publications LM

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

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

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

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

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

    Database, Office of Legacy Management | Department of Energy Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management PDF icon LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management More Documents &

  14. 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 ...

  15. Literature Survey of Crude Oil Properties Relevant to Handling...

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

    Relevant to Handling and Fire Safety in Transport - Sandia Energy Energy Search Icon ... Transportation Energy Co-Evolution of Biofuels Lignocellulosic Biomass Microalgae ...

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

    SciTech Connect (OSTI)

    Not Available

    2009-01-01

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

  17. Widget:TwitterHandleValidate | Open Energy Information

    Open Energy Info (EERE)

    common copy + paste errors, and alerting the user if the format is not a valid Twitter handle. Parameters include: fieldname - the field to validate (optional, default:...

  18. Literature Survey of Crude Oil Properties Relevant to Handling...

    Office of Scientific and Technical Information (OSTI)

    Literature Survey of Crude Oil Properties Relevant to Handling and Fire Safety in Transport. Citation Details In-Document Search Title: Literature Survey of Crude Oil Properties ...

  19. Handbook for Handling, Storing, and Dispensing E85 and Other...

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    ... Solubility in Water Ethanol is extremely hydroscopic (i.e., attracts water). Water should be removed to the extent possible from fuel ethanol handling, storage, and distribution ...

  20. Processing and Disposition of Remote-Handled Transuranic Liquid...

    Office of Scientific and Technical Information (OSTI)

    Liquid Waste Generated at Oak Ridge National Laboratory Citation Details In-Document Search Title: Processing and Disposition of Remote-Handled Transuranic Liquid Waste Generated ...

  1. Handbook for Handling, Storing, and Dispensing E85

    SciTech Connect (OSTI)

    Not Available

    2008-04-01

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

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

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

    Handling Equipment | Department of Energy An Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment An Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment This report by the National Renewable Energy Laboratory discusses an analysis of the total cost of ownership of fuel cell-powered and traditional battery-powered material handling equipment, including the capital costs of battery and fuel cell systems, the cost of

  3. Experiences with decontaminating tritium-handling apparatus

    SciTech Connect (OSTI)

    Maienschein, J.L.; Garcia, F.; Garza, R.G.; Kanna, R.L.; Mayhugh, S.R.; Taylor, D.T.

    1991-07-01

    Tritium-handling apparatus has been decontaminated as part of the shutdown of the LLNL Tritium Facility. Two stainless-steel gloveboxes that had been used to process lithium deuteride-tritide (LiDT) salt were decontaminated using the Portable Cleanup System so that they could be flushed with room air through the facility ventilation system. Further surface decontamination was performed by scrubbing the interior with paper towels and ethyl alcohol or Swish{trademark}. The surface contamination, as shown by swipe surveys, was reduced from 4{times}10{sup 4}--10{sup 6} disintegrations per minute (dpm)/cm{sup 2} to 2{times}10{sup 2}--4{times}10{sup 4} dpm/cm{sup 2}. Details on the decontamination operation are provided. A series of metal (palladium and vanadium) hydride storage beds have been drained of tritium and flushed with deuterium in order to remove as much tritium as possible. The bed draining and flushing procedure is described, and a calculational method is presented which allows estimation of the tritium remaining in a bed after it has been drained and flushed. Data on specific bed draining and flushing are given.

  4. Appendix B - Chemical and Radiological Inventories for the CEMRC, pages 1-4

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

    B-1 APPENDIX B CHEMICAL AND RADIOLOGICAL INVENTORIES FOR THE CEMRC The current inventories of chemicals and radiological materials at the Carlsbad Environmental Monitoring and Research Center (CEMRC) are provided in Tables B-1 and B-2, respectively. These tables were provided by Joel Webb, Director of the CEMRC, New Mexico State University (Webb 2002). Table B-1. Onsite CEMRC Chemical Inventory Chemical Name Amount Units SARA Limit Acetic Acid, Glacial 5,400 mL NA a Acetone 38 L NA AA Modifier

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

    SciTech Connect (OSTI)

    Lisa Harvego

    2009-06-01

    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.

  6. Order Module--DOE STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL...

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

    STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL Order Module--DOE STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL "The radiological control program discussed in ...

  7. Radiological Risk Assessment for King County Wastewater Treatment Division

    SciTech Connect (OSTI)

    Strom, Daniel J.

    2005-08-05

    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.

  8. CURRENT APPLICATIONS OF THREE MILE ISLAND-2 CORE AND DEBRIS HANDLING AT THE IDAHO NATIONAL LABORATORY

    SciTech Connect (OSTI)

    Carmack, William Jonathan; Braase, Lori Ann

    2015-09-01

    Fuel recovery from severe accidents requires careful planning and execution. The Idaho National Laboratory played a key role in the Three Mile Island (TMI) fuel and core recovery. This involved technology development to locate and handle the damaged fuel; characterization of fuel and debris; analysis of fuel interaction with structural components and materials; development of fuel drying technology for long-term storage. However, one of the critical activities from the TMI project was the extensive effort document all the activities and archive the reports and photos. A historical review of the TMI project at the INL leads to the identification of current applications and considerations for facility designs, fuel handling, robotic applications, material characterization, etc.

  9. Emergency Response Planning for Radiological Releases

    SciTech Connect (OSTI)

    Biwer, B.M.; LePoire, D.J.; Lazaro, M.A.; Allison, T.; Kamboj, S.; Chen, S.Y.

    2006-07-01

    The emergency management planning tool RISK-RDD was developed to aid emergency response planners and decision makers at all levels of government to better understand and prepare for potential problems related to a radiological release, especially those in urban areas. Radioactive release scenarios were studied by using the RISK-RDD radiological emergency management program. The scenarios were selected to investigate the key aspects of radiological risk management not always considered in emergency planning as a whole. These aspects include the evaluation of both aerosolized and non-aerosolized components of an atmospheric release, methods of release, acute and chronic human health risks, and the concomitant economic impacts as a function of the risk-based cleanup level. (authors)

  10. Interventional Radiology of Male Varicocele: Current Status

    SciTech Connect (OSTI)

    Iaccarino, Vittorio Venetucci, Pietro

    2012-12-15

    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.

  11. Routine Radiological Environmental Monitoring Plan. Volume 1

    SciTech Connect (OSTI)

    Bechtel Nevada

    1999-12-31

    The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

  12. Explosive containment and propagation evaluations for commonly used handling and storage containers

    SciTech Connect (OSTI)

    LeBlanc, R.

    1994-01-01

    A series of explosive tests were performed to establish containment integrity data for commonly used handling and storage containers of energetic materials at Sandia National Laboratories, Albuquerque, N.M. The tests consisted of two phases: (1) each container was tested for explosive integrity and propagation, and (2) the data were used to evaluate a nominal donor-receptor test matrix for verifying the confinement integrity of a typical explosives service locker.

  13. RECOMMENDATION FOR DISPOSITION OF REMOTE-HANDLED WASTE BURIED IN 33 SHAFTS AT TA-54

    Office of Environmental Management (EM)

    0-01 Approved by the NNMCAB on January 27, 2010 NORTHERN NEW MEXICO CITIZENS' ADVISORY BOARD (NNMCAB) Waste Management Committee Recommendation to the Department of Energy No. 2010-01 Recommendation for Disposition of Remote-handled Waste Buried in 33 Shafts at Technical Area 54 (TA-54) Background The Consent Order between the State of New Mexico, the Department of Energy/National Nuclear Safety Administration (DOE/NNSA) and Los Alamos National Security (LANS) requires that TA-54 Material

  14. Spectrum Sciences Decision and Data Handling Issues | Department of Energy

    Energy Savers [EERE]

    Spectrum Sciences Decision and Data Handling Issues Spectrum Sciences Decision and Data Handling Issues PDF icon spectrum sciences software_breaches.pdf PDF icon Park _IP_meeting.pdf More Documents & Publications DOE M 483.1-1 EXHIBIT A: CRADA, WFO, PUA and NPUA Comparison Table, with suggested changes Subcontractor Rights Under CRADAs and WFO Agreements

  15. Apparatus and method for handling magnetic particles in a fluid

    DOE Patents [OSTI]

    Holman, David A. (Richland, WA); Grate, Jay W. (West Richland, WA); Bruckner-Lea, Cynthia J. (Richland, WA)

    2000-01-01

    The present invention is an apparatus and method for handling magnetic particles suspended in a fluid, relying upon the known features of a magnetic flux conductor that is permeable thereby permitting the magnetic particles and fluid to flow therethrough; and a controllable magnetic field for the handling. The present invention is an improvement wherein the magnetic flux conductor is a monolithic porous foam.

  16. Method of handling radioactive alkali metal waste

    DOE Patents [OSTI]

    Wolson, Raymond D.; McPheeters, Charles C.

    1980-01-01

    Radioactive alkali metal is mixed with particulate silica in a rotary drum reactor in which the alkali metal is converted to the monoxide during rotation of the reactor to produce particulate silica coated with the alkali metal monoxide suitable as a feed material to make a glass for storing radioactive material. Silica particles, the majority of which pass through a 95 mesh screen or preferably through a 200 mesh screen, are employed in this process, and the preferred weight ratio of silica to alkali metal is 7 to 1 in order to produce a feed material for the final glass product having a silica to alkali metal monoxide ratio of about 5 to 1.

  17. Method of handling radioactive alkali metal waste

    DOE Patents [OSTI]

    Wolson, R.D.; McPheeters, C.C.

    Radioactive alkali metal is mixed with particulate silica in a rotary drum reactor in which the alkali metal is converted to the monoxide during rotation of the reactor to produce particulate silica coated with the alkali metal monoxide suitable as a feed material to make a glass for storing radioactive material. Silica particles, the majority of which pass through a 95 mesh screen or preferably through a 200 mesh screen, are employed in this process, and the preferred weight ratio of silica to alkali metal is 7 to 1 in order to produce a feed material for the final glass product having a silica to alkali metal monoxide ratio of about 5 to 1.

  18. FUEL HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2005-06-30

    The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling Facility (FHF) and the operations and processes performed therein. The current intent of the FHF is to receive transportation casks whose contents will be unloaded and transferred to waste packages (WP) or MGR Specific Casks (MSC) in the fuel transfer bays. Further, the WPs will also be prepared in the FHF for transfer to the sub-surface facility (for disposal). The MSCs will be transferred to the Aging Facility for storage. The criticality evaluation of the FHF features the following: (I) Consider the types of waste to be received in the FHF as specified below: (1) Uncanistered commercial spent nuclear fuel (CSNF); (2) Canistered CSNF (with the exception of horizontal dual-purpose canister (DPC) and/or multi-purpose canisters (MPCs)); (3) Navy canistered SNF (long and short); (4) Department of Energy (DOE) canistered high-level waste (HLW); and (5) DOE canistered SNF (with the exception of MCOs). (II) Evaluate the criticality analyses previously performed for the existing Nuclear Regulatory Commission (NRC)-certified transportation casks (under 10 CFR 71) to be received in the FHF to ensure that these analyses address all FHF conditions including normal operations, and Category 1 and 2 event sequences. (III) Evaluate FHF criticality conditions resulting from various Category 1 and 2 event sequences. Note that there are currently no Category 1 and 2 event sequences identified for FHF. Consequently, potential hazards from a criticality point of view will be considered as identified in the ''Internal Hazards Analysis for License Application'' document (BSC 2004c, Section 6.6.4). (IV) Assess effects of potential moderator intrusion into the fuel transfer bay for defense in depth. The SNF/HLW waste transfer activity (i.e., assembly and canister transfer) that is being carried out in the FHF has been classified as safety category in the ''Q-list'' (BSC 2003, p. A-6). Therefore, this design calculation is subject to the requirements of the ''Quality Assurance Requirements and Description'' (DOE 2004), even though the FHF itself has not yet been classified in the Q-list. Performance of the work scope as described and development of the associated technical product conform to the procedure AP-3.124, ''Design Calculations and Analyses''.

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

    SciTech Connect (OSTI)

    Bailey, E. N.

    2008-02-25

    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.

  20. 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

  1. ORISE: Radiological Terrorism Toolkit | How ORISE is Making a Difference

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

    Radiological Terrorism Toolkit ORISE partners with CDC to develop Radiological Terrorism: A Toolkit for Public Health Officials Radiological Terrorism: A Toolkit for Public Health Officials How ORISE is Making a Difference Working closely with the Centers for Disease Control and Prevention (CDC), the Oak Ridge Institute for Science and Education (ORISE) distributed more than 400 radiological terrorism toolkits filled with key resources, such as training guidelines, clinical directives, details

  2. radiological protection | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological protection Dedication of Radioactive Source Storage Facilities in Tajikistan (Dushanbe, Tajikistan) - On May 11, the United States' Embassy of Tajikistan, the Department of Energy/National Nuclear Security Administration (DOE/NNSA), the United Kingdom's Department of Energy and Climate Change (DECC), and the Government of Tajikistan dedicated two...

  3. Radiological Assistance Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Assistance Program NNSA Administrator visits Brookhaven National Laboratory On Friday, May 6, DOE Under Secretary for Nuclear Security and NNSA Administrator Lt. Gen. Frank G. Klotz (Ret.) visited Brookhaven National Laboratory in Upton, New York. Brookhaven Lab brings world-class facilities and expertise to the most exciting and important questions in basic and applied...

  4. Radiological Security Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Security Program Armenia Secures Dangerous Radioactive Sources in Cooperation with NNSA The Department of Energy's National Nuclear Security Administration (NNSA) joined the Republic of Armenia today to announce the safe and secure removal of three unused radioactive sources from two locations in Yerevan, Armenia. The successful completion of the radioactive source recovery campaign

  5. Radiological Contingency Planning for the Mars Science Laboratory Launch

    SciTech Connect (OSTI)

    Paul P. Guss

    2008-04-01

    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 NSTecs 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 Space and Aeronautics and Space Administration (NASA), state, and local resources, personnel, and equipment. This paper also outlines the organizational structure for response elements in radiological contingency planning.

  6. Radiological Contingency Planning for the Mars Science Laboratory Launch

    SciTech Connect (OSTI)

    Paul Guss, Robert Augdahl, Bill Nickels, Cassandra Zellers

    2008-04-16

    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 NSTecs 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.

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

    SciTech Connect (OSTI)

    Cowley, W.L.

    1996-04-25

    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.

  8. Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH TRAMPAC)

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  9. Draft Environmental Assessment on the Remote-handled Waste Disposition...

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

    Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment The U.S. Department of Energy invites the public to review...

  10. Handling and characterization of glow-discharge polymer samples...

    Office of Scientific and Technical Information (OSTI)

    of glow-discharge polymer samples for the light gas gun Citation Details In-Document Search Title: Handling and characterization of glow-discharge polymer samples for the light ...

  11. 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.

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

    SciTech Connect (OSTI)

    Donna Post Guillen

    2013-05-01

    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.

  13. Ocean FUSRAP: feasibility of ocean disposal of materials from the Formerly Utilized Sites Remedial Action Progam (FUSRAP)

    SciTech Connect (OSTI)

    Kupferman, S.L.; Anderson, D.R.; Brush, L.H.; Gomez, L.S.; Laul, J.C.; Shephard, L.E.

    1982-01-01

    The Formerly Utilized Sites Remedial Action Program (FUSRAP) of the Department of Energy is designed to identify and evaluate the radiological conditions at sites formerly used by the Corps of Engineers Manhattan Engineer District and the US Atomic Energy Commission. Where required, remedial action will be instituted to remove potential restrictions on the use of the sites due to residual low-level radioactive contamination. A total of 31 sites that may require remedial action has been identified. The purpose of the Ocean FUSRAP Program, which began in March 1981, is to assess the technical, environmental, and institutional feasibility of disposing, in the ocean and on the ocean floor, of FUSRAP soil and rubble which contains traces of natural radioactive materials. The initial focus has been on the Middlesex, New Jersey, Sampling Plant site and surrounding properties, which contain on the order of 100,000 metric tons of material. The Belgian Congo uranium ore and other uranium ores used by the United States were handled at the sampling plant site. In studying the feasibility of ocean disposal of FUSRAP material from Middlesex, New Jersey, we have begun to examine institutional requirements to be met, the composition of the source material with regard to its inventory of toxic chemical and radiochemical components and the impact of the source material in the marine environment. To date we have found nothing that would preclude safe and inexpensive disposal of this material in the ocean.

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

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Technical Report: Uranium hexafluoride: A manual of good handling practices. Revision 7 Citation Details In-Document Search Title: Uranium hexafluoride: A manual of good handling practices. Revision 7 × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to utilize additional information

  15. NREL: Process Development and Integration Laboratory - Sample Handling in

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

    the Atmospheric Processing Platform Sample Handling in the Atmospheric Processing Platform This page provides details on sample handling in the Atmospheric Processing platform. Photo of the large circular metal top of the cluster tool. Two wires cross the top and are attached to connectors on a flange at the center of the top. The chamber is surrounded by several other tools, but several of the cluster tool ports are open for future expansion. The robotic cluster tool portion of the

  16. Processing and Disposition of Remote-Handled Transuranic Liquid Waste

    Office of Scientific and Technical Information (OSTI)

    Generated at Oak Ridge National Laboratory (Conference) | SciTech Connect SciTech Connect Search Results Conference: Processing and Disposition of Remote-Handled Transuranic Liquid Waste Generated at Oak Ridge National Laboratory Citation Details In-Document Search Title: Processing and Disposition of Remote-Handled Transuranic Liquid Waste Generated at Oak Ridge National Laboratory Authors: Robinson, Sharon M [1] ; DePaoli, David W [1] ; Jubin, Robert Thomas [1] ; Patton, Bradley D [1] ;

  17. 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.

    2013-07-01

    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.

  18. NV/YMP RADIOLOGICAL CONTROL MANUAL

    SciTech Connect (OSTI)

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

    2004-11-01

    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.

  19. Fixation of Radiological Contamination; International Collaborative Development

    SciTech Connect (OSTI)

    Rick Demmer

    2013-03-01

    A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdoms 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.

  20. Radiological Safety Training for Accelerator Facilities

    Office of Environmental Management (EM)

    1-2008 August 2008 DOE HANDBOOK Radiological Assessor Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techs\ Foreword This Handbook describes an implementation process for training as recommended in Implementation Guide G441.1-1B, Radiation Protection

  1. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    SciTech Connect (OSTI)

    KOZLOWSKI, S.D.

    2007-05-30

    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.

  2. Nuclear materials management overview

    SciTech Connect (OSTI)

    DiGiallonardo, D.A. )

    1988-01-01

    The true goal of Nuclear Materials MANAGEMENT (NMM) is the strategical and economical management of all nuclear materials. Nuclear Materials Management's role involves near-term and long-term planning, reporting, forecasting, and reviewing of inventories. This function is administrative in nature. it is a growing area in need of future definition, direction, and development. Improvements are required in program structure, the way residues and wastes are determined, how ''what is and what if'' questions are handled, and in overall decision-making methods.

  3. Nuclear materials management overview

    SciTech Connect (OSTI)

    DiGiallonardo, D.A.

    1988-01-01

    The true goal of Nuclear Materials Management (NMM) is the strategical and economical management of all nuclear materials. Nuclear Materials Management's role involves near-term and long-term planning, reporting, forecasting, and reviewing of inventories. This function is administrative in nature. It is a growing area in need of future definition, direction, and development. Improvements are required in program structure, the way residues and wastes are determined, how /open quotes/What is and what if/close quotes/ questions are handled, and in overall decision-making methods. 2 refs.

  4. 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.

    1996-06-01

    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).

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

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

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

  6. Pebble Fuel Handling and Reactivity Control for Salt-Cooled High...

    Office of Scientific and Technical Information (OSTI)

    Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors Citation Details In-Document Search Title: Pebble Fuel Handling and Reactivity Control for ...

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

    SciTech Connect (OSTI)

    David Duncan

    2010-10-01

    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.

  8. 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.

    1982-11-01

    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.

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

    SciTech Connect (OSTI)

    Weiss, E.V.

    1997-03-06

    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. Enterprise Assessments, Lessons Learned from Targeted Reviews, Radiological

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

    Controls Activity-Level Implementation - January 2015 | Department of Energy Assessments, Lessons Learned from Targeted Reviews, Radiological Controls Activity-Level Implementation - January 2015 Enterprise Assessments, Lessons Learned from Targeted Reviews, Radiological Controls Activity-Level Implementation - January 2015 January 2015 Reviews of Radiological Controls Activity-Level Implementation. The Office of Nuclear Safety and Environmental Assessments, within the U.S. Department of

  11. 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations |

    Energy Savers [EERE]

    Department of Energy Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations PDF icon November 2012; Environmental Measurements in an Emergency: This is not a Drill!; Stephen V. Musolino; Brookhaven National Laboratory PDF icon November 2012; Brookhaven Graphite Research Reactor (BGRR) D&D Presentation for the DOE ERAD Working

  12. Environmental/Radiological Assistance Directory (ERAD) | Department of

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

    Energy Environmental/Radiological Assistance Directory (ERAD) Environmental/Radiological Assistance Directory (ERAD) The Environmental Radiological Assistance Directory or ERAD, developed by AU-22, serves as an assistance tool to the DOE complex for protection of the public and environment from radiation. The ERAD is a combination webinar/conference call, designed to provide DOE and its contractors a forum to share information, lessons-learned, best practices, emerging trends, compliance

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

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

    Complex ... Nuclear and Radiological Field Training Center A site used for nuclear research in Oak Ridge, Tennessee 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 Center provides world-class nuclear and radiological training in a safe, secure, realistic environment using expert instruction and personnel to serve as observers/evaluators for customer training. For military

  14. Operational Guidelines/Radiological Emergency Response | Department of

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

    Energy Operational Guidelines/Radiological Emergency Response Operational Guidelines/Radiological Emergency Response This page provides information and resources concerning the development of operational guidelines as part of planning guidance for protection and recovery following Radiological Dispersal Device (RDD) and/or Improvised Nuclear Device (IND) incidents. Operational Guidelines Technical (OGT) Manual, 2009 RESRAD-RDD Complementing Software to OGT Manual EPA Protective Action

  15. DOE Issues WIPP Radiological Release Phase II Investigation Report

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

    16, 2015 DOE Issues WIPP Radiological Release Phase II Investigation Report WASHINGTON, D.C. - Today, the Department of Energy Office of Environmental Management (EM) released the Accident Investigation Board (AIB) Phase II Report related to the Feb. 14, 2014, radiological event at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The AIB completed an exhaustive investigation at WIPP and Los Alamos National Laboratory (LANL) to examine the cause of the radiological release at

  16. Accident Investigations of the February 14, 2014, Radiological Release at

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

    the Waste Isolation Pilot Plant, Carlsbad, NM | Department of Energy Accident Investigations of the February 14, 2014, Radiological Release at the Waste Isolation Pilot Plant, Carlsbad, NM Accident Investigations of the February 14, 2014, Radiological Release at the Waste Isolation Pilot Plant, Carlsbad, NM February 14, 2014 Accident Investigations of the February 14, 2014, Radiological Release at the Waste Isolation Pilot Plant, Carlsbad, NM On February 14, 2014, at approximately 2314

  17. Federal Radiological Monitoring and Assessment Center | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Federal Radiological Monitoring and Assessment Center The Federal Radiological Monitoring and Assessment Center (FRMAC) is a federal asset available on request by the Department of Homeland Security (DHS) and state and local agencies to respond to a nuclear or radiological incident. The FRMAC is an interagency organization with representation from the NNSA, the Department of Defense (DOD), the Environmental Protection Agency (EPA), the Department of Health and Human

  18. Anniversary of Fire, Radiological Events Marks Major Progress at WIPP

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

    February 12, 2016 Anniversary of Fire, Radiological Events Marks Major Progress at WIPP February 2016 marks two years since the underground fire and radiological release events forced the temporary closure of the Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. Since that time much progress has been made in the recovery of the underground including mine stability and habitability, initial panel closure, radiological risk remediation and the addition of

  19. Implementation of focused ion beam (FIB) system in characterization of nuclear fuels and materials

    SciTech Connect (OSTI)

    A. Aitkaliyeva; J. W. Madden; B. D. Miller; J I Cole; T A Hyde

    2014-10-01

    Beginning in 2007, a program was established at the Idaho National Laboratory to update key capabilities enabling microstructural and micro-chemical characterization of highly irradiated and/or radiologically contaminated nuclear fuels and materials at scales that previously had not been achieved for these types of materials. Such materials typically cannot be contact handled and pose unique hazards to instrument operators, facilities, and associated personnel. One of the first instruments to be acquired was a Dual Beam focused ion beam (FIB)-scanning electron microscope (SEM) to support preparation of transmission electron microscopy and atom probe tomography samples. Over the ensuing years, techniques have been developed and operational experience gained that has enabled significant advancement in the ability to characterize a variety of fuel types including metallic, ceramic, and coated particle fuels, obtaining insights into in-reactor degradation phenomena not obtainable by any other means. The following article describes insights gained, challenges encountered, and provides examples of unique results obtained in adapting Dual Beam FIB technology to nuclear fuels characterization.

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

    SciTech Connect (OSTI)

    Box, W.D.; Setaro, J.

    1984-01-01

    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.

  1. Radiological Source Term Estimates for the February 14, 2014...

    Energy Savers [EERE]

    This document corresponds to Appendix D: Modeling Integrated Summary Report of the Technical Assessment Team Report. PDF icon Radiological Source Term Estimates for the February ...

  2. The New Radiological and Environmental Sciences Laboratory (RESL...

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

    None File Format: Microsoft Windows WMV File Size: 19 Kb Video of Radiological and Environmental Sciences Laboratory (RESL) Editorial Date December 7, 2011 By Danielle Miller...

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

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

    8 Radioactive Source Control Instructor's Guide 2.08-1 Course Title: Radiological Control Technician Module Title: Radioactive Source Control Module Number: 2.08 Objectives: ...

  4. Inspection Report - Radiological Waste Operations in Area G at...

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

    To help ensure that operations are conducted in a safe and efficient manner, Los Alamos developed a program to integrate management and radiological waste operations work practices ...

  5. NNSA Nuclear/Radiological Incident Response | National Nuclear...

    National Nuclear Security Administration (NNSA)

    January 01, 2009 The National Nuclear Security Administration (NNSA) has more than 60 years of nuclear weapons experience in responding to nuclear and radiological accidents and ...

  6. An Assessment Of The External Radiological Impact In Areas Of...

    Open Energy Info (EERE)

    Assessment Of The External Radiological Impact In Areas Of Greece With Elevated Natural Radioactivity Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal...

  7. ORISE: Radiological Terrorism Toolkit | How ORISE is Making a...

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

    Education (ORISE) distributed more than 400 radiological terrorism toolkits filled with key resources, such as training guidelines, clinical directives, details about radioactive...

  8. NNSA, Philippine Nuclear Research Institute to Prevent Radiological...

    National Nuclear Security Administration (NNSA)

    to our shared efforts to prevent nuclear and radiological terrorism and the proliferation of nuclear weapons," said NNSA Deputy Administrator for Defense Nuclear ...

  9. NNSA Nuclear/Radiological Incident Response | National Nuclear...

    National Nuclear Security Administration (NNSA)

    NNSA NuclearRadiological Incident Response December 01, 2008 The National Nuclear Security Administration (NNSA) has over 60 years of nuclear weapons experience in responding to ...

  10. Trending and root cause analysis of TWRS radiological problem reports

    SciTech Connect (OSTI)

    Brown, R.L.

    1997-07-31

    This document provides a uniform method for trending and performing root cause analysis for radiological problem reports at Tank Waste Remediation System (TWRS).

  11. Hospital Triage in First Hours After Nuclear or Radiological...

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

    Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster Medical professionals with the Radiation Emergency Assistance CenterTraining Site (REACTS) at the...

  12. DOE-STD-1098-99; Radiological Control

    Office of Environmental Management (EM)

    ... starts at the worker level and broadens as it ... releases as low as reasonably achievable. Radiological design criteria shall ... regard to integrated safety management (ISM) . ...

  13. DOE-HDBK-1122-99; Radiological Control Technican Training

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

    ... the highest dose received to the whole body. * Workers must leave temporary shielding in place unless they have been autho- rized to remove the shielding by Radiological Control. ...

  14. DOE-HDBK-1122-99; Radiological Technician Training

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

    ... Classification aids in the rapid communication of critical information and the initiation of appropriate time- urgent emergency response actions. Causes of radiological incidents ...

  15. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentati...

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

    Radiological Assistance Directory (ERAD) meetings PDF icon Nov 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site; Tim Janik,...

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

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

    ... Nuclear and Radiological Field Training Center A site used for nuclear research in Oak Ridge, Tennessee during the Manhattan Project is now the Y-12 National Security Complex's...

  17. DOE-HDBK-1141-2001; Radiological Assessor Training, Overheads

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

    ... and OBT may need to be based on air monitoring * Tritium effluent recovery system: - ... Objectives: * Identify the radiological properties of plutonium. * Identify the biological ...

  18. Radiological Release Event at the Waste Isolation Pilot Plant...

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

    radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following...

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

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

    Communication Systems Instructor's Guide 2.02-1 Course Title: Radiological Control Technician Module Title: Communication Systems Module Number: 2.02 Objectives: 2.02.01 Explain ...

  20. DOE-HDBK-1141-2001; Radiological Assessor Training

    Energy Savers [EERE]

    ... Goal of Training Program The goal of the training program is to provide a sufficient level of knowledge and skills in radiological assessment fundamentals commensurate with the ...

  1. Evaluation of Final Radiological Conditions at Areas of the Niagara...

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

    Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Evaluation of Final ...

  2. Radiological Dose Calculations for Fusion Facilities

    SciTech Connect (OSTI)

    Michael L. Abbott; Lee C. Cadwallader; David A. Petti

    2003-04-01

    This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

  3. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    DOE.F 1325.8 (08-93) United States Government Department of Energy memorandum DATE: May 11, 2006 REPLY TO EH-52:JRabovsky:3-2 135 ATTN OF: APPROVAL OF CHANGE NOTICE 1 TO DEPARTMENT OF ENERGY (DOE) SUBJECT. HANDBOOK 1184-2004, RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS TO: Dennis Kubicki, EH-24 Technical Standards Manager This memorandum forwards the subject Change Notice 1 to DOE Handbook, DOE- HDBK- 1184-2004, which has approved for publication and distribution. The change to

  4. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    SciTech Connect (OSTI)

    Mertz, G.

    1999-12-16

    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.

  5. Tritium handling experience at Atomic Energy of Canada Limited

    SciTech Connect (OSTI)

    Suppiah, S.; McCrimmon, K.; Lalonde, S.; Ryland, D.; Boniface, H.; Muirhead, C.; Castillo, I.

    2015-03-15

    Canada has been a leader in tritium handling technologies as a result of the successful CANDU reactor technology used for power production. Over the last 50 to 60 years, capabilities have been established in tritium handling and tritium management in CANDU stations, tritium removal processes for heavy and light water, tritium measurement and monitoring, and understanding the effects of tritium on the environment. This paper outlines details of tritium-related work currently being carried out at Atomic Energy of Canada Limited (AECL). It concerns the CECE (Combined Electrolysis and Catalytic Exchange) process for detritiation, tritium-compatible electrolysers, tritium permeation studies, and tritium powered batteries. It is worth noting that AECL offers a Tritium Safe-Handling Course to national and international participants, the course is a mixture of classroom sessions and hands-on practical exercises. The expertise and facilities available at AECL is ready to address technological needs of nuclear fusion and next-generation nuclear fission reactors related to tritium handling and related issues.

  6. Plutonium Immobilization Process: Puck Handling Module Supervisory Control System

    SciTech Connect (OSTI)

    Smail, T.R.

    2001-01-29

    This paper discusses the Supervisory Control and Data Acquisition for green puck handling. Also discussed is the overall control scheme implemented by the supervisory computer, the individual inspections completed on the puck, and the checks and balances between the computer, tray loading system and robot.

  7. Sampling device with a capped body and detachable handle

    DOE Patents [OSTI]

    Jezek, Gerd-Rainer

    2000-01-01

    The apparatus is a sampling device having a pad for sample collection, a body which supports the pad, a detachable handle connected to the body and a cap which encloses and retains the pad and body to protect the integrity of the sample.

  8. 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

    2010-05-25

    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.

  9. A decade of radiological and shielding experience at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Bunch, W.L.

    1990-01-01

    The Fast Flux Test Facility (FFTF) was designed to permit irradiation testing of fuels and materials to support the commercial development of liquid-metal-cooled fast reactors (LMRs). A secondary objective was to gain experience in the design, construction, and operation of a relatively large LMR. The radiological experience gained from the operation of the facility as it applies to the area of radiation protection and shielding is presented. Experience from 8 yr of FFTF operation has demonstrated that radiological safety can be achieved in large LMRs. Layout of plant equipment in shielded compartments, careful operational planning, and adherence to procedures have combined to minimize personnel doses at FFTF and the release of radioactivity to the environment. The experience derived form the design, construction, and operation of FFTF should be of inestimable value in supporting future LMR development.

  10. 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.

    2010-02-02

    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.

  11. FRMAC Interactions During a Radiological or Nuclear Event

    SciTech Connect (OSTI)

    Wong, C T

    2011-01-27

    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.

  12. Radiological Safety Training for Accelerator Facilities

    Energy Savers [EERE]

    ... for the senior-level radiation protection ... available. . - Program Management - Instructor's Material ... VI. RADIOACTIVE WASTE ISSUES ......

  13. PFP Commercial Grade Food Pack Cans for Plutonium Handling and Storage Critical Characteristics

    SciTech Connect (OSTI)

    BONADIE, E.P.

    2000-08-22

    This screening addresses the critical characteristics for food industry type cans and containers used for handling and storage of special nuclear materials at the Plutonium Finishing Plant (PFP). HNF-5460, Revision 0 specified a minimum tin plate of 0.50 Ib./base box. Since the food pack cans currently used and that have been tested have a listed tin plate of 0.20 lbs. per base box, Revision 1 reduced the tin plate to {ge} 0.20 Ib./base box (i.e., No. 20 tinned commercial steel or heavier). This revision lists Critical Characteristics for two (2) large filtered containers, and associated shielding over-packs. These new containers are called ''Nuclear Material Containers'' (NMCs). They are supplied in various sizes, which can be nested, one inside another. The PFP will use NMCs with volumes up to 8-quarts as needed to over-pack largely bulged containers.

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

    SciTech Connect (OSTI)

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

    2012-06-01

    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.

  15. Australian liquids-handling system cuts surges to LPG plant

    SciTech Connect (OSTI)

    McKee, G.; Stenner, T.D. )

    1990-08-06

    This paper reports how a pipeline liquids-handling facility recently commissioned allows gas production to be quickly ramped up to meet customer demand. Its design eliminates trouble-some liquid surges which had hampered plant operations. The pipeline-loop system, located at the Wallumbilla LPG processing plant, Queensland, was built for 60 of the cost of an equivalently sized conventional slug catcher. Its control system enables automatic, unattended handling of liquid surges and pigging slugs from the 102-km Silver Springs to Wallumbilla two-phase pipeline. Because of this system's simple hydraulics, normal slug-catcher piping design problems are eliminated. Safety is improved because the potentially hazardous condensate liquid is contained in a buried pipeline.

  16. Liquid class predictor for liquid handling of complex mixtures

    DOE Patents [OSTI]

    Seglke, Brent W.; Lekin, Timothy P.

    2008-12-09

    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.

  17. Handling encapsulated spent fuel in a geologic repository environment

    SciTech Connect (OSTI)

    Ballou, L.B.

    1983-02-01

    In support of the Spent Fuel Test-Climate at the U.S. Department of Energy`s Nevada Test Site, a spent-fuel canister handling system has been designed, deployed, and operated successfully during the past five years. This system transports encapsulated commercial spent-fuel assemblies between the packaging facility and the test site ({similar_to}100 km), transfers the canisters 420 m vertically to and from a geologic storage drift, and emplaces or retrieves the canisters from the storage holes in the floor of the drift. The spent-fuel canisters are maintained in a fully shielded configuration at all times during the handling cycle, permitting manned access at any time for response to any abnormal conditions. All normal operations are conducted by remote control, thus assuring as low as reasonably achievable exposures to operators; specifically, we have had no measurable exposure during 30 canister transfer operations. While not intended to be prototypical of repository handling operations, the system embodies a number of concepts, now demonstrated to be safe, reliable, and economical, which may be very useful in evaluating full-scale repository handling alternatives in the future. Among the potentially significant concepts are: Use of an integral shielding plug to minimize radiation streaming at all transfer interfaces. Hydraulically actuated transfer cask jacking and rotation features to reduce excavation headroom requirements. Use of a dedicated small diameter (0.5 m) drilled shaft for transfer between the surface and repository workings. A wire-line hoisting system with positive emergency braking device which travels with the load. Remotely activated grapples - three used in the system - which are insensitive to load orientation. Rail-mounted underground transfer vehicle operated with no personnel underground.

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

    SciTech Connect (OSTI)

    Bailey, J.C.

    1991-12-31

    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.

  19. An analysis of repository waste-handling operations

    SciTech Connect (OSTI)

    Dennis, A.W.

    1990-09-01

    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.

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

    SciTech Connect (OSTI)

    Bailey, W.J.

    1990-11-01

    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.

  1. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design.

    SciTech Connect (OSTI)

    Cochran, John R.; Hardin, Ernest

    2015-07-01

    This report presents conceptual design information for a system to handle and emplace packages containing radioactive waste, in boreholes 16,400 ft deep or possibly deeper. Its intended use is for a design selection study that compares the costs and risks associated with two emplacement methods: drill-string and wireline emplacement. The deep borehole disposal (DBD) concept calls for siting a borehole (or array of boreholes) that penetrate crystalline basement rock to a depth below surface of about 16,400 ft (5 km). Waste packages would be emplaced in the lower 6,560 ft (2 km) of the borehole, with sealing of appropriate portions of the upper 9,840 ft (3 km). A deep borehole field test (DBFT) is planned to test and refine the DBD concept. The DBFT is a scientific and engineering experiment, conducted at full-scale, in-situ, without radioactive waste. Waste handling operations are conceptualized to begin with the onsite receipt of a purpose-built Type B shipping cask, that contains a waste package. Emplacement operations begin when the cask is upended over the borehole, locked to a receiving flange or collar. The scope of emplacement includes activities to lower waste packages to total depth, and to retrieve them back to the surface when necessary for any reason. This report describes three concepts for the handling and emplacement of the waste packages: 1) a concept proposed by Woodward-Clyde Consultants in 1983; 2) an updated version of the 1983 concept developed for the DBFT; and 3) a new concept in which individual waste packages would be lowered to depth using a wireline. The systems described here could be adapted to different waste forms, but for design of waste packaging, handling, and emplacement systems the reference waste forms are DOE-owned high- level waste including Cs/Sr capsules and bulk granular HLW from fuel processing. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design July 23, 2015 iv ACKNOWLEDGEMENTS This report has benefited greatly from review principally by Steve Pye, and also by Paul Eslinger, Dave Sevougian and Jiann Su.

  2. Materials Handling for Electrical Modification of a Complex Target Surface: Analysis and Feasibility

    SciTech Connect (OSTI)

    Giles, D K; Law, S E; Tringe, J W

    2009-01-06

    This project effort, conducted as feasibility investigations addresses the transport and deposition of particulates using traveling field, electrohydrodynamic atomization and gas carrier methods. The method of investigation was experimental, using existing experimental and pre-commercial apparatus. All methods were found to be successful to varying degrees. Preliminary results were presented at LLNL in a project review meeting. The most promising methods for particle delivery were electrodynamic atomization/spraying and gas-carrier propulsion. Traveling field delivery is limited by scale up considerations and the requirement for transport through close tolerances. Electrodynamic atomization requires use of low electrical conductivity liquid carrier phases but is scalable by ganging multiple orifices and atomizing tips. Gas carrier delivery is attractive because no liquid carrier is needed and momentum can higher than the other traveling field or electrodynamic processes. Subsequent phases of the project will address electrodynamic and gas-carrier delivery.

  3. weapons material | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    material

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

    SciTech Connect (OSTI)

    Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M.; Michal, V.; Vargovcik, L.

    2012-07-01

    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)

  5. Adaptively Reevaluated Bayesian Localization (ARBL): A Novel Technique for Radiological Source Localization

    SciTech Connect (OSTI)

    Miller, Erin A.; Robinson, Sean M.; Anderson, Kevin K.; McCall, Jonathon D.; Prinke, Amanda M.; Webster, Jennifer B.; Seifert, Carolyn E.

    2015-06-01

    Adaptively Reevaluated Bayesian Localization (ARBL): A Novel Technique for Radiological Source Localization

  6. U-226: Linux Kernel SFC Driver TCP MSS Option Handling Denial...

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

    6: Linux Kernel SFC Driver TCP MSS Option Handling Denial of Service Vulnerability U-226: Linux Kernel SFC Driver TCP MSS Option Handling Denial of Service Vulnerability August 2,...

  7. Feasibiltiy of Power and Particle Handling in an ST-FNSF and...

    Office of Scientific and Technical Information (OSTI)

    Feasibiltiy of Power and Particle Handling in an ST-FNSF and the Effects of Divertor Geometry Citation Details In-Document Search Title: Feasibiltiy of Power and Particle Handling...

  8. Unified Resolve 2014: A Proof of Concept for Radiological Support...

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

    are presently referred to as "Radiological Operations Support Specialists (ROSS). The role of the ROSS cadre is envisioned to be an on-scene RN subject matter expert to Incident ...

  9. DOE-STD-1098-99; Radiological Control

    National Nuclear Security Administration (NNSA)

    RADIOLOGICAL CONTROL U.S. Department of Energy AREA SAFT Washington, D.C. 20585 ... Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. ...

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

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

    Dosimetry Instructor's Guide 2.04-1 Course Title: Radiological Control ... 2.04.05 Determine the theory of operation of a ... D. Introduce Objectives O.H.: Objectives ...

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

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

    ... Module 2.11 Radiological Work Coverage Instructor's Guide 2.11-8 e. Special ... Teach as a discussion. 1. Exposure Control Write "Exposure Control" on the board. List the ...

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

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

    Communication Systems Study Guide 2.02-1 Course Title: Radiological Control Technician Module Title: Communication Systems Module Number: 2.02 Objectives: 2.02.01 Explain the ...

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

    Office of Environmental Management (EM)

    ... Accurate data is crucial to the assignment of proper radiological controls. References: 1. DOE-HDBK-10141-92 (June 1992) "Mathematics: Volume 1 of 2"; DOE Fundamentals Handbook ...

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

    Energy Savers [EERE]

    Air Sampling ProgramMethods Instructor's Guide 2.06-1 Course Title: Radiological Control Technician Module Title: Air Sampling ProgramMethods Module Number: 2.06 Objectives: ...

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

    Energy Savers [EERE]

    Air Sampling ProgramMethods Study Guide 2.06-1 Course Title: Radiological Control Technician Module Title: Air Sampling ProgramMethods Module Number: 2.06 Objectives: 2.06.01 ...

  16. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

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

    1994-06-28

    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.

  17. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, Aed M.; Wagner, David G.; Teese, Gregory D.

    1994-01-01

    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.

  18. 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.

    1999-08-10

    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.

  19. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, Aed M.; Ward, Clyde R.; Jones, Joel D.; Mallet, William R.; Harpring, Larry J.; Collins, Montenius X.; Anderson, Erin K.

    1999-01-01

    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.

  20. Nation's Radiological Assistance Program teams practice emergency...

    National Nuclear Security Administration (NNSA)

    The teams provide a 247 response capability for any incident or accident involving radioactive material. RAP Teams consist of federal and contract employees who regularly work ...

  1. NNSA Nuclear/Radiological Incident Response | National Nuclear Security

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

    Administration NNSA Nuclear/Radiological Incident Response December 01, 2008 The National Nuclear Security Administration (NNSA) has over 60 years of nuclear weapons experience in responding to nuclear and radiological accidents and incidents. NNSA provides technical support to the Departments of Homeland Security, Justice, State, and Defense for nuclear terrorism events and domestic nuclear weapon accidents and incidents. The NNSA emergency response assets also provide support to nuclear

  2. Nation's Radiological Assistance Program teams practice emergency response

    National Nuclear Security Administration (NNSA)

    | National Nuclear Security Administration Nation's Radiological Assistance Program teams practice emergency response Thursday, March 31, 2016 - 11:05am NNSA Blog Radiological Assistance Program (RAP) teams from around the country gathered in Albuquerque in late March as part of RAP Training for Emergency Response (RAPTER). This training consists of an intensive series of drills conducted four times a year to provide recertification for members of Department of Energy (DOE)/National Nuclear

  3. Cardiovascular and Interventional Radiological Society of Europe Guidelines

    Office of Scientific and Technical Information (OSTI)

    on Endovascular Treatment in Aortoiliac Arterial Disease (Journal Article) | SciTech Connect Cardiovascular and Interventional Radiological Society of Europe Guidelines on Endovascular Treatment in Aortoiliac Arterial Disease Citation Details In-Document Search Title: Cardiovascular and Interventional Radiological Society of Europe Guidelines on Endovascular Treatment in Aortoiliac Arterial Disease PurposeThese guidelines are intended for use in assessing the standard for technical success

  4. Portsmouth Training Exercise Helps Radiological Trainees Spot Mistakes

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

    Safely | Department of Energy Portsmouth Training Exercise Helps Radiological Trainees Spot Mistakes Safely Portsmouth Training Exercise Helps Radiological Trainees Spot Mistakes Safely February 11, 2016 - 12:10pm Addthis Connie Martin performs work inside the Error Lab while trainees observe her actions for mistakes. Connie Martin performs work inside the Error Lab while trainees observe her actions for mistakes. Lorrie Graham (left) talks with trainees in a classroom setting before

  5. Radiological Source Registry and Tracking (RSRT) | Department of Energy

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

    Radiological Source Registry and Tracking (RSRT) Radiological Source Registry and Tracking (RSRT) Department of Energy (DOE) Notice N 234.1 Reporting of Radioactive Sealed Sources has been superseded by DOE Order O 231.1B Environment, Safety and Health Reporting. O 231.1B identifies the requirements for centralized inventory and transaction reporting for radioactive sealed sources. Each DOE site/facility operator that owns, possesses, uses or maintains in custody those accountable radioactive

  6. NNSA Works With Australian Agency to Counter Radiological Threats |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Works With Australian Agency to Counter Radiological Threats March 10, 2006 WASHINGTON, D.C. - - Today, the Department of Energy's National Nuclear Security Administration (NNSA) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) agreed to join forces to counter radiological threats - such as a "dirty bomb" - and respond to emergencies. NNSA's Principal Deputy Administrator Jerry Paul and ARPANSA's Chief Executive

  7. LM Records Handling System-Fernald Historical Records System, Office of

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

    Legacy Management | Department of Energy Fernald Historical Records System, Office of Legacy Management LM Records Handling System-Fernald Historical Records System, Office of Legacy Management LM Records Handling System-Fernald Historical Records System, Office of Legacy Management PDF icon LM Records Handling System-Fernald Historical Records System, Office of Legacy Management More Documents & Publications LM Records Handling System (LMRHS01) - Electronic Records Keeping System,

  8. LM Records Handling System-Freedom of Information/Privacy Act, Office of

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

    Legacy management | Department of Energy Freedom of Information/Privacy Act, Office of Legacy management LM Records Handling System-Freedom of Information/Privacy Act, Office of Legacy management LM Records Handling System-Freedom of Information/Privacy Act, Office of Legacy management PDF icon LM Records Handling System-Freedom of Information/Privacy Act, Office of Legacy management More Documents & Publications LM Records Handling System-Fernald Historical Records System, Office of

  9. Uranium hexafluoride: Safe handling, processing, and transporting: Conference proceedings

    SciTech Connect (OSTI)

    Strunk, W.D.; Thornton, S.G.

    1988-01-01

    This conference seeks to provide a forum for the exchange of information and ideas of the safety aspects and technical issue related to the handling of uranium hexafluoride. By allowing operators, engineers, scientists, managers, educators, and others to meet and share experiences of mutual concern, the conference is also intended to provide the participants with a more complete knowledge of technical and operational issues. The topics for the papers in the proceedings are widely varied and include the results of chemical, metallurgical, mechanical, thermal, and analytical investigations, as well as the developed philosophies of operational, managerial, and regulatory guidelines. Papers have been entered individually into EDB and ERA. (LTN)

  10. 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.

    1997-08-01

    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.

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

    SciTech Connect (OSTI)

    Sexton, L.

    2012-06-06

    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).

  12. DOE - Office of Legacy Management -- C G Sargent and Sons - MA...

    Office of Legacy Management (LM)

    Site Operations: Conducted extruder and drying tests with thorium in the late 1960s. ... Primary Radioactive Materials Handled: Thorium MA.17-3 Radiological Survey(s): Yes - ...

  13. DOE - Office of Legacy Management -- Pfaltz and Bauer Inc - Richfield...

    Office of Legacy Management (LM)

    Operations: Commercial supplier of thorium nitrate for manufacture of gas lantern mantles. ... Primary Radioactive Materials Handled: Thorium nitrate NJ.28-1 Radiological Survey(s): ...

  14. DOE - Office of Legacy Management -- Crucible Steel Co of America...

    Office of Legacy Management (LM)

    and Development; Small amount of Thorium forged and rolled; Large amounts of ... Primary Radioactive Materials Handled: Thorium NY.34-1 Radiological Survey(s): None ...

  15. DOE - Office of Legacy Management -- Massachusetts Institute...

    Office of Legacy Management (LM)

    involving research quantities of uranium, thorium and beryllium and other rare metals. ... Radioactive Materials Handled: Uranium, Thorium, Beryllium MA.01-4 Radiological ...

  16. DOE - Office of Legacy Management -- American Machine and Foundry...

    Office of Legacy Management (LM)

    1951 - 1954 conducted metal fabrication operation on uranium and thorium metals. ... Materials Handled: Uranium and Thorium metal NY.26-1 Radiological Survey(s): Yes ...

  17. DOE - Office of Legacy Management -- Wolff-Alport and Co - NY...

    Office of Legacy Management (LM)

    Operations: Commercial operation -- sold thorium residues to the AEC, which in turn ... Primary Radioactive Materials Handled: Thorium NY.30-2 Radiological Survey(s): No Site ...

  18. DOE - Office of Legacy Management -- Horizons Inc - OH 05

    Office of Legacy Management (LM)

    and conducted work on production of thorium metal by fused salt electrolysis. ... Primary Radioactive Materials Handled: Thorium OH.05-4 Radiological Survey(s): Yes ...

  19. DOE - Office of Legacy Management -- Colonial Uranium Co - CO...

    Office of Legacy Management (LM)

    Site Operations: Processed thorium concentrates for commercial market at another site. ... Primary Radioactive Materials Handled: Thorium CO.10-1 Radiological Survey(s): No Site ...

  20. DOE - Office of Legacy Management -- U S Bureau of Mines - PA...

    Office of Legacy Management (LM)

    Site Operations: Conducted studied on explosiveness of Uranium, Thorium and Beryllium. ... Materials Handled: Uranium and Thorium PA.36-2 Radiological Survey(s): Yes - ...

  1. DOE - Office of Legacy Management -- General Electric Co - Shelbyville...

    Office of Legacy Management (LM)

    Compacted approximately 500 pounds of thorium (small pieces) into electrodes on 25 and ... Primary Radioactive Materials Handled: Thorium IN.07-1 Radiological Survey(s): Yes ...

  2. Hydrogen Material Compatibility for Hydrogen ICE | Department of Energy

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

    Presented by Tom Joseph at the National Hydrogen Assocation Conference and Hydrogen Expo PDF icon joseph_infrastructure_for_emerging_markets.pdf More Documents & Publications Early-Stage Market Change and Effects of the Recovery Act Fuel Cell Program An Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment Early Markets: Fuel Cells for Material Handling Equipment Slides | Department of Energy

    An Overview of the Hydrogen Fueling Infrastructure

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

    SciTech Connect (OSTI)

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

    1986-11-01

    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.

  4. Session 70 - Panel: Consequence Management of a Radiological Dispersion Device

    SciTech Connect (OSTI)

    Demmer, Rick; Lenox, Dave; Wilson, Pete; Schumann, Jean; Honerlah, Hans; Chen, S.Y.; Gwiazdowski, Gene

    2006-07-01

    This was an unusual panel session in that the panelists did not give presentations but responded to a tabletop exercise where they postulated decisions necessary after radiological dispersal device detonation event (dirty bomb). Articles in the daily WM'06 newsletter sought to prepare the participants for a simulated exercise involving the sighting of a known terrorist and the theft of radiological materials. During the slide presentation (in the form of a developing television news broadcast) the audience played decision makers and their 'votes' were tallied for multiple choice decisions and questions. After that was completed, the expert panel was asked to give their best responses for those decisions. The audience was allowed to ask questions and to give opinions as the panel responded. During the exercise the session co-chairs alternated announcing the events as they unfolded in the exercise and polled the audience using multiple-choice options for decisions to be made during the event. The answers to those questions were recorded and compared to the panelists' answers. The event chronology and decisions (audience questions) are shown in this report. - An explosion was reported at the Tucson International Airport (9:35 am). 1. Who is in charge? - Witnesses report 10-20 fatalities, 50 injured and massive damage to the airport, no cause determined yet (9:55 am). 2. IC's Next Action Should Be? - KRAD (local television station) Investigative News Reporters interviewed witnesses that observed a 25 foot U-Haul truck pull up onto the departure ramp just moments before the explosion (10:02 am). Terrorism has not been ruled out. 3. When is the incident declared a potential crime scene? - City of Tucson IC has ordered an evacuation of the airport to a holding area at a nearby long term parking area (10:10 am). No information has been given as to why the evacuation took place. The explosion is suspected to contain chemical, biological or radiological agents. County and State emergency operations centers have been activated. 4. Terrorism is suspected; next action is? - KRAD News has just learned that elevated levels of radiation have been detected at the airport and by the University of Arizona remote detectors (10:17 am). A 'dirty bomb' is now suspected. 5. What should the IC do next? - KRAD reporters have learned that dose rates are approximately 7.5 mR/hr gamma radiation in the short-term parking area (10:28 am). Experts attending a conference at the Tucson Convention Center state that these levels are not life threatening, but well above acceptable levels. 6. What does the IC do next? 7. Who is the coordinating agency? - Forensics indicate that the radioactive material used in the explosion at the Tucson Airport is apparently a mixture of high jacked low level waste from a nuclear facility and stolen radiation sources for medical or industrial purposes (11:21 am). The origin of the waste material is from an audience member's plant (assume it is your own material). 8. Who is responsible for surveys and characterization? 9. Who is responsible for the decontamination? 10. Where are the injured and contaminated victims treated? KRAD learned from the University of Arizona that the plume from the 'dirty bomb' elevated radiation levels above approved levels over a 3 square mile area downwind of the Tucson Airport (1:13 pm). People in the affected area are checking in at emergency rooms at the hospital to learn if they're in danger of radiation health affects. Gridlock has set in as panicked people are either leaving the area or headed for emergency rooms. 11. What should be done to help mitigate fears? DHS raises the National Terrorism Alert to Code Red (late afternoon). 12. What should your nuclear facility do next? 13. KRAD reporter contacts you at your nuclear facility and asks, 'Since title to the waste remains with your company, will your company cover the cost of the terrorist event including all decontamination and medical expenses? The results of the question were very interesting and stimulated quite a bit of discussion am

  5. Remote handling facility and equipment used for space truss assembly

    SciTech Connect (OSTI)

    Burgess, T.W.

    1987-01-01

    The ACCESS truss remote handling experiments were performed at Oak Ridge National Laboratory's (ORNL's) Remote Operation and Maintenance Demonstration (ROMD) facility. The ROMD facility has been developed by the US Department of Energy's (DOE's) Consolidated Fuel Reprocessing Program to develop and demonstrate remote maintenance techniques for advanced nuclear fuel reprocessing equipment and other programs of national interest. The facility is a large-volume, high-bay area that encloses a complete, technologically advanced remote maintenance system that first began operation in FY 1982. The maintenance system consists of a full complement of teleoperated manipulators, manipulator transport systems, and overhead hoists that provide the capability of performing a large variety of remote handling tasks. This system has been used to demonstrate remote manipulation techniques for the DOE, the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan, and the US Navy in addition to the National Aeronautics and Space Administration. ACCESS truss remote assembly was performed in the ROMD facility using the Central Research Laboratory's (CRL) model M-2 servomanipulator. The model M-2 is a dual-arm, bilateral force-reflecting, master/slave servomanipulator which was jointly developed by CRL and ORNL and represents the state of the art in teleoperated manipulators commercially available in the United States today. The model M-2 servomanipulator incorporates a distributed, microprocessor-based digital control system and was the first successful implementation of an entirely digitally controlled servomanipulator. The system has been in operation since FY 1983. 3 refs., 2 figs.

  6. Compatible and Cost-Effective Fault Diagnostic Solutions for Air Handling

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

    Unit-Variable Air Volume and Air Handling Unit-Constant Air Volume Systems - 2014 BTO Peer Review | Department of Energy Compatible and Cost-Effective Fault Diagnostic Solutions for Air Handling Unit-Variable Air Volume and Air Handling Unit-Constant Air Volume Systems - 2014 BTO Peer Review Compatible and Cost-Effective Fault Diagnostic Solutions for Air Handling Unit-Variable Air Volume and Air Handling Unit-Constant Air Volume Systems - 2014 BTO Peer Review Presenter: Jin Wen, Drexel

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

    SciTech Connect (OSTI)

    Hazelton, R.F.

    1987-09-01

    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. Test reports for K Basins vertical fuel handling tools

    SciTech Connect (OSTI)

    Meling, T.A.

    1995-02-01

    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.

  9. 340 waste handling complex: Deactivation project management plan

    SciTech Connect (OSTI)

    Stordeur, R.T.

    1998-06-25

    This document provides an overview of the strategy for deactivating the 340 Waste Handling Complex within Hanford`s 300 Area. The plan covers the period from the pending September 30, 1998 cessation of voluntary radioactive liquid waste (RLW) transfers to the 340 Complex, until such time that those portions of the 340 Complex that remain active beyond September 30, 1998, specifically, the Retention Process Sewer (RPS), can also be shut down and deactivated. Specific activities are detailed and divided into two phases. Phase 1 ends in 2001 after the core RLW systems have been deactivated. Phase 2 covers the subsequent interim surveillance of deactivated and stand-by components during the period of continued RPS operation, through the final transfer of the entire 340 Complex to the Environmental Restoration Contractor. One of several possible scenarios was postulated and developed as a budget and schedule planning case.

  10. Automated cassette-to-cassette substrate handling system

    DOE Patents [OSTI]

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

    2014-03-18

    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. ASPECT Emergency Response Chemical and Radiological Mapping

    SciTech Connect (OSTI)

    LANL

    2008-05-12

    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.

  12. ASPECT Emergency Response Chemical and Radiological Mapping

    ScienceCinema (OSTI)

    LANL

    2009-09-01

    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.

  13. Defense Remote Handled Transuranic Waste Cost/Schedule Optimization Study

    SciTech Connect (OSTI)

    Pierce, G.D. . Joint Integration Office); Beaulieu, D.H. ); Wolaver, R.W.; Carson, P.H. Corp., Boulder, CO )

    1986-11-01

    The purpose of this study is to provide the DOE information with which it can establish the most efficient program for the long management and disposal, in the Waste Isolation Pilot Plant (WIPP), of remote handled (RH) transuranic (TRU) waste. To fulfill this purpose, a comprehensive review of waste characteristics, existing and projected waste inventories, processing and transportation options, and WIPP requirements was made. Cost differences between waste management alternatives were analyzed and compared to an established baseline. The result of this study is an information package that DOE can use as the basis for policy decisions. As part of this study, a comprehensive list of alternatives for each element of the baseline was developed and reviewed with the sites. The principle conclusions of the study follow. A single processing facility for RH TRU waste is both necessary and sufficient. The RH TRU processing facility should be located at Oak Ridge National Laboratory (ORNL). Shielding of RH TRU to contact handled levels is not an economic alternative in general, but is an acceptable alternative for specific waste streams. Compaction is only cost effective at the ORNL processing facility, with a possible exception at Hanford for small compaction of paint cans of newly generated glovebox waste. It is more cost effective to ship certified waste to WIPP in 55-gal drums than in canisters, assuming a suitable drum cask becomes available. Some waste forms cannot be packaged in drums, a canister/shielded cask capability is also required. To achieve the desired disposal rate, the ORNL processing facility must be operational by 1996. Implementing the conclusions of this study can save approximately $110 million, compared to the baseline, in facility, transportation, and interim storage costs through the year 2013. 10 figs., 28 tabs.

  14. RCUT: A Non-Invasive Method for Detection, Location, and Quantification of Radiological Contaminants in Pipes and Ducts - 12514

    SciTech Connect (OSTI)

    Bratton, Wesley L.; Maresca, Joseph W. Jr.; Beck, Deborah A.

    2012-07-01

    Radiological Characterization Using Tracers (RCUT) is a minimally invasive method for detection and location of residual radiological contamination in pipes and ducts. The RCUT technology utilizes reactive gaseous tracers that dissociate when exposed to gamma and/or beta radiation emitting from a radiological contaminant in a pipe or duct. Sulfur hexafluoride (SF{sub 6}) was selected as a tracer for this radiological application, because it is a chemically inert gas that is both nonflammable, nontoxic, and breaks down when exposed to gamma radiation. Laboratory tests demonstrated that the tracer pair of SF{sub 6} and O{sub 2} formed SO{sub 2}F{sub 2} when exposed to a gamma or beta radioactive field, which indicated the presence of radiological contamination. Field application of RCUT involves first injecting the reactive tracers into the pipe to fill the pipe being inspected and allowing sufficient time for the tracer to interact with any contaminants present. This is followed by the injection of an inert gas at one end of the pipe to push the reactive tracer at a known or constant flow velocity along the pipe and then out the exit and sampling port at the end of the pipeline where its concentration is measured by a gas chromatograph. If a radiological contaminant is present in the pipe being tested, the presence of SO{sub 2}F{sub 2} will be detected. The time of arrival of the SO{sub 2}F{sub 2} can be used to locate the contaminant. If the pipe is free of radiological contamination, no SO{sub 2}F{sub 2} will be detected. RCUT and PCUT are both effective technologies that can be used to detect contamination within pipelines without the need for mechanical or human inspection. These methods can be used to detect, locate, and/or estimate the volume of a variety of radioactive materials and hazardous chemicals such as chlorinated solvents, petroleum products, and heavy metals. While further optimization is needed for RCUT, the key first step of identification of a tracer compound appropriate for the application of detecting radioactive pipeline contamination through the detection of decomposition products of SF{sub 6} has been demonstrated. Other tracer gases that will also undergo radiolysis will be considered in the future. The next step for the RCUT development process is conducting laboratory scale tests using short pipelines to define analytical requirements, establish performance boundaries, and develop strategies for lower exposure levels. Studies to identify additional analytical techniques using equipment that is more field rugged than a GC/MS would also be beneficial. (authors)

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

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-12-29

    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.

  16. Decision Support Tool for the Management of Debris from Radiological Dispersal Devices and Other Incidents of National Significance

    SciTech Connect (OSTI)

    Lemieux, P.; Thorneloe, S.; Hayes, C.; Rodgers, M.; Christman, R.

    2008-07-01

    Unique challenges exist for the handling, transport, and disposal of debris resulting from homeland security incidents, disasters or other national emergencies. Access to guidance to facilitate decision making to ensure the safe and timely disposal of debris is critical to helping restore a community or region and prevent further contamination or spread of disease. For a radiological dispersal device (RDD), proper characterization of the quantity, properties, and level of contamination of debris can have a significant impact on cleanup costs and timelines. A suite of decision support tools (DSTs) is being developed by the U.S. EPA's Office of Research and Development to assist individuals responsible for making decisions associated with handling, transport, and disposal of such debris. The DSTs are location-specific to help identify specific facilities and contacts for making final disposal decisions. The DSTs provide quick reference to technical information, regulations, and other information to provide decision makers with assistance in guiding disposal decisions that are important for the protection of public health, first responders, and the environment. These tools are being developed in partnership with other U.S. government agencies, EPA program offices, industry, and state and local emergency response programs. (authors)

  17. High Level Waste Remote Handling Equipment in the Melter Cave Support Handling System at the Hanford Waste Treatment Plant

    SciTech Connect (OSTI)

    Bardal, M.A. [PaR Systems, Inc., Shoreview, MN (United States); Darwen, N.J. [Bechtel National, Inc., Richland, WA (United States)

    2008-07-01

    Cold war plutonium production led to extensive amounts of radioactive waste stored in tanks at the Department of Energy's (DOE) Hanford site. Bechtel National, Inc. is building the largest nuclear Waste Treatment Plant in the world located at the Department of Energy's Hanford site to immobilize the millions of gallons of radioactive waste. The site comprises five main facilities; Pretreatment, High Level Waste vitrification, Low Active Waste vitrification, an Analytical Lab and the Balance of Facilities. The pretreatment facilities will separate the high and low level waste. The high level waste will then proceed to the HLW facility for vitrification. Vitrification is a process of utilizing a melter to mix molten glass with radioactive waste to form a stable product for storage. The melter cave is designated as the High Level Waste Melter Cave Support Handling System (HSH). There are several key processes that occur in the HSH cell that are necessary for vitrification and include: feed preparation, mixing, pouring, cooling and all maintenance and repair of the process equipment. Due to the cell's high level radiation, remote handling equipment provided by PaR Systems, Inc. is required to install and remove all equipment in the HSH cell. The remote handling crane is composed of a bridge and trolley. The trolley supports a telescoping tube set that rigidly deploys a TR 4350 manipulator arm with seven degrees of freedom. A rotating, extending, and retracting slewing hoist is mounted to the bottom of the trolley and is centered about the telescoping tube set. Both the manipulator and slewer are unique to this cell. The slewer can reach into corners and the manipulator's cross pivoting wrist provides better operational dexterity and camera viewing angles at the end of the arm. Since the crane functions will be operated remotely, the entire cell and crane have been modeled with 3-D software. Model simulations have been used to confirm operational and maintenance functional and timing studies throughout the design process. Since no humans can go in or out of the cell, there are several recovery options that have been designed into the system including jack-down wheels for the bridge and trolley, recovery drums for the manipulator hoist, and a wire rope cable cutter for the slewer jib hoist. If the entire crane fails in cell, the large diameter cable reel that provides power, signal, and control to the crane can be used to retrieve the crane from the cell into the crane maintenance area. (authors)

  18. 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.

    2011-06-07

    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.

  19. Annual radiological environmental operating report: Browns Ferry Nuclear Plant, 1992. Operations Services/Technical Programs

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. Small amounts of Co-60 and Cs-134 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public.

  20. 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.

    1980-01-01

    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.

  1. Material Misfits

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

    Issues submit Material Misfits How well nanocomposite materials align at their interfaces determines what properties they have, opening broad new avenues of materials-science...

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

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    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.

  3. Radiological Worker Training Power Point Slides for App. A

    Energy Savers [EERE]

    30-2008 DOE HANDBOOK Radiological Worker Training DOE-HDBK-1130-2008 Overheads December 2008 Reaffirmed 2013 OT 1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in

  4. RADIOLOGICAL EFFLUENT AND ONSITE AREA MONITORING REPORT FOR THE

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

    327-33 a a RADIOLOGICAL EFFLUENT AND ONSITE AREA MONITORING REPORT FOR THE 0 NEVADA TEST SITE (JANUARY 1986 THROUGH DECEMBER 1986) BANEL A. GONZALEZ HEALTH PHY%ICIST SePTEMl3ER 1987 WORK PERFORMED UNDER CONTRACT NO. DE-ACXM-84-84NV10327 REYNOLDS ELECTRICAL & ENGINEERING CO., INC. POST OFFICE BOX 14400 LAS VEGAS, NV 89114 DOE/NV/10327-33 RADIOLOGICAL EFFLUENT AND ONSITE AREA MONITORING REPORT FOR THE NEVADA TEST SITE (JANUARY 1986 THROUGH DECEMBER 1986) Daniel A. Gonzalez Health Physicist

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

    Energy Savers [EERE]

    ALARA Instructor's Guide 1.10-1 Course Title: Radiological Control Technician Module Title: ALARA Module Number: 1.10 Objectives: 1.10.01 Describe the assumptions on which the current ALARA philosophy is based. 1.10.02 Identify the ALARA philosophy for collective personnel exposure and individual exposure. 1.10.03 Identify the scope of an effective radiological ALARA program. 1.10.04 Identify the purposes for conducting pre-job and/or post-job ALARA reviews. 1.10.05 Identify RCT responsibilities

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

    Energy Savers [EERE]

    ALARA Study Guide 1.10-1 Course Title: Radiological Control Technician Module Title: ALARA Module Number: 1.10 Objectives: 1.10.01 Describe the assumptions on which the current ALARA philosophy is based. 1.10.02 Identify the ALARA philosophy for collective personnel exposure and individual exposure. 1.10.03 Identify the scope of an effective radiological ALARA program. 1.10.04 Identify the purposes for conducting pre-job and/or post-job ALARA reviews. 1.10.05 Identify RCT responsibilities for

  7. Pebble Fuel Handling and Reactivity Control for Salt-Cooled High

    Office of Scientific and Technical Information (OSTI)

    Temperature Reactors (Technical Report) | SciTech Connect Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors Citation Details In-Document Search Title: Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors This report documents the work completed on the X-PREX facility under NEUP Project 11- 3172. This project seeks to demonstrate the viability of pebble fuel handling and reactivity control for fluoride salt-cooled

  8. Functional Materials

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

    Functional Materials Researchers in NETL's Functional Materials Development competency work to discover and develop advanced functional materials and component processing technologies to meet technology performance requirements and enable scale-up for proof-of-concept studies. Research includes separations materials and electrochemical and magnetic materials, specifically: Separations Materials Synthesis, purification, and basic characterization of organic substances, including polymers and

  9. First Oak Ridge Remote-Handled Transuranic Waste Shipment Arrives Safely at WIPP

    Broader source: Energy.gov [DOE]

    DOE achieved a major environmental cleanup milestone this week with the first shipment of remote-handled TRU waste leaving DOE’s Oak Ridge Reservation.

  10. 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.

    2010-10-01

    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.

  11. Automated Proactive Techniques for Commissioning Air-Handling Units

    SciTech Connect (OSTI)

    Katipamula, Srinivas ); Brambley, Michael R. ); Luskay, Larry

    2003-08-30

    Many buildings today use sophisticated building automation systems (BASs) to manage a wide and varied range of building systems. Although the capabilities of the BASs seem to have increased over time, many buildings still are not properly commissioned, operated or maintained. Lack of or improper commissioning, the inability of the building operators to grasp the complex controls, and lack of proper maintenance leads to inefficient operations and reduced lifetimes of the equipment. If regularly scheduled manual maintenance or re-commissioning practices are adopted, they can be expensive and time consuming. Automated proactive commissioning and diagnostic technologies address two of the main barriers to commissioning: cost and schedules. Automated proactive continuous commissioning tools can reduce both the cost and time associated with commissioning, as well as enhance the persistence of commissioning fixes. In the long run, automation even offers the potential for automatically correcting problems by reconfiguring controls or changing control algorithms dynamically. This paper will discuss procedures and processes that can be used to automate and continuously commission the economizer operation and outdoor-air ventilation systems of an air-handling unit.

  12. Urenco`s experience of UF{sub 6} handling

    SciTech Connect (OSTI)

    Saelmans, F.; Scane, C.; Christofzik, J.

    1991-12-31

    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.

  13. Self-actuating mechanical grapple for lifting and handling objects

    DOE Patents [OSTI]

    Hovis, Gregory L. (North Augusta, SC); Etheredge, Jr., Carl T. (Tuscaloosa, AL)

    2001-01-01

    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.

  14. 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

    2013-07-01

    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.

  15. DOE Issues WIPP Radiological Release Phase II Investigation Report

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – Today, the Department of Energy Office of Environmental Management (EM) released the Accident Investigation Board (AIB) Phase II Report related to the Feb. 14, 2014, radiological event at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico.

  16. 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.)

  17. Radiological safety training for accelerator facilities: DOE handbook

    SciTech Connect (OSTI)

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M&O) contractors having responsibility for implementing the core training recommended by the RadCon Manual.

  18. EM-Led Radiological Incident Response Program Receives Honors

    Broader source: Energy.gov [DOE]

    A program led by EM’s Carlsbad Field Office (CBFO) that coordinates analytical capabilities throughout DOE for response to potential national radiological incidents recently received recognition for the best-in-track poster at a waste management conference earlier this year.

  19. Radiology utilizing a gas multiwire detector with resolution enhancement

    DOE Patents [OSTI]

    Majewski, Stanislaw; Majewski, Lucasz A.

    1999-09-28

    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.

  20. Structural Materials

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

    Structural Materials Structural Materials Development enables advanced technologies through the discovery, development, and demonstration of cost-effective advanced structural materials for use in extreme environments (high-temperature, high-stress, erosive, and corrosive environments, including the performance of materials in contact with molten slags and salts). Research includes materials design and discovery, materials processing and manufacturing, and service-life prediction of materials

  1. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-02-01

    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.

  2. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-05-01

    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.

  3. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-10-01

    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.

  4. Resources for Handling Transcripts | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Graduate Transcripts for Current Graduate Institution » Resources for Handling Transcripts DOE Office of Science Graduate Student Research (SCGSR) Program SCGSR Home Eligibility Benefits Participant Obligations How to Apply Identifying a Collaborating DOE Laboratory Scientist Research Proposal Guidelines Office of Science Priority Research Areas for SCGSR Program Letters of Support Graduate Transcripts for Current Graduate Institution Resources for Handling Transcripts Application Evaluation

  5. Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1992. Operations Services/Technical Programs

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment.

  6. Materials Selection Considerations for Thermal Process Equipment: A

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

    BestPractices Process Heating Technical Brief | Department of Energy Materials Selection Considerations for Thermal Process Equipment: A BestPractices Process Heating Technical Brief Materials Selection Considerations for Thermal Process Equipment: A BestPractices Process Heating Technical Brief This technical brief is a guide to selecting high-temperature metallic materials for use in process heating applications such as burners, electrical heating elements, material handling, load support,

  7. Reference Materials

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

    Reference Materials Reference Materials Large Scale Computing and Storage Requirements for Biological and Environmental Research May 7-8, 2009 Invitation Workshop Invitation Letter...

  8. Reference Materials

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

    Reference Materials Reference Materials Large Scale Computing and Storage Requirements for Basic Energy Sciences February 9-10, 2010 Official DOE Invitation Workshop Invitation...

  9. Materials Science

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

    Materials Science science-innovationassetsimagesicon-science.jpg Materials Science National security depends on science and technology. The United States relies on Los Alamos ...

  10. Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities

    SciTech Connect (OSTI)

    Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E.; Martin, N.

    2008-01-15

    The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys.

  11. Introduction The Radiological/Nuclear Countermeasures Test and Evaluation

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

    Radiological/Nuclear Countermeasures Test and Evaluation Complex (RNCTEC) is a multi-use test and evaluation platform that will serve the U.S. homeland security mission. Background The Department of Homeland Security's Domestic Nuclear Detection Office (DNDO), with assistance from the U.S. Department of Energy National Nuclear Security Administration, has established the RNCTEC at the Nevada National Security Site, formerly known as the Nevada Test Site, to support all federal agencies to

  12. Fifth Anniversary of Radiological Alarm Response Training for Local Law

    National Nuclear Security Administration (NNSA)

    Enforcement and First Responders across the Country | National Nuclear Security Administration fieldoffices / Welcome to the NNSA Production Office / NPO News Releases Fifth Anniversary of Radiological Alarm Response Training for Local Law Enforcement and First Responders across the Country February 10, 2014 This week marks the fifth anniversary of the Department of Energy's National Nuclear Security Administration's (NNSA) Alarm Response Training (ART) program for local law enforcement and

  13. ORISE Resources: Radiological and Nuclear Terrorism: Medical Response to

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

    Mass Casualties Training Clinicians for Response to a Radiological or Nuclear Terrorism Attack The Centers for Disease Control and Prevention and its Radiation Studies Branch in the National Center for Environmental Health asked the Oak Ridge Institute for Science and Education (ORISE) to develop a Web-based and CD-ROM training program to prepare clinicians-medical doctors and registered nurses in hospital emergency service settings-on how to locally respond to mass casualties that may

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

    Energy Savers [EERE]

    3 Radiation Detector Theory Instructor's Guide 1.13-1 Course Title: Radiological Control Technician Module Title: Radiation Detector Theory Module Number: 1.13 Objectives: 1.13.01 Identify the three fundamental laws associated with electrical charges. 1.13.02 Identify the definition of current, voltage and resistance and their respective units. 1.13.03 Select the function of the detector and readout circuitry components in a radiation measurement system. 1.13.04 Identify the parameters that

  15. DOE-HDBK-1131-98; General Employee Radiological Training

    Energy Savers [EERE]

    DOE-HDBK-1131-98 December 1998 Change Notice No. 1 November 2003 Reaffirmation with Errata April 2004 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of

  16. Fifth Anniversary of Radiological Alarm Response Training for Local Law

    National Nuclear Security Administration (NNSA)

    Enforcement and First Responders Across the Country | National Nuclear Security Administration Fifth Anniversary of Radiological Alarm Response Training for Local Law Enforcement and First Responders Across the Country Wednesday, February 12, 2014 - 3:00pm This week marks the fifth anniversary of NNSA's Alarm Response Training (ART) program for local law enforcement and other critical first responders around the country. In the five years of providing this course, NNSA has trained more than

  17. Surface Contamination Guidelines/Radiological Clearance of Property

    Broader source: Energy.gov [DOE]

    Table IV-1, DOE O 5400.5, DOE Draft 441.XX, Authorized Limits govern the control and clearance of personal and real property. They are radionuclide concentrations or activity levels approved by DOEto permit the clearance of property under DOE radiological control for either restricted or unrestricted use, consistent with DOE’s radiation protection framework and standards for workers, the general public, and the environment.

  18. Materials Scientist

    Broader source: Energy.gov [DOE]

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

  19. material protection

    National Nuclear Security Administration (NNSA)

    %2A en Office of Weapons Material Protection http:nnsa.energy.govaboutusourprogramsnonproliferationprogramofficesinternationalmaterialprotectionandcooperation-1

  20. material protection

    National Nuclear Security Administration (NNSA)

    %2A en Office of Weapons Material Protection http:www.nnsa.energy.govaboutusourprogramsnonproliferationprogramofficesinternationalmaterialprotectionandcooperation-1

  1. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Timothy Solack; Carol Mason

    2012-03-01

    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.

  2. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-02-01

    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.

  3. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-05-01

    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.

  4. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect (OSTI)

    Asou, M. [CEA/DEN/VALRHO/UMODD, 30207 Bagnols-sur-Ceze Cedex (France); Le Goaller, C. [CEA/DEN/VALRHO/DDCO, 30207 Bagnols-sur-Ceze Cedex (France); Martin, F. [AREVA NC DAP/MOP (France)

    2007-07-01

    Cleanup operations in the Marcoule Vitrification Facility (AVM) will start in 2007. This plant includes 20 highly irradiating storage tanks for high-level liquid waste before vitrification. The objective of the cleanup phase is to significantly decrease the amount of highly radioactive waste resulting from dismantling. A comprehensive radiological survey of the plant was initiated in 2000. Most of the tanks were characterized using advanced technologies: gamma imaging, CdZnTe gamma spectroscopy, dose rate measurements and 3D calculations codes. At the same time, inspections were conducted to develop 3D geometrical models of the tanks. The techniques used and the main results obtained are described as well as lessons learned from these operations. The rinsing program was defined in 2006. Decontamination operations are expected to begin in 2007, and radiological surveys will be followed up to monitor the efficiency of the decontamination process. Specific rinsing of all tanks and equipment will be carried out from 2007 to 2009. Concentrated liquid solutions will be vitrified between 2008 and 2010; the decommissioning of AVM will be delayed until the end of 2010. This strategy aims at producing less than 5% 'B' type (long-lived intermediate-level) waste from the decommissioning operations, as well as reducing the dose rate and risks by simplified remote dismantling. The paper reviews the main options selected for decontamination, as well as the radiological characterization strategy. Some cost-related aspects will also be analyzed. (authors)

  5. Critical Materials:

    Energy Savers [EERE]

    Facilities » Critical Materials Hub Critical Materials Hub Green light reflection from a low-oxygen environment 3D printer laser deposition of metal powder alloys. Photo courtesy of The Critical Materials Institute, Ames Laboratory Green light reflection from a low-oxygen environment 3D printer laser deposition of metal powder alloys. Photo courtesy of The Critical Materials Institute, Ames Laboratory Critical materials, including some rare earth elements that possess unique magnetic,

  6. Central Characterization Program (CCP) Contact-Handled (CH) TRU Waste Certification and Waste Information System/Waste Data System (WWIS/WDS) Data Entry

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  7. Step-By-Step Guide for Waste Handling at WIPP - Fact Sheet

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

    the nation's nuclear waste disposal problem Step-By-Step Guide for Waste Handling at WIPP The handling and disposal of contact-handled transuranic waste at the Waste Isolation Pilot Plant (WIPP) involves a series of steps. The following is an overview of those steps. Ž A waste shipment arrives at the WIPP by tractor-trailer. Each tractor-trailer is capable of carrying up to three Transuranic Packaging Transporter Model IIs (TRUPACT-IIs) or HalfPACT's. Ž Upon arrival the tractor trailer and

  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.

    2006-08-01

    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. Compilation of Requirements for Safe Handling of Fluorine and Fluorine-Containing Products of Uranium Hexafluoride Conversion

    SciTech Connect (OSTI)

    Ferrada, J.J.

    2000-04-03

    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. Limitations Influencing Interventional Radiology in Canada: Results of a National Survey by the Canadian Interventional Radiology Association (CIRA)

    SciTech Connect (OSTI)

    O'Brien, Jeremy; Baerlocher, Mark Otto Asch, Murray R.; Hayeems, Eran; Kachura, John R.; Collingwood, Peter

    2007-09-15

    Purpose. To describe the current state and limitations to interventional radiology (IR) in Canada through a large, national survey of Canadian interventional radiologists. Methods. An anonymous online survey was offered to members of the Canadian Interventional Radiology Association (CIRA). Only staff radiologists were invited to participate. Results. Seventy-five (75) responses were received from a total of 247, giving a response rate of 30%. Respondents were split approximately equally between academic centers (47%) and community practice (53%), and the majority of interventional radiologists worked in hospitals with either 200-500 (49%) or 500-1,000 (39%) beds. Procedures listed by respondents as most commonly performed in their practice included PICC line insertion (83%), angiography and stenting (65%), and percutaneous biopsy (37%). Procedures listed as not currently performed but which interventional radiologists believed would benefit their patient population included radiofrequency ablation (36%), carotid stenting (34%), and aortic stenting (21%); the majority of respondents noted that a lack of support from referring services was the main reason for not performing these procedures (56%). Impediments to increasing scope and volume of practice in Canadian IR were most commonly related to room or equipment shortage (35%), radiologist shortage (33%), and a lack of funding or administrative support (28%). Conclusion. Interventional radiology in Canada is limited by a number of factors including funding, manpower, and referral support. A concerted effort should be undertaken by individual interventional radiologists and IR organizations to increase training capacity, funding, remuneration, and public exposure to IR in order to help advance the subspecialty.

  11. Explosive scabbling of structural materials

    DOE Patents [OSTI]

    Bickes, Jr., Robert W.; Bonzon, Lloyd L.

    2002-01-01

    A new approach to scabbling of surfaces of structural materials is disclosed. A layer of mildly energetic explosive composition is applied to the surface to be scabbled. The explosive composition is then detonated, rubbleizing the surface. Explosive compositions used must sustain a detonation front along the surface to which it is applied and conform closely to the surface being scabbled. Suitable explosive compositions exist which are stable under handling, easy to apply, easy to transport, have limited toxicity, and can be reliably detonated using conventional techniques.

  12. 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

    2011-12-27

    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.

  13. Development of an Outdoor Concentrating Photovoltaic Module Testbed, Module Handling and Testing Procedures, and Initial Energy Production Results

    SciTech Connect (OSTI)

    Muller, M.

    2009-09-01

    This report addresses the various aspects of setting up a CPV testbed and procedures for handling and testing CPV modules.

  14. Remote-Handled Low-Level Waste 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.

    2012-06-01

    The Remote-Handled Low-Level Waste (LLW) 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 2017). Development of a new onsite disposal facility 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. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  15. Remote-Handled Low-Level Waste Disposal Project Code of Record

    SciTech Connect (OSTI)

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

    2015-04-01

    The Remote-Handled Low-Level Waste (LLW) 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 2017). Development of a new onsite disposal facility 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. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  16. Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment

    SciTech Connect (OSTI)

    Not Available

    1992-09-01

    The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

  17. Remote-Handled Low-Level Waste 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.

    2014-06-01

    The Remote-Handled Low-Level Waste (LLW) 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 2017). Development of a new onsite disposal facility 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. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  18. 29 C.F.R. Part 24: Procedures for the Handling of Retaliation...

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

    Federal Employee Protection Statutes 29 C.F.R. Part 24: Procedures for the Handling of ... Stakeholders: DOE Employees and Employees of DOE Contractors Scope: 29 C.F.R. Part 24 ...

  19. Remote-Handled Low-Level Waste 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.

    2012-04-01

    The Remote-Handled Low-Level Waste (LLW) 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 2017). Development of a new onsite disposal facility 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. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  20. Remote-Handled Low-Level Waste 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.

    2011-04-01

    The Remote-Handled Low-Level Waste (LLW) 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 2017). 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. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.