Sample records for materials transportation safety

  1. Enhancing Railroad Hazardous Materials Transportation Safety...

    Office of Environmental Management (EM)

    Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Presentation made by Kevin...

  2. Helpful links for materials transport, safety, etc.

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

    Helpful links for materials transport, safety, etc. relating to experiment safety at the APS. Internal Reference Material: Transporting Hazardous Materials "Natural" radioactivity...

  3. Hazardous Material Transportation Safety (South Dakota)

    Broader source: Energy.gov [DOE]

    This legislation authorizes the Division of Highway Safety, in the Department of Public Safety, to promulgate regulations pertaining to the safe transportation of hazardous materials by a motor...

  4. Hazardous Materials Packaging and Transportation Safety

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

    2015-04-20T23:59:59.000Z

    The Order establishes safety requirements for the proper packaging and transportation of Department of offsite shipments and onsite transfers of radioactive and other hazardous materials, and for modal transportation.

  5. Enhancing Railroad Hazardous Materials Transportation Safety

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010 SNFEnergySession0-02 -Railroad Hazardous g Materials

  6. Center for Intermodal Transportation Safety

    E-Print Network [OSTI]

    Fernandez, Eduardo

    Center for Intermodal Transportation Safety and Security Panagiotis Scarlatos, Ph.D., Director Transportation Safety and Security #12;Center for Intermodal Transportation Safety and Security Partners #12 evacuations · Tracking systems for hazardous materials Center for Intermodal Transportation Safety

  7. DRAFT - DOE O 460.1D, Hazardous Materials Packaging and Transportation Safety

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

    The Order establishes safety requirements for the proper packaging and transportation of Department of offsite shipments and onsite transfers of radioactive and other hazardous materials, and for modal transportation.

  8. Packaging and Transportation Safety

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

    1995-09-27T23:59:59.000Z

    Establishes safety requirements for the proper packaging and transportation of offsite shipments and onsite transfers of hazardous materials andor modal transport. Cancels DOE 1540.2 and DOE 5480.3

  9. Packaging and Transportation Safety

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

    1995-09-27T23:59:59.000Z

    Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Canceled by DOE 460.1A

  10. Packaging and Transportation Safety

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

    1996-10-02T23:59:59.000Z

    Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1.

  11. Romanian Experience for Enhancing Safety and Security in Transport of Radioactive Material - 12223

    SciTech Connect (OSTI)

    Vieru, Gheorghe [Institute for Nuclear Research, P.O.BOX 78, 0300 PITESTI (Romania)

    2012-07-01T23:59:59.000Z

    The transport of Dangerous Goods-Class no.7 Radioactive Material (RAM), is an important part of the Romanian Radioactive Material Management. The overall aim of this activity is for enhancing operational safety and security measures during the transport of the radioactive materials, in order to ensure the protection of the people and the environment. The paper will present an overall of the safety and security measures recommended and implemented during transportation of RAM in Romania. Some aspects on the potential threat environment will be also approached with special referring to the low level radioactive material (waste) and NORM transportation either by road or by rail. A special attention is given to the assessment and evaluation of the possible radiological consequences due to RAM transportation. The paper is a part of the IAEA's Vienna Scientific Research Contract on the State Management of Nuclear Security Regime (Framework) concluded with the Institute for Nuclear Research, Romania, where the author is the CSI (Chief Scientific Investigator). The transport of RAM in Romania is a very sensible and complex problem taking into consideration the importance and the need of the security and safety for such activities. The Romanian Nuclear Regulatory Body set up strictly regulation and procedures according to the Recommendation of the IAEA Vienna and other international organizations. There were implemented the adequate regulation and procedures in order to keep the environmental impacts and the radiological consequences at the lower possible level and to assure the effectiveness of state nuclear security regime due to possible malicious acts in carrying out these activities including transport and the disposal site at the acceptable international levels. The levels of the estimated doses and risk expectation values for transport and disposal are within the acceptable limits provided by national and international regulations and recommendations but can increase, significantly during potential malicious acts. (authors)

  12. Packaging and Transportation Safety

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

    2003-04-04T23:59:59.000Z

    To establish safety requirements for the proper packaging and transportation of Department of Energy (DOE)/National Nuclear Security Administration (NNSA) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1A. Canceled by DOE O 460.1C.

  13. Packaging and Transportation Safety

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

    2010-05-14T23:59:59.000Z

    The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of radioactive and other hazardous materials and for modal transportation. Cancels DOE O 460.1B, 5-14-10

  14. Sandia National Laboratories: Transportation Safety

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

    Experimental Testing Phenomenological Modeling Risk and Safety Assessment Cyber-Based Vulnerability Assessments Uncertainty Analysis Transportation Safety Fire Science Human...

  15. Transporting particulate material

    DOE Patents [OSTI]

    Aldred, Derek Leslie (North Hollywood, CA); Rader, Jeffrey A. (North Hollywood, CA); Saunders, Timothy W. (North Hollywood, CA)

    2011-08-30T23:59:59.000Z

    A material transporting system comprises a material transporting apparatus (100) including a material transporting apparatus hopper structure (200, 202), which comprises at least one rotary transporting apparatus; a stationary hub structure (900) constraining and assisting the at least one rotary transporting apparatus; an outlet duct configuration (700) configured to permit material to exit therefrom and comprising at least one diverging portion (702, 702'); an outlet abutment configuration (800) configured to direct material to the outlet duct configuration; an outlet valve assembly from the material transporting system venting the material transporting system; and a moving wall configuration in the material transporting apparatus capable of assisting the material transporting apparatus in transporting material in the material transporting system. Material can be moved from the material transporting apparatus hopper structure to the outlet duct configuration through the at least one rotary transporting apparatus, the outlet abutment configuration, and the outlet valve assembly.

  16. Transporting Hazardous Materials

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

    Transporting Hazardous Materials The procedures given below apply to all materials that are considered to be hazardous by the U.S. Department of Transportation (DOT). Consult your...

  17. Sandia Energy - Transportation Safety

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del Sol Home DistributionTransportation Safety Home Stationary Power Nuclear Fuel Cycle

  18. Radioactive Material Transportation Practices

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

    2002-09-23T23:59:59.000Z

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

  19. Material Safety Data Sheet

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighand Retrievals from a New 183-GHzMAR Os2010Material Safety Data Sheet

  20. 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.

  1. Management and Safety of Transportation Systems

    E-Print Network [OSTI]

    Carver, Jeffrey C.

    Management and Safety of Transportation Systems University Transportation Center for Alabama A N N@eng.ua.edu www.eng.ua.edu Editors: James Cruise, Ph.D. Barbara Moore University Transportation Center for Alabama Transportation Center for Alabama (UTCA). The contents of this Annual Report reflect the views of the editors

  2. Toolbox Safety Talk DOT Materials of Trade

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Toolbox Safety Talk DOT ­ Materials of Trade Environmental Health & Safety Facilities Safety by Trades personnel that meet the definition of hazardous materials even though they may be sold as consumer commodities. The DOT regulations have exceptions for Materials of Trade (MOT). The MOT exception provides

  3. National Transportation Safety Board Office of Aviation Safety

    E-Print Network [OSTI]

    Droegemeier, Kelvin K.

    NWS and Federal Aviation Administration (FAA) Advisory Circular "Aviation Weather Services", AC 00 Electronics Engineer Federal Aviation Administration 1 UTC ­ is an abbreviation for Coordinated Universal Time1 National Transportation Safety Board Office of Aviation Safety Washington, D.C. 20594

  4. Radioactive Material Transportation Practices Manual

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

    2008-06-04T23:59:59.000Z

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

  5. Food Safety Participant Materials for Notebook

    E-Print Network [OSTI]

    foods. · Not eating foods that have been irradiated. · Eating whole foods instead of processed foodsUNIT 5: Food Safety Participant Materials for Notebook #12;Navigating for Success Food Safety p 1 Food Safety Good food safety practices are crucial to reducing foodborne illnesses. Nutrition educators

  6. Order Module--DOE O 460.1C, PACKAGING AND TRANSPORTATION SAFETY...

    Office of Environmental Management (EM)

    DOE O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, DOE O 460.2A, DEPARTMENTAL MATERIALS TRANSPORTATION AND PACKAGING MANAGEMENT Order Module--DOE O 460.1C, PACKAGING AND...

  7. Safety analysis report for packaging (onsite) sample pig transport system

    SciTech Connect (OSTI)

    MCCOY, J.C.

    1999-03-16T23:59:59.000Z

    This Safety Analysis Report for Packaging (SARP) provides a technical evaluation of the Sample Pig Transport System as compared to the requirements of the U.S. Department of Energy, Richland Operations Office (RL) Order 5480.1, Change 1, Chapter III. The evaluation concludes that the package is acceptable for the onsite transport of Type B, fissile excepted radioactive materials when used in accordance with this document.

  8. BNL | CFN: Transport of Hazardous Materials

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

    Transportation of Hazardous Materials and Nanomaterials The following contains guidance for transporting materials to and from BNL and for on-site transfers. All staff and users...

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

    Office of Environmental Management (EM)

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

  10. A critical review of world jet transport safety

    E-Print Network [OSTI]

    Achtmann, Eric D.

    1995-01-01T23:59:59.000Z

    This thesis is intended to serve as a comprehensive introduction to world jet transport safety and aviation fire safety. Divided into six sections, this thesis contains: 1) a statistical review of overall levels of safety ...

  11. August 1999 Radiation Safety Manual Section 12 Shipment of Radioactive Materials

    E-Print Network [OSTI]

    Wilcock, William

    August 1999 Radiation Safety Manual Section 12 ­ Shipment of Radioactive Materials UW Environmental Health and Safety Page 12-1 Section 12 Shipment of Radioactive Materials Contents A. Shipping Regulations regulations for the safe transportation of radioactive materials. These regulations are adopted from those

  12. Structural analysis in support of the waterborne transport of radioactive materials

    SciTech Connect (OSTI)

    Ammerman, D.J.

    1996-08-01T23:59:59.000Z

    The safety of the transportation of radioactive materials by road and rail has been well studied and documented. However, the safety of waterborne transportation has received much less attention. Recent highly visible waterborne transportation campaigns have led to DOE and IAEA to focus attention on the safety of this transportation mode. In response, Sandia National Laboratories is conducting a program to establish a method to determine the safety of these shipments. As part of that program the mechanics involved in ship-to-ship collisions are being evaluated to determine the loadings imparted to radioactive material transportation packages during these collisions. This paper will report on the results of these evaluations.

  13. Materials Sciences Division Integrated Safety Management Plan

    E-Print Network [OSTI]

    Materials Sciences Division Integrated Safety Management Plan Revised: February 9, 2012 Prepared by: signed Feb. 9, 2012 Rick Kelly, Facility/EH&S Manager Submitted by: signed Feb. 9, 2012 Miquel Salmeron.1 RESPONSIBILITY AND AUTHORITY THROUGH LINE MANAGEMENT............................................................5

  14. Hanford Site Wide Transportation Safety Document [SEC 1 Thru 3

    SciTech Connect (OSTI)

    MCCALL, D L

    2002-06-01T23:59:59.000Z

    This safety evaluation report (SER) documents the basis for the US Department of Energy (DOE), Richland Operations Office (RL) to approve the Hanford Sitewide Transportation Safety Document (TSD) for onsite Transportation and Packaging (T&P) at Hanford. Hanford contractors, on behalf of DOE-RL, prepared and submitted the Hanford Sitewide Transportation Safety Document, DOE/RL-2001-0036, Revision 0, (DOE/RL 2001), dated October 4, 2001, which is referred to throughout this report as the TSD. In the context of the TSD, Hanford onsite shipments are the activities of moving hazardous materials, substances, and wastes between DOE facilities and over roadways where public access is controlled or restricted and includes intra-area and inter-area movements. The TSD sets forth requirements and standards for onsite shipment of radioactive and hazardous materials and wastes within the confines of the Hanford Site on roadways where public access is restricted by signs, barricades, fences, or other means including road closures and moving convoys controlled by Hanford Site security forces.

  15. Departmental Materials Transportation and Packaging Management

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

    2010-11-18T23:59:59.000Z

    Establishes requirements and responsibilities for management of Department of Energy (DOE), including National Nuclear Security Administration, materials transportation and packaging and ensures the safe, secure, efficient packaging and transportation of materials, both hazardous and non-hazardous.

  16. Fusion reactor breeder material safety compatibility studies

    SciTech Connect (OSTI)

    Jeppson, D.W.; Cohen, S.; Muhlestein, L.D.

    1983-09-01T23:59:59.000Z

    Tritium breeder material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Breeder material safety compatibility studies are being conducted to identify and characterize breeder-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate the following. 1. Ternary oxides (LiAlO/sub 2/, Li/sub 2/ZrO/sub 3/, Li/sub 2/SiO/sub 3/, Li/sub 4/SiO/sub 4/, and LiTiO/sub 3/) at postulated blanket operating temperatures are chemically compatible with water coolant, while liquid lithium and Li/sub 7/Pb/sub 2/ reactions with water generate heat, aerosol, and hydrogen. 2. Lithium oxide and 17Li-83Pb alloy react mildly with water requiring special precautions to control hydrogen release. 3. Liquid lithium reacts substantially, while 17Li83Pb alloy reacts mildly with concrete to produce hydrogen. 4. Liquid lithium-air reactions may present some major safety concerns. Additional scoping tests are needed, but the ternary oxides, lithium oxide, and 17Li-83Pb have definite safety advantages over liquid lithium and Li/sub 7/Pb/sub 2/. The ternary oxides present minimal safetyrelated problems when used with water as coolant, air or concrete; but they do require neutron multipliers, which may have safety compatibility concerns with surrounding materials. The combined favorable neutronics and minor safety compatibility concerns of lithium oxide and 17Li-83Pb make them prime candidates as breeder materials. Current safety efforts are directed toward assessing the compatibility of lithium oxide and the lithium-lead alloy with coolants and other materials.

  17. DOW CORNING CORPORATION Material Safety Data Sheet

    E-Print Network [OSTI]

    Garmestani, Hamid

    -88-3 Toluene The above components are hazardous as defined in 29 CFR 1910.1200. 3. HAZARDS or water spray. Water can be used to cool fire exposed containers. Fire Fighting Measures: Self to keep fire exposed containers cool. #12;DOW CORNING CORPORATION Material Safety Data Sheet Page: 3 of 8

  18. Essays on Transportation Safety, Economics, and Policy

    E-Print Network [OSTI]

    Scholl, Patricia Lynn

    2011-01-01T23:59:59.000Z

    2002. TCF, 2000, “Widening the Transportation Divide: HowGovernor Davis’ Transportation Plan Leaves Transit-People Stranded”, Transportation Choices Forum, 2000.

  19. Regulatory and extra-regulatory testing to demonstrate radioactive material packaging safety

    SciTech Connect (OSTI)

    Ammerman, D.J.

    1997-06-01T23:59:59.000Z

    Packages for the transportation of radioactive material must meet performance criteria to assure safety and environmental protection. The stringency of the performance criteria is based on the degree of hazard of the material being transported. Type B packages are used for transporting large quantities of radioisotopes (in terms of A{sub 2} quantities). These packages have the most stringent performance criteria. Material with less than an A{sub 2} quantity are transported in Type A packages. These packages have less stringent performance criteria. Transportation of LSA and SCO materials must be in {open_quotes}strong-tight{close_quotes} packages. The performance requirements for the latter packages are even less stringent. All of these package types provide a high level of safety for the material being transported. In this paper, regulatory tests that are used to demonstrate this safety will be described. The responses of various packages to these tests will be shown. In addition, the response of packages to extra-regulatory tests will be discussed. The results of these tests will be used to demonstrate the high level of safety provided to workers, the public, and the environment by packages used for the transportation of radioactive material.

  20. Departmental Materials Transportation and Packaging Management

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

    2004-12-22T23:59:59.000Z

    The Order establishes requirements and responsibilities for management of Department of Energy (DOE), including National Nuclear Security Administration (NNSA), materials transportation and packaging to ensure the safe, secure, efficient packaging and transportation of materials, both hazardous and nonhazardous. Cancels DOE O 460.2 and DOE O 460.2 Chg 1

  1. Chemical and Hazardous Materials Department of Environmental Health and Safety

    E-Print Network [OSTI]

    O'Toole, Alice J.

    Chemical and Hazardous Materials Safety Department of Environmental Health and Safety 800 West information useful in the recognition, evaluation, and control of workplace hazards and environmental factors safety, fire safety, and hazardous waste disposal. Many chemicals have properties that make them

  2. Apparatus for transporting hazardous materials

    DOE Patents [OSTI]

    Osterman, Robert A. (Canonsburg, PA); Cox, Robert (West Mifflin, PA)

    1992-01-01T23:59:59.000Z

    An apparatus and method are provided for selectively receiving, transporting, and releasing one or more radioactive or other hazardous samples for analysis on a differential thermal analysis (DTA) apparatus. The apparatus includes a portable sample transporting apparatus for storing and transporting the samples and includes a support assembly for supporting the transporting apparatus when a sample is transferred to the DTA apparatus. The transporting apparatus includes a storage member which includes a plurality of storage chambers arrayed circumferentially with respect to a central axis. An adjustable top door is located on the top side of the storage member, and the top door includes a channel capable of being selectively placed in registration with the respective storage chambers thereby permitting the samples to selectively enter the respective storage chambers. The top door, when closed, isolates the respective samples within the storage chambers. A plurality of spring-biased bottom doors are located on the bottom sides of the respective storage chambers. The bottom doors isolate the samples in the respective storage chambers when the bottom doors are in the closed position. The bottom doors permit the samples to leave the respective storage chambers from the bottom side when the respective bottom doors are in respective open positions. The bottom doors permit the samples to be loaded into the respective storage chambers after the analysis for storage and transport to a permanent storage location.

  3. Departmental Materials Transportation and Packaging Management

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

    1995-09-27T23:59:59.000Z

    Establishes Department of Energy (DOE) policies and requirements to supplement applicable laws, rules, regulations, and other DOE Orders for materials transportation and packaging operations. Cancels DOE 1540.1A, DOE 1540.2, DOE 1540.3A.

  4. Departmental Materials Transportation and Packaging Management

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

    1995-10-26T23:59:59.000Z

    Establishes Department of Energy (DOE) policies and requirements to supplement applicable laws, rules, regulations, and other DOE Orders for materials transportation and packaging operations. Cancels: DOE 1540.1A, DOE 1540.2, and DOE 1540.3A.

  5. Electronic transport in atomically thin layered materials

    E-Print Network [OSTI]

    Baugher, Britton William Herbert

    2014-01-01T23:59:59.000Z

    Electronic transport in atomically thin layered materials has been a burgeoning field of study since the discovery of isolated single layer graphene in 2004. Graphene, a semi-metal, has a unique gapless Dirac-like band ...

  6. Enhancing Railroad Hazardous Materials Transportation Safety | Department

    Office of Environmental Management (EM)

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

  7. UNIVERSITY OF WASHINGTON Hazardous Materials Environmental Health & Safety

    E-Print Network [OSTI]

    Wilcock, William

    UNIVERSITY OF WASHINGTON Hazardous Materials Environmental Health & Safety Design Guide Mercury used in many laboratory areas on campus. All laboratory areas and former laboratory areas should. Cleanup by a hazardous materials contractor is required before demolition or construction can begin

  8. Criticality safety analysis on fissile materials in Fukushima reactor cores

    SciTech Connect (OSTI)

    Liu, Xudong; Lemaitre-Xavier, E.; Ahn, Joonhong [Department of Nuclear Engineering, University of California, Berkeley, Berkeley, CA 94720 (United States); Hirano, Fumio [Japan Atomic Energy Agency, Geological Isolation Research and Development Directorate, Tokai-mura, Ibaraki 319-1194 (Japan)

    2013-07-01T23:59:59.000Z

    The present study focuses on the criticality analysis for geological disposal of damaged fuels from Fukushima reactor cores. Starting from the basic understanding of behaviors of plutonium and uranium, a scenario sequence for criticality event is considered. Due to the different mobility of plutonium and uranium in geological formations, the criticality safety is considered in two parts: (1) near-field plutonium system and (2) far-field low enriched uranium (LEU) system. For the near-field plutonium system, a mathematical analysis for pure-solute transport was given, assuming a particular buffer material and waste form configuration. With the transport and decay of plutonium accounted, the critical mass of plutonium was compared with the initial load of a single canister. Our calculation leads us to the conclusion that our system with the initial loading being the average mass of plutonium in an assembly just before the accident is very unlikely to become critical over time. For the far-field LEU system, due to the uncertainties in the geological and geochemical conditions, calculations were made in a parametric space that covers the variation of material compositions and different geometries. Results show that the LEU system could not remain sub-critical within the entire parameter space assumed, although in the iron-rich rock, the neutron multiplicity is significantly reduced.

  9. Heat transport system, method and material

    DOE Patents [OSTI]

    Musinski, D.L.

    1987-04-28T23:59:59.000Z

    A heat transport system, method and composite material are disclosed in which a plurality of hollow spherical shells or microspheres having an outside diameter of less than or equal to 500 microns are encapsulated or embedded within a bulk material. Each shell has captured therein a volatile working fluid, such that each shell operates as a microsized heat pipe for conducting heat through the composite structure. 1 fig.

  10. RADTRAN3. Radioactive Material Transport Risk

    SciTech Connect (OSTI)

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

    1986-02-01T23:59:59.000Z

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

  11. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    - Hazards Identification EMERGENCY OVERVIEW Irritant. Irritating to eyes, respiratory system and skin. HMIS CONTROLS Mechanical exhaust required. Safety shower and eye bath. PERSONAL PROTECTIVE EQUIPMENT Respiratory

  12. Safety evaluation for packaging 222-S laboratory cargo tank for onetime type B material shipment

    SciTech Connect (OSTI)

    Nguyen, P.M.

    1994-08-19T23:59:59.000Z

    The purpose of this Safety Evaluation for Packaging (SEP) is to evaluate and document the safety of the onetime shipment of bulk radioactive liquids in the 222-S Laboratory cargo tank (222-S cargo tank). The 222-S cargo tank is a US Department of Transportation (DOT) MC-312 specification (DOT 1989) cargo tank, vehicle registration number HO-64-04275, approved for low specific activity (LSA) shipments in accordance with the DOT Title 49, Code of Federal Regulations (CFR). In accordance with the US Department of Energy, Richland Operations Office (RL) Order 5480.1A, Chapter III (RL 1988), an equivalent degree of safety shall be provided for onsite shipments as would be afforded by the DOT shipping regulations for a radioactive material package. This document demonstrates that this packaging system meets the onsite transportation safety criteria for a onetime shipment of Type B contents.

  13. WATER TRANSPORT IN VESSELLESS ANGIOSPERMS: CONDUCTING EFFICIENCY AND CAVITATION SAFETY

    E-Print Network [OSTI]

    Hacke, Uwe

    WATER TRANSPORT IN VESSELLESS ANGIOSPERMS: CONDUCTING EFFICIENCY AND CAVITATION SAFETY U. G. Hacke. Second, vesselless wood ought to be exceptionally safe from cavitation if the small cumulative area woods averaged a cavitation pressure of Ã?3:4 6 0:3 MPa, which is low for their wet habitats

  14. Modeling of diffusive mass transport in micropores in cement based materials

    SciTech Connect (OSTI)

    Yamaguchi, Tetsuji, E-mail: yamaguchi.tetsuji@jaea.go.j [Japan Atomic Energy Agency, Shirakata, Tokai, Ibaraki 319-1195 (Japan); Negishi, Kumi [Japan Atomic Energy Agency, Shirakata, Tokai, Ibaraki 319-1195 (Japan); Taiheiyo Consultant Company Limited, 2-4-2, Osaku, Sakura, Chiba 285-8655 (Japan); Hoshino, Seiichi; Tanaka, Tadao [Japan Atomic Energy Agency, Shirakata, Tokai, Ibaraki 319-1195 (Japan)

    2009-12-15T23:59:59.000Z

    In order to predict long-term leaching behavior of cement constituents for safety assessments of radioactive waste disposal, we modeled diffusive mass transport in micropores in cement based materials. Based on available knowledge on the pore structure, we developed a transport porosity model that enables us to estimate effective porosity available for diffusion (transport porosity) in cement based materials. We microscopically examined the pore structure of hardened cement pastes to partially verify the model. Effective diffusivities of tritiated water in hardened cement pastes were also obtained experimentally, and were shown to be proportional to the estimated transport porosity.

  15. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    OVERVIEW Harmful. Irritating to eyes, respiratory system and skin. Harmful in contact with skin - Exposure Controls / PPE ENGINEERING CONTROLS Safety shower and eye bath. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved respirator. Hand: Compatible chemical

  16. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    OVERVIEW Irritant. Irritating to eyes, respiratory system and skin. HMIS RATING HEALTH: 2 FLAMMABILITY: 0 Controls / PPE ENGINEERING CONTROLS Safety shower and eye bath. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved respirator. Hand: Compatible chemical-resistant gloves

  17. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    to eyes, respiratory system and skin. HMIS RATING #12;HEALTH: 2 FLAMMABILITY: 0 REACTIVITY: 0 NFPA RATING Safety shower and eye bath. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory

  18. UNIVERSITY OF WASHINGTON Hazardous Materials Environmental Health & Safety

    E-Print Network [OSTI]

    Wilcock, William

    project having the potential to impact lead-containing building materials, including lead paint. ResultsUNIVERSITY OF WASHINGTON Hazardous Materials Environmental Health & Safety Design Guide Lead Basis, lead-containing materials have the potential to negatively impact the health of construction workers

  19. Fire safety of LPG in marine transportation

    SciTech Connect (OSTI)

    Martinsen, W.E.; Johnson, D.W.; Welker, J.R.

    1980-08-01T23:59:59.000Z

    This report contains an analytical examination of cargo spill and fire hazard potential associated with the marine handling of liquefied petroleum gas (LPG) as cargo. Principal emphasis was on cargo transfer operations for ships unloading at receiving terminals, and barges loading or unloading at a terminal. Major safety systems, including emergency shutdown systems, hazard detection systems, and fire extinguishment and control systems were included in the analysis. Spill probabilities were obtained from fault tree analyses utilizing composite LPG tank ship and barge designs. Failure rates for hardware in the analyses were generally taken from historical data on similar generic classes of hardware, there being very little historical data on the specific items involved. Potential consequences of cargo spills of various sizes are discussed and compared to actual LPG vapor cloud incidents. The usefulness of hazard mitigation systems (particularly dry chemical fire extinguishers and water spray systems) in controlling the hazards posed by LPG spills and spill fires is also discussed. The analysis estimates the probability of fatality for a terminal operator is about 10/sup -6/ to 10/sup -5/ per cargo transfer operation. The probability of fatality for the general public is substantially less.

  20. MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI SITE REMEDIATION

    E-Print Network [OSTI]

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

  1. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Irritating to eyes, respiratory system and skin. Very toxic to aquatic organisms, may cause long-term adverse and eye bath. Use nonsparking tools. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved respirator. Hand: Compatible chemical-resistant gloves. Eye: Chemical safety

  2. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    to eyes, respiratory system and skin. Target organ(s): Blood. Central nervous system. HMIS RATING HEALTH Safety shower and eye bath. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT SIGMA - MB1 www.sigma-aldrich.com Page 2 #12;Respiratory: Government approved respirator. Hand: Compatible chemical-resistant gloves. Eye

  3. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    Irritant. Irritating to eyes, respiratory system and skin. HMIS RATING HEALTH: 2 FLAMMABILITY: 0 REACTIVITY Safety shower and eye bath. Mechanical exhaust required. ALDRICH - 258741 www.sigma-aldrich.com Page 2 #12;PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved respirator. Hand: Compatible

  4. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Irritating to eyes, respiratory system and skin. For additional information on toxicity, please refer - Exposure Controls / PPE ENGINEERING CONTROLS Safety shower and eye bath. Mechanical exhaust required. ALDRICH - M80806 www.sigma-aldrich.com Page 2 #12;PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government

  5. Compendium of Material Composition Data for Radiation Transport Modeling

    SciTech Connect (OSTI)

    McConn, Ronald J.; Gesh, Christopher J.; Pagh, Richard T.; Rucker, Robert A.; Williams III, Robert

    2011-03-04T23:59:59.000Z

    Introduction Meaningful simulations of radiation transport applications require realistic definitions of material composition and densities. When seeking that information for applications in fields such as homeland security, radiation shielding and protection, and criticality safety, researchers usually encounter a variety of materials for which elemental compositions are not readily available or densities are not defined. Publication of the Compendium of Material Composition Data for Radiation Transport Modeling, Revision 0, in 2006 was the first step toward mitigating this problem. Revision 0 of this document listed 121 materials, selected mostly from the combined personal libraries of staff at the Pacific Northwest National Laboratory (PNNL), and thus had a scope that was recognized at the time to be limited. Nevertheless, its creation did provide a well-referenced source of some unique or hard-to-define material data in a format that could be used directly in radiation transport calculations being performed at PNNL. Moreover, having a single common set of material definitions also helped to standardize at least one aspect of the various modeling efforts across the laboratory by providing separate researchers the ability to compare different model results using a common basis of materials. The authors of the 2006 compendium understood that, depending on its use and feedback, the compendium would need to be revised to correct errors or inconsistencies in the data for the original 121 materials, as well as to increase (per users suggestions) the number of materials listed. This 2010 revision of the compendium has accomplished both of those objectives. The most obvious change is the increased number of materials from 121 to 372. The not-so-obvious change is the mechanism used to produce the data listed here. The data listed in the 2006 document were compiled, evaluated, entered, and error-checked by a group of individuals essentially by hand, providing no library file or mechanism for revising the data in a consistent and traceable manner. The authors of this revision have addressed that problem by first compiling all of the information (i.e., numbers and references) for all the materials into a single database, maintained at PNNL, that was then used as the basis for this document.

  6. Driving toward excellence in transportation and logistics operations and safety

    SciTech Connect (OSTI)

    Ashworth, D. [Office of Transportation, U.S. Dept. of Energy, Washington, DC (United States)

    2007-07-01T23:59:59.000Z

    DoE's EM is the largest cleanup project in the world: 114 sites, 31 states, 2,000,000 acres. EM scope includes remediation, processing and transportation of approximately: 25 tons of plutonium, 108 tons of plutonium residues, 88 million gallons of radioactive liquid waste, 2,500 tons of spent nuclear fuel, 137,000 cubic meters of transuranic waste, 1.3 million cubic meters of low-level waste. This series of slides presents: the Rocky Flats Status, the Fernald Closure Project, the Mound/Miamisburg and Battelle Columbus statuses, the DUF{sub 6} (Depleted Uranium Hexafluoride) Conversion Project Overview, Conversion and Transport Logistics; DoE's EM Measures of Success and performance (transportation incident criteria); the application of technology to Enhance Motor Carrier Performance, Safety, and Emergency Preparedness (technological capabilities for DOE to improve driver performance, shipment safety, and emergency response); the Motor Carrier Tracking and Alert system; DOE Load Securement Field Guide and Checklist developed to ensure all shipments are secured prior to shipment; The transportation Emergency Preparedness Program (TEPP) and outreach support; the EM Transportation Community Awareness and Emergency Response (TransCAER); and the Commodity Flow Survey data of Tennessee, Flagstaff, and Texas/Louisiana.

  7. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    by separating the eyelids with fingers. Call a physician. Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION DATA Dust Potential: This material, like most materials in powder form, is capable of creating a dust explosion. FLASH POINT N/A AUTOIGNITION TEMP N/A FLAMMABILITY N/A EXTINGUISHING

  8. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    by separating the eyelids with fingers. Call a physician. Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION DATA Dust Potential: This material, like most materials in powder form, is capable of creating a dust explosion. FLASH POINT 482 °F 250 °C Method: closed cup AUTOIGNITION TEMP 410

  9. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS May explode. Heating may cause an explosion. Toxic by inhalation and if swallowed. Irritating to respiratory system when heated. EXPLOSION DATA Dust Potential: This material, like most materials in powder form

  10. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    with fingers. Call a physician. Section 5 - Fire Fighting Measures EXPLOSION DATA Dust Potential: This material, like most materials in powder form, is capable of creating a dust explosion. FLASH POINT N and protective clothing to prevent contact with skin and eyes. Specific Hazard(s): Emits toxic fumes under fire

  11. Materials and Transportation Services | The Ames Laboratory

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

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

  12. Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

    SciTech Connect (OSTI)

    McConnell, J.W., Jr; Ayers, A.L. Jr; Tyacke, M.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1996-02-01T23:59:59.000Z

    This report provides a graded approach for classification of components used in transportation packaging and dry spent fuel storage systems. This approach provides a method for identifying, the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements The general types of transportation packagings and dry storage systems were identified. Discussions were held with suppliers and fabricators of packagings and storage systems to determine current practices. The methodology used in this report is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This report also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems. The safety importance of each component is discussed, and a classification category is assigned.

  13. Lightweight materials for transportation: Program plan

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    This Program Plan has been prepared by the Office of Transportation Materials in response to a request by the House Committee on Appropriations. It recognizes that a significant commitment to long-term, stable materials research and development (R&D) is required to realize the benefits of lighter weight vehicles, including economic, environmental and energy related benefits. Extensive input was obtained from the major US automakers and from representative materials and component suppliers. Considerable interaction with the key members of the US Automotive Materials Partnership (USAMP) has ensured consistency of technical direction. The program will support R&D activity at industrial sites through competitively bid subcontracts with cost sharing anticipated at 30--50%, with the higher amounts in process scale-up and manufacturing technology development. The recommended LWM Program will enable industry to develop pecessary technology by utilizing their capabilities as well as accessing supporting technology at national laboratories, universities, ongoing program activity at NASA, DoD, DOT, NIST, etc., and thereby leverage industry resources through integrated team approaches. Many individual program efforts are currently in place that address small portions of the overall needs of the LWM Program, both within DOE and in other agencies. Cognizance of these and overall integration of research activities are planned as significant program management tasks. Because of the international nature of the automobile business, benchmarking of foreign technology and tracking of worldwide developments are also key program elements.

  14. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Vakni, David

    and in contact with skin. Irritating to eyes, respiratory system and skin. Target organ(s): Liver. Kidneys. HMIS and Storage STORAGE Store at 2-8°C Section 8 - Exposure Controls / PPE ENGINEERING CONTROLS Mechanical exhaust: Material is irritating to mucous membranes and upper respiratory tract. Multiple Routes: Harmful if inhaled

  15. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Vakni, David

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

  16. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    by separating the eyelids with fingers. Call a physician. Section 5 - Fire Fighting Measures EXPLOSION HAZARDS Container explosion may occur under fire conditions. EXPLOSION DATA Dust Potential: This material, like most fire. Harmful if swallowed. Irritating to eyes, respiratory system and skin. May cause sensitization

  17. TRANSPORTATION CASK RECEIPT/RETURN FACILITY CRITICALITY SAFETY EVALUATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2005-04-26T23:59:59.000Z

    The purpose of this design calculation is to demonstrate that the handling operations of transportation casks performed in the Transportation Cask Receipt and Return Facility (TCRRF) and Buffer Area meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC [Bechtel SAIC Company] 2004 [DIRS 171599], Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''Transportation Cask Receipt/Return Facility Description Document'' (BSC 2004 [DIRS 170217], Section 3.2.3). Specific scope of work contained in this activity consists of the following items: (1) Evaluate criticality effects for both dry and fully flooded conditions pertaining to TCRRF and Buffer Area operations for defense in depth. (2) Evaluate Category 1 and 2 event sequences for the TCRRF as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). This evaluation includes credible fuel reconfiguration conditions. In addition to the scope of work listed above, an evaluation was also performed of modeling assumptions for commercial spent nuclear fuel (CSNF) regarding inclusion of plenum and end regions of the active fuel. This calculation is limited to CSNF and US Department of Energy (DOE) SNF. it should be mentioned that the latter waste form is evaluated more in depth in the ''Canister Handling Facility Criticality Safety Calculations (BSC 2004 [DIRS 167614]). Further, the design and safety analyses of the naval SNF canisters are the responsibility of the US 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 TCRRF and Buffer Area 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 TCRRF is included in the Q-List (BSC 2004 [DIRS 168361], 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].

  18. Hazardous Material Identification and Material Safety Data Sheets UT-B Contracts Div Page 1 of 1

    E-Print Network [OSTI]

    Pennycook, Steve

    Hazardous Material Identification and Material Safety Data Sheets UT-B Contracts Div July 2006 Page 1 of 1 haz-mat-id-msds-ext-july06.doc HAZARDOUS MATERIAL IDENTIFICATION AND MATERIAL SAFETY DATA SHEETS (July 2006) (a) "Hazardous material," as used in this clause, means any material defined

  19. Base Technology for Radioactive Material Transportation Packaging Systems

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

    1992-07-08T23:59:59.000Z

    To establish Department of Energy (DOE) policies and responsibilities for coordinating and planning base technology for radioactive material transportation packaging systems.

  20. Water Transport in PEM Fuel Cells: Advanced Modeling, Material...

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

    Testing and Design Optimization Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing and Design Optimization Part of a 100 million fuel cell award...

  1. Water Transport in PEM Fuel Cells: Advanced Modeling, Material...

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

    Testing, and Design Optimization Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing, and Design Optimization This presentation, which focuses on...

  2. Fusion-reactor blanket-material safety-compatibility studies

    SciTech Connect (OSTI)

    Jeppson, D.W.; Muhlestein, L.D.; Keough, R.F.; Cohen, S.

    1982-11-01T23:59:59.000Z

    Blanket material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Blanket material safety compatibility studies are being conducted to identify and characterize blanket-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate that : (1) ternary oxides (LiAlO/sub 2/, Li/sub 2/ZrO/sub 3/, Li/sub 2/SiO/sub 3/, Li/sub 4/SiO/sub 4/ and LiTiO/sub 3/) at postulated blanket operating temperatures are compatible with water coolant, while liquid lithium and Li/sub 7/Pb/sub 2/ alloy reactions with water generate heat, aerosol and hydrogen; (2) lithium oxide and Li/sub 17/Pb/sub 83/ alloy react mildly with water requiring special precautions to control hydrogen release; (3) liquid lithium reacts substantially, while Li/sub 17/Pb/sub 83/ alloy reacts mildly with concrete to produce hydrogen; and (4) liquid lithium-air reactions present some major safety concerns.

  3. Gas Generation Test Support for Transportation and Storage of Plutonium Residue Materials - Part 1: Rocky Flats Sand, Slag, and Crucible Residues

    SciTech Connect (OSTI)

    Livingston, R.R.

    1999-08-24T23:59:59.000Z

    The purpose of this report is to present experimental results that can be used to establish one segment of the safety basis for transportation and storage of plutonium residue materials.

  4. Hazardous Material Packaging for Transport - Administrative Procedures

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

    1986-09-30T23:59:59.000Z

    To establ1sh administrative procedures for the certification and use of radioactive and other hazardous materials packaging by the Department of Energy (DOE).

  5. Ontario Hydro`s transportation of radioactive material and emergency response plan

    SciTech Connect (OSTI)

    Karmali, N. [Ontario Hydro, Toronto, Ontario (Canada). Nuclear Operations Branch

    1993-12-31T23:59:59.000Z

    Ontario Hydro has been transporting radioactive material for almost 30 years without any exposure to the public or release to the environment. However, there have been three accidents involving Hydro`s shipments of radioactive material. In addition to the quality packaging and shipping program, Ontario Hydro has an Emergency Response Plan and capability to deal with an accident involving a shipment of radioactive material. The Corporation`s ability to respond, to effectively control and contain the situation, site remediation, and to provide emergency public information in the event of a road accident minimizes the risk to the public and the environment. This emphasizes their commitment to worker safety, public safety and impact to the environment. Response capability is mandated under various legislation and regulations in Canada.

  6. Hazardous materials transportation and emergency response programs

    SciTech Connect (OSTI)

    Joy, D.S.; Fore, C.S.

    1983-01-01T23:59:59.000Z

    This presentation consists of the following visual aids; (1) detailed routing capabilities of truck, rail, barge; (2) legislative data base for hazardous materials; and (3) emergency response of accident site Eddyville, Kentucky (airports in vicinity of Eddyville, KY).

  7. European Aviation Safety Agency announces acceptance of NCAMP material certification process

    E-Print Network [OSTI]

    developed through the FAA process described in Federal Aviation Administration Memorandum AIR100European Aviation Safety Agency announces acceptance of NCAMP material certification process Wichita, KS, January 30, 2014 ­ The European Aviation Safety Agency (EASA) recently released Certification

  8. Implementation Guide for Use with DOE O 460.1A, Packaging and Transportation Safety

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

    1997-06-05T23:59:59.000Z

    This Guide provides information concerning the use of current principles and practices, including regulatory guidance from the U. S. Department of Transportation and the U. S. Nuclear Regulatory Commission, where available, to establish and implement effective packaging and transportation safety programs.

  9. BIOFUELS FOR TRANSPORT IN THE 21st WHY FIRE SAFETY IS A REAL ISSUE

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    BIOFUELS FOR TRANSPORT IN THE 21st CENTURY: WHY FIRE SAFETY IS A REAL ISSUE Guy Marlair1 , Patricia's), with thé new century venue we are assisting of a booming industry regarding biofuels of biofuels for transport. This contribution is a fîrst output from a National research program named

  10. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    SciTech Connect (OSTI)

    P. Calderoni; P. Sharpe; M. Shimada

    2009-09-01T23:59:59.000Z

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  11. LEVERAGING AGING MATERIALS DATA TO SUPPORT EXTENSION OF TRANSPORTATION SHIPPING PACKAGES SERVICE LIFE

    SciTech Connect (OSTI)

    Dunn, K. [Savannah River National Laboratory; Bellamy, S. [Savannah River National Laboratory; Daugherty, W. [Savannah River National Laboratory; Sindelar, R. [Savannah River National Laboratory; Skidmore, E. [Savannah River National Laboratory

    2013-08-18T23:59:59.000Z

    Nuclear material inventories are increasingly being transferred to interim storage locations where they may reside for extended periods of time. Use of a shipping package to store nuclear materials after the transfer has become more common for a variety of reasons. Shipping packages are robust and have a qualified pedigree for performance in normal operation and accident conditions but are only certified over an approved transportation window. The continued use of shipping packages to contain nuclear material during interim storage will result in reduced overall costs and reduced exposure to workers. However, the shipping package materials of construction must maintain integrity as specified by the safety basis of the storage facility throughout the storage period, which is typically well beyond the certified transportation window. In many ways, the certification processes required for interim storage of nuclear materials in shipping packages is similar to life extension programs required for dry cask storage systems for commercial nuclear fuels. The storage of spent nuclear fuel in dry cask storage systems is federally-regulated, and over 1500 individual dry casks have been in successful service up to 20 years in the US. The uncertainty in final disposition will likely require extended storage of this fuel well beyond initial license periods and perhaps multiple re-licenses may be needed. Thus, both the shipping packages and the dry cask storage systems require materials integrity assessments and assurance of continued satisfactory materials performance over times not considered in the original evaluation processes. Test programs for the shipping packages have been established to obtain aging data on materials of construction to demonstrate continued system integrity. The collective data may be coupled with similar data for the dry cask storage systems and used to support extending the service life of shipping packages in both transportation and storage.

  12. Analysis of emitter material transport in thermionic converter

    SciTech Connect (OSTI)

    Paramonov, D.V.; El-Genk, M.S. [Institute for Space and Nuclear Power Studies, Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, New Mexico 87131 (United States)

    1996-03-01T23:59:59.000Z

    Output power and efficiency of a thermionic converter depend on temperatures, cesiated work functions, and emissivities of electrodes as well as the interelectrode gap size. Operation lifetime of a thermionic converter is directly related to the values as well as the stability of these parameters, which can be seriously altered by the transport of emitter material to the collector during operation. Loss rate of tungsten, a preferred emitter material, by sublimation at typical operating temperatures is small (about 3{times}10{sup 7} atom/cm{sup 2}sec at 2000 K). The loss rate, however, can be several orders of magnitude higher in the presence of gaseous contaminants. Accelerated transport of emitter material to collector surface changes the effective emissivity and work functions of the electrodes, resulting in performance degradation. A phenomenological model was developed to simulate emitter material transport to the collector in the presence of oxygen, water vapor, and carbon oxide contaminants. The model accounts for interaction of these contaminants with both emitter and collector. Model results were in agreement with experimental data and theoretical results of other investigators. An analysis was performed to determine steady-state chemical composition of deposited material onto the collector surface in the presence of H{sub 2}O, O{sub 2}, and H{sub 2} gaseous contaminants. {copyright} {ital 1996 American Institute of Physics.}

  13. Use of inelastic design for radioactive material transportation packages

    SciTech Connect (OSTI)

    Heinstein, M.W.; Ammerman, D.J.

    1993-12-01T23:59:59.000Z

    There is much interest within the radioactive material transportation container design community in the use of inelastic analysis. In other industries where inelastic analysis is used in design there is typically an improved knowledge of the capacity of the structure and a more efficient use of material. This report describes the results of a program in which the incentives for inelastic analysis for radioactive material transport container design were investigated to determine if there are similar benefits. Detailed are the elastic and inelastic analyses of two containers subjected to impacts onto a rigid target following a thirty-foot free fall in end-on, side-on, and center-of-gravity- over-corner orientations.

  14. Development on inelastic analysis acceptance criteria for radioactive material transportation packages

    SciTech Connect (OSTI)

    Ammerman, D.J.; Ludwigsen, J.S.

    1995-12-31T23:59:59.000Z

    The response of radioactive material transportation packages to mechanical accident loadings can be more accurately characterized by non-linear dynamic analysis than by the ``Equivalent dynamic`` static elastic analysis typically used in the design of these packages. This more accurate characterization of the response can lead to improved package safety and design efficiency. For non-linear dynamic analysis to become the preferred method of package design analysis, an acceptance criterion must be established that achieves an equivalent level of safety as the currently used criterion defined in NRC Regulatory Guide 7.6 (NRC 1978). Sandia National Laboratories has been conducting a study of possible acceptance criteria to meet this requirement. In this paper non-linear dynamic analysis acceptance criteria based on stress, strain, and strain-energy-density will be discussed. An example package design will be compared for each of the design criteria, including the approach of NRC Regulatory Guide 7.6.

  15. Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing |

    Office of Environmental Management (EM)

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

  16. Department of Transportation Pipeline and Hazardous Materials Safety Administration Activities

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office of Policy,Policy Act ImplementingAL 2010-07 Federal Employee

  17. Hazardous Materials Packaging and Transportation Safety - DOE Directives,

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cn SunnybankD.jpgHanford LEED&soilASTI-SORTI Comparison T.

  18. Department of Transportation Pipeline and Hazardous Materials Safety

    Office of Environmental Management (EM)

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

  19. The Kiewit Center for Infrastructure & Transportation Fundamentals of Traffic Safety

    E-Print Network [OSTI]

    Tullos, Desiree

    Economic Appraisal & Project Prioritization Safety Effectiveness INSTRUCTORS Prof. Karen Dixon has broad and Environmental Engineering in the Maseeh College of Engineering & Computer Science at Portland State University, continental breakfast, break refreshments, and lunch. This two-day workshop provides basic training

  20. Transporting radioactive materials: Q & A to your questions

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    Over 2 million packages of radioactive materials are shipped each year in the United States. These shipments are carried by trucks, trains, ships, and airplanes every day just like other commodities. Compliance with Federal regulations ensures that radioactive materials are transported safely. Proper packaging is the key to safe shipment. Package designs for radioactive materials must protect the public and the environment even in case of an accident. As the level of radioactivity increases, packaging design requirements become more stringent. Radioactive materials have been shipped in this country for more than 40 years. As with other commodities, vehicles carrying these materials have been involved in accidents. However, no deaths or serious injuries have resulted from exposure to the radioactive contents of these shipments. People are concerned about how radioactive shipments might affect them and the environment. This booklet briefly answers some of the commonly asked questions about the transport of radioactive materials. More detailed information is available from the sources listed at the end of this booklet.

  1. University of Connecticut Health Center Policy for Transporting, Shipping, Importing / Exporting Hazardous Materials

    E-Print Network [OSTI]

    Kim, Duck O.

    Hazardous Materials Policy The University of Connecticut Health Center requires that all materials classified as "hazardous materials" by the U.S. Department of Transportation and/or the State of Connecticut be transported in approved containers and in compliance with all transportation regulations. Hazardous materials

  2. Benchmarking of finite element codes for radioactive material transportation packages

    SciTech Connect (OSTI)

    Ammerman, D.J.

    1996-10-01T23:59:59.000Z

    The increased power of computers and computer codes makes the use of nonlinear dynamic finite element analyses attractive for use as a tool used in the design and certification of radioactive material transportation packages. For this analysis technique to be acceptable it must be demonstrated. The technique has the ability to accurately capture the response of the packages to accident environments required by the regulations. The best method of demonstrating this ability is via a series of benchmark analyses. In this paper three benchmark problems involving significant inelastic deformations will be discussed. One of the problems has been analyzed using many different finite element codes. The other two problems involve comparison of finite element calculations to the results form physical tests. The ability of the finite element method to accurately capture the response in these three problems indicates the method should be acceptable for radioactive material transportation package design and certification.

  3. Transportation CPS Safety Challenges Philip Koopman Michael Wagner

    E-Print Network [OSTI]

    Koopman, Philip

    in the context of normal human experience. In more everyday units, a 10-9 /hr failure rate is one 1 Permissible. To that end, transportation systems typically have an allowable catastrophic failure rate in the neighborhood a mishap involving the death of many people (e.g., airplane crash with hull loss; major train derailment

  4. Department of Energy Receives Highest Transportation Industry Safety Award

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China U.S.Contamination ControlDecisionsGeothermal PlantJob SafetyModernizeQuadrennial|

  5. HAZARDOUS MATERIAL SAFETY Effective Date: January 1, 1992

    E-Print Network [OSTI]

    Cui, Yan

    to Hazardous Chemicals in Laboratories, as noted in Subject H. Laboratory Safety. Items in the CHP include hazardous waste (see sample CHP for definitions), it is subject to the RCRA generator rules which are found

  6. Safety Verification of the Small Aircraft Transportation System Concept of Operations

    E-Print Network [OSTI]

    Muñoz, César A.

    performed for the Small Aircraft Transportation System (SATS) Concept of Operations (ConOps). The concept of operation complies with a set of safety requirements. It is also shown that the ConOps has some desirable of Operations for Higher Volume Operation (SATS-HVO ConOps) has been developed by a team at NASA Langley

  7. Material Safety Data Sheet Ashland Chemical Co. Date Prepared: 01/06/98

    E-Print Network [OSTI]

    Rubloff, Gary W.

    Material Safety Data Sheet Ashland Chemical Co. Date Prepared: 01/06/98 Date Printed: 06/23/99 MSDS General or Generic ID: BLEND Company Emergency Telephone Number: Ashland Chemical Co. 1-800-ASHLAND (1

  8. Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

    SciTech Connect (OSTI)

    Jardine, L.J. [Lawrence Livermore National Lab., CA (United States); Peddicord, K.L. [Texas A and M Univ., College Station, TX (United States); Witmer, F.E.; Krumpe, P.F. [USDOE, Washington, DC (United States); Lazarev, L.; Moshkov, M. [Radievyj Inst., Leningrad (Russian Federation)

    1997-04-09T23:59:59.000Z

    The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment.

  9. Fire safety of LPG in marine transportation. Final report

    SciTech Connect (OSTI)

    Martinsen, W.E.; Johnson, D.W.; Welker, J.R.

    1980-06-01T23:59:59.000Z

    This report contains an analytical examination of cargo spill and fire hazard potential associated with the marine handling of liquefied petroleum gas (LPG) as cargo. Principal emphasis was on cargo transfer operations for ships unloading at receiving terminals, and barges loading or unloading at a terminal. Major safety systems, including emergency shutdown systems, hazard detection systems, and fire extinguishment and control systems were included in the analysis. Spill probabilities were obtained from fault tree analyses utilizing composite LPG tank ship and barge designs. Failure rates for hardware in the analyses were generally taken from historical data on similar generic classes of hardware, there being very little historical data on the specific items involved. Potential consequences of cargo spills of various sizes are discussed and compared to actual LPG vapor cloud incidents. The usefulness of hazard mitigation systems (particularly dry chemical fire extinguishers and water spray systems) in controlling the hazards posed by LPG spills and spill fires is also discussed. The analysis estimates the probability of fatality for a terminal operator is about 10/sup -6/ to 10/sup -5/ per cargo transfer operation. The probability of fatality for the general public is substantially less.

  10. Productivity Techniques and Quality Aspects in the Criticality Safety Evaluation of Y-12 Type-B Fissile Material Packages

    SciTech Connect (OSTI)

    DeClue, J. F.

    2011-06-28T23:59:59.000Z

    The inventory of certified Type-B fissile material packages consists of ten performance-based packages for offsite transportation purposes, serving transportation programs at the Y-12 National Security Complex. The containment vessels range from 5 to 19 in. in diameter and from 17 to 58 in. in height. The drum assembly external to the containment vessel ranges from 18 to 34 in. in diameter and from 26 to 71 in. in height. The weight of the packaging (drum assembly and containment vessel) ranges from 239 to 1550 lb. The older DT-nn series of Cellotex-based packages are being phased-out and replaced by a new generation of Kaolite-based ('Y-12 patented insulation') packages capable of withstanding the dynamic crush test 10 CFR 71.73(c)(2). Three replacement packages are in various stages of development; two are in use. The U.S. Department of Transportation (DOT) 6M specification package, which does not conform to the U.S. Nuclear Regulatory Commission requirements for Type-B packages, is no longer authorized for service on public roads. The ES-3100 shipping package is an example of a Kaolite-based Type-B fissile material package developed as a replacement package for the DOT 6M. With expanded utility, the ES-3100 is designed and licensed for transporting highly enriched uranium and plutonium materials on public roads. The ES-3100 provides added capability for air transport of up to 7-kg quantities of uranium material. This paper presents the productivity techniques and quality aspects in the criticality safety evaluation of Y-12 packages using the ES-3100 as an example.

  11. On the Criticality Safety of Transuranic Sodium Fast Reactor Fuel Transport Casks

    SciTech Connect (OSTI)

    Samuel Bays; Ayodeji Alajo

    2010-05-01T23:59:59.000Z

    This work addresses the neutronic performance and criticality safety issues of transport casks for fuel pertaining to low conversion ratio sodium cooled fast reactors, conventionally known as Advanced Burner Reactors. The criticality of a one, three, seven and 19-assembly cask capacity is presented. Both dry “helium” and flooded “water” filled casks are considered. No credit for fuel burnup or fission products was assumed. As many as possible of the conservatisms used in licensing light water reactor universal transport casks were incorporated into this SFR cask criticality design and analysis. It was found that at 7-assemblies or more, adding moderator to the SFR cask increases criticality margin. Also, removal of MAs from the fuel increases criticality margin of dry casks and takes a slight amount of margin away for wet casks. Assuming credit for borated fuel tube liners, this design analysis suggests that as many as 19 assemblies can be loaded in a cask if limited purely by criticality safety. If no credit for boron is assumed, the cask could possibly hold seven assemblies if low conversion ratio fast reactor grade fuel and not breeder reactor grade fuel is assumed. The analysis showed that there is a need for new cask designs for fast reactors spent fuel transportation. There is a potential of modifying existing transportation cask design as the starting point for fast reactor spent fuel transportation.

  12. Materials Science and Materials Chemistry for Large Scale Electrochemical Energy Storage: From Transportation to Electrical Grid

    SciTech Connect (OSTI)

    Liu, Jun; Zhang, Jiguang; Yang, Zhenguo; Lemmon, John P.; Imhoff, Carl H.; Graff, Gordon L.; Li, Liyu; Hu, Jian Z.; Wang, Chong M.; Xiao, Jie; Xia, Guanguang; Viswanathan, Vilayanur V.; Baskaran, Suresh; Sprenkle, Vincent L.; Li, Xiaolin; Shao, Yuyan; Schwenzer, Birgit

    2013-02-15T23:59:59.000Z

    Large-scale electrical energy storage has become more important than ever for reducing fossil energy consumption in transportation and for the widespread deployment of intermittent renewable energy in electric grid. However, significant challenges exist for its applications. Here, the status and challenges are reviewed from the perspective of materials science and materials chemistry in electrochemical energy storage technologies, such as Li-ion batteries, sodium (sulfur and metal halide) batteries, Pb-acid battery, redox flow batteries, and supercapacitors. Perspectives and approaches are introduced for emerging battery designs and new chemistry combinations to reduce the cost of energy storage devices.

  13. UNIVERSITY OF WASHINGTON Hazardous Materials Environmental Health & Safety

    E-Print Network [OSTI]

    Wilcock, William

    air pollution control agency and the Department of Labor and Industries (L&I) at least ten (10) days construction and renovation projects. Asbestos is a stringently regulated hazardous material and many Construction projects which impact existing building materials must include an environmental consultant

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

    SciTech Connect (OSTI)

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

    2012-07-01T23:59:59.000Z

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

  15. Safety analysis report for packaging, onsite, long-length contaminated equipment transport system

    SciTech Connect (OSTI)

    McCormick, W.A.

    1997-05-09T23:59:59.000Z

    This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks.

  16. COGEMA operating experience in the transportation of spent fuel, nuclear materials and radioactive waste

    SciTech Connect (OSTI)

    Bernard, H. [COGEMA, Velizy-Villacoublay (France)

    1993-12-31T23:59:59.000Z

    Were a spent fuel transportation accident to occur, no matter how insignificant, the public outcry could jeopardize both reprocessing operations and power plant operations for utilities that have elected to reprocess their spent fuel. Aware of this possibility, COGEMA has become deeply involved in spent fuel transportation to ensure that it is performed according to the highest standards of transportation safety. Spent fuel transportation is a vital link between the reactor site and the reprocessing plant. This paper gives an overview of COGEMA`s experience in the transportation of spent fuel.

  17. How to Translate a Material Safety Data Sheet (MSDS)

    E-Print Network [OSTI]

    Sherrill, David

    ­ Section 6- Health Hazards ­ Section 7- Storage and Handling Procedures ­ Section 8- Emergency First Aid = 1, Propane =1.6, Hydrogen = 0.1, Gasoline = 3.0 - 4.0 Vapor Density is Important Because If # > 1, the material will sink Examples: Water = 1, Gasoline = 0.8 #12;Specific Gravity is Important

  18. Transportation legislative data base: State radioactive materials transportation statute compilation, 1989--1993

    SciTech Connect (OSTI)

    NONE

    1994-04-01T23:59:59.000Z

    The Transportation Legislative Data Base (TLDB) is a computer-based information service containing summaries of federal, state and certain local government statutes and regulations relating to the transportation of radioactive materials in the United States. The TLDB has been operated by the National Conference of State Legislatures (NCSL) under cooperative agreement with the US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management since 1992. The data base system serves the legislative and regulatory information needs of federal, state, tribal and local governments, the affected private sector and interested members of the general public. Users must be approved by DOE and NCSL. This report is a state statute compilation that updates the 1989 compilation produced by Battelle Memorial Institute, the previous manager of the data base. This compilation includes statutes not included in the prior compilation, as well as newly enacted laws. Statutes not included in the prior compilation show an enactment date prior to 1989. Statutes that deal with low-level radioactive waste transportation are included in the data base as are statutes from the states of Alaska and Hawaii. Over 155 new entries to the data base are summarized in this compilation.

  19. Inelastic analysis acceptance criteria for radioactive material transportation containers

    SciTech Connect (OSTI)

    Ammerman, D.J.; Ludwigsen, J.S.

    1993-06-01T23:59:59.000Z

    The design criteria currently used in the design of radioactive material (RAM) transportation containers are taken from the ASME Boiler and Pressure Vessel Code (ASME, 1992). These load-based criteria are ideally suited for pressure vessels where the loading is quasistatic and all stresses are in equilibrium with externally applied loads. For impact events, the use of load-based criteria is less supportable. Impact events tend to be energy controlled, and thus, energy-based acceptance criteria would appear to be more appropriate. Determination of an ideal design criteria depends on what behavior is desired. Currently there is not a design criteria for inelastic analysis for RAM nation packages that is accepted by the regulatory agencies. This lack of acceptance criteria is one of the major factors in limiting the use of inelastic analysis. In this paper inelastic analysis acceptance criteria based on stress and strain-energy density will be compared for two stainless steel test units subjected to impacts onto an unyielding target. Two different material models are considered for the inelastic analysis, a bilinear fit of the stress-strain curve and a power law hardening model that very closely follows the stress-strain curve. It is the purpose of this paper to stimulate discussion and research into the area of strain-energy density based inelastic analysis acceptance criteria.

  20. Nanofluidic Ion Transport through Reconstructed Layered Materials Kalyan Raidongia and Jiaxing Huang*

    E-Print Network [OSTI]

    Huang, Jiaxing

    Nanofluidic Ion Transport through Reconstructed Layered Materials Kalyan Raidongia and Jiaxing counterparts. Fabrication of nanofluidic devices typically relies on expensive lithography techniques up to 50 mM. Nanofluidic devices based on reconstructed layer materials have distinct advantages

  1. Assessment and evaluation of a safety factor with respect to ocean disposal of waste materials

    E-Print Network [OSTI]

    Zapatka, Thomas Francis

    1976-01-01T23:59:59.000Z

    &M University Chairman of Advisory Committee: Dr. Roy W. Harm, Jr. In the past, waste materials too toxic or hazardous for disposal on land or in estuaries have customarily been disposed of at sea. Assessment of the risk and consequent environmental harm... was to investigate and define the correlations between acute and chronic toxicities for known hazardous materials. This relationship is vital for the deter- mination of an appropriate safety factor to be used in evaluating allowable discharges or concentrations...

  2. Assessment and evaluation of a safety factor with respect to ocean disposal of waste materials 

    E-Print Network [OSTI]

    Zapatka, Thomas Francis

    1976-01-01T23:59:59.000Z

    &M University Chairman of Advisory Committee: Dr. Roy W. Harm, Jr. In the past, waste materials too toxic or hazardous for disposal on land or in estuaries have customarily been disposed of at sea. Assessment of the risk and consequent environmental harm... was to investigate and define the correlations between acute and chronic toxicities for known hazardous materials. This relationship is vital for the deter- mination of an appropriate safety factor to be used in evaluating allowable discharges or concentrations...

  3. PROPANE -C3H8 MSDS (Document # 001045) PAGE 1 OF 8 MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    PROPANE - C3H8 MSDS (Document # 001045) PAGE 1 OF 8 MATERIAL SAFETY DATA SHEET Prepared to U in an emergency? 1. PRODUCT IDENTIFICATION CHEMICAL NAME; CLASS: PROPANE - C3H8 Document Number: 001045 PRODUCT IN AIR ACGIH OSHA TLV STEL PEL STEL IDLH OTHER ppm ppm ppm ppm ppm Propane 74-98-6 > 96.0 Simple

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

    E-Print Network [OSTI]

    Rollins, Andrew M.

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

  5. FEMA: a Finite Element Model of Material Transport through Aquifers

    SciTech Connect (OSTI)

    Yeh, G.T.; Huff, D.D.

    1985-01-01T23:59:59.000Z

    This report documents the construction, verification, and demonstration of a Finite Element Model of Material Transport through Aquifers (FEMA). The particular features of FEMA are its versatility and flexibility to deal with as many real-world problems as possible. Mechanisms included in FEMA are: carrier fluid advection, hydrodynamic dispersion and molecular diffusion, radioactive decay, sorption, source/sinks, and degradation due to biological, chemical as well as physical processes. Three optional sorption models are embodied in FEMA. These are linear isotherm and Freundlich and Langmuir nonlinear isotherms. Point as well as distributed source/sinks are included to represent artificial injection/withdrawals and natural infiltration of precipitation. All source/sinks can be transient or steady state. Prescribed concentration on the Dirichlet boundary, given gradient on the Neumann boundary segment, and flux at each Cauchy boundary segment can vary independently of each other. The aquifer may consist of as many formations as desired. Either completely confined or completely unconfined or partially confined and partially unconfined aquifers can be dealt with effectively. FEMA also includes transient leakage to or from the aquifer of interest through confining beds from or to aquifers lying below and/or above.

  6. Packaging and Transfer or Transportation of Materials of National Security Interest

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

    2000-09-29T23:59:59.000Z

    To establish requirements and responsibilities for the Transportation Safeguards System (TSS) packaging and transportation and onsite transfer of nuclear explosives, nuclear components, Naval nuclear fuel elements, Category I and Category II special nuclear materials, special assemblies, and other materials of national security interest. Cancels: DOE 5610.12 and DOE 5610.14.

  7. Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

    SciTech Connect (OSTI)

    Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

    2008-03-01T23:59:59.000Z

    This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

  8. NGATS ATM-Airportal Project Reference Material (External Release) Next Generation Air Transportation System

    E-Print Network [OSTI]

    NGATS ATM-Airportal Project Reference Material (External Release) Next Generation Air Transportation System (NGATS) Air Traffic Management (ATM) - Airportal Project Reference Material May 23, 2007 Manager NASA Mike Madson Project Scientist NASA #12;NGATS ATM-Airportal Project Reference Material

  9. Modeling transport of disposed dredged material from placement sites in Grays Harbor, WA

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Modeling transport of disposed dredged material from placement sites in Grays Harbor, WA E- to mid- term dredge material management strategies for the Federal Navigation Project at Grays Harbor dredging quantities. However, the most heavily used dredged material placement sites lie in proximity

  10. Exciton transport and coherence in molecular and nanostructured materials

    E-Print Network [OSTI]

    Akselrod, Gleb M. (Gleb Markovitch)

    2013-01-01T23:59:59.000Z

    Over the past 20 years a new classes of optically active materials have been developed that are composites of nano-engineered constituents such as molecules, polymers, and nanocrystals. These disordered materials have ...

  11. Thermal Transport in Nanoporous Materials for Energy Applications

    E-Print Network [OSTI]

    Fang, Jin

    2012-01-01T23:59:59.000Z

    based materials as supercapacitor electrodes”, Chemicalas electrochemical supercapacitor electrodes”, Chemicaland heat management of supercapacitor modules for vehicle

  12. Improvement of operational safety of dual-purpose transport packaging set for naval SNF in storage

    SciTech Connect (OSTI)

    Guskov, Vladimir; Korotkov, Gennady [JSC 'KBSM' (Russian Federation); Barnes, Ella [US Environmental Protection Agency - EPA (United States); Snipes, Randy [Oak Ridge National Laboratory - ORNL, 1 Bethel Valley Rd, Oak Ridge, TN 37830 (United States)

    2007-07-01T23:59:59.000Z

    Available in abstract form only. Full text of publication follows: In recent ten years a new technology of management of irradiated nuclear fuel (SNF) at the final stage of fuel cycle has been intensely developing on a basis of a new type of casks used for interim storage of SNF and subsequent transportation therein to the place of processing, further storage or final disposal. This technology stems from the concept of a protective cask which provides preservation of its content (SNF) and fulfillment of all other safety requirements for storage and transportation of SNF. Radiation protection against emissions and non-distribution of activity outside the cask is ensured by physical barriers, i.e. all-metal or composite body, shells, inner cavities for irradiated fuel assemblies (SFA), lids with sealing systems. Residual heat release of SFA is discharged to the environment by natural way: through emission and convection of surrounding air. By now more than 100 dual purpose packaging sets TUK-108/1 are in operation in the mode of interim storage and transportation of SNF from decommissioned nuclear powered submarines (NPS). In accordance with certificate, spent fuel is stored in TUK-108/1 on the premises of plants involved in NPS dismantlement for 2 years, whereupon it is transported for processing to PO Mayak. At one Far Eastern plant Zvezda involved in NPS dismantlement there arose a complicated situation due to necessity to extend period of storage of SNF in TUK- 108/1. To ensure safety over a longer period of storage of SNF in TUK-108/1 it is essential to modify conditions of storage by removing of residual water and filling the inner cavity of the cask with an inert gas. Within implementation of the international 1.1- 2 project Development of drying technology for the cask TUK-108/1 intended for naval SNF under the Program, there has been developed the technology of preparation of the cask for long-term storage of SNF in TUK-108/1, the design of a mobile TUK-108/1 drying facility; a pilot facility has been manufactured. This report describes key issues of cask drying technology, justification of terms of dry storage of naval SNF in no-108/1, design features of the mobile drying facility, results of tests of the pilot facility at the Far Eastern plant Zvezda. (authors)

  13. Fundamentals of Melt-Water Interfacial Transport Phenomena: Improved Understanding for Innovative Safety Technologies in ALWRs

    SciTech Connect (OSTI)

    M. Anderson; M. Corradini; K.Y. Bank; R. Bonazza; D. Cho

    2005-04-26T23:59:59.000Z

    The interaction and mixing of high-temperature melt and water is the important technical issue in the safety assessment of water-cooled reactors to achieve ultimate core coolability. For specific advanced light water reactor (ALWR) designs, deliberate mixing of the core-melt and water is being considered as a mitigative measure, to assure ex-vessel core coolability. The goal of this work is to provide the fundamental understanding needed for melt-water interfacial transport phenomena, thus enabling the development of innovative safety technologies for advanced LWRs that will assure ex-vessel core coolability. The work considers the ex-vessel coolability phenomena in two stages. The first stage is the melt quenching process and is being addressed by Argonne National Lab and University of Wisconsin in modified test facilities. Given a quenched melt in the form of solidified debris, the second stage is to characterize the long-term debris cooling process and is being addressed by Korean Maritime University in via test and analyses. We then address the appropriate scaling and design methodologies for reactor applications.

  14. Molecular Level Assessment of Thermal Transport and Thermoelectricity in Materials: From Bulk Alloys to Nanostructures 

    E-Print Network [OSTI]

    Kinaci, Alper

    2013-05-02T23:59:59.000Z

    applications. Carbon- and boron nitride-based nanomaterials also offer new opportunities in many applications from thermoelectrics to fast heat removers. For these materials, molecular dynamics calculations are used to evaluate lattice thermal transport. To do...

  15. Implementation Guide for Use with DOE O 460.2 Departmental Materials Transportation and Packaging Management

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

    1996-11-15T23:59:59.000Z

    The purpose of this guide is to assist those responsible for transporting and packaging Department materials, and to provide an understanding of Department policies on activities which supplement regulatory requirements.

  16. Regulations Establishing Restricted Zones for the Transportation of Hazardous Materials (Connecticut)

    Broader source: Energy.gov [DOE]

    These regulations establish a Shore Clearance Line which cannot be crossed except in an emergency by any vessel transporting oil or hazardous materials in bulk in Long Island Sound. For the purpose...

  17. Notice of Intent to Revise Department of Energy Order 460.1C, Packaging and Transportation Safety

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

    2015-01-15T23:59:59.000Z

    The purpose of this memorandum is to provide justification for the proposed revision of Department of Energy (DOE} Order (O} 460.lC, Packaging and Transportation Safety as part of the quadrennial review and recertification required by DOE O 251.lC, Departmental Directives Program.

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

    SciTech Connect (OSTI)

    John Didlake

    1999-11-15T23:59:59.000Z

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

  19. Disposed Material Mobility and Transport in the Vicinity of the

    E-Print Network [OSTI]

    Voulgaris, George

    after the day of deployment. A 1-D sediment resuspension and transport model was verified using to be in suspension for the majority of the time and in particular following a resuspension event. The low settling velocities allow them to be in resuspension for long times (over 24 hours). Finally, we recommend monitoring

  20. Cathode and electrolyte materials for solid oxide fuel cells and ion transport membranes

    DOE Patents [OSTI]

    Jacobson, Allan J; Wang, Shuangyan; Kim, Gun Tae

    2014-01-28T23:59:59.000Z

    Novel cathode, electrolyte and oxygen separation materials are disclosed that operate at intermediate temperatures for use in solid oxide fuel cells and ion transport membranes based on oxides with perovskite related structures and an ordered arrangement of A site cations. The materials have significantly faster oxygen kinetics than in corresponding disordered perovskites.

  1. Multiscale modeling of fluid transport in heterogeneous materials using discrete Boltzmann methods

    E-Print Network [OSTI]

    Bentz, Dale P.

    transport in porous materials like ceramics, concrete, soils, and rocks plays an impor- tant role in many geometries like porous materials. Here, we review some of our previous work and discuss some recent environmental and technological processes [11.For example, the service life and durability of concrete can

  2. Assuring safety through operational approval : challenges in assessing and approving the safety of systems-level changes in air transportation

    E-Print Network [OSTI]

    Weibel, Roland E. (Roland Everett)

    2010-01-01T23:59:59.000Z

    To improve capacity and efficiency of the air transportation system, a number of new systems-level changes have been proposed. Key aspects of the proposed changes are combined functionality across technology and procedures ...

  3. Definition of Small Gram Quantity Contents for Type B Radioactive Material Transportation Packages: Activity-Based Content Limitations

    SciTech Connect (OSTI)

    Sitaraman, S; Kim, S; Biswas, D; Hafner, R; Anderson, B

    2010-10-27T23:59:59.000Z

    Since the 1960's, the Department of Transportation Specification (DOT Spec) 6M packages have been used extensively for transportation of Type B quantities of radioactive materials between Department of Energy (DOE) facilities, laboratories, and productions sites. However, due to the advancement of packaging technology, the aging of the 6M packages, and variability in the quality of the packages, the DOT implemented a phased elimination of the 6M specification packages (and other DOT Spec packages) in favor of packages certified to meet federal performance requirements. DOT issued the final rule in the Federal Register on October 1, 2004 requiring that use of the DOT Specification 6M be discontinued as of October 1, 2008. A main driver for the change was the fact that the 6M specification packagings were not supported by a Safety Analysis Report for Packaging (SARP) that was compliant with Title 10 of the Code of Federal Regulations part 71 (10 CFR 71). Therefore, materials that would have historically been shipped in 6M packages are being identified as contents in Type B (and sometimes Type A fissile) package applications and addenda that are to be certified under the requirements of 10 CFR 71. The requirements in 10 CFR 71 include that the Safety Analysis Report for Packaging (SARP) must identify the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents (10 CFR 71.33(b)(1) and 10 CFR 71.33(b)(2)), and that the application (i.e., SARP submittal or SARP addendum) demonstrates that the external dose rate (due to the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents) on the surface of the packaging (i.e., package and contents) not exceed 200 mrem/hr (10 CFR 71.35(a), 10 CFR 71.47(a)). It has been proposed that a 'Small Gram Quantity' of radioactive material be defined, such that, when loaded in a transportation package, the dose rates at external points of an unshielded packaging not exceed the regulatory limits prescribed by 10 CFR 71 for non-exclusive shipments. The mass of each radioisotope presented in this paper is limited by the radiation dose rate on the external surface of the package, which per the regulatory limit should not exceed 200 mrem/hr. The results presented are a compendium of allowable masses of a variety of different isotopes (with varying impurity levels of beryllium in some of the actinide isotopes) that, when loaded in an unshielded packaging, do not result in an external dose rate on the surface of the package that exceeds 190 mrem/hr (190 mrem/hr was chosen to provide 5% conservatism relative to the regulatory limit). These mass limits define the term 'Small Gram Quantity' (SGQ) contents in the context of radioactive material transportation packages. The term SGQ is isotope-specific and pertains to contents in radioactive material transportation packages that do not require shielding and still satisfy the external dose rate requirements. Since these calculated mass limits are for contents without shielding, they are conservative for packaging materials that provide some limited shielding or if the contents are placed into a shielded package. The isotopes presented in this paper were chosen as the isotopes that Department of Energy (DOE) sites most likely need to ship. Other more rarely shipped isotopes, along with industrial and medical isotopes, are planned to be included in subsequent extensions of this work.

  4. The risks and consequences from the transport of low specific activity materials by truck

    SciTech Connect (OSTI)

    Finley, N.C.; McClure, J.D.; Cashwell, J.W.; Ostmeyer, R.O.; Wangler, M.

    1989-01-01T23:59:59.000Z

    The packaging and transport category of low specific activity (LSA) material was conceived for radioactive materials (RAM) that were considered inherently safe for transport. Such materials could be transported in ''strong, tight'' packages. The primary concern for the radionuclide content in LSA materials was associated with the potential for inhalation of particulate radioactive material. Thus, the specifications for the category in terms of specific activity were structured to preclude excessive inhalation hazard. The current version of the International Atomic Energy Agency (IAEA) regulations maintains the inhalation-related limits but also shows concern that the restrictions on the LSA category may not preclude an excessive external radiation hazard for gamma-emitting materials. This paper presents the results of an investigation of the potential for such excessive external radiation hazards, particularly for LSA materials with specific activity levels near the current regulatory limit. Analyses are discussed that were performed to evaluate the potential radiological impacts of highway accidents leading to the release of high radiation level-low specific activity (HRL-LSA) materials from their packagings. The results of the analyses are intended to provide a basis for evaluating restrictions on the quantity of gamma-emitting radionuclides that can be contained in an LSA shipment. 8 refs., 2 tabs.

  5. Development of a container for the transportation and storage of plutonium bearing materials

    SciTech Connect (OSTI)

    Ammerman, D. [Sandia National Labs., Albuquerque, NM (United States); Geinitz, R.; Thorp, D. [Safe Sites of Colorado, Golden, CO (United States); Rivera, M. [Los Alamos Technology Associates, Golden, CO (United States)

    1998-03-01T23:59:59.000Z

    There is a large backlog of plutonium contaminated materials at the Rocky Flats Environmental Technology Site near Denver, Colorado, USA. The clean-up of this site requires this material to be packaged in such a way as to allow for efficient transportation to other sites or to a permanent geologic repository. Prior to off-site shipment of the material, it may be stored on-site for a period of time. For this reason, it is desirable to have a container capable of meeting the requirements for storage as well as the requirements for transportation. Most of the off-site transportation is envisioned to take place using the TRUPACT-II Type B package, with the Waste Isolation Pilot Plant (WIPP) as the destination. Prior to the development of this new container, the TRUPACT-II had a limit of 325 FGE (fissile gram equivalents) of plutonium due to criticality control concerns. Because of the relatively high plutonium content in the material to be transported, transporting 325 FGE per TRUPACT-II is uneconomical. Thus, the purpose of the new containers is to provide criticality control to increase the allowed TRUPACT-II payload and to provide a safe method for on-site storage prior to transport. This paper will describe the analysis and testing used to demonstrate that the Pipe Overpack Container provides safe on-site storage of plutonium bearing materials in unhardened buildings and provides criticality control during transportation within the TRUPACT-II. Analyses included worst-case criticality analyses, analyses of fork-lift time impacts, and analyses of roof structure collapse onto the container. Testing included dynamic crush tests, bare pipe impact tests, a 30-minute totally engulfing pool-fire test, and multiple package impact tests in end-on and side-on orientations.

  6. Center for Nanophase Materials Sciences (CNMS) - TRES: Transport,

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041clothAdvanced Materials Advanced. C o w l i t z C oCNMS RESEARCHInstitute

  7. The environmental assessment of nuclear materials disposition options: A transportation perspective

    SciTech Connect (OSTI)

    Wilson, R.K.; Clauss, D.B.; Moyer, J.W.

    1994-12-31T23:59:59.000Z

    The US Department of Energy has undertaken a program to evaluate and select options for the long-term storage and disposition of fissile materials declared surplus to defense needs as a result of the end of the Cold War. The transport of surplus fissile material will be an important and highly visible aspect of the environmental impact studies and other planning documents required for implementation of the disposition options. This report defines the roles and requirements for transportation of fissile materials in the program, and discusses an existing methodology for determining the environmental impact in terms of risk. While it will be some time before specific alternatives are chosen that will permit the completion of detailed risk calculations, the analytical models for performing the probabilistic risk assessments already exist with much of the supporting data related to the transportation system. This report summarizes the various types of data required and identifies sources for that data.

  8. Health and Safety Handbook UPDATED: June 27, 2012

    E-Print Network [OSTI]

    Roy, Subrata

    .......................................................................................................5 Material Safety Data Sheets/ Chemical Inventories

  9. An OSHA based approach to safety analysis for nonradiological hazardous materials

    SciTech Connect (OSTI)

    Yurconic, M.

    1992-08-01T23:59:59.000Z

    The PNL method for chemical hazard classification defines major hazards by means of a list of hazardous substances (or chemical groups) with associated trigger quantities. In addition, the functional characteristics of the facility being classified is also be factored into the classification. In this way, installations defined as major hazard will only be those which have the potential for causing very serious incidents both on and off site. Because of the diversity of operations involving chemicals, it may not be possible to restrict major hazard facilities to certain types of operations. However, this hazard classification method recognizes that in the industrial sector major hazards are most commonly associated with activities involving very large quantities of chemicals and inherently energetic processes. These include operations like petrochemical plants, chemical production, LPG storage, explosives manufacturing, and facilities which use chlorine, ammonia, or other highly toxic gases in bulk quantities. The basis for this methodology is derived from concepts used by OSHA in its proposed chemical process safety standard, the Dow Fire and Explosion Index Hazard Classification Guide, and the International Labor Office`s program on chemical safety. For the purpose of identifying major hazard facilities, this method uses two sorting criteria, (1) facility function and processes and (2) quantity of substances to identify facilities requiringclassification. Then, a measure of chemical energy potential (material factor) is used to identify high hazard class facilities.

  10. An OSHA based approach to safety analysis for nonradiological hazardous materials

    SciTech Connect (OSTI)

    Yurconic, M.

    1992-08-01T23:59:59.000Z

    The PNL method for chemical hazard classification defines major hazards by means of a list of hazardous substances (or chemical groups) with associated trigger quantities. In addition, the functional characteristics of the facility being classified is also be factored into the classification. In this way, installations defined as major hazard will only be those which have the potential for causing very serious incidents both on and off site. Because of the diversity of operations involving chemicals, it may not be possible to restrict major hazard facilities to certain types of operations. However, this hazard classification method recognizes that in the industrial sector major hazards are most commonly associated with activities involving very large quantities of chemicals and inherently energetic processes. These include operations like petrochemical plants, chemical production, LPG storage, explosives manufacturing, and facilities which use chlorine, ammonia, or other highly toxic gases in bulk quantities. The basis for this methodology is derived from concepts used by OSHA in its proposed chemical process safety standard, the Dow Fire and Explosion Index Hazard Classification Guide, and the International Labor Office's program on chemical safety. For the purpose of identifying major hazard facilities, this method uses two sorting criteria, (1) facility function and processes and (2) quantity of substances to identify facilities requiringclassification. Then, a measure of chemical energy potential (material factor) is used to identify high hazard class facilities.

  11. Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing,

    E-Print Network [OSTI]

    Optimization J. Vernon Cole and Ashok Gidwani CFDRC Prepared for: DOE Hydrogen Fuel Cell Kickoff MeetingWater Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing, and Design fuel cell design and operation; Demonstrate improvements in water management resulting in improved

  12. Radioisotope thermoelectric generator transportation system safety analysis report for packaging. Volumes 1 and 2

    SciTech Connect (OSTI)

    Ferrell, P.C.

    1996-04-18T23:59:59.000Z

    This SARP describes the RTG Transportation System Package, a Type B(U) packaging system that is used to transport an RTG or similar payload. The payload, which is included in this SARP, is a generic, enveloping payload that specifically encompasses the General Purpose Heat Source (GPHS) RTG payload. The package consists of two independent containment systems mounted on a shock isolation transport skid and transported within an exclusive-use trailer.

  13. PERMEABILITY, SOLUBILITY, AND INTERACTION OF HYDROGEN IN POLYMERS- AN ASSESSMENT OF MATERIALS FOR HYDROGEN TRANSPORT

    SciTech Connect (OSTI)

    Kane, M

    2008-02-05T23:59:59.000Z

    Fiber-reinforced polymer (FRP) piping has been identified as a leading candidate for use in a transport system for the Hydrogen Economy. Understanding the permeation and leakage of hydrogen through the candidate materials is vital to effective materials system selection or design and development of safe and efficient materials for this application. A survey of the literature showed that little data on hydrogen permeation are available and no mechanistically-based models to quantitatively predict permeation behavior have been developed. However, several qualitative trends in gaseous permeation have been identified and simple calculations have been performed to identify leakage rates for polymers of varying crystallinity. Additionally, no plausible mechanism was found for the degradation of polymeric materials in the presence of pure hydrogen. The absence of anticipated degradation is due to lack of interactions between hydrogen and FRP and very low solubility coefficients of hydrogen in polymeric materials. Recommendations are made to address research and testing needs to support successful materials development and use of FRP materials for hydrogen transport and distribution.

  14. The Use of the Hanford Onsite Packaging and Transportation Safety Program to Meet Cleanup Milestones Under the Hanford Site Cleanup 2015 Vision and the American Recovery and Reinvestment Act of 2009 - 12403

    SciTech Connect (OSTI)

    Lavender, John C. [CH2M HILL Plateau Remediation Company, Richland, WA 99354 (United States); Edwards, W. Scott [Areva Federal Services, Richland, WA 99354 (United States); Macbeth, Paul J.; Self, Richard J. [U.S. Department of Energy Richland Operations Office, Richland, WA 99352 (United States); West, Lori D. [Materials and Energy Corporation, Richland, WA 99354 (United States)

    2012-07-01T23:59:59.000Z

    The Hanford Site presents unique challenges in meeting the U.S. Department of Energy Richland Operations Office (DOE-RL) 2015 Cleanup Vision. CH2M Hill Plateau Remediation Company (CHPRC), its subcontractors, and DOE-RL were challenged to retrieve, transport and remediate a wide range of waste materials. Through a collaborative effort by all Hanford Onsite Central Plateau Cleanup Team Members, disposition pathways for diverse and seemingly impossible to ship wastes were developed under a DOE Order 460.1C-compliant Hanford Onsite Transportation Safety Program. The team determined an effective method for transporting oversized compliant waste payloads to processing and disposition facilities. The use of the onsite TSD packaging authorizations proved to be vital to safely transporting these materials for processing and eventual final disposition. The American Recovery and Reinvestment Act of 2009 (ARRA) provided additional resources to expedite planning and execution of these important cleanup milestones. Through the innovative and creative use of the TSD, the Hanford Onsite Central Plateau Cleanup Team Members have developed and are executing an integrated project plan that enables the safe and compliant transport of a wide variety of difficult-to-transport waste items, accelerating previous cleanup schedules to meet cleanup milestones. (authors)

  15. Light-water-reactor safety materials engineering research programs. Quarterly progress report, January-March 1985. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1986-03-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems. 42 refs.

  16. Light-water-reactor safety materials engineering research programs. Volume 3. Quarterly progress report, October-December 1984

    SciTech Connect (OSTI)

    Not Available

    1985-10-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems.

  17. A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation

    SciTech Connect (OSTI)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

    2012-08-01T23:59:59.000Z

    This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

  18. Novel Energy Sources -Material Architecture and Charge Transport in Solid State Ionic Materials for Rechargeable Li ion Batteries

    SciTech Connect (OSTI)

    Katiyar, Ram S; Gómez, M; Majumder, S B; Morell, G; Tomar, M S; Smotkin, E; Bhattacharya, P; Ishikawa, Y

    2009-01-19T23:59:59.000Z

    Since its introduction in the consumer market at the beginning of 1990s by Sony Corporation ‘Li-ion rechargeable battery’ and ‘LiCoO2 cathode’ is an inseparable couple for highly reliable practical applications. However, a separation is inevitable as Li-ion rechargeable battery industry demand more and more from this well serving cathode. Spinel-type lithium manganate (e.g., LiMn2O4), lithium-based layered oxide materials (e.g., LiNiO2) and lithium-based olivine-type compounds (e.g., LiFePO4) are nowadays being extensively studied for application as alternate cathode materials in Li-ion rechargeable batteries. Primary goal of this project was the advancement of Li-ion rechargeable battery to meet the future demands of the energy sector. Major part of the research emphasized on the investigation of electrodes and solid electrolyte materials for improving the charge transport properties in Li-ion rechargeable batteries. Theoretical computational methods were used to select electrodes and electrolyte material with enhanced structural and physical properties. The effect of nano-particles on enhancing the battery performance was also examined. Satisfactory progress has been made in the bulk form and our efforts on realizing micro-battery based on thin films is close to give dividend and work is progressing well in this direction.

  19. Transportation impact analysis for shipment of irradiated N-reactor fuel and associated materials

    SciTech Connect (OSTI)

    Daling, P.M.; Harris, M.S.

    1994-12-01T23:59:59.000Z

    An analysis of the radiological and nonradiological impacts of highway transportation of N-Reactor irradiated fuel (N-fuel) and associated materials is described in this report. N-fuel is proposed to be transported from its present locations in the 105-KE and 105-KW Basins, and possibly the PUREX Facility, to the 327 Building for characterization and testing. Each of these facilities is located on the Hanford Site, which is near Richland, Washington. The projected annual shipping quantity is 500 kgU/yr for 5 years for a total of 2500 kgU. It was assumed the irradiated fuel would be returned to the K- Basins following characterization, so the total amount of fuel shipped was assumed to be 5000 kgU. The shipping campaign may also include the transport and characterization of liquids, gases, and sludges from the storage basins, including fuel assembly and/or canister parts that may also be present in the basins. The impacts of transporting these other materials are bounded by the impacts of transporting 5000 kgU of N-fuel. This report was prepared to support an environmental assessment of the N-fuel characterization program. The RADTRAN 4 and GENII computer codes were used to evaluate the radiological impacts of the proposed shipping campaign. RADTRAN 4 was used to calculate the routine exposures and accident risks to workers and the general public from the N-fuel shipments. The GENII computer code was used to calculate the consequences of the maximum credible accident. The results indicate that the transportation of N-fuel in support of the characterization program should not cause excess radiological-induced latent cancer fatalities or traffic-related nonradiological accident fatalities. The consequences of the maximum credible accident are projected to be small and result in no excess latent cancer fatalities.

  20. Ferromagnetism and Nonmetallic Transport of Thin-Film ? - FeSi 2 : A Stabilized Metastable Material

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Cao, Guixin; Singh, D.?J.; Zhang, X.-G.; Samolyuk, German; Qiao, Liang; Parish, Chad; Jin, Ke; Zhang, Yanwen; Guo, Hangwen; Tang, Siwei; Wang, Wenbin; Yi, Jieyu; Cantoni, Claudia; Siemons, Wolter; Payzant, E. Andrew; Biegalski, Michael; Ward, T.?Z.; Mandrus, David; Stocks, G.?M.; Gai, Zheng

    2015-04-01T23:59:59.000Z

    A metastable phase ?-FeSi? was epitaxially stabilized on a silicon substrate using pulsed laser deposition. Nonmetallic and ferromagnetic behaviors are tailored on ?-FeSi? (111) thin films, while the bulk material of ?-FeSi? is metallic and nonmagnetic. The transport property of the films renders two different conducting states with a strong crossover at 50 K, which is accompanied by the onset of a ferromagnetic transition as well as a substantial magnetoresistance. These experimental results are discussed in terms of the unusual electronic structure of ?-FeSi? obtained within density functional calculations and Boltzmann transport calculations with and without strain. Our finding sheds light on achieving ferromagnetic semiconductors through both their structure and doping tailoring, and provides an example of a tailored material with rich functionalities for both basic research and practical applications.

  1. Recycled tire rubber and other waste materials in asphalt mixtures. Transportation research record

    SciTech Connect (OSTI)

    NONE

    1995-12-31T23:59:59.000Z

    The papers in this volume, dealing with various facets of recycled tire rubber and other waste materials in asphalt mixtures, should be of interest to state and local construction, design, materials, and research engineers as well as contractors and material producers. In the first papers, Rebala and Estakhri, Malpass and Khosla, and Baker and Connolly describe research related to crumb rubber modified mixtures that was done for the Texas, North Carolina, and New Jersey State Departments of Transportation. Ali et al. report on their research in Canada to determine the feasibility of sing reclaimed roofing materials in hot mix asphalt pavement. Emery discusses the evaluation of 11 Ontario rubber modified demonstration projects in terms of pavement performance, environmental impacts, and recyclability. In the last paper, Fwa and Aziz report on their work in Singapore related to the use of incinerator residue in asphalt mixtures.

  2. Workshop on Functional Requirements for the Modeling of Fate and Transport of Waterborne CBRN Materials

    SciTech Connect (OSTI)

    Giles, GE

    2005-02-03T23:59:59.000Z

    The purpose of this Workshop on ''Functional Requirements for the Modeling of Fate and Transport of Waterborne CBRN Materials'' was to solicit functional requirements for tools that help Incident Managers plan for and deal with the consequences of industrial or terrorist releases of materials into the nation's waterways and public water utilities. Twenty representatives attended and several made presentations. Several hours of discussions elicited a set of requirements. These requirements were summarized in a form for the attendees to vote on their highest priority requirements. These votes were used to determine the prioritized requirements that are reported in this paper and can be used to direct future developments.

  3. Packaging and Transportation for Offsite Shipment of Materials of National Security Interest

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

    2010-12-20T23:59:59.000Z

    The purpose of this Order is to make clear that the packaging and transportation of all offsite shipments of materials of national security interest for DOE must be conducted in accordance with DOT and Nuclear Regulatory Commission (NRC) regulations that would be applicable to comparable commercial shipments, except where an alternative course of action is identified in this Order. Cancels DOE O 461.1A.

  4. Hole-transport material variation in fully vacuum deposited perovskite solar cells

    SciTech Connect (OSTI)

    Polander, Lauren E.; Pahner, Paul; Schwarze, Martin; Saalfrank, Matthias; Koerner, Christian; Leo, Karl, E-mail: karl.leo@iapp.de [Institut für Angewandte Photophysik, Technische Universität Dresden, 01069 Dresden (Germany)

    2014-08-01T23:59:59.000Z

    This work addresses the effect of energy level alignment between the hole-transporting material and the active layer in vacuum deposited, planar-heterojunction CH{sub 3}NH{sub 3}PbI{sub x?3}Cl{sub x} perovskite solar cells. Through a series of hole-transport materials, with conductivity values set using controlled p-doping of the layer, we correlate their ionization potentials with the open-circuit voltage of the device. With ionization potentials beyond 5.3 eV, a substantial decrease in both current density and voltage is observed, which highlights the delicate energetic balance between driving force for hole-extraction and maximizing the photovoltage. In contrast, when an optimal ionization potential match is found, the open-circuit voltage can be maximized, leading to power conversion efficiencies of up to 10.9%. These values are obtained with hole-transport materials that differ from the commonly used Spiro-MeO-TAD and correspond to a 40% performance increase versus this reference.

  5. Environmental, health, and safety issues of fuel cells in transportation. Volume 1: Phosphoric acid fuel-cell buses

    SciTech Connect (OSTI)

    Ring, S.

    1994-12-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) chartered the Phosphoric Acid Fuel-Cell (PAFC) Bus Program to demonstrate the feasibility of fuel cells in heavy-duty transportation systems. As part of this program, PAFC- powered buses are being built to meet transit industry design and performance standards. Test-bed bus-1 (TBB-1) was designed in 1993 and integrated in March 1994. TBB-2 and TBB-3 are under construction and should be integrated in early 1995. In 1987 Phase I of the program began with the development and testing of two conceptual system designs- liquid- and air-cooled systems. The liquid-cooled PAFC system was chosen to continue, through a competitive award, into Phase H, beginning in 1991. Three hybrid buses, which combine fuel-cell and battery technologies, were designed during Phase III. After completing Phase II, DOE plans a comprehensive performance testing program (Phase HI) to verify that the buses meet stringent transit industry requirements. The Phase III study will evaluate the PAFC bus and compare it to a conventional diesel bus. This NREL study assesses the environmental, health, and safety (EH&S) issues that may affect the commercialization of the PAFC bus. Because safety is a critical factor for consumer acceptance of new transportation-based technologies the study focuses on these issues. The study examines health and safety together because they are integrally related. In addition, this report briefly discusses two environmental issues that are of concern to the Environmental Protection Agency (EPA). The first issue involves a surge battery used by the PAFC bus that contains hazardous constituents. The second issue concerns the regulated air emissions produced during operation of the PAFC bus.

  6. Environmental Health and Safety Department

    E-Print Network [OSTI]

    . Fire Safety, Radiation Safety and Hazardous Materials Facility are at other locations on campus Training Requirements If you work with: · Biological Materials · Chemical Agents · Radiological Materials

  7. Safety Analysis: Evaluation of Accident Risks in the Transporation of Hazardous Materials by Truck and Rail at the Savannah River Plant

    SciTech Connect (OSTI)

    Blanchard, A.

    1999-04-15T23:59:59.000Z

    This report presents an analysis of the consequences and risks of accidents resulting from hazardous material transportation at the Savannah River Plant.

  8. The role of radiation transport in the thermal response of semitransparent materials to localized laser heating

    SciTech Connect (OSTI)

    Colvin, Jeffrey; Shestakov, Aleksei; Stoelken, James; Vignes, Ryan [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551 (United States)

    2011-03-01T23:59:59.000Z

    Lasers are widely used to modify the internal structure of semitransparent materials for a wide variety of applications, including waveguide fabrication and laser glass damage healing. The gray diffusion approximation used in past models to describe radiation cooling is not adequate for these materials, particularly near the heated surface layer. In this paper we describe a computational model based upon solving the radiation transport equation in 1D by the P{sub n} method with {approx}500 photon energy bands, and by multi-group radiation diffusion in 2D with fourteen photon energy bands. The model accounts for the temperature-dependent absorption of infrared laser light and subsequent redistribution of the deposited heat by both radiation and conductive transport. We present representative results for fused silica irradiated with 2-12 W of 4.6 or 10.6 {mu}m laser light for 5-10 s pulse durations in a 1 mm spot, which is small compared to the diameter and thickness of the silica slab. We show that, unlike the case for bulk heating, in localized infrared laser heating radiation transport plays only a very small role in the thermal response of silica.

  9. Property Valuation and Radioactive Materials Transportation: A Legal, Economic and Public Perception Analysis

    SciTech Connect (OSTI)

    Holm, J. A.; Thrower, A. W.; Widmayer, D. A.; Portner, W.

    2003-02-26T23:59:59.000Z

    The shipment of transuranic (TRU) radioactive waste to the Waste Isolation Pilot Plant (WIPP) in New Mexico raised a serious socioeconomic issue - the potential devaluation of property values due to the transportation of TRU waste from generator sites to the disposal facility. In 1992, the New Mexico Supreme Court held in City of Santa Fe v. Komis that a loss in value from public perception of risk was compensable. This issue has become an extremely important one for the development of the Yucca Mountain repository in Nevada for disposal of spent nuclear fuel and high-level radioactive waste. Much research has been conducted about the potential impacts of transportation of spent fuel and radioactive waste. This paper examines the pertinent studies conducted since the Komis case. It examines how the public debate on radioactive materials transportation continues and is now focused on transportation of high-level waste and spent nuclear fuel to the proposed Yucca Mountain repository. Finally, the paper suggests a path forward DOE can take to address this issue.

  10. Multi-Scale Studies of Transport and Adsorption Phenomena of Cement-based Materials in Aqueous and Saline Environment

    E-Print Network [OSTI]

    Yoon, Se Yoon

    2012-01-01T23:59:59.000Z

    saturated concrete during drying, Transport in Porous Media,Concrete is a composite material consisting of a porousand Concrete Research, 34 (2004) 1579- [25] L.A. Richards, Capillary conduction of liquids through porous

  11. Transportation

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

    Transportation Home Agenda Awards Exhibitors Lodging Posters Registration Transportation Workshops Contact Us User Meeting Archives Users' Executive Committee Getting to Berkeley...

  12. Transportation

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

    Transportation Print Home Agenda Awards Exhibitors Lodging Posters Registration Transportation Workshops Contact Us User Meeting Archives Users' Executive Committee Getting to...

  13. Management of radioactive material safety programs at medical facilities. Final report

    SciTech Connect (OSTI)

    Camper, L.W.; Schlueter, J.; Woods, S. [and others

    1997-05-01T23:59:59.000Z

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

  14. efficiency, productivity, and safety of transportation, and to alleviate the impact

    E-Print Network [OSTI]

    Pennycook, Steve

    transportation community with innovative, practical tools and techniques for the analysis and management Laboratory-- conducts research on a wide range of applications, focusing primarily on remote sensing and weigh-in-motion, spectroscopy, full-spectrum solar energy, and sensors. Power Electronics and Electric

  15. Safety Requirements for the Packaging and Transportation of Hazardous Materials, Hazardous Substances, and Hazardous Wastes

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

    1985-07-09T23:59:59.000Z

    Cancels Chapter 3 of DOE 5480.1A. Canceled by DOE O 460.1 of 9-27-1995 and by DOE N 251.4 & Para. 9c canceled by DOE O 231.1 of 9-30-1995.

  16. Peer review of the National Transportation Safety Board structural analysis of the I-35W bridge collapse.

    SciTech Connect (OSTI)

    Gwinn, Kenneth West; Redmond, James Michael; Wellman, Gerald William

    2008-10-01T23:59:59.000Z

    The Engineering Sciences Center at Sandia National Laboratories provided an independent peer review of the structural analysis supporting the National Transportation Safety Board investigation of the August 1, 2007 collapse of the I-35W Bridge in Minneapolis. The purpose of the review was to provide an impartial critique of the analysis approach, assumptions, solution techniques, and conclusions. Subsequent to reviewing numerous supporting documents, a SNL team of staff and management visited NTSB to participate in analysis briefings, discussions with investigators, and examination of critical elements of the bridge wreckage. This report summarizes the opinion of the review team that the NTSB analysis effort was appropriate and provides compelling supporting evidence for the NTSB probable cause conclusion.

  17. Framework for a flexible, real-time controller for automated material transport systems

    E-Print Network [OSTI]

    Edlabadkar, Abhay

    1995-01-01T23:59:59.000Z

    The Manager Module. 5. 5. 1 Configuration 1. . 5. 5. 2 Configurations 2 2k 3. 5. 5. 3 Configuratron 4. . 5. 5. 4 Error Handling and Recovery Routines. . . . . . 5. 6 The Dispatcher Module. . 5. 6. 1 Configurations I 2k 4 5. 6. 2 Configurations 2 & 3... for the manager module. MTC control structure. 25 28 43 61 16 17 19 20 Material transport system layout . Intermediate decision ports . . Intermediate MTS network representation. . Graph representation of the MTS. . . Basic flowchart for the MTC...

  18. Regulatory compliance in the design of packages used to transport radioactive materials

    SciTech Connect (OSTI)

    Raske, D.T.

    1993-06-01T23:59:59.000Z

    Shipments of radioactive materials within the regulatory jurisdiction of the US Department of Energy (DOE) must meet the package design requirements contained in Title 10 of the Code of Federal Regulations, Part 71, and DOE Order 5480.3. These regulations do not provide design criteria requirements, but only detail the approval standards, structural performance criteria, and package integrity requirements that must be met during transport. The DOE recommended design criterion for high-level Category I radioactive packagings is Section III, Division 1, of the ASME Boiler and Pressure Vessel Code. However, alternative design criteria may be used if all the design requirements are satisfied. The purpose of this paper is to review alternatives to the Code criteria and discuss their applicability to the design of containment vessels in packages for high-level radioactive materials. Issues such as design qualification by physical testing, the use of scale models, and problems encountered using a non-ASME design approach are addressed.

  19. Mode-selective vibrational control of charge transport in $?$-conjugated molecular materials

    E-Print Network [OSTI]

    Artem A. Bakulin; Robert Lovrin?i?; Yu Xi; Oleg Selig; Huib J. Bakker; Yves L. A. Rezus; Pabitra K. Nayak; Alexandr Fonari; Veaceslav Coropceanu; Jean-Luc Brédas; David Cahen

    2015-03-02T23:59:59.000Z

    The soft character of organic materials leads to strong coupling between molecular nuclear and electronic dynamics. This coupling opens the way to control charge transport in organic electronic devices by inducing molecular vibrational motions. However, despite encouraging theoretical predictions, experimental realization of such control has remained elusive. Here we demonstrate experimentally that photoconductivity in a model organic optoelectronic device can be controlled by the selective excitation of molecular vibrations. Using an ultrafast infrared laser source to create a coherent superposition of vibrational motions in a pentacene/C60 photoresistor, we observe that excitation of certain modes in the 1500-1700 cm$^{-1}$ region leads to photocurrent enhancement. Excited vibrations affect predominantly trapped carriers. The effect depends on the nature of the vibration and its mode-specific character can be well described by the vibrational modulation of intermolecular electronic couplings. Vibrational control thus presents a new tool for studying electron-phonon coupling and charge dynamics in (bio)molecular materials.

  20. Assessment of the safety of spent fuel transportation in urban environs

    SciTech Connect (OSTI)

    Sandoval, R.P.; Weber, J.P.; Levine, H.S.; Romig, A.D.; Johnson, J.D.; Luna, R.E.; Newton, G.J.; Wong, B.A.; Marshall, R.W. Jr.; Alvarez, J.L.

    1983-06-01T23:59:59.000Z

    The results of a program to provide an experimental data base for estimating the radiological consequences from a hypothetical sabotage attack on a light-water-reactor spent fuel shipping cask in a densely populated area are presented. The results of subscale and full-scale experiments in conjunction with an analytical modeling study are described. The experimental data were used as input to a reactor-safety consequence model to predict radiological health consequences resulting from a hypothetical sabotage attack on a spent-fuel shipping cask in the Manhattan borough of New York City. The results of these calculations are presented.

  1. Application of United States Department of Transportation regulations to hazardous material and waste shipments on the Hanford Site

    SciTech Connect (OSTI)

    Burnside, M.E.

    1992-01-01T23:59:59.000Z

    All hazardous material and waste transported over roadways open to the public must be in compliance with the US Department of Transportation (DOT) regulations. The DOT states that the hazardous material regulations (HMR) also apply to government-owned, contractor-operated (GOCO) transportation operations over any US Department of Energy (DOE) site roadway where the public has free and unrestricted access. Hazardous material and waste in packages that do not meet DOE regulations must be transported on DOE site roadways in a manner that excludes the public and nonessential workers. At the DOE Richland Field Office (the Hanford Site), hazardous material and waste movements that do not meet DOE requirements are transported over public access roadways during off-peak hours with the roadways barricaded. These movements are accomplished using a transportation plan that involves the DOE, DOE contractors, and private utilities who operate on or near the Hanford Site. This method, which is used at the Hanford Site to comply with DOE regulations onsite, can be communicated to other DOE sites to provide a basis for achieving consistency in similar transportation operations.

  2. Constraint-Based Routing Models for the Transport of Radioactive Materials

    SciTech Connect (OSTI)

    Peterson, Steven K [ORNL

    2015-01-01T23:59:59.000Z

    The Department of Energy (DOE) has a historic programmatic interest in the safe and secure routing, tracking, and transportation risk analysis of radiological materials in the United States. In order to address these program goals, DOE has funded the development of several tools and related systems designed to provide insight to planners and other professionals handling radioactive materials shipments. These systems include the WebTRAGIS (Transportation Routing Analysis Geographic Information System) platform. WebTRAGIS is a browser-based routing application developed at Oak Ridge National Laboratory (ORNL) focused primarily on the safe transport of spent nuclear fuel from US nuclear reactors via railway, highway, or waterway. It is also used for the transport planning of low-level radiological waste to depositories such as the Waste Isolation Pilot Plant (WIPP) facility. One particular feature of WebTRAGIS is its coupling with high-resolution population data from ORNL s LandScan project. This allows users to obtain highly accurate population count and density information for use in route planning and risk analysis. To perform the routing and risk analysis WebTRAGIS incorporates a basic routing model methodology, with the additional application of various constraints designed to mimic US Department of Transportation (DOT), DOE, and Nuclear Regulatory Commission (NRC) regulations. Aside from the routing models available in WebTRAGIS, the system relies on detailed or specialized modal networks for the route solutions. These include a highly detailed network model of the US railroad system, the inland and coastal waterways, and a specialized highway network that focuses on the US interstate system and the designated hazardous materials and Highway Route Controlled Quantity (HRCQ) -designated roadways. The route constraints in WebTRAGIS rely upon a series of attributes assigned to the various components of the different modal networks. Routes are determined via a constrained shortest-path Dijkstra algorithm that has an assigned impedance factor. The route constraints modify the various impedance weights to bias or prefer particular network characteristics as desired by the user. Both the basic route model and the constrained impedance function calculations are determined by a series of network characteristics and shipment types. The study examines solutions under various constraints modeled by WebTRAGIS including possible routes from select shut-down reactor sites in the US to specific locations in the US. For purposes of illustration, the designated destinations are Oak Ridge National Laboratory in Tennessee and the Savannah River Site in South Carolina. To the degree that routes express sameness or variety under constraints serves to illustrate either a) the determinism of particular transport modes by either configuration or regulatory compliance, and/or b) the variety of constrained routes that are regulation compliant but may not be operationally feasible.

  3. Toolbox Safety Talk Welding & Metal Work Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Toolbox Safety Talk Welding & Metal Work Safety Environmental Health & Safety Facilities Safety or harmful emission giving metals. Welding Safety When welding outside of a designated welding booth, ensure injury. Avoid welding on materials such as galvanized or stainless steel in order to minimize toxic fume

  4. Transportation

    E-Print Network [OSTI]

    Vinson, Steve

    2013-01-01T23:59:59.000Z

    Transportation in ancient Egypt entailed the use of boats2007 Land transport in Roman Egypt: A study of economics andDieter 1991 Building in Egypt: Pharaonic stone masonry. New

  5. ALCOJET MSDS -ALCOJET MSDS -ALCOJET MSDS -ALCOJET MSDS MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Dickerson, Russell R.

    of available chlorine. Other Precautions: No special requirements other than the good industrial hygiene Generally Aggravated by Exposure: Not established. Unnecessary exposure to this product or any industrial and safety practices employed with any industrial chemical. VIII. CONTROL MEASURES Respiratory Protection

  6. Materials science division light-water-reactor safety research program. Quarterly progress report, October - December 1981

    SciTech Connect (OSTI)

    Not Available

    1982-05-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1981 on water-reactor-safety problems. The research and development areas covered are environmentally assisted cracking in light water reactors, transient fuel response and fission-product release, and clad properties for code verification.

  7. Safety of high speed guided ground transportation systems: Comparison of magnetic and electric fields of conventional and advanced electrified transportation systems. Final report, September 1992-March 1993

    SciTech Connect (OSTI)

    Dietrich, F.M.; Feero, W.E.; Jacobs, W.L.

    1993-08-01T23:59:59.000Z

    Concerns exist regarding the potential safety, environmental and health effects on the public and on transportation workers due to electrification along new or existing rail corridors, and to proposed maglev and high speed rail operations. Therefore, the characterization of electric and magnetic fields (EMF) produced by both steady (dc) and alternating currents (ac) at power frequency (50 Hz in Europe and 60 Hz in the U.S.) and above, in the Extreme Low Frequency (ELF) range (3-3000 Hz) is of interest. The report summarizes and compares the results of a survey of EMF characteristics (spatial, temporal and frequency bands) for representative conventional railroad and transit and advanced high-speed systems including: the German TR-07 maglev system; the Amtrak Northeast Corridor (NEC) and North Jersey Transit (NJT) trains; the Washington, DC Metrorail (WMATA) and the Boston, MA (MBTA) transit systems; and the French TGV-A high speed rail system. This comprehensive comparative EMF survey produced both detailed data and statistical summaries of EMF profiles, and their variability in time and space. EMF ELF levels for WMATA are also compared to those produced by common environmental sources at home, work, and under power lines, but have specific frequency signatures.

  8. WAG 2 remedial investigation and site investigation site-specific work plan/health and safety checklist for the sediment transport modeling task

    SciTech Connect (OSTI)

    Holt, V.L.; Baron, L.A.

    1994-05-01T23:59:59.000Z

    This site-specific Work Plan/Health and Safety Checklist (WP/HSC) is a supplement to the general health and safety plan (HASP) for Waste Area Grouping (WAG) 2 remedial investigation and site investigation (WAG 2 RI&SI) activities [Health and Safety Plan for the Remedial Investigation and Site Investigation of Waste Area Grouping 2 at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (ORNL/ER-169)] and provides specific details and requirements for the WAG 2 RI&SI Sediment Transport Modeling Task. This WP/HSC identifies specific site operations, site hazards, and any recommendations by Oak Ridge National Laboratory (ORNL) health and safety organizations [i.e., Industrial Hygiene (IH), Health Physics (HP), and/or Industrial Safety] that would contribute to the safe completion of the WAG 2 RI&SI. Together, the general HASP for the WAG 2 RI&SI (ORNL/ER-169) and the completed site-specific WP/HSC meet the health and safety planning requirements specified by 29 CFR 1910.120 and the ORNL Hazardous Waste Operations and Emergency Response (HAZWOPER) Program Manual. In addition to the health and safety information provided in the general HASP for the WAG 2 RI&SI, details concerning the site-specific task are elaborated in this site-specific WP/HSC, and both documents, as well as all pertinent procedures referenced therein, will be reviewed by all field personnel prior to beginning operations.

  9. A Review of Removable Surface Contamination on Radioactive Materials Transportation Containers

    SciTech Connect (OSTI)

    Kennedy, Jr, W. E.; Watson, E. C.; Murphy, D. W.; Harrer, B. J.; Harty, R.; Aldrich, J. M.

    1981-05-01T23:59:59.000Z

    This report contains the results of a study sponsored by the U.S. Nuclear Regulatory Commission (NRC) of removable surface contamination on radioactive materials transportation containers. The purpose of the study is to provide information to the NRC during their review of existing regulations. Data was obtained from both industry and literature on three major topics: 1) radiation doses, 2) economic costs, and 3) contamination frequencies. Containers for four categories of radioactive materials are considered including radiopharmaceuticals, industrial sources, nuclear fuel cycle materials, and low-level radioactive waste. Assumptions made in this study use current information to obtain realistic yet conservative estimates of radiation dose and economic costs. Collective and individual radiation doses are presented for each container category on a per container basis. Total doses, to workers and the public, are also presented for spent fuel cask and low-level waste drum decontamination. Estimates of the additional economic costs incurred by lowering current limits by factors of 10 and 100 are presented. Current contamination levels for each category of container are estimated from the data collected. The information contained in this report is designed to be useful to the NRC in preparing their recommendations for new regulations.

  10. PAT-2 (Plutonium Air-Transportable Model 2) safety analysis report

    SciTech Connect (OSTI)

    Andersen, J.A.; Davis, E.J.; Duffey, T.A.; Dupree, S.A.; George, O.L. Jr.; Ortiz, Z.

    1981-07-01T23:59:59.000Z

    The PAT-2 package is designed for the safe transport of plutonium and/or uranium in small quantities. The PAT-2 package is resistant to severe accidents, including that of a high-speed jet aircraft crash, and is designed to withstand such environments as extreme impact, crushing, puncturing and slashing loads, severe hydrocarbon-fueled fires, and deep underwater immersion, with no escape of contents. The package meets the requirements of 10 CFR 71 for Fissile Class I packages with a cargo of 15 grams of Pu-239, or other isotopic forms described herein, not to exceed 2 watts of thermal activity. This SAR presents design and oprational information including evaluations and analyses, test results, operating procedures, maintenance, and quality assurance information.

  11. Aerosol particle transport modeling for preclosure safety studies of nuclear waste repositories

    SciTech Connect (OSTI)

    Gelbard, F. [Sandia National Labs., Albuquerque, NM (USA)

    1989-01-01T23:59:59.000Z

    An important concern for preclosure safety analysis of a nuclear waste repository is the potential release to the environment of respirable aerosol particles. Such particles, less than 10 {mu}m in aerodynamic diameter, may have significant adverse health effects if inhaled. To assess the potential health effects of these particles, it is not sufficient to determine the mass fraction of respirable aerosol. The chemical composition of the particles is also of importance since different radionuclides may pose vastly different health hazards. Thus, models are needed to determine under normal and accident conditions the particle size and the chemical composition distributions of aerosol particles as a function of time and of position in the repository. In this work a multicomponent sectional aerosol model is used to determine the aerosol particle size and composition distributions in the repository. A range of aerosol mass releases with varying mean particle sizes and chemical compositions is used to demonstrate the sensitivities and uncertainties of the model. Decontamination factors for some locations in the repository are presented. 8 refs., 1 tab.

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

    SciTech Connect (OSTI)

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

    2013-07-01T23:59:59.000Z

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

  13. Safety analysis report for packaging (onsite) steel drum

    SciTech Connect (OSTI)

    McCormick, W.A.

    1998-09-29T23:59:59.000Z

    This Safety Analysis Report for Packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the steel drum packaging system meets the transportation safety requirements of HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments, for an onsite packaging containing Type B quantities of solid and liquid radioactive materials. The basic component of the steel drum packaging system is the 208 L (55-gal) steel drum.

  14. Criticality Safety Scoping Study for the Transport of Weapons-Grade Mixed-Oxide Fuel Using the MO-1 Shipping Package

    SciTech Connect (OSTI)

    Dunn, M.E.; Fox, P.B.

    1999-05-01T23:59:59.000Z

    This report provides the criticality safety information needed for obtaining certification of the shipment of mixed-oxide (MOX) fuel using the MO-1 [USA/9069/B()F] shipping package. Specifically, this report addresses the shipment of non-weapons-grade MOX fuel as certified under Certificate of Compliance 9069, Revision 10. The report further addresses the shipment of weapons-grade MOX fuel using a possible Westinghouse fuel design. Criticality safety analysis information is provided to demonstrate that the requirements of 10 CFR S 71.55 and 71.59 are satisfied for the MO-1 package. Using NUREG/CR-5661 as a guide, a transport index (TI) for criticality control is determined for the shipment of non-weapons-grade MOX fuel as specified in Certificate of Compliance 9069, Revision 10. A TI for criticality control is also determined for the shipment of weapons-grade MOX fuel. Since the possible weapons-grade fuel design is preliminary in nature, this report is considered to be a scoping evaluation and is not intended as a substitute for the final criticality safety analysis of the MO-1 shipping package. However, the criticality safety evaluation information that is presented in this report does demonstrate the feasibility of obtaining certification for the transport of weapons-grade MOX lead test fuel using the MO-1 shipping package.

  15. Projected environmental impacts of radioactive material transportation to the first US repository site

    SciTech Connect (OSTI)

    Neuhauser, K.S.; Cashwell, J.W.; Reardon, P.C.; Ostmeyer, R.M.; McNair, G.W.

    1986-12-31T23:59:59.000Z

    This paper discusses the relative national environmental impacts of transporting nuclear wastes to each of the nine candidate repository sites in the United States. Several of the potential sites are closely clustered and, for the purpose of distance and routing calculations, are treated as a single location. These are: Cypress Creek Dome and Richton Dome in Mississippi (Gulf Interior Region), Deaf Smith County and Swisher County sites in Texas (Permian Basin), and Davis Canyon and Lavender Canyon site in Utah (Paradox Basin). The remaining sites are: Vacherie Dome, Louisiana; Yucca Mountain, Nevada; and Hanford Reservation, Washington. For compatibility with both the repository system authorized by the NWPA and with the MRS option, two separate scenarios were analyzed. In belief, they are (1) shipment of spent fuel and high-level wastes (HLW) directly from waste generators to a repository (Reference Case) and (2) shipment of spent fuel to a Monitored Retrievable Storage (MRS) facility and then to a repository. Between 17 and 38 truck accident fatalities, between 1.4 and 7.7 rail accident fatalities, and between 0.22 and 12 radiological health effects can be expected to occur as a result of radioactive material transportation during the 26-year operating period of the first repository. During the same period in the United States, about 65,000 total deaths from truck accidents and about 32,000 total deaths from rail accidents would occur; also an estimated 58,300 cancer fatalities are predicted to occur in the United States during a 26-year period from exposure to background radiation alone (not including medical and other manmade sources). The risks reported here are upper limits and are small by comparison with the "natural background" of risks of the same type. 3 refs., 6 tabs.

  16. DOE Partnerships with States, Tribes and Other Federal Programs Help Responders Prepare for Challenges Involving Transport of Radioactive Materials

    SciTech Connect (OSTI)

    Marsha Keister

    2001-02-01T23:59:59.000Z

    DOE Partnerships with States, Tribes and Other Federal Programs Help Responders Prepare for Challenges Involving Transport of Radioactive Materials Implementing adequate institutional programs and validating preparedness for emergency response to radiological transportation incidents along or near U.S. Department of Energy (DOE) shipping corridors poses unique challenges to transportation operations management. Delayed or insufficient attention to State and Tribal preparedness needs may significantly impact the transportation operations schedule and budget. The DOE Transportation Emergency Preparedness Program (TEPP) has successfully used a cooperative planning process to develop strong partnerships with States, Tribes, Federal agencies and other national programs to support responder preparedness across the United States. DOE TEPP has found that building solid partnerships with key emergency response agencies ensures responders have access to the planning, training, technical expertise and assistance necessary to safely, efficiently and effectively respond to a radiological transportation accident. Through the efforts of TEPP over the past fifteen years, partnerships have resulted in States and Tribal Nations either using significant portions of the TEPP planning resources in their programs and/or adopting the Modular Emergency Response Radiological Transportation Training (MERRTT) program into their hazardous material training curriculums to prepare their fire departments, law enforcement, hazardous materials response teams, emergency management officials, public information officers and emergency medical technicians for responding to transportation incidents involving radioactive materials. In addition, through strong partnerships with Federal Agencies and other national programs TEPP provided technical expertise to support a variety of radiological response initiatives and assisted several programs with integration of the nationally recognized MERRTT program into other training venues, thus ensuring consistency of radiological response curriculums delivered to responders. This presentation will provide an overview of the steps to achieve coordination, to avoid redundancy, and to highlight several of the successful partnerships TEPP has formed with States, Tribes, Federal agencies and other national programs. Events, accident scenarios, and training where TEPP was proven to be integral in building the radiological response capabilities for first responders to actual radiological incidents are also highlighted. Participants will gain an appreciation for the collaborative efforts States and Tribes are engaging in with the DOE to ensure that responders all along the DOE transportation corridors are adequately prepared to respond to shipments of radioactive materials through their communities.

  17. Table of Organization Environmental Health & Safety

    E-Print Network [OSTI]

    Jia, Songtao

    Safety Continues Page 3 Lauren Kelly Manager Hazardous Materials June, 2014 James Kaznosky, Senior Research Safety Lauren Kelly Manager Hazardous Materials Radioactive Waste (only) Hazardous Materials Assistant Physicist Vacant Assistant Physicist 2 #12;Environmental Safety/Hazardous Materials Management

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

    SciTech Connect (OSTI)

    none,

    1992-01-01T23:59:59.000Z

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

  19. Deposition of hole-transport materials in solid-state dye-sensitized solar cells by doctor-blading

    E-Print Network [OSTI]

    McGehee, Michael

    Deposition of hole-transport materials in solid-state dye-sensitized solar cells by doctor Accepted 19 April 2010 Available online xxxx Keywords: Dye-sensitized solar cells Organic semiconductors)-9,90 -spirobifluorene) in solid-state dye-sensitized solar cells. Doctor-blading is a roll

  20. Interagency cooperation in the development of a cost-effective transportation and disposal solution for vitrified radium bearing material

    SciTech Connect (OSTI)

    Smith, M.L.; Nixon, D.A.; Stone, T.J.; Tope, W.G.; Vogel, R.A. [Fernald Environmental Restoration Management Corp., Cincinnati, OH (United States); Allen, R.B. [USDOE, Fernald Area Office, Cincinnati, OH (United States); Schofield, W.D. [Foster Wheeler Environmental Corp. (United States)

    1996-02-01T23:59:59.000Z

    Fernald radium bearing ore residue waste, stored within Silos 1 and 2 (K-65) and Silo 3 waste, will be vitrified for disposal at the Nevada Test Site (NTS). A comprehensive, parametric evaluation of waste form, shielding requirements, packaging, and transportation alternatives was completed to identify the safest, most cost-effective approach. The impacts of waste loading, waste form, regulatory requirements, NTS waste acceptance criteria, as-low-as-resonably-achievable principles, and material handling costs were factored into the recommended approach. Through cooperative work between the U.S. Department of Energy (DOE) and the U.S. Department of Transportation (DOT), the vitrified K-65 and Silo 3 radioactive material will be classified consistent with the regulations promulgated by DOT in the September 28, 1995 Federal Register. These new regulations adopt International Atomic Energy Agency language to promote a consistent approach for the transportation and management of radioactive material between the international community and the DOT. Use of the new regulations allows classification of the vitrified radioactive material from the Fernald silos under the designation of low specific activity-II and allows the development of a container that is optimized to maximize payload while minimizing internal void space, external surface radiation levels, and external volume. This approach minimizes the required number of containers and shipments, and the related transportation and disposal costs.

  1. Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory

    SciTech Connect (OSTI)

    Crandall, R.S.; Nelson, B.P.; Moskowitz, P.D.; Fthenakis, V.M.

    1992-07-01T23:59:59.000Z

    To ensure the continued safety of SERI's employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMS). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance. This document contains the appendices to the NREL safety analysis report.

  2. Pipeline Safety Rule (Tennessee)

    Broader source: Energy.gov [DOE]

    The Pipeline Safety Rule simply states, "The Minimum Federal Safety Standards for the transportation of natural and other gas by pipeline (Title 49, Chapter 1, Part 192) as published in the Federal...

  3. Environment, Safety, and Health Risk Assessment Program (ESHRAP)

    SciTech Connect (OSTI)

    Eide, Steven Arvid; Thomas Wierman

    2003-12-01T23:59:59.000Z

    The Environment, Safety and Health Risk Assessment Program (ESHRAP) models human safety and health risk resulting from waste management and environmental restoration activities. Human safety and health risks include those associated with storing, handling, processing, transporting, and disposing of radionuclides and chemicals. Exposures to these materials, resulting from both accidents and normal, incident-free operation, are modeled. In addition, standard industrial risks (falls, explosions, transportation accidents, etc.) are evaluated. Finally, human safety and health impacts from cleanup of accidental releases of radionuclides and chemicals to the environment are estimated. Unlike environmental impact statements and safety analysis reports, ESHRAP risk predictions are meant to be best estimate, rather than bounding or conservatively high. Typically, ESHRAP studies involve risk predictions covering the entire waste management or environmental restoration program, including such activities as initial storage, handling, processing, interim storage, transportation, and final disposal. ESHRAP can be used to support complex environmental decision-making processes and to track risk reduction as activities progress.

  4. Safety Analysis Report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory

    SciTech Connect (OSTI)

    Crandall, R.S.; Nelson, B.P. (National Renewable Energy Lab., Golden, CO (United States)); Moskowitz, P.D.; Fthenakis, V.M. (Brookhaven National Lab., Upton, NY (United States))

    1992-07-01T23:59:59.000Z

    To ensure the continued safety of SERI's employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMs). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 Occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance.

  5. TRUE COLORS: LEDS AND THE RELATIONSHIP BETWEEN CCT, CRI, OPTICAL SAFETY, MATERIAL DEGRADATION, AND PHOTOBIOLOGICAL STIMULATION

    SciTech Connect (OSTI)

    Royer, Michael P.

    2014-08-30T23:59:59.000Z

    This document analyzes the optical, material, and photobiological hazards of LED light sources compared to conventional light sources. It documents that LEDs generally produce the same amount of blue light, which is the primary contributor to the risks, as other sources at the same CCT. Duv may have some effect on the amount of blue light, but CRI does not.

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

    SciTech Connect (OSTI)

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

    2010-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2010-10-28T23:59:59.000Z

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

  8. GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report

    SciTech Connect (OSTI)

    Halsey, W

    2009-01-15T23:59:59.000Z

    This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research & Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the baseline for waste management calculations for the GNEP Programmatic Environmental Impact Statement (PEIS). The IWMS represents a collaborative effort between the Systems Analysis, Waste Forms, and Separations Campaigns with contributing authors from multiple laboratories. The IWMS reference is: 'Global Nuclear Energy Partnership Integrated Waste Management Strategy, D. Gombert, INL, et al, GNEP-WAST-WAST-AI-RT-2008-000214, March 2008'. (2) As input to the IWMS and support for program decisions, an evaluation of the current regulatory framework in the U.S. pertaining to the disposal of radioactive wastes under an advanced nuclear fuel cycle was completed by ANL. This evaluation also investigated potential disposal pathways for these wastes. The entire evaluation is provided in Appendix A of this report. (3) Support was provided to the development of the GNEP Programmatic Environmental Impact Statement from INL, SNL and ANL M-TSD staff. (4) M-TSD staff prepared input for DSARR (Dynamic Systems Analysis Report for Nuclear Fuel Recycle) report. The DSARR is an INL led report to examine the time-dependent dynamics for a transition from the current open fuel cycle to either a 1-tier or 2-tier closed fuel cycle. Section 5.3 Waste Management Impacts was provided to INL for incorporation into the DSARR. (5) SNL M-TSD staff prepared a M2 milestone report 'Material Transportation, Storage and Disposal Contribution for Secretarial Decision Package'. The report purpose was to comprehensively evaluate and discuss packaging, storage, and transportation for all potential nuclear and radioactive materials in the process and waste streams being considered by the GNEP program. In particular, a systems view was used to capture all packaging, storage, and transport operations needed to link the various functional aspects of the fuel cycle. (6) SRNL M-TSD staff developed a deliverable report 'Management of Decay Heat from Spent Nuclear Fuel'. This report evaluated a range of options for managing the near-term decay heat associated with Cs and Sr in spent nuclear fuel (SNF) reprocessing waste

  9. School of Forest Safety Training

    E-Print Network [OSTI]

    Thomas, Andrew

    ) · Laboratories: ­ Material Safety Data Sheets (MSDS) for chemicals ­ Chemical hygiene plan (CHP) manual

  10. Transportation Security | ornl.gov

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

    Transportation Security SHARE Global Threat Reduction Initiative Transportation Security Cooperation Secure Transport Operations (STOP) Box Security of radioactive material while...

  11. The basics in transportation of low-level radioactive waste

    SciTech Connect (OSTI)

    Allred, W.E.

    1998-06-01T23:59:59.000Z

    This bulletin gives a basic understanding about issues and safety standards that are built into the transportation system for radioactive material and waste in the US. An excellent safety record has been established for the transport of commercial low-level radioactive waste, or for that matter, all radioactive materials. This excellent safety record is primarily because of people adhering to strict regulations governing the transportation of radioactive materials. This bulletin discusses the regulatory framework as well as the regulations that set the standards for packaging, hazard communications (communicating the potential hazard to workers and the public), training, inspections, routing, and emergency response. The excellent safety record is discussed in the last section of the bulletin.

  12. Assessing recycling versus incineration of key materials in municipal waste: The importance of efficient energy recovery and transport distances

    SciTech Connect (OSTI)

    Merrild, Hanna [Department of Environmental Engineering, Technical University of Denmark, Miljoevej, Building 113, DK-2800 Kongens Lyngby (Denmark); Larsen, Anna W., E-mail: awla@env.dtu.dk [Department of Environmental Engineering, Technical University of Denmark, Miljoevej, Building 113, DK-2800 Kongens Lyngby (Denmark); Christensen, Thomas H. [Department of Environmental Engineering, Technical University of Denmark, Miljoevej, Building 113, DK-2800 Kongens Lyngby (Denmark)

    2012-05-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer We model the environmental impact of recycling and incineration of household waste. Black-Right-Pointing-Pointer Recycling of paper, glass, steel and aluminium is better than incineration. Black-Right-Pointing-Pointer Recycling and incineration of cardboard and plastic can be equally good alternatives. Black-Right-Pointing-Pointer Recyclables can be transported long distances and still have environmental benefits. Black-Right-Pointing-Pointer Paper has a higher environmental benefit than recyclables found in smaller amounts. - Abstract: Recycling of materials from municipal solid waste is commonly considered to be superior to any other waste treatment alternative. For the material fractions with a significant energy content this might not be the case if the treatment alternative is a waste-to-energy plant with high energy recovery rates. The environmental impacts from recycling and from incineration of six material fractions in household waste have been compared through life cycle assessment assuming high-performance technologies for material recycling as well as for waste incineration. The results showed that there are environmental benefits when recycling paper, glass, steel and aluminium instead of incinerating it. For cardboard and plastic the results were more unclear, depending on the level of energy recovery at the incineration plant, the system boundaries chosen and which impact category was in focus. Further, the environmental impact potentials from collection, pre-treatment and transport was compared to the environmental benefit from recycling and this showed that with the right means of transport, recyclables can in most cases be transported long distances. However, the results also showed that recycling of some of the material fractions can only contribute marginally in improving the overall waste management system taking into consideration their limited content in average Danish household waste.

  13. Safety evaluation for packaging for the transport of K Basin sludge samples in the PAS-1 cask

    SciTech Connect (OSTI)

    SMITH, R.J.

    1998-11-17T23:59:59.000Z

    This safety evaluation for packaging authorizes the shipment of up to two 4-L sludge samples to and from the 325 Lab or 222-S Lab for characterization. The safety of this shipment is based on the current U.S. Department of Energy Certification of Compliance (CoC) for the PAS-1 cask, USA/9184/B(U) (DOE).

  14. PROCEEDINGS: Conference on Transportation in Developing Countries

    E-Print Network [OSTI]

    Cervero, Robert; Sperling, Daniel; Mason, Jonathan

    1998-01-01T23:59:59.000Z

    Environment, and Ecology Enhancing Mobility: Transportation Technologies, Operations, Design Non-Motorized Transportation: Mobility and Safety Economics, Financing,

  15. Safety Analysis Report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory

    SciTech Connect (OSTI)

    Crandall, R.S.; Nelson, B.P. [National Renewable Energy Lab., Golden, CO (United States); Moskowitz, P.D.; Fthenakis, V.M. [Brookhaven National Lab., Upton, NY (United States)

    1992-07-01T23:59:59.000Z

    To ensure the continued safety of SERI`s employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMs). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 Occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance.

  16. Computational study of the transport mechanisms of molecules and ions in solid materials 

    E-Print Network [OSTI]

    Zhang, Yingchun

    2009-06-02T23:59:59.000Z

    DOE target of 6.5wt% at at 294 bar at 273 K, and 309 bar at 300 K. In the second part of this dissertation, we study the lithium ion transport from a solid electrolyte phase to a solid electrode phase. Improvement of ionic transport in solid...

  17. Zintl Phases as Thermoelectric Materials: Tuned Transport Properties of the Compounds CaxYb1xZn2Sb2**

    E-Print Network [OSTI]

    Zintl Phases as Thermoelectric Materials: Tuned Transport Properties of the Compounds CaxYb1±xZn2Sb. Introduction Because of their ability to convert waste heat into electricity, thermoelectric materials have in efficiency, thermoelectric materials could pro- vide a substantial amount of electrical power from automotive

  18. Reducing the Risk of Rail Transport of Hazardous Materials by Route Rationalization

    E-Print Network [OSTI]

    Barkan, Christopher P.L.

    Kawprasert (Corresponding Author) Graduate Research Assistant Railroad Engineering Program Department practices intended to reduce the likelihood or severity of accidents involving trains transporting certain Engineering Program Department of Civil and Environmental Engineering University of Illinois at Urbana

  19. NMR and Transport Studies on Group IV Clathrates and Related Intermetallic Materials 

    E-Print Network [OSTI]

    Zheng, Xiang

    2012-10-19T23:59:59.000Z

    thermoelectric materials are the intermetallic clathrates. Clathrates are cage-structured materials with guest atoms enclosed. Previous studies have shown lower thermal conductivities compared with many other bulk compounds, and it is believed that guest atom...

  20. Capital requirements for the transportation of energy materials: 1979 arc estimates

    SciTech Connect (OSTI)

    Not Available

    1980-08-29T23:59:59.000Z

    Summaries of transportation investment requirements through 1990 are given for the low, medium and high scenarios. Total investment requirements for the three modes and the three energy commodities can accumulate to a $46.3 to $47.0 billion range depending on the scenario. The high price of oil, following the evidence of the last year, is projected to hold demand for oil below the recent past. Despite the overall decrease in traffic some investment in crude oil and LPG pipelines is necessary to reach new sources of supply. Although natural gas production and consumption is projected to decline through 1990, new investments in carrying capacity also are required due to locational shifts in supply. The Alaska Natural Gas Transportation System is the dominant investment for energy transportation in the next ten years. This year's report focuses attention on waterborne coal transportation to the northeast states in keeping with a return to significant coal consumption projected for this area. A resumption of such shipments will require a completely new fleet. The investment estimates given in this report identify capital required to transport projected energy supplies to market. The requirement is strategic in the sense that other reasonable alternatives do not exist or that a shared load of new growth can be expected. Not analyzed or forecasted are investments in transportation facilities made in response to local conditions. The total investment figures, therefore, represent a minimum necessary capital improvement to respond to changes in interregional supply conditions.

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

    E-Print Network [OSTI]

    Lovell, Cheryl Alane

    1993-01-01T23:59:59.000Z

    Dealing with hazardous materials on a day-to-day basis requires a fine--tuned material management system to minimize risk of exposure or injury to workers or to the public. An effective hazardous material management system should also keep up...

  2. Waste management facilities cost information for transportation of radioactive and hazardous materials

    SciTech Connect (OSTI)

    Feizollahi, F.; Shropshire, D.; Burton, D.

    1995-06-01T23:59:59.000Z

    This report contains cost information on the U.S. Department of Energy (DOE) Complex waste streams that will be addressed by DOE in the programmatic environmental impact statement (PEIS) project. It describes the results of the task commissioned by DOE to develop cost information for transportation of radioactive and hazardous waste. It contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, Greater-Than-Class C (GTCC) LLW and DOE equivalent waste, transuranic (TRU) waste, spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled (<200 mrem/hr contact dose) and remote-handled (>200 mrem/hr contact dose) radioactive waste are estimated. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the U.S. Department of Transportation (DOT), the U.S. Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations.

  3. ONSITE TRANSPORTATION AUTHORIZATION CHALLENGES AT THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Watkins, R.; Loftin, B.; Hoang, D.; Maxted, M.

    2012-05-30T23:59:59.000Z

    Prior to 2008, transfers of radioactive material within the Savannah River Site (SRS) boundary, referred to as onsite transfers, were authorized by Transportation Safety Basis (TSB) documents that only required approval by the SRS contractor. This practice was in accordance with the existing SRS Transportation Safety Document (TSD). In 2008 the Department of Energy Savannah River Field Office (DOE-SR) requested that the SRS TSD be revised to require DOE-SR approval of all Transportation Safety Basis (TSB) documents. As a result, the primary SRS contractor embarked on a multi-year campaign to consolidate old or generate new TSB documents and obtain DOE-SR approval for each. This paper focuses on the challenges incurred during the rewriting or writing of and obtaining DOE-SR approval of all Savannah River Site Onsite Transportation Safety Basis documents.

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

    E-Print Network [OSTI]

    Lovell, Cheryl Alane

    1993-01-01T23:59:59.000Z

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

  5. MATERIAL SAFETY Flammability: 0

    E-Print Network [OSTI]

    Rollins, Andrew M.

    Respiratory Protection : N/A Ventilation : Local Exhaust : N/A Mechanical : N/A Special : N/A Other : N

  6. NMR and Transport Studies on Group IV Clathrates and Related Intermetallic Materials

    E-Print Network [OSTI]

    Zheng, Xiang

    2012-10-19T23:59:59.000Z

    challenge. In this work, Nuclear Magnetic Resonance (NMR), heat capacity and transport measurements have been used to study several clathrate systems, especially the well- known type-I Ba8Ga16Sn30, which has been reported to have one of the lowest thermal...

  7. Packaging and Transfer or Transportation of Materials of National Security Interest

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

    2004-04-26T23:59:59.000Z

    To establish requirements and responsibilities for offsite shipments of naval nuclear fuel elements, Category I and Category II special nuclear material, nuclear explosives, nuclear components, special assemblies, and other materials of national security interest. Cancels DOE O 461.1. Canceled by DOE O 461.1B and DOE O 461.2.

  8. Understanding and engineering molecular interactions and electronic transport at 2D materials interfaces

    E-Print Network [OSTI]

    Shih, Chih-Jen, Ph. D. Massachusetts Institute of Technology

    2014-01-01T23:59:59.000Z

    2D materials are defined as solids with strong in-plane chemical bonds but weak out-of-plane, van der Waals (vdW) interactions. In order to realize potential applications of 2D materials in the areas of optoelectronics, ...

  9. DRAFT - DOE O 460.1D, Hazardous Materials Packaging and Transportation

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisitingContract Management Fermi SitePARTOffice ofHaleREPORT NUCLEARDirectives,Safety

  10. Effect of flow oscillations on axial energy transport in a porous material

    SciTech Connect (OSTI)

    Siegel, R. (NASA Lewis Research Center, Cleveland, OH (USA))

    1987-02-01T23:59:59.000Z

    It has been shown analytically and experimentally that flow oscillations of a fluid within a channel can enhance the axial transfer of energy. The transport arises from an axial gradient in fluid temperature resulting from having reservoirs at different temperatures at either end of the channel. The present analysis develops relations for axial energy diffusion in a porous medium with oscillating flow. In some devices, such as the Sterling engine, there are regenerators with oscillating flow. Axial transport in the regenerator provides an energy loss; hence it is desirable to determine what factors can limit this diffusion. A regenerator in the form of a porous medium is difficult to model since the flow is continually disrupted by the irregularities of the porous structure. The formulation here will employ an internal heat transfer coefficient that couples the fluid and solid temperatures. The final result shows how the diffusion depends on the magnitude of the heat transfer coefficient and the maximum fluid displacement.

  11. Computational study of the transport mechanisms of molecules and ions in solid materials

    E-Print Network [OSTI]

    Zhang, Yingchun

    2009-06-02T23:59:59.000Z

    and alkali metal-doped corannulene are investigated as candidate materials for hydrogen storage. Molecularalso investigated. Using computational chemistry, we predict enhanced H2 adsorption on molecular systems with modification and hydrogen uptake can reach...

  12. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    SciTech Connect (OSTI)

    Komann, Steffen; Groeke, Carsten; Droste, Bernhard [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)] [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)

    2013-07-01T23:59:59.000Z

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  13. Molten Salt Heat Transport Loop: Materials Corrosion and Heat Transfer Phenomena

    SciTech Connect (OSTI)

    Dr. Kumar Sridharan; Dr. Mark Anderson; Dr. Michael Corradini; Dr. Todd Allen; Luke Olson; James Ambrosek; Daniel Ludwig

    2008-07-09T23:59:59.000Z

    An experimental system for corrosion testing of candidate materials in molten FLiNaK salt at 850 degree C has been designed and constructed. While molten FLiNaK salt was the focus of this study, the system can be utilized for evaluation of materials in other molten salts that may be of interest in the future. Using this system, the corrosion performance of a number of code-certified alloys of interest to NGNP as well as the efficacy of Ni-electroplating have been investigated. The mechanisums underlying corrosion processes have been elucidated using scanning electron microscopy, x-ray diffraction, and x-ray photoelectron spectroscopy of the materials after the corrosion tests, as well as by the post-corrosion analysis of the salts using inductively coupled plasma (ICP) and neutron activation analysis (NAA) techniques.

  14. Emerging Technologies Applicable to the Safe and Secure Transportation of Hazardous Materials

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office ofEnergyFinalEnergyEVProposedNational Transportation Stakeholders

  15. Evaluation of Basic Parameters for Packaging, Storage and Transportation of Biomass Material from Field to Biorefinery

    E-Print Network [OSTI]

    Paliwal, Richa

    2012-02-14T23:59:59.000Z

    Logistics and Building a Function Structure for Biomass Materials????????????????????.. 14 2.6.1 Cotton Logistics ....................................................................... 14 2... tolerance, and its adaptability to a wide range of soils have made it 6 a potential energy crop [2, 4, 14, 15]. Cundiff et al. [16] also states the benefit of using switchgrass: it can be harvested and baled using conventional agricultural equipment...

  16. Direct-hydrogen-fueled proton-exchange-membrane fuel cell system for transportation applications. Hydrogen vehicle safety report

    SciTech Connect (OSTI)

    Thomas, C.E. [Directed Technologies, Inc., Arlington, VA (United States)

    1997-05-01T23:59:59.000Z

    This report reviews the safety characteristics of hydrogen as an energy carrier for a fuel cell vehicle (FCV), with emphasis on high pressure gaseous hydrogen onboard storage. The authors consider normal operation of the vehicle in addition to refueling, collisions, operation in tunnels, and storage in garages. They identify the most likely risks and failure modes leading to hazardous conditions, and provide potential countermeasures in the vehicle design to prevent or substantially reduce the consequences of each plausible failure mode. They then compare the risks of hydrogen with those of more common motor vehicle fuels including gasoline, propane, and natural gas.

  17. Natural Gas Pipeline Safety (Kansas)

    Broader source: Energy.gov [DOE]

    This article states minimum safety standards for the transportation of natural gas by pipeline and reporting requirements for operators of pipelines.

  18. Transport of Technetium and Rhenium into Refractory Materials during Bulk Vitrification

    SciTech Connect (OSTI)

    Bagaasen, L.M.; Brouns, T.M.; Elliott, M.L.; Hrma, P.R.; Kim, D.S.; Matyas, J.; Pierce, E.M.; McGrail, B.P.; Schweiger, M.J.; Beck, A.E. [Pacific Northwest National Laboratory, P.O. Box 999, Richland, WA 99352 (United States); Campbell, B.E. [AMEC Earth and Environmental, Inc., GeoMelt Division, 1135 Jadwin Ave., Richland, WA 99352 (United States)

    2006-07-01T23:59:59.000Z

    Bulk vitrification (BV) was selected as a potential supplemental waste treatment process to support the commitment for cleanup of low-activity waste (LAW) stored in large waste storage tanks at the U.S. Department of Energy's Hanford Site. In the BV process, LAW, soil, and glass-forming chemicals are mixed, dried, and placed within a castable refractory block (CRB) and sand, all within a metal box. Electric current, supplied through two graphite electrodes in the box, melts the waste feed and produces a durable glass waste form. During engineering-scale tests of By, a small fraction of radioactive technetium-99 (Tc) and rhenium (Re) (a nonradioactive surrogate) were transferred out of the LAW glass feed and molten LAW glass and deposited on the surface and within the pores of the CRB. Tc is a primary risk driver for long-term performance of immobilized LAW; therefore, even small fractions of Tc present in a readily leachable form rather than immobilized in a glass matrix can impact long-term performance of the immobilized waste. Laboratory and engineering-scale studies were undertaken to reduce or eliminate the readily leachable Tc in the CRB. These studies focused on 1) understanding the mechanisms of the transport of Tc/Re into the CRB during vitrification, and 2) evaluating various means of protecting the CRB against the deposition of leachable Tc/Re. The tests used either Re as a chemical surrogate for Tc, or Re and Tc together. A conceptual Tc/Re transport model was developed based on observed laboratory experiments to attempt to explain the transport behavior seen in engineering-scale tests. At temperatures below 650 deg. C, molten ionic salt (MIS) containing Tc and Re penetrates by capillarity from the feed into the CRB open porosity. At approximately 650 to 750 deg. C, the MIS decomposes through the loss of NO{sub x}, leaving mainly sulfate and chloride salts. The Na{sub 2}O formed during decomposition of the nitrates reacts with insoluble grains in the feed and the aluminosilicates in the CRB to form more viscous liquids that reduce further liquid penetration into the CRB. At 750 to 950 deg. C, a continuous glass phase traps the remains of the MIS in the form of inclusions in the bulk glass melt. At 950 to 1200 deg. C, the salt inclusions in the glass slowly dissolve but also rise to the surface. The Tc/Re salts also evaporate from the free surface of the glass melt that is rapidly renewed by convective currents. The vapors condense on cooler surfaces in the upper portion of the CRB, the box lid, and the off gas system. Results of the engineering-scale tests helped to validate the conceptual transport model of Tc/Re deposition and improved the understanding of likely mechanisms of deposition in the CRB. As a result, there is increased potential that Tc deposition can be controlled and reduced to ensure that the BV waste form will provide acceptable performance. (authors)

  19. Development and evaluation of measurement devices used to support testing of radioactive material transportation packages

    SciTech Connect (OSTI)

    Uncapher, W. L.; Ammerman, D. J.; Stenberg, D.R.; Bronowski, D. R.; Arviso, M.

    1992-01-01T23:59:59.000Z

    Radioactive material package designers use structural testing to verify and demonstrate package performance. A major part of evaluating structural response is the collection of instrumentation measurement data. Sandia National Laboratories (SNL) has an ongoing program to develop and evaluate measurement devices to support testing of radioactive material packages. Measurement devices developed in support of this activity include evaluation channels, ruggedly constructed linear variable differential transformers, and piezoresistive accelerometers with enhanced measurement capabilities. In addition to developing measurement devices, a method has been derived to evaluate accelerometers and strain gages for measurement repeatability, ruggedness, and manufacturers' calibration data under both laboratory and field conditions. The developed measurement devices and evaluation technique will be discussed and the results of the evaluation will be presented.

  20. Facility Safety

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

    1996-10-24T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  1. Facility Safety

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

    1995-11-16T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  2. Radiation Safety Reference Material Policy: 7.01 Created: 08/29/2014 Version: 1.0 Revised

    E-Print Network [OSTI]

    Jia, Songtao

    ­ Radiological Research Accelerator Facility D. Policy Below is a list of regulations governing the medical use/29/2014 Version: 1.0 Revised: Environmental Health & Safety Page 2 of 3 n. Part 170 ­ Fees for Facilities (Health) Part 16 ­ Ionizing Radiation https://www.health.ny.gov/environmental/radiological

  3. Materials Science and Technology Division light-water-reactor safety research program: quarterly progress report, January-March 1983

    SciTech Connect (OSTI)

    Not Available

    1984-04-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during January, February and March 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

  4. Materials Science Division light-water-reactor safety-research program. Quarterly progress report, April-June 1982. Volume 2

    SciTech Connect (OSTI)

    Shack, W.J.; Rest, J.; Kassner, T.F.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.; Ruther, W.E.; Yaggee, F.L.

    1983-05-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1982 on water-reactor-safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, and Clad Properties for Code Verification.

  5. Materials Science Division light-water-reactor safety research program. Quarterly progress report, July-September 1982

    SciTech Connect (OSTI)

    Shack, W.J.; Rest, J.; Kassner, T.F.; Neimark, L.A.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

    1983-08-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1982 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, Posttest Fuel Examination of the ORNL Fission Product Release Tests, and Examination of TMI-2 Fuel Specimens.

  6. Comments on a paper tilted `The sea transport of vitrified high-level radioactive wastes: Unresolved safety issues`

    SciTech Connect (OSTI)

    Sprung, J.L.; McConnell, P.E.; Nigrey, P.J.; Ammerman, D.J. [and others

    1997-05-01T23:59:59.000Z

    The cited paper estimates the consequences that might occur should a purpose-built ship transporting Vitrified High Level Waste (VHLW) be involved in a severe collision that causes the VHLW canisters in one Type-B package to spill onto the floor of a major ocean fishing region. Release of radioactivity from VHLW glass logs, failure of elastomer cask seals, failure of VHLW canisters due to stress corrosion cracking (SCC), and the probabilities of the hypothesized accident scenario, of catastrophic cask failure, and of cask recovery from the sea are all discussed.

  7. WaterTransport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing and Design Optimization

    SciTech Connect (OSTI)

    J. Vernon Cole; Abhra Roy; Ashok Damle; Hari Dahr; Sanjiv Kumar; Kunal Jain; Ned Djilai

    2012-10-02T23:59:59.000Z

    Water management in Proton Exchange Membrane, PEM, Fuel Cells is challenging because of the inherent conflicts between the requirements for efficient low and high power operation. Particularly at low powers, adequate water must be supplied to sufficiently humidify the membrane or protons will not move through it adequately and resistance losses will decrease the cell efficiency. At high power density operation, more water is produced at the cathode than is necessary for membrane hydration. This excess water must be removed effectively or it will accumulate in the Gas Diffusion Layers, GDLs, between the gas channels and catalysts, blocking diffusion paths for reactants to reach the catalysts and potentially flooding the electrode. As power density of the cells is increased, the challenges arising from water management are expected to become more difficult to overcome simply due to the increased rate of liquid water generation relative to fuel cell volume. Thus, effectively addressing water management based issues is a key challenge in successful application of PEMFC systems. In this project, CFDRC and our partners used a combination of experimental characterization, controlled experimental studies of important processes governing how water moves through the fuel cell materials, and detailed models and simulations to improve understanding of water management in operating hydrogen PEM fuel cells. The characterization studies provided key data that is used as inputs to all state-of-the-art models for commercially important GDL materials. Experimental studies and microscopic scale models of how water moves through the GDLs showed that the water follows preferential paths, not branching like a river, as it moves toward the surface of the material. Experimental studies and detailed models of water and airflow in fuel cells channels demonstrated that such models can be used as an effective design tool to reduce operating pressure drop in the channels and the associated costs and weight of blowers and pumps to force air and hydrogen gas through the fuel cell. Promising improvements to materials structure and surface treatments that can potentially aid in managing the distribution and removal of liquid water were developed; and improved steady-state and freeze-thaw performance was demonstrated for a fuel cell stack under the self-humidified operating conditions that are promising for stationary power generation with reduced operating costs.

  8. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

  9. TRANSPORTATION Annual Report

    E-Print Network [OSTI]

    Minnesota, University of

    2003 CENTER FOR TRANSPORTATION STUDIES Annual Report #12;Center for Transportation Studies University of Minnesota 200 Transportation and Safety Building 511 Washington Avenue S.E. Minneapolis, MN publication is a report of transportation research, education, and outreach activities for the period July

  10. Transportation Analysis, Modeling, and Simulation (TAMS) Application

    E-Print Network [OSTI]

    Transportation Analysis, Modeling, and Simulation (TAMS) Application Center for Transportation Passenger Flows Supply Chain Efficiency Transportation: Energy Environment Safety Security Vehicle Technologies T he Center for Transportation Analysis (CTA) TAMS application is a web-based tool that supports

  11. A high integrity transportable supercompactor

    SciTech Connect (OSTI)

    Sims, J.; Schmidt, G.

    1993-12-31T23:59:59.000Z

    Current transportable equipment produced to utilize high force compaction to reduce the overall volume of drums containing solid radioactive material prior to disposal, were originally designed to standards which will eventually become obsolete. At the time these machines were produced, they were state-of-the-art, but are now indicating their weaknesses in operational and safety aspects. This paper formulates a concept for a Transportable Supercompactor for handling alpha and beta/gamma bearing wastes, low operator dose uptake, contamination and radiation control systems, liquids collection, the maintenance demands of a contained press, etc., taking into account the latest technical and safety considerations. The possibility of using the concept as a skid mounted fixed Supercompactor is also reviewed in this paper.

  12. DOE Order Self Study Modules - DOE O 460.1C Packaging and Transportation Safety and DOE O 460.2A Departmental Materials Transportation and Packaging Management

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office of Policy, OAPM |TRU WasteAdministrator |20.1C Briefing

  13. Safety evaluation for packaging (onsite) SERF cask

    SciTech Connect (OSTI)

    Edwards, W.S.

    1997-10-24T23:59:59.000Z

    This safety evaluation for packaging (SEP) documents the ability of the Special Environmental Radiometallurgy Facility (SERF) Cask to meet the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B quantities (up to highway route controlled quantities) of radioactive material within the 300 Area of the Hanford Site. This document shall be used to ensure that loading, tie down, transport, and unloading of the SERF Cask are performed in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required.

  14. Design and optimization of a multi-particle accelerator beam transport and delivery system for material irradiation in nuclear and fusion science

    E-Print Network [OSTI]

    Sordelet, Tyler Christopher

    2012-01-01T23:59:59.000Z

    A beam delivery and transport system were designed for the use in MIT Materials Test Facility (M2TF). The purpose of this beam delivery system was to design a 36 MeV Proton Cyclotron for DPA accumulation and a 100 MeV ...

  15. Incompatible Chemicals The following list is to be used only as a general guideline. Please refer to your Material Safety

    E-Print Network [OSTI]

    Slatton, Clint

    , butane, methane, propane(or other petroleum gases), hydrogen, sodium carbide, benzene, finely divided other chemicals Hydrocarbons (such as butane, propane, benzene) Fluorine, chlorine, bromine, chromic) Tellurides Reducing Agents #12;CHEMICAL STORAGE GUIDELINES STORE MATERIALS OUTLINED BY BOXES SEPARATELY

  16. Alternative p-doped hole transport material for low operating voltage and high efficiency organic light-emitting diodes

    SciTech Connect (OSTI)

    Murawski, Caroline, E-mail: caroline.murawski@iapp.de; Fuchs, Cornelius; Hofmann, Simone; Leo, Karl [Institut für Angewandte Photophysik, Technische Universität Dresden, George-Bähr-Str. 1, 01062 Dresden (Germany); Gather, Malte C. [Institut für Angewandte Photophysik, Technische Universität Dresden, George-Bähr-Str. 1, 01062 Dresden (Germany); SUPA, School of Physics and Astronomy, University of St Andrews, North Haugh, St Andrews, KY16 9SS Scotland (United Kingdom)

    2014-09-15T23:59:59.000Z

    We investigate the properties of N,N?-[(Diphenyl-N,N?-bis)9,9,-dimethyl-fluoren-2-yl]-benzidine (BF-DPB) as hole transport material (HTL) in organic light-emitting diodes (OLEDs) and compare BF-DPB to the commonly used HTLs N,N,N?,N?-tetrakis(4-methoxyphenyl)-benzidine (MeO-TPD), 2,2?,7,7?-tetrakis(N,N?-di-p-methylphenylamino)-9,9?-spirobifluorene (Spiro-TTB), and N,N?-di(naphtalene-1-yl)-N,N?-diphenylbenzidine (NPB). The influence of 2,2?-(perfluoronaphthalene-2,6-diylidene)dimalononitrile (F6-TCNNQ p-dopant) concentration in BF-DPB on the operation voltage and efficiency of red and green phosphorescent OLEDs is studied; best results are achieved at 4?wt. % doping. Without any light extraction structure, BF-DPB based red (green) OLEDs achieve a luminous efficacy of 35?.1?lm/W (74?.0?lm/W) at 1000?cd/m{sup 2} and reach a very high brightness of 10?000 cd/m{sup 2} at a very low voltage of 3.2 V (3.1 V). We attribute this exceptionally low driving voltage to the high ionization potential of BF-DPB which enables more efficient hole injection from BF-DPB to the adjacent electron blocking layer. The high efficiency and low driving voltage lead to a significantly lower luminous efficacy roll-off compared to the other compounds and render BF-DPB an excellent HTL material for highly efficient OLEDs.

  17. Transportation of medical isotopes

    SciTech Connect (OSTI)

    Nielsen, D.L.

    1997-11-19T23:59:59.000Z

    A Draft Technical Information Document (HNF-1855) is being prepared to evaluate proposed interim tritium and medical isotope production at the Fast Flux Test Facility (FFTF). This assessment examines the potential health and safety impacts of transportation operations associated with the production of medical isotopes. Incident-free and accidental impacts are assessed using bounding source terms for the shipment of nonradiological target materials to the Hanford Site, the shipment of irradiated targets from the FFTF to the 325 Building, and the shipment of medical isotope products from the 325 Building to medical distributors. The health and safety consequences to workers and the public from the incident-free transportation of targets and isotope products would be within acceptable levels. For transportation accidents, risks to works and the public also would be within acceptable levels. This assessment is based on best information available at this time. As the medical isotope program matures, this analysis will be revised, if necessary, to support development of a final revision to the Technical Information Document.

  18. Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory. Volume 2, Appendices

    SciTech Connect (OSTI)

    Crandall, R.S.; Nelson, B.P.; Moskowitz, P.D.; Fthenakis, V.M.

    1992-07-01T23:59:59.000Z

    To ensure the continued safety of SERI`s employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMS). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance. This document contains the appendices to the NREL safety analysis report.

  19. Materials

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

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

  20. RESEARCH SAFETY RADIATION SAFETY

    E-Print Network [OSTI]

    and Communications Manager (951) 827-6303 janette.ducut@ucr.edu Beiwei Tu, MS, CIH, CSP Safety and Industrial Hygiene

  1. Improving Transportation Safety Through Accident

    E-Print Network [OSTI]

    Minnesota, University of

    ;10! Investigative Groups ·" Highway Factors & Bridge Construction ·" Bridge Design ·" Witness ·" Survival accidents. ·" Major Railroad accidents. ·" Major Pipeline accidents. ·" Major marine accidents of the U10 gusset plates, due to a design error by the bridge design firm . . . Contributing to the design

  2. The Safety Data Sheet, or SDS, is written or printed material used to convey the hazards of a hazardous chemical product. It contains 16 sections of important chemical information, including

    E-Print Network [OSTI]

    The Safety Data Sheet, or SDS, is written or printed material used to convey the hazards of a hazardous chemical product. It contains 16 sections of important chemical information, including: Chemical characteristics; Physical and health hazards, including relevant exposure limits; Precautions for safe handling

  3. Automated Transportation Management System (ATMS) Software Project Management Plan (SPMP). Revision 2

    SciTech Connect (OSTI)

    Weidert, R.S.

    1995-05-26T23:59:59.000Z

    As a cabinet level federal agency with a diverse range of missions and an infrastructure spanning the United States, the US Department of Energy (DOE) has extensive freight transportation requirements. Performance and management of this freight activity is a critical function. DOE`s Transportation Management Division (TMD) has an agency-wide responsibility for overseeing transportation activities. Actual transportation operations are handled by government or contractor staff at the field locations. These staff have evolved a diverse range of techniques and procedures for performing transportation functions. In addition to minimizing the economic impact of transportation on programs, facility transportation staff must be concerned with the increasingly complex task of complying with complex shipment safety regulations. Maintaining the department`s safety record for shipping hazardous and radioactive materials is a primary goal. Use of automation to aid transportation functions is not widespread within DOE, though TMD has a number of software systems designed to gather and analyze data pertaining to field transportation activities. These systems are not integrated. Historically, most field facilities have accomplished transportation-related tasks manually or with minimal computer assistance. At best, information and decision support systems available to transportation staffs within the facilities are fragmented. In deciding where to allocate resources for automation, facility managers have not tended to give the needs of transportation departments a high priority. This diversity causes TMD significant difficulty in collecting data for use in managing department-wide transportation activities.

  4. CONSTRUCTION SAFETY MANUAL ADMINISTRATIVE POLICIES

    E-Print Network [OSTI]

    Knowles, David William

    Revised 06/10 10.1 Subcontractor Safety Policy 10.2 Scope 10.2.1 General 10.2.2 Department of Energy 10 the integration of safety management into all construction processes. Project managers, construction managers.7 Engineered Protective Systems 10.8 Procurement of Hazardous Material 10.9 Safety Training and Education 10

  5. Breaking symmetries in ordered materials : spin polarized light transport in magnetized noncentrosymmetric 1D photonic crystals, and photonic gaps and fabrication of quasiperiodic structured materials from interference lithography

    E-Print Network [OSTI]

    Bita, Ion

    2006-01-01T23:59:59.000Z

    Effects of breaking various symmetries on optical properties in ordered materials have been studied. Photonic crystals lacking space-inversion and time-reversal symmetries were shown to display nonreciprocal dispersion ...

  6. Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

    SciTech Connect (OSTI)

    Estrella, R.

    1994-10-01T23:59:59.000Z

    Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

  7. BIOLOGICAL SAFETY POLICY PROGRAM TOPICS

    E-Print Network [OSTI]

    Fang-Yen, Christopher

    research protocols involving hazardous materials, reviews construction design for safety features with or near biologically hazardous materials (infectious agents, biohazards or recombinant DNA). 1.3 "Infectious waste" or "biohazardous waste" is defined by the Pennsylvania Department of Environmental

  8. __________________________________ Environment, Health, & Safety ________________________________ Training Program

    E-Print Network [OSTI]

    Eisen, Michael

    commercial drivers license endorsement to transport radioactive or hazardous waste. Course Objectives: After to transport Radioactive materials to an offsite location. Recall who is allowed to prepare and package radioactive materials for delivery to an offsite locations Select an appropriate vehicle for transporting

  9. Safety analysis report for packaging (onsite) doorstop samplecarrier system

    SciTech Connect (OSTI)

    Obrien, J.H.

    1997-02-24T23:59:59.000Z

    The Doorstop Sample Carrier System consists of a Type B certified N-55 overpack, U.S. Department of Transportation (DOT) specification or performance-oriented 208-L (55-gal) drum (DOT 208-L drum), and Doorstop containers. The purpose of the Doorstop Sample Carrier System is to transport samples onsite for characterization. This safety analysis report for packaging (SARP) provides the analyses and evaluation necessary to demonstrate that the Doorstop Sample Carrier System meets the requirements and acceptance criteria for both Hanford Site normal transport conditions and accident condition events for a Type B package. This SARP also establishes operational, acceptance, maintenance, and quality assurance (QA) guidelines to ensure that the method of transport for the Doorstop Sample Carrier System is performed safely in accordance with WHC-CM-2-14, Hazardous Material Packaging and Shipping.

  10. Electric transport properties of the pentatelluride materials HfTe{sub 5} and ZrTe{sub 5}

    SciTech Connect (OSTI)

    Tritt, T.M.; Wilson, M.L.; Littleton, R.L. [and others

    1997-07-01T23:59:59.000Z

    The authors have measured the resistivity and thermopower of single crystals as well as polycrystalline pressed powders of the low-dimensional pentatelluride materials: HfTe{sub 5} and ZrTe{sub 5}. They have performed these measurements as a function of temperature between 5K and 320K. In the single crystals there is a peak in the resistivity for both materials at a peak temperature, T{sub p} where T{sub p} {approx} 80K for HfTe{sub 5} and T{sub p} {approx} 145K for ZrTe{sub 5}. Both materials exhibit a large p-type thermopower around room temperature which undergoes a change to n-type below the peak. These data are similar to behavior observed previously in these materials. They have also synthesized pressed powders of polycrystalline pentatelluride materials, HfTe{sub 5} and ZrTe{sub 5}. They have measured the resistivity and thermopower of these polycrystalline materials as a function of temperature between 5K and 320K. For the polycrystalline material, the room temperature thermopower for each of these materials is relatively high, +95 {micro}V/K and +65 {micro}V/K for HfTe{sub 5} and ZrTe{sub 5}, respectively. These values compare closely to thermopower values for single crystals of these materials. At 77 K, the thermopower is +55 {micro}V/K for HfTe{sub 5} and +35 {micro}V/K for ZrTe{sub 5}. In fact, the thermopower for the polycrystals decreases monotonically with temperature to T {approx} 5K, thus exhibiting p-type behavior over the entire range of temperature. As expected, the resistivity for the polycrystals is higher than the single crystal material, with values of 430 m{Omega}-cm and 24 m{Omega}-cm for HfTe{sub 5} and ZrTe{sub 5} respectively, compared to single crystal values of 0.35 m{Omega}-cm (HfTe{sub 5}) and 1.0 m{Omega}-cm (ZrTe{sub 5}). The authors have found that the peak in the resistivity evident in both single crystal materials is absent in these polycrystalline materials. They will discuss these materials in relation to their potential as candidates for thermoelectric applications.

  11. Materials Science and Materials Chemistry for Large Scale Electrochemi...

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

    Science and Materials Chemistry for Large Scale Electrochemical Energy Storage: From Transportation to Electrical Grid Materials Science and Materials Chemistry for Large Scale...

  12. Primary system fission product release and transport: A state-of-the-art report to the committee on the safety of nuclear installations

    SciTech Connect (OSTI)

    Wright, A.L. [Oak Ridge National Lab., TN (United States)

    1994-06-01T23:59:59.000Z

    This report presents a summary of the status of research activities associated with fission product behavior (release and transport) under severe accident conditions within the primary systems of water-moderated and water-cooled nuclear reactors. For each of the areas of fission product release and fission product transport, the report summarizes relevant information on important phenomena, major experiments performed, relevant computer models and codes, comparisons of computer code calculations with experimental results, and general conclusions on the overall state of the art. Finally, the report provides an assessment of the overall importance and knowledge of primary system release and transport phenomena and presents major conclusions on the state of the art.

  13. Transportation Faculty Position The Department of Civil and Environmental Engineering at the University of Washington continues

    E-Print Network [OSTI]

    Transportation Faculty Position The Department of Civil and Environmental Engineering of this action, applications are being solicited for a full-time, tenure-track faculty position in transportation in traffic operations, freight transportation, transportation planning, transportation safety

  14. Facility Safety

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

    2000-11-20T23:59:59.000Z

    The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

  15. A monthly report on transportation research, education, and outreach activities at the University of Minnesota September 2007 Rural safety institute.............. 2

    E-Print Network [OSTI]

    Minnesota, University of

    A monthly report on transportation research, education, and outreach activities at the University-624-3708, cceconf5@umn.edu. Updates are posted on the Oberstar Forum Web page at www.cts.umn.edu/oberstarforum. CTS

  16. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16T23:59:59.000Z

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  17. Safety analysis report for packaging, Oak Ridge Y-12 Plant, model DC-1 package with HEU oxide contents. Change pages for Rev.1

    SciTech Connect (OSTI)

    NONE

    1995-01-18T23:59:59.000Z

    This Safety Analysis Report for Packaging for the Oak Ridge Y-12 Plant for the Model DC-1 package with highly enriched uranium (HEU) oxide contents has been prepared in accordance with governing regulations form the Nuclear Regulatory Commission and the Department of Transportation and orders from the Department of energy. The fundamental safety requirements addressed by these regulations and orders pertain to the containment of radioactive material, radiation shielding, and nuclear subcriticality. This report demonstrates how these requirements are met.

  18. August 2004 Radiation Safety Manual Section 5 -Training

    E-Print Network [OSTI]

    Wilcock, William

    August 2004 Radiation Safety Manual Section 5 - Training UW Environmental Health and Safety Page 5-1 Section 5 Radiation Safety Training Contents A. Individuals Directly Using Radioactive Materials..........................................5-1 1. Regulations for Training.................................................................. 5

  19. Electronic transport in Lithium Nickel Manganese Oxide, a high-voltage cathode material for Lithium-Ion batteries

    E-Print Network [OSTI]

    Ransil, Alan Patrick Adams

    2013-01-01T23:59:59.000Z

    Potential routes by which the energy densities of lithium-ion batteries may be improved abound. However, the introduction of Lithium Nickel Manganese Oxide (LixNi1i/2Mn3/2O4, or LNMO) as a positive electrode material appears ...

  20. Secure Transportation Management

    SciTech Connect (OSTI)

    Gibbs, P. W. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2014-10-15T23:59:59.000Z

    Secure Transport Management Course (STMC) course provides managers with information related to procedures and equipment used to successfully transport special nuclear material. This workshop outlines these procedures and reinforces the information presented with the aid of numerous practical examples. The course focuses on understanding the regulatory framework for secure transportation of special nuclear materials, identifying the insider and outsider threat(s) to secure transportation, organization of a secure transportation unit, management and supervision of secure transportation units, equipment and facilities required, training and qualification needed.

  1. Safety of magnetic fusion facilities: Requirements

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This Standard identifies safety requirements for magnetic fusion facilities. Safety functions are used to define outcomes that must be achieved to ensure that exposures to radiation, hazardous materials, or other hazards are maintained within acceptable limits. Requirements applicable to magnetic fusion facilities have been derived from Federal law, policy, and other documents. In addition to specific safety requirements, broad direction is given in the form of safety principles that are to be implemented and within which safety can be achieved.

  2. Safety Evaluation Report: Development of a Novel Efficient Solid-Oxide Hybrid for Co-generation of Hydrogen and Electricity Using Nearby Resources for Local Applications, Materials and Systems Research, Inc. (MSRI), Salt Lake City, UT, February 17, 2009

    SciTech Connect (OSTI)

    Barilo, Nick F.; Frikken, Don; Skolnik, Edward G.; Weiner, Steven C.

    2009-07-16T23:59:59.000Z

    Following a telephone interview with Materials and Systems Research, Inc. (MSRI) by members of the Hydrogen Safety Panel on December 4, 2008, a safety review team was dispatched to Salt Lake City, UT to perform a site-visit review. The major topic of concern was the presence of a hydrogen storage and dispensing shed on the MSRI premises close to both its own laboratory/office building and to the adjoining property. The metal shed contains 36 cylinders (two 18-cylinder "pods") of hydrogen all connected to a common manifold and used to supply hydrogen to a U.S. Department of Energy (DOE) fuel cell project plus several other projects using an entire pod as a common supply. In busy times, MSRI uses and replaces one pod per week. As a result of the site visit, the safety review team has raised some concern with the shed’s location, design, use, and safety features as well as other components of the facility, including the laboratory area.

  3. Transportation Energy Futures

    E-Print Network [OSTI]

    DeLuchi, Mark A.

    1989-01-01T23:59:59.000Z

    TRANSPORTATION ment of Oil Shale Technology. Washing- ton,interest and investments in oil shale, ethanol, coal liquidsbiomass materials, coal, oil shale, tar sands, natural gas,

  4. Determination of the transport and change in composition of fluorescent materials in hydrologic systems by use of EEM spectroscopy

    SciTech Connect (OSTI)

    Goldberg, M.C. (Geological Survey, Lakewood, CO (USA))

    1990-01-01T23:59:59.000Z

    EEM spectra are sufficiently selective to allow fluorescence pattern characterization of the organic load of a river at a given location and to follow, qualitatively, the changes that ensue in that load as it moves in the river. By comparing the patterns of the load to specific materials such as illustrated by the Suwannee River pattern, humic acid fraction, comparison; it is possible to label major fluorescing components and to discern their appearance and disappearance as a function of location.

  5. Facility Safety

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

    2005-12-22T23:59:59.000Z

    The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

  6. Biological Safety

    Broader source: Energy.gov [DOE]

    The DOE's Biological Safety Program provides a forum for the exchange of best practices, lessons learned, and guidance in the area of biological safety. This content is supported by the Biosurety Executive Team. The Biosurety Executive Team is a DOE-chartered group. The DOE Office of Worker Safety and Health Policy provides administrative support for this group. The group identifies biological safety-related issues of concern to the DOE and pursues solutions to issues identified.

  7. Facility Safety

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

    1995-10-13T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

  8. Facility Safety

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

    2005-12-22T23:59:59.000Z

    This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

  9. Facility Safety

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

    2012-12-04T23:59:59.000Z

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

  10. Nuclear explosive safety study process

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    Nuclear explosives by their design and intended use require collocation of high explosives and fissile material. The design agencies are responsible for designing safety into the nuclear explosive and processes involving the nuclear explosive. The methodology for ensuring safety consists of independent review processes that include the national laboratories, Operations Offices, Headquarters, and responsible Area Offices and operating contractors with expertise in nuclear explosive safety. A NES Study is an evaluation of the adequacy of positive measures to minimize the possibility of an inadvertent or deliberate unauthorized nuclear detonation, high explosive detonation or deflagration, fire, or fissile material dispersal from the pit. The Nuclear Explosive Safety Study Group (NESSG) evaluates nuclear explosive operations against the Nuclear Explosive Safety Standards specified in DOE O 452.2 using systematic evaluation techniques. These Safety Standards must be satisfied for nuclear explosive operations.

  11. Langevin and Fokker-Planck analyses of inhibited molecular passing processes controlling transport and reactivity in nanoporous materials

    SciTech Connect (OSTI)

    Wang, Chi-Jen [Ames Laboratory; Ackerman, David M. [Ames Laboratory; Slowing, Igor I. [Ames Laboratory; Evans, James W. [Ames Laboratory

    2014-07-14T23:59:59.000Z

    Inhibited passing of reactant and product molecules within the linear pores of nanoporous catalytic materials strongly reduces reactivity. The dependence of the passing propensity P on pore radius R is analyzed utilizing Langevin dynamics to account for solvent effects. We find that P?(R?Rc)?, where passing is sterically blocked for R?Rc, with ? below the transition state theory value. Deeper insight comes from analysis of the corresponding high-dimensional Fokker-Planck equation, which facilitates an effective small-P approximation, and dimensional reduction enabling utilization of conformal mapping ideas. We analyze passing for spherical molecules and also assess the effect of rotational degrees of freedom for elongated molecules.

  12. Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask

    SciTech Connect (OSTI)

    Romano, T.

    1997-09-29T23:59:59.000Z

    This safety evaluation for packaging (SEP) provides the evaluation necessary to demonstrate that the Plutonium Recycle Test Reactor (PRTR) Graphite Cask meets the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B, fissile, non-highway route controlled quantities of radioactive material within the 300 Area of the Hanford Site. The scope of this SEP includes risk, shieldling, criticality, and.tiedown analyses to demonstrate that onsite transportation safety requirements are satisfied. This SEP also establishes operational and maintenance guidelines to ensure that transport of the PRTR Graphite Cask is performed safely in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required.

  13. CCB Laboratory Safety Orientation Checklist Laboratory Safety Training Review

    E-Print Network [OSTI]

    Heller, Eric

    ) Location and use of hazardous waste accumulation areas Location of Safety Data hazardous materials, equipment, or processes that pertain to the research program and meeting area Location of fire extinguishers and closest pull station Location

  14. Recent Theoretical Results for Advanced Thermoelectric Materials...

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

    Materials Recent Theoretical Results for Advanced Thermoelectric Materials Transport theory and first principles calculations applied to oxides, chalcogenides and skutterudite...

  15. Final Safety Evaluation Report to license the construction and operation of a facility to receive, store, and dispose of 11e.(2) byproduct material near Clive, Utah (Docket No. 40-8989)

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    The Final Safety Evaluation Report (FSER) summarizes the US Nuclear Regulatory Commission (NRC) staff`s review of Envirocare of Utah, Inc.`s (Envirocare`s) application for a license to receive, store, and dispose of uranium and thorium byproduct material (as defined in Section 11e.(2) of the Atomic Energy Act of 1954, as amended) at a site near Clive, Utah. Envirocare proposes to dispose of high-volume, low-activity Section 11e.(2) byproduct material in separate earthen disposal cells on a site where the applicant currently disposes of naturally occurring radioactive material (NORM), low-level waste, and mixed waste under license by the Utah Department of Environmental Quality. The NRC staff review of the December 23, 1991, license application, as revised by page changes dated July 2 and August 10, 1992, April 5, 7, and 10, 1993, and May 3, 6, 7, 11, and 21, 1993, has identified open issues in geotechnical engineering, water resources protection, radon attenuation, financial assurance, and radiological safety. The NRC will not issue a license for the proposed action until Envirocare adequately resolves these open issues.

  16. Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Quarterly progress report, April-June 1983. Volume 2

    SciTech Connect (OSTI)

    Shack, W.J.

    1984-06-01T23:59:59.000Z

    The progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

  17. Materials Science and Technology Division light-water-reactor safety research program. Quarterly progress report, July-September 1983. Volume 3

    SciTech Connect (OSTI)

    Not Available

    1984-07-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors (reported elsewhere), Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems (reported elsewhere).

  18. Transportation Decision Support Systems Oak Ridge National Laboratory

    E-Print Network [OSTI]

    Transportation Decision Support Systems Oak Ridge National Laboratory managed by UT-Battelle, LLC Passenger Flows Supply Chain Efficiency Transportation: Energy Environment Safety Security Vehicle and implementation of automated transportation decision support models for the scheduling and routing of cargo

  19. Packaging and Transfer of Materials of National Security Interest Manual

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

    2000-09-29T23:59:59.000Z

    This Technical Manual establishes requirements for operational safety controls for onsite operations and provides Department of Energy (DOE) technical safety requirements and policy objectives for development of an Onsite Packaging and Transfer Program, pursuant to DOE O 461.1A, Packaging and Transfer or Transportation of Materials of National Security Interest. The DOE contractor must document this program in its Onsite Packaging and Transfer Manual/Procedures. Admin Chg 1, 7-26-05. Certified 2-2-07. Canceled by DOE O 461.2.

  20. Safety and Training | Advanced Photon Source

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

    Form Reference Material APS domain only Configuration Control Incidents and Follow-ups Facility Hazard Analysis Glove Selection | Safety Shoe Mobile LOM Shop Usage Recycling:...

  1. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J. (Clairton, PA)

    1980-03-11T23:59:59.000Z

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature.

  2. HIGHWAY INFRASTRUCTURE FOCUS AREA NEXT-GENERATION INFRASTRUCTURE MATERIALS VOLUME I - TECHNICAL PROPOSAL & MANAGEMENTENHANCEMENT OF TRANSPORTATION INFRASTRUCTURE WITH IRON-BASED AMORPHOUS-METAL AND CERAMIC COATINGS

    SciTech Connect (OSTI)

    Farmer, J C

    2007-12-04T23:59:59.000Z

    The infrastructure for transportation in the United States allows for a high level of mobility and freight activity for the current population of 300 million residents, and several million business establishments. According to a Department of Transportation study, more than 230 million motor vehicles, ships, airplanes, and railroads cars were used on 6.4 million kilometers (4 million miles) of highways, railroads, airports, and waterways in 1998. Pipelines and storage tanks were considered to be part of this deteriorating infrastructure. The annual direct cost of corrosion in the infrastructure category was estimated to be approximately $22.6 billion in 1998. There were 583,000 bridges in the United States in 1998. Of this total, 200,000 bridges were steel, 235,000 were conventional reinforced concrete, 108,000 bridges were constructed using pre-stressed concrete, and the balance was made using other materials of construction. Approximately 15 percent of the bridges accounted for at this point in time were structurally deficient, primarily due to corrosion of steel and steel reinforcement. Iron-based amorphous metals, including SAM2X5 (Fe{sub 49.7}Cr{sub 17.7}Mn{sub 1.9}Mo{sub 7.4}W{sub 1.6}B{sub 15.2}C{sub 3.8}Si{sub 2.4}) and SAM1651 (Fe{sub 48}Mo{sub 14}Cr{sub 15}Y{sub 2}C{sub 15}B{sub 6}) have been developed, and have very good corrosion resistance. These materials have been prepared as a melt-spun ribbons, as well as gas atomized powders and thermal-spray coatings. During electrochemical testing in several environments, including seawater at 90 C, the passive film stabilities of these materials were found to be comparable to that of more expensive high-performance alloys, based on electrochemical measurements of the passive film breakdown potential and general corrosion rates. These materials also performed very well in standard salt fog tests. Chromium (Cr), molybdenum (Mo) and tungsten (W) provided corrosion resistance, and boron (B) enabled glass formation. The high boron content of this particular amorphous metal made it an effective neutron absorber, and suitable for criticality control applications. These amorphous alloys appear to maintain their corrosion resistance up to the glass transition temperature. Visionary research is proposed to extend the application of corrosion-resistant iron-based amorphous metal coatings, and variants of these coatings, to protection of the Nation's transportation infrastructure. Specific objectives of the proposed work are: (1) fabrication of appropriate test samples for evaluation of concept; (2) collection of production and test data for coated steel reinforcement bars, enabling systematic comparison of various coating options, based upon performance and economic considerations; and (3) construction and testing of concrete structures with coated steel reinforcement bars, thereby demonstrating the value of amorphous-metal coatings. The benefits of ceramic coatings as thermal barriers will also be addressed.

  3. Enhancing the safety of tailings management facilities

    SciTech Connect (OSTI)

    Meggyes, T.; Niederleithinger, E.; Witt, K.J.; Csovari, M.; Kreft-Burman, K.; Engels, J.; McDonald, C.; Roehl, K.E. [BAM, Berlin (Germany). Federal Institute for Material Research & Testing

    2008-07-01T23:59:59.000Z

    Unsafe tailings management facilities (TMFs) have caused serious accidents in Europe threatening human health/life and the environment. While advanced design, construction and management procedures are available, their implementation requires greater emphasis. An integrated research project funded by the European Union was carried out between 2002 and 2005 with the overall goal of improving the safety of TMFs (Sustainable Improvement in Safety of Tailings Facilities - TAILSAFE, http://www.tailsafe.com/). The objective of TAILSAFE was to develop and apply methods of parameter evaluation and measurement for the assessment and improvement of the safety state of tailings facilities, with particular attention to the stability of tailings dams and slurries, the special risks inherent when such materials include toxic or hazardous wastes, and authorization and management procedures for tailings facilities. Aspects of tailings facilities design, water management and slurry transport, non-destructive and minimally intrusive testing methods, monitoring and the application of sensors, intervention and remediation options were considered in TAILSAFE. A risk reduction framework (the TAILSAFE Parameter Framework) was established to contribute to the avoidance of catastrophic accidents and hazards from tailings facilities. Tailings from the mining and primary processing of metals, minerals and coal were included within the scope of TAILSAFE. The project focused on the avoidance of hazards by developing procedures and methods for investigating and improving the stability of tailings dams and tailings bodies.

  4. Safety evaluation for packaging (onsite) product removal can containers

    SciTech Connect (OSTI)

    Boettger, J.S.

    1997-04-29T23:59:59.000Z

    This safety evaluation for packaging allows the transport of nine Product Removal (PR) Cans with their Containers from the PUREX Facility to the Plutonium Finishing Plant.

  5. Revised 4/15/2002 _____________________________ Environment, Health, & Safety _________ __________________

    E-Print Network [OSTI]

    Eisen, Michael

    Revised 4/15/2002 _____________________________ Environment, Health, & Safety, medium, and large dewars o Recognize policy concerning transporting dewars in an elevator Written Exam

  6. Selected Failure Rate Values from ITER Safety Assessment

    Office of Scientific and Technical Information (OSTI)

    NFPA National Fire Protection Association NSSR Non-site Specific Safety Report OREDA Offshore Reliability Data Pa Pascal PHTS Primary Heat Transport System PRA Probabilistic...

  7. Spent Fuel Transportation Package Performance Study - Experimental Design Challenges

    SciTech Connect (OSTI)

    Snyder, A. M.; Murphy, A. J.; Sprung, J. L.; Ammerman, D. J.; Lopez, C.

    2003-02-25T23:59:59.000Z

    Numerous studies of spent nuclear fuel transportation accident risks have been performed since the late seventies that considered shipping container design and performance. Based in part on these studies, NRC has concluded that the level of protection provided by spent nuclear fuel transportation package designs under accident conditions is adequate. [1] Furthermore, actual spent nuclear fuel transport experience showcase a safety record that is exceptional and unparalleled when compared to other hazardous materials transportation shipments. There has never been a known or suspected release of the radioactive contents from an NRC-certified spent nuclear fuel cask as a result of a transportation accident. In 1999 the United States Nuclear Regulatory Commission (NRC) initiated a study, the Package Performance Study, to demonstrate the performance of spent fuel and spent fuel packages during severe transportation accidents. NRC is not studying or testing its current regulations, a s the rigorous regulatory accident conditions specified in 10 CFR Part 71 are adequate to ensure safe packaging and use. As part of this study, NRC currently plans on using detailed modeling followed by experimental testing to increase public confidence in the safety of spent nuclear fuel shipments. One of the aspects of this confirmatory research study is the commitment to solicit and consider public comment during the scoping phase and experimental design planning phase of this research.

  8. Special Clinical Staff Training Specialized Radiation Safety

    E-Print Network [OSTI]

    Baker, Chris I.

    Special Clinical Staff Training Specialized Radiation Safety Training Courses for: Nurses these training courses by contacting the Radiation Safety Training Office at 496-2255. Radiation Safety for Clinical Center Employees A great introduction to radiation and radioactive material for new Clinical

  9. Safety Analysis Report for Packaging: The unirradiated fuel shipping container USA/9853/AF

    SciTech Connect (OSTI)

    Not Available

    1991-10-18T23:59:59.000Z

    The HFBR Unirradiated Fuel Shipping Container was designed and fabricated at the Oak Ridge National Laboratory in 1978 for the transport of fuel for the High Flux Beam Reactor (HFBR) for Brookhaven National Laboratory. The package has been evaluated analytically, as well as the comparison to tests on similar packages, to demonstrate compliance with the applicable regulations governing packages in which radioactive and fissile materials are transported. The contents of this Safety Analysis Report for Packaging (SARP) are based on Regulatory Guide 7.9 (proposed Revision 2 - May 1986), 10 CFR Part 71, DOE Order 1540.2, DOE Order 5480.3, and 49 CFR Part 173.

  10. Impact of Fuel Failure on Criticality Safety of Used Nuclear Fuel

    SciTech Connect (OSTI)

    Marshall, William BJ J [ORNL] [ORNL; Wagner, John C [ORNL] [ORNL

    2012-01-01T23:59:59.000Z

    Commercial used nuclear fuel (UNF) in the United States is expected to remain in storage for considerably longer periods than originally intended (e.g., <40 years). Extended storage (ES) time and irradiation of nuclear fuel to high-burnup values (>45 GWd/t) may increase the potential for fuel failure during normal and accident conditions involving storage and transportation. Fuel failure, depending on the severity, can result in changes to the geometric configuration of the fuel, which has safety and regulatory implications. The likelihood and extent of fuel reconfiguration and its impact on the safety of the UNF is not well understood. The objective of this work is to assess and quantify the impact of fuel reconfiguration due to fuel failure on criticality safety of UNF in storage and transportation casks. This effort is primarily motivated by concerns related to the potential for fuel degradation during ES periods and transportation following ES. The criticality analyses consider representative UNF designs and cask systems and a range of fuel enrichments, burnups, and cooling times. The various failed-fuel configurations considered are designed to bound the anticipated effects of individual rod and general cladding failure, fuel rod deformation, loss of neutron absorber materials, degradation of canister internals, and gross assembly failure. The results quantify the potential impact on criticality safety associated with fuel reconfiguration and may be used to guide future research, design, and regulatory activities. Although it can be concluded that the criticality safety impacts of fuel reconfiguration during transportation subsequent to ES are manageable, the results indicate that certain configurations can result in a large increase in the effective neutron multiplication factor, k{sub eff}. Future work to inform decision making relative to which configurations are credible, and therefore need to be considered in a safety evaluation, is recommended.

  11. Management of Transuranic Contaminated Material

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

    1982-09-30T23:59:59.000Z

    To establish guidelines for the generation, treatment, packaging, storage, transportation, and disposal of transuranic (TRU) contaminated material.

  12. Safety study application guide. Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly {open_quotes}low{close_quotes}) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, {open_quotes}Technical Safety Requirements,{close_quotes} and 5480.23, {open_quotes}Nuclear Safety Analysis Reports.{close_quotes} A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis.

  13. Hazardous Material Security (Maryland)

    Broader source: Energy.gov [DOE]

    All facilities processing, storing, managing, or transporting hazardous materials must be evaluated every five years for security issues. A report must be submitted to the Department of the...

  14. LASER SAFETY POLICY MANUAL ENVIRONMENTAL HEALTH & SAFETY

    E-Print Network [OSTI]

    Houston, Paul L.

    LASER SAFETY POLICY MANUAL ISSUED BY ENVIRONMENTAL HEALTH & SAFETY OFFICE OF RADIOLOGICAL SAFETY and GEORGIA TECH LASER SAFETY COMMITTEE July 1, 2010 Revised July 31, 2012 #12;Laser Safety Program 1-1 #12;Laser Safety Policy Manual TABLE OF CONTENTS 1. POLICY AND SCOPE

  15. ENVIRONMENTAL HEALTH AND SAFETY GENERAL SAFETY MANUAL

    E-Print Network [OSTI]

    Maroncelli, Mark

    ENVIRONMENTAL HEALTH AND SAFETY GENERAL SAFETY MANUAL May 10, 2002 #12;i Acknowledgements Environmental Health and Safety gratefully acknowledges the assistance provided by the University Safety Council extremely helpful. #12;ii Environmental Health and Safety General Safety Manual Table of Contents Section

  16. Material transport method and apparatus

    DOE Patents [OSTI]

    Ramsey, J. Michael (Knoxville, TN); Ramsey, Roswitha S. (Knoxville, TN)

    2001-01-01T23:59:59.000Z

    An electrospray apparatus uses a microchannel formed in a microchip. Fluid is pumped through the channel to an outlet orifice using either hydraulic or electrokinetic means. An electrospray is generated by establishing a sufficient potential difference between the fluid at the outlet orifice and a target electrode spaced from the outlet orifice. Electrokinetic pumping is also utilized to provide additional benefits to microchip devices.

  17. Material transport method and apparatus

    DOE Patents [OSTI]

    Ramsey, J. Michael (Knoxville, TN); Ramsey, Roswitha S. (Knoxville, TN)

    2000-01-01T23:59:59.000Z

    An electrospray apparatus uses a microchannel formed in a microchip. Fluid is pumped through the channel to an outlet orifice using either hydraulic or electrokinetic means. An electrospray is generated by establishing a sufficient potential difference between the fluid at the outlet orifice and a target electrode spaced from the outlet orifice. Electrokinetic pumping is also utilized to provide additional benefits to microchip devices.

  18. Safety Bulletin

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

    in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and the...

  19. Facility Safety

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

    2002-05-20T23:59:59.000Z

    To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

  20. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, Ernest (Wilmette, IL)

    1986-01-01T23:59:59.000Z

    A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

  1. Passive Safety of the STAR-LM HLMC Natural Convection Reactor

    SciTech Connect (OSTI)

    Sienicki, James J. [Argonne National Laboratory, 9700 S. Cass Avenue Argonne, IL 60439 (United States); Petkov, Plamen V. [University of Illinois at Urbana Champaign, Urbana, IL 61801 (United States)

    2002-07-01T23:59:59.000Z

    The STAR-LM 300 to 400 MWt class modular, factory fabricated, fully transportable, proliferation resistant, autonomous, reactor system achieves passive safety by taking advantage of the intrinsic benefits of inert lead-bismuth eutectic heavy liquid metal coolant, 100+% natural circulation heat transport, a fast neutron spectrum core utilizing high thermal conductivity transuranic nitride fuel, redundant passive air cooling of the outside of the guard/containment vessel driven by natural circulation, and seismic isolation where required by site conditions. Postulated loss-of-heat sink without scram, overcooling without scram, and unprotected transient overpower accidents are analyzed for the 300 MWt STAR-LM design using a coupled thermal hydraulics-neutron kinetics plant dynamics analysis computer code. In all cases, STAR-LM is calculated to exhibit passive safety with peak cladding and coolant temperatures remaining within the existing database for lead-bismuth eutectic coolant and ferritic steel core materials. (authors)

  2. Rev: 04.2014 Page 1 of 2 Safety Training Matrix Safety Training Matrix

    E-Print Network [OSTI]

    Jalali. Bahram

    ? * will use pyrophorics, explosives or large quantities of flammables? * Shop Safety will use shop equipment? * Radiation Safety will handle radioactive materials? * will work with lasers? will work with X-Ray equipment EHS 16 New Radiation Worker Qualification (NRWQ) Annual EHS 5 Lab-Specific Safety Training ­ required

  3. Toolbox Safety Talk Ladder Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Health & Safety for recordkeeping. Slips, trips, and falls constitute the majority of general industry and construction worker injuries. Falls cause 15% of all accidental deaths, and are second only to motor vehicle

  4. Chemical Hazards and Safety Issues in Fusion Safety Design

    SciTech Connect (OSTI)

    Cadwallader, L.C. [Idaho National Engineering and Environmental Laboratory (United States)

    2003-09-15T23:59:59.000Z

    Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard.

  5. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  6. Work with Biological Materials

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

    Work with Biological Materials Print Planning A complete Experiment Safety Sheet (ESS) is required before work can be done at the ALS. This ESS is either a part of the proposal...

  7. Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation - 13042

    SciTech Connect (OSTI)

    Li, Zhian; Rahimi, Meraj; Tang, David; Aissa, Mourad; Flaganan, Michelle [U.S. Nuclear Regulatory Commission - NRC, Washington, DC 20555-0001 (United States)] [U.S. Nuclear Regulatory Commission - NRC, Washington, DC 20555-0001 (United States); Wagner, John C. [Oak Ridge National Laboratory (United States)] [Oak Ridge National Laboratory (United States)

    2013-07-01T23:59:59.000Z

    The recent experiments conducted by Argonne National Laboratory on high burnup fuel cladding material property show that the ductile to brittle transition temperature of high burnup fuel cladding is dependent on: (1) cladding material, (2) irradiation conditions, and (3) drying-storage histories (stress at maximum temperature) [1]. The experiment results also show that the ductile to brittle temperature increases as the fuel burnup increases. These results indicate that the current knowledge in cladding material property is insufficient to determine the structural performance of the cladding of high burnup fuel after it has been stored in a dry cask storage system for some time. The uncertainties in material property and the elevated ductile to brittle transition temperature impose a challenge to the storage cask and transportation packaging designs because the cask designs may not be able to rely on the structural integrity of the fuel assembly for control of fissile material, radiation source, and decay heat source distributions. The fuel may reconfigure during further storage and/or the subsequent transportation conditions. In addition, the fraction of radioactive materials available for release from spent fuel under normal condition of storage and transport may also change. The spent fuel storage and/or transportation packaging vendors, spent fuel shippers, and the regulator may need to consider this possible fuel reconfiguration and its impact on the packages' ability to meet the safety requirements of Part 72 and Part 71 of Title 10 of the Code of Federal Regulations. The United States Nuclear Regulatory Commission (NRC) is working with the scientists at Oak Ridge National Laboratory (ORNL) to assess the impact of fuel reconfiguration on the safety of the dry storage systems and transportation packages. The NRC Division of Spent Fuel Storage and Transportation has formed a task force to work on the safety and regulatory concerns in relevance to high burnup fuel storage and transportation. This paper discusses the staff's preliminary considerations on the safety implication of fuel reconfiguration with respect to nuclear safety (subcriticality control), radiation shielding, containment, the performance of the thermal functions of the packages, and the retrievability of the contents from regulatory perspective. (authors)

  8. NEW APPROACH TO ADDRESSING GAS GENERATION IN RADIOACTIVE MATERIAL PACKAGING

    SciTech Connect (OSTI)

    Watkins, R; Leduc, D; Askew, N

    2009-06-25T23:59:59.000Z

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

  9. Online Safety Monitoring Using Safety Modes Jeremie Guiochet, David Powell and Etienne Baudin

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    : transportation [3], space [4], medical systems [5], [6], civil engineering [7], nuclear power plants [8- functional robotic systems. We present an approach and a formalization of the process for determining safety by the monitored system. In practice, each safety mode is related to one or several functional modes

  10. Chemical Transport Policy Virginia Tech Chemistry Department

    E-Print Network [OSTI]

    Crawford, T. Daniel

    Chemical Transport Policy Virginia Tech Chemistry Department This policy was enacted. The purpose of this policy is to ensure the safety of personnel transporting chemicals and anyone who might be affected by a problem occurring during such transport. The policy also helps to shield stockroom personnel

  11. Transportation and Stationary Power

    E-Print Network [OSTI]

    ) is small. Previous feedback from industry has indicated that existing transportation fuel providers (oil for multiple fuel cell applications, including material handling equipment, backup power, and light- or heavy

  12. Criticality Safety Evaluation of a LLNL Training Assembly for Criticality Safety (TACS)

    SciTech Connect (OSTI)

    Heinrichs, D P

    2006-06-26T23:59:59.000Z

    Hands-on experimental training in the physical behavior of multiplying systems is one of ten key areas of training required for practitioners to become qualified in the discipline of criticality safety as identified in DOE-STD-1135-99, ''Guidance for Nuclear Criticality Safety Engineer Training and Qualification''. This document is a criticality safety evaluation of the training activities (or operations) associated with HS-3200, ''Laboratory Class for Criticality Safety''. These activities utilize the Training Assembly for Criticality Safety (TACS). The original intent of HS-3200 was to provide LLNL fissile material handlers with a practical hands-on experience as a supplement to the academic training they receive biennially in HS-3100, ''Fundamentals of Criticality Safety'', as required by ANSI/ANS-8.20-1991, ''Nuclear Criticality Safety Training''. HS-3200 is to be enhanced to also address the training needs of nuclear criticality safety professionals under the auspices of the NNSA Nuclear Criticality Safety Program.

  13. Gas Generation from Actinide Oxide Materials

    SciTech Connect (OSTI)

    George Bailey; Elizabeth Bluhm; John Lyman; Richard Mason; Mark Paffett; Gary Polansky; G. D. Roberson; Martin Sherman; Kirk Veirs; Laura Worl

    2000-12-01T23:59:59.000Z

    This document captures relevant work performed in support of stabilization, packaging, and long term storage of plutonium metals and oxides. It concentrates on the issue of gas generation with specific emphasis on gas pressure and composition. Even more specifically, it summarizes the basis for asserting that materials loaded into a 3013 container according to the requirements of the 3013 Standard (DOE-STD-3013-2000) cannot exceed the container design pressure within the time frames or environmental conditions of either storage or transportation. Presently, materials stabilized and packaged according to the 3013 Standard are to be transported in certified packages (the certification process for the 9975 and the SAFKEG has yet to be completed) that do not rely on the containment capabilities of the 3013 container. Even though no reliance is placed on that container, this document shows that it is highly likely that the containment function will be maintained not only in storage but also during transportation, including hypothetical accident conditions. Further, this document, by summarizing materials-related data on gas generation, can point those involved in preparing Safety Analysis Reports for Packages (SARPs) to additional information needed to assess the ability of the primary containment vessel to contain the contents and any reaction products that might reasonably be produced by the contents.

  14. Nuclear Safety Regulatory Framework

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

    overall Nuclear Safety Policy & ESH Goals Safety Basis Review and Approval In the DOE governance model, contractors responsible for the facility develop the safety basis and...

  15. Gas Pipeline Safety (Indiana)

    Broader source: Energy.gov [DOE]

    This section establishes the Pipeline Safety Division within the Utility Regulatory Commission to administer federal pipeline safety standards and establish minimum state safety standards for...

  16. Module Safety Issues (Presentation)

    SciTech Connect (OSTI)

    Wohlgemuth, J.

    2012-02-01T23:59:59.000Z

    Description of how to make PV modules so that they are less likely to turn into safety hazards. Making modules inherently safer with minimum additional cost is the preferred approach for PV. Safety starts with module design to ensure redundancy within the electrical circuitry to minimize open circuits and proper mounting instructions to prevent installation related ground faults. Module manufacturers must control the raw materials and processes to ensure that that every module is built like those qualified through the safety tests. This is the reason behind the QA task force effort to develop a 'Guideline for PV Module Manufacturing QA'. Periodic accelerated stress testing of production products is critical to validate the safety of the product. Combining safer PV modules with better systems designs is the ultimate goal. This should be especially true for PV arrays on buildings. Use of lower voltage dc circuits - AC modules, DC-DC converters. Use of arc detectors and interrupters to detect arcs and open the circuits to extinguish the arcs.

  17. Optimal concentrations in transport systems

    E-Print Network [OSTI]

    Kim, Wonjung

    Many biological and man-made systems rely on transport systems for the distribution of material, for example matter and energy. Material transfer in these systems is determined by the flow rate and the concentration of ...

  18. "By the hundred's of thousand's, these unlikely transportation revolutionaries are forgoing the safety of a steel cage with airbags and anti-lock brakes for a wispy two-wheeled exoskeleton as they make their way to work,

    E-Print Network [OSTI]

    Duchowski, Andrew T.

    the safety of a steel cage with airbags and anti-lock brakes for a wispy two-wheeled exoskeleton as they make

  19. A review of extended-range operations by transport aircraft

    E-Print Network [OSTI]

    Simpson, R. W.

    1987-01-01T23:59:59.000Z

    Introduction: The safety of enroute operations of aircraft engaged in public transport has been a continuous concern since the early days of air transportation. There are a variety of inflight emergency situations which ...

  20. Laser Safety Introduction

    E-Print Network [OSTI]

    McQuade, D. Tyler

    use Integrated Safety Management here at the lab to reduce risk and work to improve the quality and safety of the work? #12;Integrated Safety Management Use (greater in size than wavelength) #12;Integrated Safety Management Remember, we

  1. Transportation System Readiness and Resiliency Assessment Framework: Readiness and Assess Resiliency of

    E-Print Network [OSTI]

    Transportation System Readiness and Resiliency Assessment Framework: Readiness and Assess Resiliency of Transportation Systems (Infrastructure, Systems, Organization and Services) to Deter, Detect Flows Passenger Flows Supply Chain Efficiency Transportation: Energy Environment Safety Security Vehicle

  2. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, E.

    1983-08-15T23:59:59.000Z

    A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.

  3. Electrical safety device

    DOE Patents [OSTI]

    White, David B. (Greenock, PA)

    1991-01-01T23:59:59.000Z

    An electrical safety device for use in power tools that is designed to automatically discontinue operation of the power tool upon physical contact of the tool with a concealed conductive material. A step down transformer is used to supply the operating power for a disconnect relay and a reset relay. When physical contact is made between the power tool and the conductive material, an electrical circuit through the disconnect relay is completed and the operation of the power tool is automatically interrupted. Once the contact between the tool and conductive material is broken, the power tool can be quickly and easily reactivated by a reset push button activating the reset relay. A remote reset is provided for convenience and efficiency of operation.

  4. Essays on Transportation Safety, Economics, and Policy

    E-Print Network [OSTI]

    Scholl, Patricia Lynn

    2011-01-01T23:59:59.000Z

    vehicle crashes. ” Accident Analysis & Prevention 43 (4) (s licensing program. Accident Analysis & Prevention 40, no.survival analysis. Accident Analysis & Prevention 42, no.

  5. MODEL 9977 B(M)F-96 SAFETY ANALYSIS REPORT FOR PACKAGING

    SciTech Connect (OSTI)

    Abramczyk, G; Paul Blanton, P; Kurt Eberl, K

    2006-05-18T23:59:59.000Z

    This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on and for the 9977 Shipping Package, referred to as the General Purpose Fissile Package (GPFP). The performance evaluation presented in this SARP documents the compliance of the 9977 package with the regulatory safety requirements for Type B packages. Per 10 CFR 71.59, for the 9977 packages evaluated in this SARP, the value of ''N'' is 50, and the Transport Index based on nuclear criticality control is 1.0. The 9977 package is designed with a high degree of single containment. The 9977 complies with 10 CFR 71 (2002), Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10 CFR 20 (2003) for As Low As Reasonably Achievable (ALARA) principles. The 9977 also satisfies the requirements of the Regulations for the Safe Transport of Radioactive Material--1996 Edition (Revised)--Requirements. IAEA Safety Standards, Safety Series No. TS-R-1 (ST-1, Rev.), International Atomic Energy Agency, Vienna, Austria (2000). The 9977 package is designed, analyzed and fabricated in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1992 edition.

  6. Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

  7. Facility Safety

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

    2013-06-21T23:59:59.000Z

    DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

  8. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C. (Malmoe, SE)

    1984-01-01T23:59:59.000Z

    The safety valve contains a resilient gland to be held between a valve seat and a valve member and is secured to the valve member by a sleeve surrounding the end of the valve member adjacent to the valve seat. The sleeve is movable relative to the valve member through a limited axial distance and a gap exists between said valve member and said sleeve.

  9. ENVIRONMENTAL HEALTH & SAFETY University of Rochester

    E-Print Network [OSTI]

    Portman, Douglas

    contain finish materials that are wood or combustible products. Doors, flooring, paneling, trim://www.safety.rochester.edu/fire/pdf/flammabilityguideline.pdf c. The materials used in furniture upholstery and mattresses can be extremely combustible. Various materials used on floors and walls of buildings are designed to reduce the generation of smoke, heat, flames

  10. Nanoengineered membranes for controlled transport

    DOE Patents [OSTI]

    Doktycz, Mitchel J. (Oak Ridge, TN) [Oak Ridge, TN; Simpson, Michael L. (Knoxville, TN) [Knoxville, TN; McKnight, Timothy E. (Greenback, TN) [Greenback, TN; Melechko, Anatoli V. (Oak Ridge, TN) [Oak Ridge, TN; Lowndes, Douglas H. (Knoxville, TN) [Knoxville, TN; Guillorn, Michael A. (Knoxville, TN) [Knoxville, TN; Merkulov, Vladimir I. (Oak Ridge, TN) [Oak Ridge, TN

    2010-01-05T23:59:59.000Z

    A nanoengineered membrane for controlling material transport (e.g., molecular transport) is disclosed. The membrane includes a substrate, a cover definining a material transport channel between the substrate and the cover, and a plurality of fibers positioned in the channel and connected to an extending away from a surface of the substrate. The fibers are aligned perpendicular to the surface of the substrate, and have a width of 100 nanometers or less. The diffusion limits for material transport are controlled by the separation of the fibers. In one embodiment, chemical derivitization of carbon fibers may be undertaken to further affect the diffusion limits or affect selective permeability or facilitated transport. For example, a coating can be applied to at least a portion of the fibers. In another embodiment, individually addressable carbon nanofibers can be integrated with the membrane to provide an electrical driving force for material transport.

  11. Chapter 10 -Elevated Work Surface Safety Rules

    E-Print Network [OSTI]

    and edges of the roof using one of the following: a. Motion stopping safety device b. Warning line system c. Safety monitoring system on roofs of 50 feet or less in width 4. A warning line system consists of a rope and locked into safe position. 10. All portable ladders should have insulating non-slip material supplied

  12. Systems Issues in Nuclear Reactor Safety

    E-Print Network [OSTI]

    de Weck, Olivier L.

    Systems Issues in Nuclear Reactor Safety Commissioner George ApostolakisCommissioner George Apostolakis U.S. Nuclear Regulatory Commission CmrApostolakis@nrc.gov MIT SDM Conference on Systems Thinking, source, and special nuclear materials to ensure adequate protection of public health and safety, 3

  13. Safety, Health, and Environmental (SHE) Program

    E-Print Network [OSTI]

    Waliser, Duane E.

    Safety, Health, and Environmental (SHE) Program Construction Awareness Training (SHE 101C) Marshall Space Flight Center Safety, Health, & Environmental (SHE) Program SHE 101C Presented By: MSFC Industrial personnel to avoid critical delays If there is an injury to personnel or damage to MSFC property, material

  14. Vehicle Battery Safety Roadmap Guidance

    SciTech Connect (OSTI)

    Doughty, D. H.

    2012-10-01T23:59:59.000Z

    The safety of electrified vehicles with high capacity energy storage devices creates challenges that must be met to assure commercial acceptance of EVs and HEVs. High performance vehicular traction energy storage systems must be intrinsically tolerant of abusive conditions: overcharge, short circuit, crush, fire exposure, overdischarge, and mechanical shock and vibration. Fail-safe responses to these conditions must be designed into the system, at the materials and the system level, through selection of materials and safety devices that will further reduce the probability of single cell failure and preclude propagation of failure to adjacent cells. One of the most important objectives of DOE's Office of Vehicle Technologies is to support the development of lithium ion batteries that are safe and abuse tolerant in electric drive vehicles. This Roadmap analyzes battery safety and failure modes of state-of-the-art cells and batteries and makes recommendations on future investments that would further DOE's mission.

  15. Safety Share from National Safety Council

    Broader source: Energy.gov [DOE]

    Slide Presentation by Joe Yanek, Fluor Government Group. National Safety Council Safety Share. The Campbell Institute is the “Environmental, Health and Safety (EHS) Center of Excellence” at the National Safety Council and provides a Forum for Leaders in EHS to exchange ideas and collaborate across industry sectors and organizational types.

  16. Nuclear Safety Information Agreement Between the U.S. Nuclear...

    Office of Environmental Management (EM)

    Information Agreement Between the U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, and the U.S. Department of Energy, Office of Environment,...

  17. AWEA Wind Project Operations and Maintenance and Safety Seminar

    Office of Energy Efficiency and Renewable Energy (EERE)

    The AWEA Wind Project O&M and Safety Seminar is designed for owners, operators, turbine manufactures, material suppliers, wind technicians, managers, supervisors, engineers, and occupational...

  18. Nuclear Safety Component and Services Procurement, June 29, 2011...

    Office of Environmental Management (EM)

    require component and materials replacement identified and implemented? * Are appropriate preventive maintenance requirements for stored safety-related equipment identified and...

  19. Intermetallic Electrodes Improve Safety and Performance in Lithium...

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

    Intermetallic Electrodes Improve Safety and Performance in Lithium-Ion Batteries Technology available for licensing: A new class of intermetallic material that can be used as a...

  20. Standardization of Transport Properties Measurements: Internal Energy Agency (IEA-AMT) Annex on Thermoelectric

    Broader source: Energy.gov [DOE]

    Thermoelectric materials transport properties measurements improvement and standardization is undertaken by new IEA annex under the Advanced Materials for Transportation implementing agreement

  1. Leveraging Available Data to Support Extension of Transportation Packages Service Life

    SciTech Connect (OSTI)

    Dunn, K.; Abramczyk, G.; Bellamy, S.; Daugherty, W.; Hackney, B.; Hoffman, E.; Skidmore, E.; Stefek, T.

    2012-06-12T23:59:59.000Z

    Data obtained from testing shipping package materials have been leveraged to support extending the service life of select shipping packages while in nuclear materials transportation. Increasingly, nuclear material inventories are being transferred to an interim storage location where they will reside for extended periods of time. Use of a shipping package to store nuclear materials in an interim storage location has become more attractive for a variety of reasons. Shipping packages are robust and have a qualified pedigree for their performance in normal operation and accident conditions within the approved shipment period and storing nuclear material within a shipping package results in reduced operations for the storage facility. However, the shipping package materials of construction must maintain a level of integrity as specified by the safety basis of the storage facility through the duration of the storage period, which is typically well beyond the one year transportation window. Test programs have been established to obtain aging data on materials of construction that are the most sensitive/susceptible to aging in certain shipping package designs. The collective data are being used to support extending the service life of shipping packages in both transportation and storage.

  2. Formal Management Review of the Safety Basis Calculations Noncompliance

    SciTech Connect (OSTI)

    Altenbach, T J

    2008-06-24T23:59:59.000Z

    In Reference 1, LLNL identified a failure to adequately implement an institutional commitment concerning administrative requirements governing the documentation of Safety Basis calculations supporting the Documented Safety Analysis (DSA) process for LLNL Hazard Category 2 and Category 3 nuclear facilities. The AB Section has discovered that the administrative requirements of AB procedure AB-006, 'Safety Basis Calculation Procedure for Category 2 and 3 Nuclear Facilities', have not been uniformly or consistently applied in the preparation of Safety Basis calculations for LLNL Hazard Category 2 and 3 Nuclear Facilities. The SEP Associated Director has directed the AB Section to initiate a formal management review of the issue that includes, but is not necessarily limited to the following topics: (1) the basis establishing Ab-006 as a required internal procedure for Safety Basis calculations; (2) how requirements for Safety Basis calculations flow down in the institutional DSA process; (3) the extent to which affected Laboratory organizations have explicitly complied with the requirements of Procedure AB-006; (4) what alternative approaches LLNL organizations has used for Safety Basis calculations and how these alternate approaches compare with Procedure AB-006 requirements; and (5) how to reconcile Safety Basis calculations that were performed before Procedure AB-006 came into existence (i.e., August 2001). The management review2 also includes an extent-of-condition evaluation to determine how widespread the discovered issue is throughout Laboratory organizations responsible for operating nuclear facilities, and to determine if implementation of AB procedures other than AB-006 has been similarly affected. In Reference 2, Corrective Action 1 was established whereby the SEP Directorate will develop a plan for performing a formal management review of the discovered condition, including an extent-of condition evaluation. In Reference 3, a plan was provided to prepare a formal management review, satisfying Corrective Action 1. An AB-006 Working Group was formed,led by the AB Section, with representatives from the Nuclear Materials Technology Program (NMTP), the Radioactive and Hazardous Waste Management (RHWM) Division, and the Packaging and Transportation Safety (PATS) Program. The key action of this management review was for Working Group members to conduct an assessment of all safety basis calculations referenced in their respective DSAs. Those assessments were tasked to provide the following information: (1) list which safety basis calculations correctly follow AB-006 and therefore require no additional documentation; (2) identify and list which safety basis calculations do not strictly follow AB-006, these include NMTP Engineering Notes, Engineering Safety Notes, and calculations by organizations external to the nuclear facilities (such as Plant Engineering), subcontractor calculations, and other internally generated calculations. Each of these will be reviewed and listed on a memorandum with the facility manager's (or designee's) signature accepting that calculation for use in the DSA. If any of these calculations are lacking the signature of a technical reviewer, they must also be reviewed for technical content and that review documented per AB-006.

  3. Comparison and Analysis of Regulatory and Derived Requirements for Certain DOE Spent Nuclear Fuel Shipments; Lessons Learned for Future Spent Fuel Transportation Campaigns

    SciTech Connect (OSTI)

    Kramer, George L., Ph.D.; Fawcett, Rick L.; Rieke, Philip C.

    2003-02-27T23:59:59.000Z

    Radioactive materials transportation is stringently regulated by the Department of Transportation and the Nuclear Regulatory Commission to protect the public and the environment. As a Federal agency, however, the U.S. Department of Energy (DOE) must seek State, Tribal and local input on safety issues for certain transportation activities. This interaction has invariably resulted in the imposition of extra-regulatory requirements, greatly increasing transportation costs and delaying schedules while not significantly enhancing the level of safety. This paper discusses the results an analysis of the regulatory and negotiated requirements established for a July 1998 shipment of spent nuclear fuel from foreign countries through the west coast to the Idaho National Engineering and Environmental Laboratory (INEEL). Staff from the INEEL Nuclear Materials Engineering and Disposition Department undertook the analysis in partnership with HMTC, to discover if there were instances where requirements derived from stakeholder interactions duplicate, contradict, or otherwise overlap with regulatory requirements. The study exhaustively lists and classifies applicable Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations. These are then compared with a similarly classified list of requirements from the Environmental Impact Statements (EIS) and those developed during stakeholder negotiations. Comparison and analysis reveals numerous attempts to reduce transportation risk by imposing more stringent safety measures than those required by DOT and NRC. These usually took the form of additional inspection, notification and planning requirements. There are also many instances of overlap with, and duplication of regulations. Participants will gain a greater appreciation for the need to understand the risk-oriented basis of the radioactive materials regulations and their effectiveness in ensuring safety when negotiating extra-regulatory requirements.

  4. The Regional Role in Addressing DOE Transportation Concerns

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

    CSG's Midwestern Radioactive Materials Transportation Project Presented to the U.S. Department of Energy's Transportation External Coordination Working Group April 21, 2004 Lisa R....

  5. Phosphine Oxide Based Electron Transporting and Hole Blocking...

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

    Oxide Based Electron Transporting and Hole Blocking Materials for Blue Electrophosphorescent Organic Light Emitting Phosphine Oxide Based Electron Transporting and Hole Blocking...

  6. Thermoelectric transport in the coupled valence-band model

    E-Print Network [OSTI]

    Ramu, Ashok; Cassels, Laura; Hackman, Nathan; Lu, Hong; Zide, Joshua; Bowers, John E.

    2011-01-01T23:59:59.000Z

    109, 033704 ?2011? Thermoelectric transport in the coupledapplied to the problem of thermoelectric transport in p-typeef?ciency p-type thermoelectric material, are calculated and

  7. Delivering safety

    SciTech Connect (OSTI)

    Baldwin, N.D.; Spooner, K.G.; Walkden, P. [British Nuclear Group Ltd, Daresbury, Warrington (United Kingdom)

    2007-07-01T23:59:59.000Z

    In the United Kingdom there have been significant recent changes to the management of civil nuclear liabilities. With the formation in April 2005 of the Nuclear Decommissioning Authority (NDA), ownership of the civil nuclear licensed sites in the UK, including the Magnox Reactor Stations, passed to this new organisation. The NDAs mission is to seek acceleration of the nuclear clean up programme and deliver increased value for money and, consequently, are driving their contractors to seek more innovative ways of performing work. British Nuclear Group manages the UK Magnox stations under contract to the NDA. This paper summarises the approach being taken within its Reactor Sites business to work with suppliers to enhance working arrangements at sites, improve the delivery of decommissioning programmes and deliver improvements in safety and environmental performance. The UK Magnox stations are 1. generation gas-graphite reactors, constructed in the 1950's and 1960's. Two stations are currently still operating, three are shut-down undergoing defueling and the other five are being decommissioned. Despite the distractions of industry restructuring, an uncompromising policy of demanding improved performance in conjunction with improved safety and environmental standards has been adopted. Over the past 5 years, this policy has resulted in step-changes in performance at Reactor Sites, with increased electrical output and accelerated defueling and decommissioning. The improvements in performance have been mirrored by improvements in safety (DACR of 0 at 5 sites); environmental standards (reductions in energy and water consumption, increased waste recycling) and the overall health of the workforce (20% reduction in sickness absence). These achievements have, in turn, been recognised by external bodies, resulting in several awards, including: the world's first ISRS and IERS level 10 awards (Sizewell, 2006), the NUMEX plant maintenance award (Bradwell, 2006), numerous RoSPA awards at site and sector level and nomination, at Company level, for the RoSPA George Earle trophy for outstanding performance in Health and Safety (Reactor Sites, 2006). After 'setting the scene' and describing the challenges that the company has had to respond to, the paper explains how these improvements have been delivered. Specifically it explains the process that has been followed and the parts played by sites and suppliers to deliver improved performance. With the experience of already having transitioned several Magnox stations from operations to defueling and then to decommissioning, the paper describes the valuable experience that has been gained in achieving an optimum change process and maintaining momentum. (authors)

  8. Safety, Security

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

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

  9. Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries

    SciTech Connect (OSTI)

    Marshall, William BJ J [ORNL] [ORNL; Rearden, Bradley T [ORNL] [ORNL

    2012-01-01T23:59:59.000Z

    ANSI/ANS-8.1-1998;2007, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, and ANSI/ANS-8.24-2007, Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations, require validation of a computer code and the associated data through benchmark evaluations based on physical experiments. The performance of the code and data are validated by comparing the calculated and the benchmark results. A SCALE procedure has been established to generate a Verified, Archived Library of Inputs and Data (VALID). This procedure provides a framework for preparing, peer reviewing, and controlling models and data sets derived from benchmark definitions so that the models and data can be used with confidence. The procedure ensures that the models and data were correctly generated using appropriate references with documented checks and reviews. Configuration management is implemented to prevent inadvertent modification of the models and data or inclusion of models that have not been subjected to the rigorous review process. VALID entries for criticality safety are based on critical experiments documented in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE). The findings of a criticality safety validation of SCALE 6.1 utilizing the benchmark models vetted in the VALID library at Oak Ridge National Laboratory are summarized here.

  10. Recommended research on LNG safety

    SciTech Connect (OSTI)

    Carpenter, H.J.; Gilmore, F.R.

    1981-03-01T23:59:59.000Z

    The US Department of Energy (DOE) is conducting research on the safety and other environmental aspects of liquefied energy gases including liquefied natural gas (LNG). The effort reported here was conducted as part of the planning for further research into the safety aspects of transporting and storing LNG, with primary emphasis on public safety. Although the modern LNG industry has enjoyed excellent success in providing for safe operations, significant questions remain on the part of many, the expressions of which were intensified with the addition of marine-based LNG import terminals. Public safety with regard to large-scale importation of this fuel has received widespread attention in the US Congress, state legislatures, county and city governments, and from various individuals and public groups, with coverage in all the news media, including books published on the subject. The safety concerns have centered around the consequences to the public of a large spill of the cryogenic liquid from an ocean tanker or a larger storage tank, either of which might hold as much as 125,000 m/sup 3/ of LNG.

  11. CRAD, Nuclear Safety Delegations for Documented Safety Analysis...

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

    Safety Delegations for Documented Safety Analysis Approval - January 8, 2015 (EA CRAD 31-09, Rev. 0) CRAD, Nuclear Safety Delegations for Documented Safety Analysis Approval -...

  12. Materials Characterization | Advanced Materials | ORNL

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighand Retrievals from a New 183-GHzMAR Os2010Material Safety Electron

  13. Safety evaluation for packaging (onsite) for cesium chloride capsules with type W overpacks

    SciTech Connect (OSTI)

    McCoy, J.C.

    1997-09-15T23:59:59.000Z

    This Safety Evaluation for Packaging (SEP) documents the evaluation of a new basket design and overpacked cesium chloride capsule payload for the Beneficial Uses Shipping System (BUSS) Cask in accordance with the onsite transportation requirements of the Hazardous Material Packaging and Shipping manual, WHC-CM-2-14. This design supports the one-time onsite shipment of 16 cesium chloride capsules with Type W overpacks from the 324 Building to the 224T Building at the Waste Encapsulation and Storage Facility (WESF). The SEP is valid for a one-time onsite shipment or until August 1, 1998, whichever occurs first.

  14. U.S. Department of Transportation

    E-Print Network [OSTI]

    . This advisory circular (AC) describes the Federal Aviation Administration (FAA) Aviation Safety ReportingU.S. Department of Transportation Federal Aviation Administration Advisory Circular Subject of the FAA is to promote aviation safety. To further this mission, the FAA instituted a voluntary ASRP

  15. TYPE A FISSILE PACKAGING FOR AIR TRANSPORT PROJECT OVERVIEW

    SciTech Connect (OSTI)

    Eberl, K.; Blanton, P.

    2013-10-11T23:59:59.000Z

    This paper presents the project status of the Model 9980, a new Type A fissile packaging for use in air transport. The Savannah River National Laboratory (SRNL) developed this new packaging to be a light weight (<150-lb), drum-style package and prepared a Safety Analysis for Packaging (SARP) for submission to the DOE/EM. The package design incorporates unique features and engineered materials specifically designed to minimize packaging weight and to be in compliance with 10CFR71 requirements. Prototypes were fabricated and tested to evaluate the design when subjected to Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC). An overview of the design details, results of the regulatory testing, and lessons learned from the prototype fabrication for the 9980 will be presented.

  16. Local Transportation

    E-Print Network [OSTI]

    Local Transportation. Transportation from the Airport to Hotel. There are two types of taxi companies that operate at the airport: special and regular taxis (

  17. Greening Transportation

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

    Transportation Goal 2: Greening Transportation LANL supports and encourages employees to reduce their personal greenhouse gas emissions by offering various commuting and work...

  18. Computational Chemical Materials Engineering

    E-Print Network [OSTI]

    Home Computational Chemical and Materials Engineering Tahir Cagin Chemical Engineering Department through processing for improving their performance for engineering applications · Use and develop with usable ­ Chemical ­ Electronic ­ Optical ­ Magnetic ­ Transport, thermal and mechanical properties

  19. Street typology and bicyclist safety : a systems approach

    E-Print Network [OSTI]

    Minikel, Eric Vallabh

    2010-01-01T23:59:59.000Z

    Cycling is an attractive transportation mode but has not attained a large mode share in the United States, in part because it is correctly perceived as dangerous. Much literature on cyclist safety and the built environment ...

  20. Nuclear reactor safety heat transfer

    SciTech Connect (OSTI)

    Jones, O.C.

    1982-07-01T23:59:59.000Z

    Reviewed is a book which has 5 parts: Overview, Fundamental Concepts, Design Basis Accident-Light Water Reactors (LWRs), Design Basis Accident-Liquid-Metal Fast Breeder Reactors (LMFBRs), and Special Topics. It combines a historical overview, textbook material, handbook information, and the editor's personal philosophy on safety of nuclear power plants. Topics include thermal-hydraulic considerations; transient response of LWRs and LMFBRs following initiating events; various accident scenarios; single- and two-phase flow; single- and two-phase heat transfer; nuclear systems safety modeling; startup and shutdown; transient response during normal and upset conditions; vapor explosions, natural convection cooling; blockages in LMFBR subassemblies; sodium boiling; and Three Mile Island.

  1. ADVANCED CUTTINGS TRANSPORT STUDY

    SciTech Connect (OSTI)

    Troy Reed; Stefan Miska; Nicholas Takach; Kaveh Ashenayi; Mark Pickell; Len Volk; Mike Volk; Lei Zhou; Zhu Chen; Crystal Redden; Aimee Washington

    2003-01-30T23:59:59.000Z

    This is the second quarterly progress report for Year-4 of the ACTS Project. It includes a review of progress made in: (1) Flow Loop construction and development and (2) research tasks during the period of time between October 1, 2002 and December 30, 2002. This report presents a review of progress on the following specific tasks. (a) Design and development of an Advanced Cuttings Transport Facility Task 3: Addition of a Cuttings Injection/Separation System, Task 4: Addition of a Pipe Rotation System. (b) New research project (Task 9b): ''Development of a Foam Generator/Viscometer for Elevated Pressure and Elevated Temperature (EPET) Conditions''. (d) Research project (Task 10): ''Study of Cuttings Transport with Aerated Mud Under Elevated Pressure and Temperature Conditions''. (e) Research on three instrumentation tasks to measure: Cuttings concentration and distribution in a flowing slurry (Task 11), Foam texture while transporting cuttings. (Task 12), and Viscosity of Foam under EPET (Task 9b). (f) New Research project (Task 13): ''Study of Cuttings Transport with Foam under Elevated Pressure and Temperature Conditions''. (g) Development of a Safety program for the ACTS Flow Loop. Progress on a comprehensive safety review of all flow-loop components and operational procedures. (Task 1S). (h) Activities towards technology transfer and developing contacts with Petroleum and service company members, and increasing the number of JIP members.

  2. Chamber transport

    SciTech Connect (OSTI)

    OLSON,CRAIG L.

    2000-05-17T23:59:59.000Z

    Heavy ion beam transport through the containment chamber plays a crucial role in all heavy ion fusion (HIF) scenarios. Here, several parameters are used to characterize the operating space for HIF beams; transport modes are assessed in relation to evolving target/accelerator requirements; results of recent relevant experiments and simulations of HIF transport are summarized; and relevant instabilities are reviewed. All transport options still exist, including (1) vacuum ballistic transport, (2) neutralized ballistic transport, and (3) channel-like transport. Presently, the European HIF program favors vacuum ballistic transport, while the US HIF program favors neutralized ballistic transport with channel-like transport as an alternate approach. Further transport research is needed to clearly guide selection of the most attractive, integrated HIF system.

  3. Nanotube Composite Anode Materials | Argonne National Laboratory

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

    available for licensng: A composite material suitable for use in an anode for a lithium-ion battery Reduces manufacturing costs. Provides increase capacity, safety, long-term...

  4. achieve product safety: Topics by E-print Network

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

    that are adaptively secure under a standard assumption 29 1Page ofProduct Code: 051000 Revision: 5 07 MAR 2002Issued: 7 Material Safety Data Sheet Materials Science Websites...

  5. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    ) * Bis(4-hydroxyphenyl) dimethylmethane * Bis(4-hydroxyphenyl)propane * 2,2-Bis(p-hydroxyphenyl)propane * 2,2-Bis(4-hydroxyphenyl)propane * Bisphenol * Bisphenol A (OSHA) * 4,4'-Bisphenol A * DIAN * p,p'-Dihydroxydiphenyldimethylmethane * 4,4'-Dihydroxydiphenyldimethylmethane * p,p'-Dihydroxydiphenylpropane * 2,2-(4,4'-Dihydroxydiphenyl)propane

  6. Material Safety Data Sheet 1. PRODUCT IDENTIFICATION

    E-Print Network [OSTI]

    Rollins, Andrew M.

    . Ventilation: General; local exhaust ventilation as necessary to control any air contaminants to within ventilation. Take up with an inert absorbent. Store in a closed waste container until disposal. 7. HANDLING

  7. "Safety Concrete" A Material Designed to Fail

    E-Print Network [OSTI]

    platen Bottom steel platen 10 ft tall PVC pipe (3" ID) Outer PVC shield collects fragments Sample #12

  8. MATERIAL SAFETY DATA SHEET 1. IDENTIFICATION

    E-Print Network [OSTI]

    Alpay, S. Pamir

    the first 5 minutes, then continue rinsing eye. Call a poison control center or doctor for treatment advice. Call a poison control center or doctor for treatment advice. If Swallowed: Call poison control center not induce vomiting unless told to do so by the poison control center or doctor. Do not give anything

  9. Material Safety Data Sheet HMIS FLAMMABILITY

    E-Print Network [OSTI]

    Rollins, Andrew M.

    .0 Extinguishing Media - Use water fog, foam, dry chemical or CO2. Use water spray to cool fire-exposed containers spray. Prevent spill from entering drains, sewers, streams or other bodies of water. If run-off occurs shield, bunker coats, gloves and rubber boots), including a positive pressure NIOSH approved self

  10. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    -propylalkohol (German) * IPS 1 (alcohol) * Lutosol * 1-Methylethanol * 1-Methylethyl alcohol * Petrohol * PRO * 2-Propanol * i-Propanol (German) * n-Propan-2-ol * sec-Propyl alcohol * 2-Propyl alcohol * i

  11. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    Identification EMERGENCY OVERVIEW Irritant. Irritating to eyes, respiratory system and skin. HMIS RATING HEALTH. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved respirator. Hand

  12. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Highly flammable. Irritating to eyes, respiratory system and skin. Very toxic to aquatic organisms, may. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved respirator. Hand

  13. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    with skin and if swallowed. Irritating to eyes, respiratory system and skin. May cause sensitization by skin nonsparking tools. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved

  14. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    3 - Hazards Identification EMERGENCY OVERVIEW Irritant. Irritating to eyes, respiratory system. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved respirator. Hand

  15. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    for the environment. Harmful by inhalation and if swallowed. Irritating to eyes, respiratory system and skin. Toxic nonsparking tools. Mechanical exhaust required. PERSONAL PROTECTIVE EQUIPMENT Respiratory: Government approved

  16. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    (Polish) * Methyl toluene * NCI-C55232 * RCRA waste number U239 * Violet 3 * Xiloli (Italian) * Xylene fumes under fire conditions. Specific Method(s) of Fire Fighting: Use water spray to cool fire-exposed

  17. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    1.3 Section 1 - Product and Company Information Product Name 2,2-DIMETHOXY-2-PHENYLACETOPHENONE, 99% Product Number 196118 Brand ALDRICH Company Sigma-Aldrich Street Address 3050 Spruce Street City, State Coefficient Log Kow: 3.42 Decomposition Temp. N/A Flash Point > 374 °F > 190 °C Explosion Limits N

  18. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    1.1 Section 1 - Product and Company Information Product Name BUTYL ACRYLATE, 99+% Product Number 234923 Brand ALDRICH Company Sigma-Aldrich Street Address 3050 Spruce Street City, State, Zip, Country °C Partition Coefficient Log Kow: 2.38 Decomposition Temp. N/A Flash Point 96.8 °F 36 °C Method

  19. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    1.4 Section 1 - Product and Company Information Product Name 4-TERT-BUTYLPHENOL, 99% Product Number B99901 Brand ALDRICH Company Sigma-Aldrich Street Address 3050 Spruce Street City, State, Zip/A Evaporation Rate N/A Viscosity N/A Surface Tension N/A Partition Coefficient Log Kow: 3.29 Decomposition Temp

  20. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    1.7 Section 1 - Product and Company Information Product Name TRIFLUOROACETIC ACID, REDISTILLED, 99+%,SUITABLE FOR PROTEIN SEQUENCING Product Number 299537 Brand ALDRICH Company Sigma-Aldrich Street Address/A Partition Coefficient Log Kow: -2.1 Decomposition Temp. N/A Flash Point N/A Explosion

  1. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    1.5 Section 1 - Product and Company Information Product Name 1-PROPANOL, 99.5+%, HPLC GRADE Product Number 293288 Brand ALDRICH Company Sigma-Aldrich Street Address 3050 Spruce Street City, State, Zip Coefficient Log Kow: 0.25 - 0.

  2. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    1.6 Section 1 - Product and Company Information Product Name BENZYL ALCOHOL, ANHYDROUS, 99.8% Product Number 305197 Brand ALDRICH Company Sigma-Aldrich Street Address 3050 Spruce Street City, State Tension 39 mN/m 20 °C Partition Coefficient Log Kow: 1.1 Decomposition Temp. N/A Flash Point 204.8 °F 96

  3. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    * Bactolatex * Bakelite SMD 3500 * BASF III * BDH 29-790 * Bextrene XL 750 * Bicolastic A 75 * Bicolene H * Bio6475000 Section 3 - Hazards Identification HMIS RATING HEALTH: 0 FLAMMABILITY: 0 REACTIVITY: 0 NFPA RATING

  4. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    FLAMMABILITY: 1 REACTIVITY: 3 SPECIAL HAZARD(S): Oxidizer NFPA RATING HEALTH: 2 FLAMMABILITY: 1 REACTIVITY: 3 or Pressure Molecular Weight 194.23 AMU pH N/A BP/BP Range 75 - 76 °C 0.2 mmHg MP/MP Range N/A Freezing Point

  5. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    5-98 * Lemol 12-88 * Lemol 16-98 * Lemol 24-98 * Lemol 30-98 * Lemol 51-98 * Lemol 60-98 * Lemol 75 HEALTH: 0 FLAMMABILITY: 1 REACTIVITY: 0 NFPA RATING HEALTH: 0 #12;FLAMMABILITY: 1 REACTIVITY: 0

  6. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Harmful if swallowed. HMIS RATING HEALTH: 1 FLAMMABILITY: 2 REACTIVITY: 1 NFPA RATING HEALTH: 1 NDS 15 MG/M3 Poland NDSCh 75 MG/M3 Poland NDSP - Section 9 - Physical/Chemical Properties Appearance

  7. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    HEALTH: 3 FLAMMABILITY: 3 REACTIVITY: 1 NFPA RATING HEALTH: 3 FLAMMABILITY: 3 REACTIVITY: 1. FLASH POINT 75 °F 24 °C Method: closed cup AUTOIGNITION TEMP N/A FLAMMABILITY N/A EXTINGUISHING MEDIA

  8. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    -2-PROPANOL 75-65-0 Yes Formula C4H10O Synonyms Alcool butylique tertiaire (French) * Arconol * t* FLAMMABILITY: 3 REACTIVITY: 0 NFPA RATING HEALTH: 2 FLAMMABILITY: 3 REACTIVITY: 0 *additional chronic hazards

  9. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    polystyrene * Bactolatex * Bakelite SMD 3500 * BASF III * BDH 29-790 * Bextrene XL 750 * Bicolastic A 75 NFPA RATING HEALTH: 0 FLAMMABILITY: 0 #12;REACTIVITY: 0 For additional information on toxicity, please

  10. Denatured Alcohol MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Rollins, Andrew M.

    lights, and turn off stoves, heaters, electric motors and all other sources of ignition during use damage, and death. No data available. Signs and Symptoms Of Exposure Diseases of the liver. Medical

  11. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    * Compalox * Conopal * Diadur * Dialuminum trioxide * Dispal alumina * Dispal M * Dotment 324 * Dotment 358

  12. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    /A FLAMMABILITY N/A EXTINGUISHING MEDIA Suitable: Water spray. Carbon dioxide, dry chemical powder, or appropriate Products: Carbon monoxide, Carbon dioxide. Section 11 - Toxicological Information ROUTE OF EXPOSURE. Wash contaminated clothing before reuse. Section 9 - Physical/Chemical Properties Appearance Color

  13. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    Method: closed cup AUTOIGNITION TEMP N/A FLAMMABILITY N/A EXTINGUISHING MEDIA Suitable: Carbon dioxide Decomposition Products: Carbon monoxide, Carbon dioxide. Section 11 - Toxicological Information ROUTE thoroughly after handling. Wash contaminated clothing before reuse. Section 9 - Physical/Chemical Properties

  14. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Carbon dioxide, dry chemical powder, or appropriate foam. FIREFIGHTING Protective Equipment: Wear self Decomposition Products: Carbon monoxide, Carbon dioxide. Section 11 - Toxicological Information ROUTE clothing before reuse. Section 9 - Physical/Chemical Properties Appearance Color: White Form: Fine crystals

  15. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    spray. Carbon dioxide, dry chemical powder, or appropriate foam. FIREFIGHTING Protective Equipment: Wear Hazardous Decomposition Products: Carbon monoxide, Carbon dioxide. HAZARDOUS POLYMERIZATION Hazardous goggles. GENERAL HYGIENE MEASURES Wash thoroughly after handling. Section 9 - Physical/Chemical Properties

  16. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    MEDIA Suitable: Water spray. Carbon dioxide, dry chemical powder, or appropriate foam. FIREFIGHTING DECOMPOSITION PRODUCTS Hazardous Decomposition Products: Carbon monoxide, Carbon dioxide. HAZARDOUS - Physical/Chemical Properties ALDRICH - 158399 www.sigma-aldrich.com Page 2 #12;Appearance Color: White Form

  17. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Vakni, David

    N/A EXTINGUISHING MEDIA Suitable: Water spray. Carbon dioxide, dry chemical powder, or appropriate DECOMPOSITION PRODUCTS Hazardous Decomposition Products: Carbon monoxide, Carbon dioxide. HAZARDOUS.sigma-aldrich.com Page 2 #12;Section 9 - Physical/Chemical Properties Appearance Physical State: Solid. Color: Very

  18. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Vakni, David

    : Water spray. Carbon dioxide, dry chemical powder, or appropriate foam. FIREFIGHTING Protective Equipment monoxide, Carbon dioxide. HAZARDOUS POLYMERIZATION Hazardous Polymerization: Will not occur Section 11. Section 9 - Physical/Chemical Properties Appearance Physical State: Solid. Color: White ALDRICH - 216941

  19. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    /A FLAMMABILITY N/A EXTINGUISHING MEDIA Suitable: Water spray. Carbon dioxide, dry chemical powder, or appropriate DECOMPOSITION PRODUCTS Hazardous Decomposition Products: Carbon monoxide, Carbon dioxide, Zinc/zinc oxides handling. Section 9 - Physical/Chemical Properties Appearance Physical State: Solid Color: White Form

  20. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    /A FLAMMABILITY N/A EXTINGUISHING MEDIA Suitable: Water spray. Carbon dioxide, dry chemical powder, or appropriate Decomposition Products: Carbon monoxide, Carbon dioxide. HAZARDOUS POLYMERIZATION Hazardous Polymerization/Chemical Properties Appearance Physical State: Solid Property Value At Temperature or Pressure Molecular Weight 204

  1. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Carbon dioxide, dry chemical powder, or appropriate foam. FIREFIGHTING Protective Equipment: Wear self DECOMPOSITION PRODUCTS Hazardous Decomposition Products: Carbon monoxide, Carbon dioxide, Sulfur oxides. GENERAL HYGIENE MEASURES Wash thoroughly after handling. Section 9 - Physical/Chemical Properties

  2. Guidance Document Material Safety Data Sheet

    E-Print Network [OSTI]

    and physical properties, health effects, fire/explosion data, reactivity, handling, storage, and personal

  3. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    to source of ignition and flash back. Container explosion may occur under fire conditions. FLASH POINT 59 °F, immediately flush eyes with copious amounts of water for at least 15 minutes. Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS Vapor may travel considerable distance

  4. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Section 5 - Fire Fighting Measures EXPLOSION HAZARDS May form explosive mixtures with air EXPLOSION DATA explosion. CONDITIONS OF FLAMMABILITY Static charges generated by emptying package in or near flammable vapors may cause flash fire. FLASH POINT N/A AUTOIGNITION TEMP 370 °C FLAMMABILITY N/A EXTINGUISHING

  5. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes Organic Peroxide: Yes EXPLOSION may occur under fire conditions. FLASH POINT 1.4 °F -17 °C Method: closed cup EXPLOSION LIMITS Lower (EU). Harmful. May form explosive peroxides. Harmful if swallowed. Irritating to eyes, respiratory

  6. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS Container explosion may occur under fire conditions. Forms explosive mixtures in air. FLASH POINT 89.6 °F 32 °C Method: closed cup EXPLOSION LIMITS Lower: 1.1 % Upper: 8.9 % AUTOIGNITION TEMP 480 °C FLAMMABILITY N

  7. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    explosion may occur under fire conditions. FLASH POINT 12 °F -11 °C Method: closed cup EXPLOSION LIMITS with fingers. Call a physician. Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS Vapor may travel considerable distance to source of ignition and flash back. Container

  8. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Container explosion may occur under fire conditions. FLASH POINT 17.6 °F -8 °C Method: closed cup EXPLOSION amounts of water for at least 15 minutes. Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS Vapor may travel considerable distance to source of ignition and flash back

  9. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    for at least 15 minutes. Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION may occur under fire conditions. FLASH POINT -14.8 °F -26 °C Method: closed cup EXPLOSION LIMITS Lower HAZARDS Vapor may travel considerable distance to source of ignition and flash back. Container explosion

  10. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS May explode when heated. Container explosion may occur under fire conditions. EXPLOSION DATA Sensitivity Section 3 - Hazards Identification EMERGENCY OVERVIEW Explosive. Toxic. Risk of explosion by shock

  11. SIGMA-ALDRICH Material Safety Data Sheet

    E-Print Network [OSTI]

    Rubloff, Gary W.

    under fire conditions. Explosion Hazards: Vapor may travel considerable distance to source of ignition and flash back. Container explosion may occur under fire conditions. SPECIAL PROTECTIVE EQUIPMENT a physician. 5 - Fire Fighting Measures EXTINGUISHING MEDIA Suitable: Water spray. Carbon dioxide, dry

  12. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS Vapor may fire conditions. Forms explosive mixtures in air. FLASH POINT 26.6 °F -3 °C Method: closed cup travel considerable distance to source of ignition and flash back. Container explosion may occur under

  13. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    . Section 5 - Fire Fighting Measures FLAMMABLE HAZARDS Flammable Hazards: Yes EXPLOSION HAZARDS Vapor may fire conditions. FLASH POINT 30 °F -1 °C Method: closed cup EXPLOSION LIMITS Lower: 1.8 % Upper: 10 travel considerable distance to source of ignition and flash back. Container explosion may occur under

  14. SIGMA-ALDRICH MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Choi, Kyu Yong

    cause fire. Risk of explosion by shock, friction, fire, or other sources of ignition. Irritating to eyes Fighting Measures EXPLOSION HAZARDS May explode when heated. Container explosion may occur under fire RTECS Number: DM8575000 Section 3 - Hazards Identification EMERGENCY OVERVIEW Explosive. Irritant. May

  15. SIGMA-ALDRICH Material Safety Data Sheet

    E-Print Network [OSTI]

    Choi, Kyu Yong

    RISKS Specific Hazard(s): Emits toxic fumes under fire conditions. Explosion Hazards: Container explosion may occur under fire conditions. SPECIAL PROTECTIVE EQUIPMENT FOR FIREFIGHTERS Wear self person is conscious. Call a physician. 5 - Fire Fighting Measures EXTINGUISHING MEDIA Suitable: Use water

  16. Nanoscale Materials Safety at the Department's Laboratories

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagement ofConverDyn NOPRNancy Sutley About Us Nancy Sutley U.S.

  17. Safety control circuit for a neutronic reactor

    DOE Patents [OSTI]

    Ellsworth, Howard C. (Richland, WA)

    2004-04-27T23:59:59.000Z

    A neutronic reactor comprising an active portion containing material fissionable by neutrons of thermal energy, means to control a neutronic chain reaction within the reactor comprising a safety device and a regulating device, a safety device including means defining a vertical channel extending into the reactor from an aperture in the upper surface of the reactor, a rod containing neutron-absorbing materials slidably disposed within the channel, means for maintaining the safety rod in a withdrawn position relative to the active portion of the reactor including means for releasing said rod on actuation thereof, a hopper mounted above the active portion of the reactor having a door disposed at the bottom of the hopper opening into the vertical channel, a plurality of bodies of neutron-absorbing materials disposed within the hopper, and means responsive to the failure of the safety rod on actuation thereof to enter the active portion of the reactor for opening the door in the hopper.

  18. Intermodal Transportation, USACE Style

    SciTech Connect (OSTI)

    Grumski, K. M.; Coutts, P. W.

    2002-02-27T23:59:59.000Z

    The US Army Corps of Engineers (USACE) has developed project management techniques with a proven track record for safe and successful results for constructing large scale and massive projects such as improving our nations water transportation systems, flood control, bridges and dams. Applying many of these techniques to the Formerly Utilized Sites Remedial Action Program (FUSRAP) managed by USACE to remediate the environment is achieving the same safe and successful results as their construction projects. This paper examines the additional economics and improved safety results of using intermodal containers and a combination of rail and truck transportation conveyances to transport the contaminated soil and debris from the Linde FUSRAP site, located in Tonawanda, New York.

  19. Acceptable NSLS Safety Documentation

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

    Acceptable NSLS Safety Documentation Print NSLS users who have completed NSLS Safety Module must present a copy of one of the following documents to receive ALS 1001: Safety at the...

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

    E-Print Network [OSTI]

    Natelson, Douglas

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

  1. RADIATION SAFETY TRAINING MANUAL Radiation Safety Office

    E-Print Network [OSTI]

    Sibille, Etienne

    protection and the potential risks of ionizing radiation. Radiation Safety Office personnel provide.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 II. OVERVIEW OF REGULATIONS, PROTECTION STANDARDS, AND RADIATION SAFETY ORGANIZATION.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 V. BASIC RADIATION PROTECTION PRINCIPLES

  2. Safety Aspects of Dry Spent Fuel Storage and Spent Fuel Management - 13559

    SciTech Connect (OSTI)

    Botsch, W.; Smalian, S.; Hinterding, P. [TUV NORD Nuclear c/o TUV NORD EnSys Hannover GmbH and Co.KG, Dept. Radiation Protection and Waste Disposal, Am TueV 1, 30519 Hannover (Germany)] [TUV NORD Nuclear c/o TUV NORD EnSys Hannover GmbH and Co.KG, Dept. Radiation Protection and Waste Disposal, Am TueV 1, 30519 Hannover (Germany); Voelzke, H.; Wolff, D.; Kasparek, E. [BAM Federal Institute for Materials Research and Testing Division 3.4 Safety of Storage Containers Unter den Eichen 44-46, 12203 Berlin (Germany)] [BAM Federal Institute for Materials Research and Testing Division 3.4 Safety of Storage Containers Unter den Eichen 44-46, 12203 Berlin (Germany)

    2013-07-01T23:59:59.000Z

    Dry storage systems are characterized by passive and inherent safety systems ensuring safety even in case of severe incidents or accidents. After the events of Fukushima, the advantages of such passively and inherently safe dry storage systems have become more and more obvious. As with the storage of all radioactive materials, the storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Following safety aspects must be achieved throughout the storage period: - safe enclosure of radioactive materials, - safe removal of decay heat, - securing nuclear criticality safety, - avoidance of unnecessary radiation exposure. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. Furthermore, transport capability must be guaranteed during and after storage as well as limitation and control of radiation exposure. The safe enclosure of radioactive materials in dry storage casks can be achieved by a double-lid sealing system with surveillance of the sealing system. The safe removal of decay heat must be ensured by the design of the storage containers and the storage facility. The safe confinement of radioactive inventory has to be ensured by mechanical integrity of fuel assembly structures. This is guaranteed, e.g. by maintaining the mechanical integrity of the fuel rods or by additional safety measures for defective fuel rods. In order to ensure nuclear critically safety, possible effects of accidents have also to be taken into consideration. In case of dry storage it might be necessary to exclude the re-positioning of fissile material inside the container and/or neutron moderator exclusion might be taken into account. Unnecessary radiation exposure can be avoided by the cask or canister vault system itself. In Germany dry storage of SF in casks fulfills both transport and storage requirements. Mostly, storage facilities are designed as concrete buildings above the ground, but due to regional constraints, one storage facility has also been built as a rock tunnel. The decay heat is always removed by natural air flow; further technical equipment is not needed. The removal of decay heat and shielding had been modeled and calculated by state-of-the-art computer codes before such a facility has been built. TueV and BAM present their long experience in the licensing process for sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel. Different storage systems and facilities in Germany, Europe and world-wide are compared with respect to the safety aspects mentioned above. Initial points are the safety issues of wet storage of SF, and it is shown how dry storage systems can ensure the compliance with the mentioned safety criteria over a long storage period. The German storage concept for dry storage of SF and HLW is presented and discussed. Exemplarily, the process of licensing, erection and operation of selected German dry storage facilities is presented. (authors)

  3. Chapter 13 Employee Health and Safety 13.04 Safety Committees

    E-Print Network [OSTI]

    Sheridan, Jennifer

    compliance in hazardous waste management, environmental permits and other issues related to chemical safety involving use of hazardous biological materials including recombinant DNA for compliance with NIH guidelines and tuberculosis prevention are areas of special concern. Contacts can be made with these committees or with safety

  4. (BSET) FIRE SAFETY ENGINEERING TECHNOLOGY CURRICULUM FOUR YEAR FIRE SAFETY CONCENTRATION CURRICULUM

    E-Print Network [OSTI]

    Raja, Anita

    (BSET) FIRE SAFETY ENGINEERING TECHNOLOGY CURRICULUM FOUR YEAR FIRE SAFETY CONCENTRATION CURRICULUM System ETFS 2144 3 Engineering Tech Computer Applic. ETGR 1100 3 Arts and Society3 LBST 110X3 3 21266 3 Hazardous Materials ETFS 2230 3 Fire Behavior & Combustion ETFS 2264 3 Building Construction

  5. Technical safety appraisal of the Naval Petroleum Reserve No. 1, Elk Hills, California

    SciTech Connect (OSTI)

    Not Available

    1989-04-01T23:59:59.000Z

    The existing Elk Hills facilities for fluid production consist of tank settings, gas and oil/water gathering pipelines, gas plants, compressor facilities, lease automatic custody transfer units which meter the crude oil going to sales, and natural gas sales meters and pipelines, water injection and source wells, and gas injection pipelines and wells. The principal safety concerns presented by operations at Elk Hills are fire, occupational safety and industrial hygiene considerations. Transportation and motor vehicle accidents are also of great concern because of the large amount of miles driven on more than 900 miles of roads. Typical operations involve hazardous materials and processing equipment such as vessels, compressors, boilers, piping and valves. The aging facilities, specifically the 35R Gas Plant (constructed in 1952) and many of the pipelines, introduce an additional element of hazard to the operations.

  6. COG - Special Features of Interest to Criticality Safety Practitioners

    SciTech Connect (OSTI)

    Buck, R M; Heinrichs, D P; Krass, A W; Lent, E M

    2010-01-14T23:59:59.000Z

    COG is a modern, general-purpose, high fidelity, multi-particle transport code developed at the Lawrence Livermore National Laboratory specifically for use in deep penetration (shielding) and criticality safety calculations. This paper describes some features in COG of special interest to criticality safety practitioners.

  7. DOE explosives safety manual. Revision 7

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    This manual prescribes the Department of Energy (DOE) safety rules used to implement the DOE safety policy for operations involving explosives. This manual is applicable to all DOE facilities engaged in operations of development, manufacturing, handling, storage, transportation, processing, or testing of explosives, pyrotechnics and propellants, or assemblies containing these materials. The standards of this manual deal with the operations involving explosives, pyrotechnics and propellants, and the safe management of such operations. The design of all new explosives facilities shall conform to the requirements established in this manual and implemented in DOE 6430.1A, ``General Design Criteria Manual.`` It is not intended that existing physical facilities be changed arbitrarily to comply with these provisions, except as required by law. Existing facilities that do not comply with these standards may continue to be used for the balance of their functional life, as long as the current operation presents no significantly greater risk than that assumed when the facility was originally designed and it can be demonstrated clearly that a modification to bring the facility into compliance is not feasible. However, in the case of a major renovation, the facility must be brought into compliance with current standards. The standards are presented as either mandatory or advisory. Mandatory standards, denoted by the words ``shall,`` ``must,`` or ``will,`` are requirements that must be followed unless written authority for deviation is granted as an exemption by the DOE. Advisory standards denoted by ``should`` or ``may`` are standards that may be deviated from with a waiver granted by facility management.

  8. Dam Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

    The Pennsylvania Department of Environmental Protection's Division of Dam Safety provides for the regulation and safety of dams and reservoirs throughout the Commonwealth in order to protect the...

  9. Pipeline Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

    The Pennsylvania legislature has empowered the Public Utility Commission to direct and enforce safety standards for pipeline facilities and to regulate safety practices of certificated utilities...

  10. SHSD Manager Safety Engineering Group Manager

    E-Print Network [OSTI]

    Safety, Machine Shop Safety, Tier I Program, Traffic Safety S. Moss: Nuclear Criticality Safety G. Shepherd: Explosives Safety, Facility Authorization Basis, Nuclear Safety R. Travis: Readiness Evaluations

  11. Environmental Health and Safety Fire and Life Safety Laboratory Assessment

    E-Print Network [OSTI]

    Environmental Health and Safety Fire and Life Safety Laboratory Assessment PI or environmental concerns were identified. B. Items of safety or environmental concerns were identified. C. Uncorrected repeated safety or environmental items were identified. Safety Equipment # Compliance Items

  12. LABORATORY SAFETY CHECKLIST Department of Environment, Health and Safety v.1.9 July 2014 Page 1

    E-Print Network [OSTI]

    Machel, Hans

    or radioactive waste have the appropriate label. b) Refrigerators and freezers used for radioactive material storage have the appropriate label. c) Equipment used to handle or manipulate radioactive material hasLABORATORY SAFETY CHECKLIST Department of Environment, Health and Safety v.1.9 July 2014 Page 1

  13. DEVELOPMENT OF THE HS99 AIR TRANSPORT TYPE A FISSILE PACKAGE

    SciTech Connect (OSTI)

    Blanton, P.; Eberl, K.

    2012-07-10T23:59:59.000Z

    An air-transport Type A Fissile radioactive shipping package for the transport of special form uranium sources has been developed by the Savannah River National Laboratory (SRNL) for the Department of Homeland Security. The Package model number is HS99 for Homeland Security Model 99. This paper presents the major design features of the HS99 and highlights engineered materials necessary for meeting the design requirements for this light-weight Type AF packaging. A discussion is provided demonstrating how the HS99 complies with the regulatory safety requirements of the Nuclear Regulatory Commission. The paper summarizes the results of structural testing to specified in 10 CFR 71 for Normal Conditions of Transport and Hypothetical Accident Conditions events. Planned and proposed future missions for this packaging are also addressed.

  14. Tank farms criticality safety manual

    SciTech Connect (OSTI)

    FORT, L.A.

    2003-03-27T23:59:59.000Z

    This document defines the Tank Farms Contractor (TFC) criticality safety program, as required by Title 10 Code of Federal Regulations (CFR), Subpart 830.204(b)(6), ''Documented Safety Analysis'' (10 CFR 830.204 (b)(6)), and US Department of Energy (DOE) 0 420.1A, Facility Safety, Section 4.3, ''Criticality Safety.'' In addition, this document contains certain best management practices, adopted by TFC management based on successful Hanford Site facility practices. Requirements in this manual are based on the contractor requirements document (CRD) found in Attachment 2 of DOE 0 420.1A, Section 4.3, ''Nuclear Criticality Safety,'' and the cited revisions of applicable standards published jointly by the American National Standards Institute (ANSI) and the American Nuclear Society (ANS) as listed in Appendix A. As an informational device, requirements directly imposed by the CRD or ANSI/ANS Standards are shown in boldface. Requirements developed as best management practices through experience and maintained consistent with Hanford Site practice are shown in italics. Recommendations and explanatory material are provided in plain type.

  15. SciTech Connect: Atomistic mechanisms of rapid energy transport...

    Office of Scientific and Technical Information (OSTI)

    (fuels), solid state lighting, charge transport, materials and chemistry by design, optics, synthesis (novel materials), synthesis (self-assembly), synthesis (scalable...

  16. West Valley Demonstration Project Transportation Emergency Management...

    Office of Environmental Management (EM)

    WVDP emergency management programs in dealing with transportation events involving hazardous materials (not related to nuclear weapons components), since the site is...

  17. Electrical and Thermoelectrical Transport Properties of Graphene

    E-Print Network [OSTI]

    Wang, Deqi

    2011-01-01T23:59:59.000Z

    IV Large Memory Effect in Graphene Based Devices IV-1Transport Properties of Graphene A Dissertation submitted into study the new material, graphene. By investigating the

  18. 2011 Annual Criticality Safety Program Performance Summary

    SciTech Connect (OSTI)

    Andrea Hoffman

    2011-12-01T23:59:59.000Z

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The TSR limits fuel plate bundles to 1085 grams U-235, which is the maximum loading of an ATR fuel element. The overloaded fuel plate bundle contained 1097 grams U-235 and was assembled under an 1100 gram U-235 limit in 1982. In 2003, the limit was reduced to 1085 grams citing a new criticality safety evaluation for ATR fuel elements. The fuel plate bundle inventories were not checked for compliance prior to implementing the reduced limit. A subsequent review of the NMIS inventory did not identify further violations. Requirements Management - The INL Criticality Safety program is organized and well documented. The source requirements for the INL Criticality Safety Program are from 10 CFR 830.204, DOE Order 420.1B, Chapter III, 'Nuclear Criticality Safety,' ANSI/ANS 8-series Industry Standards, and DOE Standards. These source requirements are documented in LRD-18001, 'INL Criticality Safety Program Requirements Manual.' The majority of the criticality safety source requirements are contained in DOE Order 420.1B because it invokes all of the ANSI/ANS 8-Series Standards. DOE Order 420.1B also invokes several DOE Standards, including DOE-STD-3007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities.' DOE Order 420.1B contains requirements for DOE 'Heads of Field Elements' to approve the criticality safety program and specific elements of the program, namely, the qualification of criticality staff and the method for preparing criticality safety evaluations. This was accomplished by the approval of SAR-400, 'INL Standardized Nuclear Safety Basis Manual,' Chapter 6, 'Prevention of Inadvertent Criticality.' Chapter 6 of SAR-400 contains sufficient detail and/or reference to the specific DOE and contractor documents that adequately describe the INL Criticality Safety Program per the elements specified in DOE Order 420.1B. The Safety Evaluation Report for SAR-400 specifically recognizes that the approval of SAR-400 approves the INL Criticality Safety Program. No new source requirements were released in 2011. A revision to LRD-18001 is

  19. Proving the Absence of RunTime Errors in SafetyCritical Avionics Code

    E-Print Network [OSTI]

    Cousot, Patrick

    , time­triggered, real­time, safety critical, embedded software as found in earth transportation, nuclearProving the Absence of Run­Time Errors in Safety­Critical Avionics Code Patrick Cousot École is not acceptable in safety and mission crit­ ical applications. An avenue is therefore opened for formal methods

  20. Automatic safety rod for reactors

    DOE Patents [OSTI]

    Germer, John H. (San Jose, CA)

    1988-01-01T23:59:59.000Z

    An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-core flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.

  1. Characterization of materials for a reactive transport model validation experiment: Interim report on the caisson experiment. Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Siegel, M.D.; Cheng, W.C. [Sandia National Labs., Albuquerque, NM (United States); Ward, D.B.; Bryan, C.R. [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Earth and Planetary Sciences

    1995-08-01T23:59:59.000Z

    Models used in performance assessment and site characterization activities related to nuclear waste disposal rely on simplified representations of solute/rock interactions, hydrologic flow field and the material properties of the rock layers surrounding the repository. A crucial element in the design of these models is the validity of these simplifying assumptions. An intermediate-scale experiment is being carried out at the Experimental Engineered Test Facility at Los Alamos Laboratory by the Los Alamos and Sandia National Laboratories to develop a strategy to validate key geochemical and hydrological assumptions in performance assessment models used by the Yucca Mountain Site Characterization Project.

  2. Westinghouse Earns Safety Excellence Award

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengtheningWildfiresImpurity Transport,12,Top Mine Safety AwardFor Immediate

  3. Small Column Ion Exchange Design and Safety Strategy

    SciTech Connect (OSTI)

    Huff, T.; Rios-Armstrong, M.; Edwards, R.; Herman, D.

    2011-02-07T23:59:59.000Z

    Small Column Ion Exchange (SCIX) is a transformational technology originally developed by the Department of Energy (DOE) Environmental Management (EM-30) office and is now being deployed at the Savannah River Site (SRS) to significantly increase overall salt processing capacity and accelerate the Liquid Waste System life-cycle. The process combines strontium and actinide removal using Monosodium Titanate (MST), Rotary Microfiltration, and cesium removal using Crystalline Silicotitanate (CST, specifically UOP IONSIV{reg_sign}IE-911 ion exchanger) to create a low level waste stream to be disposed in grout and a high level waste stream to be vitrified. The process also includes preparation of the streams for disposal, e.g., grinding of the loaded CST material. These waste processing components are technically mature and flowsheet integration studies are being performed including glass formulations studies, application specific thermal modeling, and mixing studies. The deployment program includes design and fabrication of the Rotary Microfilter (RMF) assembly, ion-exchange columns (IXCs), and grinder module, utilizing an integrated system safety design approach. The design concept is to install the process inside an existing waste tank, Tank 41H. The process consists of a feed pump with a set of four RMFs, two IXCs, a media grinder, three Submersible Mixer Pumps (SMPs), and all supporting infrastructure including media receipt and preparation facilities. The design addresses MST mixing to achieve the required strontium and actinide removal and to prevent future retrieval problems. CST achieves very high cesium loadings (up to 1,100 curies per gallon (Ci/gal) bed volume). The design addresses the hazards associated with this material including heat management (in column and in-tank), as detailed in the thermal modeling. The CST must be size reduced for compatibility with downstream processes. The design addresses material transport into and out of the grinder and includes provisions for equipment maintenance including remote handling. The design includes a robust set of nuclear safety controls compliant with DOE Standard (STD)-1189, Integration of Safety into the Design Process. The controls cover explosions, spills, boiling, aerosolization, and criticality. Natural Phenomena Hazards (NPH) including seismic event, tornado/high wind, and wildland fire are considered. In addition, the SCIX process equipment was evaluated for impact to existing facility safety equipment including the waste tank itself. SCIX is an innovative program which leverages DOE's technology development capabilities to provide a basis for a successful field deployment.

  4. Simplifying documentation while approaching site closure: integrated health & safety plans as documented safety analysis

    SciTech Connect (OSTI)

    Brown, Tulanda

    2003-06-01T23:59:59.000Z

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). By isolating any remediation activities that deal with Enriched Restricted Materials, the SBRs and PRs assure that the hazard categories of former nuclear facilities undergoing remediation remain less than Nuclear. These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D&D) of over 150 structures, including six major nuclear production plants. This paper presents the FCP method for maintaining safety basis documentation, using the D&D I-HASP as an example.

  5. Porous Materials Porous Materials

    E-Print Network [OSTI]

    Berlin,Technische Universität

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

  6. TWRS safety program plan

    SciTech Connect (OSTI)

    Calderon, L.M., Westinghouse Hanford

    1996-08-01T23:59:59.000Z

    Management of Nuclear Safety, Industrial Safety, Industrial Hygiene, and Fire Protection programs, functions, and field support resources for Tank Waste Remediation Systems (TWRS) has, until recently, been centralized in TWRS Safety, under the Emergency, Safety, and Quality organization. Industrial hygiene technician services were also provided to support operational needs related to safety basis compliance. Due to WHC decentralization of safety and reengineering efforts in West Tank Farms, staffing and safety responsibilities have been transferred to the facilities. Under the new structure, safety personnel for TWRS are assigned directly to East Tank Farms, West Tank Farms, and a core Safety Group in TWRS Engineering. The Characterization Project Operations (CPO) safety organization will remain in tact as it currently exists. Personnel assigned to East Tank Farms, West Tank Farms, and CPO will perform facility-specific or project-specific duties and provide field implementation of programs. Those assigned to the core group will focus on activities having a TWRS-wide or programmatic focus. Hanford-wide activities will be the responsibility of the Safety Center of Expertise. In order to ensure an effective and consistent safety program for TWRS under the new organization program functions, goals, organizational structure, roles, responsibilities, and path forward must be clearly established. The purpose of the TWRS Safety Program Plan is to define the overall safety program, responsibilities, relationships, and communication linkages for safety personnel under the new structure. In addition, issues associated with reorganization transition are addressed, including training, project ownership, records management, and dissemination of equipment. For the purpose of this document ``TWRS Safety`` refers to all safety professionals and technicians (Industrial Safety, Industrial Hygiene, Fire Protection, and Nuclear Safety) within the TWRS organization, regardless of their location in the organization.

  7. Department of Energy Construction Safety Reference Guide

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    DOE has adopted the Occupational Safety and Health Administration (OSHA) regulations Title 29 Code of Federal Regulations (CFR) 1926 ``Safety and Health Regulations for Construction,`` and related parts of 29 CFR 1910, ``Occupational Safety and Health Standards.`` This nonmandatory reference guide is based on these OSHA regulations and, where appropriate, incorporates additional standards, codes, directives, and work practices that are recognized and accepted by DOE and the construction industry. It covers excavation, scaffolding, electricity, fire, signs/barricades, cranes/hoists/conveyors, hand and power tools, concrete/masonry, stairways/ladders, welding/cutting, motor vehicles/mechanical equipment, demolition, materials, blasting, steel erection, etc.

  8. Construction safety program for the National Ignition Facility, Appendix A

    SciTech Connect (OSTI)

    Cerruti, S.J.

    1997-06-26T23:59:59.000Z

    Topics covered in this appendix include: General Rules-Code of Safe Practices; 2. Personal Protective Equipment; Hazardous Material Control; Traffic Control; Fire Prevention; Sanitation and First Aid; Confined Space Safety Requirements; Ladders and Stairways; Scaffolding and Lift Safety; Machinery, Vehicles, and Heavy Equipment; Welding and Cutting-General; Arc Welding; Oxygen/Acetylene Welding and Cutting; Excavation, Trenching, and Shoring; Fall Protection; Steel Erection; Working With Asbestos; Radiation Safety; Hand Tools; Electrical Safety; Nonelectrical Work Performed Near Exposed High-Voltage Power-Distribution Equipment; Lockout/Tagout Requirements; Rigging; A-Cranes; Housekeeping; Material Handling and Storage; Lead; Concrete and Masonry Construction.

  9. Oak Ridge National Laboratory Health and Safety Long-Range Plan: Fiscal years 1989--1995

    SciTech Connect (OSTI)

    Not Available

    1989-06-01T23:59:59.000Z

    The health and safety of its personnel is the first concern of ORNL and its management. The ORNL Health and Safety Program has the responsibility for ensuring the health and safety of all individuals assigned to ORNL activities. This document outlines the principal aspects of the ORNL Health and Safety Long-Range Plan and provides a framework for management use in the future development of the health and safety program. Each section of this document is dedicated to one of the health and safety functions (i.e., health physics, industrial hygiene, occupational medicine, industrial safety, nuclear criticality safety, nuclear facility safety, transportation safety, fire protection, and emergency preparedness). Each section includes functional mission and objectives, program requirements and status, a summary of program needs, and program data and funding summary. Highlights of FY 1988 are included.

  10. PHENOMENON OF CORROSION AND THE INDUSTRIAL SAFETY

    E-Print Network [OSTI]

    Bensaada S; Bouziane M. T; Mohammedi F; Achour B

    The problem of corrosion has taken nowadays a considerable importance considering the great use more and more of metals and alloys in our modern life. From the economic point of view and safety, the corrosion is a real thread. The replacement of corroded material composes for the industrie a financial burden which is very high. I taws estimated that more than 100 milliards of dollars constituting the yearly lusts caused by the corrosion in the American economy. The corrosion also can be translated by a modification and weakening of mechanical properties of corroded materials, consequentially it can’t fill in all safety its functions to which it is distinated. The aim of this study is to evident links which existed between corrosion and safety of materials and persons.

  11. Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities

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

    2007-02-07T23:59:59.000Z

    This standard provides a framework for generating Criticality Safety Evaluations (CSE) supporting fissionable material operations at Department of Energy (DOE) nonreactor nuclear facilities. This standard imposes no new criticality safety analysis requirements.

  12. Effect of doping, microstructure, and CO{sub 2} on La{sub 2}NiO{sub 4+{delta}}-based oxygen-transporting materials

    SciTech Connect (OSTI)

    Klande, Tobias, E-mail: tobias.klande@pci.uni-hannover.de [Institute of Physical Chemistry and Electrochemistry, Leibniz Universitaet Hannover, Callinstr. 3-3a, D-30179 Hannover (Germany); Efimov, Konstantin [Institute of Physical Chemistry and Electrochemistry, Leibniz Universitaet Hannover, Callinstr. 3-3a, D-30179 Hannover (Germany); Cusenza, Salvatore; Becker, Klaus-Dieter [Institute of Physical and Theoretical Chemistry, Technische Universitaet Braunschweig, Hans-Sommer-Str. 10, D-38106 Braunschweig (Germany); Feldhoff, Armin [Institute of Physical Chemistry and Electrochemistry, Leibniz Universitaet Hannover, Callinstr. 3-3a, D-30179 Hannover (Germany)

    2011-12-15T23:59:59.000Z

    Alkaline earth-free La{sub 2}NiO{sub 4+{delta}} based materials were synthesized by a sol-gel method and studied by X-ray diffraction (XRD), scanning electron microscopy (SEM) and transmission electron microscopy (TEM) techniques as well as oxygen permeation experiments. Effects of doping the nickel position with a variety of cations (Al, Co, Cu, Fe, Mg, Ta, and Zr) were investigated with regards to oxygen flux and microstructure. Doping was always found to diminish the oxygen flux as compared to the reference composition. However, larger grains, which were achieved by longer annealing times at 1723 K have a minor negative impact on oxygen permeation flux in case of La{sub 2}NiO{sub 4+{delta}} and La{sub 2}Ni{sub 0.9}Fe{sub 0.1}O{sub 4+{delta}} system. Moessbauer spectroscopy shows that the iron-doped system exhibits a secondary phase, which was identified by high-resolution transmission electron microscopy (HRTEM) as a higher Ruddlesden-Popper phase. In-situ XRD in an atmosphere containing 50 vol% CO{sub 2} and long-term oxygen permeation experiments using pure CO{sub 2} as the sweep gas revealed a high tolerance of the materials towards CO{sub 2}. - Graphical Abstract: The vibrational polished La{sub 2}Ni{sub 0.9}Fe{sub 0.1}O{sub 4+{delta}} membrane revealed formation of secondary phases, which were confirmed by Moessbauer spectroscopy. Highlights: Black-Right-Pointing-Pointer La{sub 2}NiO{sub 4+{delta}} systematically doped with different valent cations. Black-Right-Pointing-Pointer Large grains have a negative impact on oxygen-permeation performance. Black-Right-Pointing-Pointer CO{sub 2}-stability proved by in-situ XRD in 50 vol% CO{sub 2}. Black-Right-Pointing-Pointer Constant long-term permeation in presence of CO{sub 2}. Black-Right-Pointing-Pointer Moessbauer and TEM reveal multiple phases in La{sub 2}Ni{sub 0.9}Fe{sub 0.1}O{sub 4+{delta}} system.

  13. Overview of experimental support for fission-product transport analyses at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Wichner, R.P.

    1983-01-01T23:59:59.000Z

    The program was designed to determine fission product and aerosol release rates from irradiated fuel under accident conditions, to identify the chemical forms of the released material, and to correlate the results with experimental and specimen conditions with the data from related experiments. These tests of PWR fuel were conducted and fuel specimen and test operating data are presented. The nature and rate of fission product vapor interaction with aerosols were studied. Aerosol deposition rates and transport in the reactor vessel during LWR core-melt accidents were studied. The Nuclear Safety Pilot Plant is dedicated to developing an expanded data base on the behavior of aerosols generated during a severe accident.

  14. NREL Simulations Provide New Insight on Polymer-Based Energy Storage Materials (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-08-01T23:59:59.000Z

    Atomistic simulations correlate molecular packing and electron transport in polymer-based energy storage materials.

  15. Coal Mine Safety Act (Virginia)

    Broader source: Energy.gov [DOE]

    This Act is the primary legislation pertaining to coal mine safety in Virginia. It contains information on safety rules, safety standards and required certifications for mine workers, prohibited...

  16. Nuclear Safety Research and Development...

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

    Nuclear Safety Research and Development Proposal Review and Prioritization Process and Criteria Nuclear Safety Research and Development Program Office of Nuclear Safety Office of...

  17. Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

    SciTech Connect (OSTI)

    Koponen, B.L.; Hampel, V.E.

    1982-10-21T23:59:59.000Z

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

  18. Magnetic Field Safety Magnetic Field Safety

    E-Print Network [OSTI]

    McQuade, D. Tyler

    Magnetic Field Safety Training #12;Magnetic Field Safety Strong Magnetic Fields exist around energized magnets. High magnetic fields alone are a recognized hazard only for personnel with certain medical conditions such as pacemakers, magnetic implants, or embedded shrapnel. In addition, high magnetic

  19. RECERTIFICATION OF THE MODEL 9977 RADIOACTIVE MATERIAL PACKAGING

    SciTech Connect (OSTI)

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

    2013-06-05T23:59:59.000Z

    The Model 9977 Packaging was initially issued a Certificate of Compliance (CoC) by the Department of Energy’s Office of Environmental Management (DOE-EM) for the transportation of radioactive material (RAM) in the Fall of 2007. This first CoC was for a single radioactive material and two packing configurations. In the five years since that time, seven Addendums have been written to the Safety Analysis Report for Packaging (SARP) and five Letter Amendments have been written that have authorized either new RAM contents or packing configurations, or both. This paper will discuss the process of updating the 9977 SARP to include all the contents and configurations, including the addition of a new content, and its submittal for recertification.

  20. EC Transmission Line Materials

    SciTech Connect (OSTI)

    Bigelow, Tim S [ORNL

    2012-05-01T23:59:59.000Z

    The purpose of this document is to identify materials acceptable for use in the US ITER Project Office (USIPO)-supplied components for the ITER Electron cyclotron Heating and Current Drive (ECH&CD) transmission lines (TL), PBS-52. The source of material property information for design analysis shall be either the applicable structural code or the ITER Material Properties Handbook. In the case of conflict, the ITER Material Properties Handbook shall take precedence. Materials selection, and use, shall follow the guidelines established in the Materials Assessment Report (MAR). Materials exposed to vacuum shall conform to the ITER Vacuum Handbook. [Ref. 2] Commercial materials shall conform to the applicable standard (e.g., ASTM, JIS, DIN) for the definition of their grade, physical, chemical and electrical properties and related testing. All materials for which a suitable certification from the supplier is not available shall be tested to determine the relevant properties, as part of the procurement. A complete traceability of all the materials including welding materials shall be provided. Halogenated materials (example: insulating materials) shall be forbidden in areas served by the detritiation systems. Exceptions must be approved by the Tritium System and Safety Section Responsible Officers.

  1. International Experience in Transportation Analysis and Planning

    E-Print Network [OSTI]

    material transportation regulatory training in association with the IAEA in the People's Republic of China. ORNL staff worked with Ministry of Transport of the People's Republic of China to train staff;Center for Transportation Analysis 2360 Cherahala Boulevard Knoxville, TN 37932 865-946-1311 Website: cta.ornl.gov

  2. Safety Issues Chemical Storage

    E-Print Network [OSTI]

    Cohen, Robert E.

    Safety Issues · Chemical Storage ·Store in compatible containers that are in good condition to store separately. #12;Safety Issues · Flammable liquid storage -Store bulk quantities in flammable storage cabinets -UL approved Flammable Storage Refrigerators are required for cold storage · Provide

  3. Office of Nuclear Safety

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Safety establishes nuclear safety requirements and expectations for the Department to ensure protection of workers and the public from the hazards associated with nuclear operations with all Department operations.

  4. Dam Safety Program (Maryland)

    Broader source: Energy.gov [DOE]

    The Dam Safety Division within the Department of the Environment is responsible for administering a dam safety program to regulate the construction, operation, and maintenance of dams to prevent...

  5. Dam Safety (Delaware)

    Broader source: Energy.gov [DOE]

    The Delaware Dam Safety Law was adopted in 2004 and provides the framework for proper design, construction, operation, maintenance, and inspection of dams in the interest of public health, safety,...

  6. MSE 891: Materials for Energy Applications Spring 2010

    E-Print Network [OSTI]

    include: unconventional geologic fuels and biofuels; photovoltaic materials and solar energy conversion: thermoelectric materials Thermal and electrical transport properties; model systems Morelli Feb 1, 3 Module I

  7. Low Cost Carbon Fiber Research in the ALM Materials Program

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

    Carbon Fiber Research in the ALM Materials Program 27 February 2008 C. David (Dave) Warren Field Technical Manager Transportation Composite Materials Research Oak Ridge National...

  8. Nuclear Explosive Safety Manual

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

    2009-04-14T23:59:59.000Z

    This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

  9. DOE handbook electrical safety

    SciTech Connect (OSTI)

    NONE

    1998-01-01T23:59:59.000Z

    Electrical Safety Handbook presents the Department of Energy (DOE) safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety guidance and information for DOE installations to effect a reduction or elimination of risks associated with the use of electrical energy. The objectives of this handbook are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  10. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  11. Department of Environmental Health & Safety Emergency Management

    E-Print Network [OSTI]

    O'Toole, Alice J.

    Management Fire & Life Safety Industrial Hygiene Laboratory Safety Occupational & General Safety Management Environmental Management Fire & Life Safety Industrial Hygiene Laboratory Safety Occupational Values A Note from the Director Environmental Management Fire & Life Safety Lab Safety & Industrial

  12. Environmental Health & Safety

    E-Print Network [OSTI]

    Environmental Health & Safety Sub Department Name 480 Oak Rd, Stanford, CA 94305 T 650.723.0448 F 650.725.3468 DEPUTY DIRECTOR, ENVIRONMENTAL HEALTH AND SAFETY Exempt, Full-Time (100% FTE) Posted May 1, 2014 The Department of Environmental Health and Safety (EH&S) at Stanford University seeks

  13. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

    Report of Earth Sciences Departmental Safety Committee 2011 - 12 5 Chemical Safety 21 - 22 Chemical Waste Assessment Hire Vehicle Checklist Department Driving Protocol: Bullard vehicles 38 - 48 Electrical Safety 24 and outside adjacent to areas which present a particular fire hazard. Persons wishing to smoke are asked to do

  14. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

    Report of Earth Sciences Departmental Safety Committee 2012 - 13 5 Chemical Safety 21 - 22 Chemical Waste Assessment Hire Vehicle Checklist Department Driving Protocol: Bullard vehicles 38 - 48 Electrical Safety 24 and outside adjacent to areas which present a particular fire hazard. Persons wishing to smoke are asked to do

  15. Computational Transportation

    E-Print Network [OSTI]

    Illinois at Chicago, University of

    ), in-vehicle computers, and computers in the transportation infrastructure are integrated ride- sharing, real-time multi-modal routing and navigation, to autonomous/assisted driving

  16. September 2013 Laboratory Safety Manual Section 7 -Safety Training

    E-Print Network [OSTI]

    Wilcock, William

    September 2013 Laboratory Safety Manual Section 7 - Safety Training UW Environmental Health and Safety Page 7-1 Section 7 - Safety Training Contents A. SAFETY TRAINING REQUIREMENTS ......................................................7-1 B. EH&S SAFETY TRAINING AND RECORDS ..............................................7-1 C

  17. Safety Manual Prepared by the

    E-Print Network [OSTI]

    Alpay, S. Pamir

    -3113 Emergency maintenance to report a water leak, electrical outage, non-working fume hood, etc. after normal Radiation and Laser Safety 19 Laser Safety 21 Compressed Gas and Cryogenic Safety 22 Electrical Safety 24

  18. Material Challenges and Perspectives

    SciTech Connect (OSTI)

    Choi, Daiwon; Wang, Wei; Yang, Zhenguo

    2011-12-14T23:59:59.000Z

    General history and principals of Li-ion battery, characterization techniques and terminology of its operation will be discussed and explained. Current Li-ion battery applications and comparison to other energy storage and conversion systems will be outlined. Chemistry, material and design of currently commercialized Li-ion batteries will be discussed including various electrode materials for cathodes and anodes. The electrode material candidates and its physical and chemical properties including crystal structure, capacity, cycling stability, cost and safety. Also, current limitations of Li-ion batteries will be discussed.

  19. Pressure Safety Program Implementation at ORNL

    SciTech Connect (OSTI)

    Lower, Mark [ORNL; Etheridge, Tom [ORNL; Oland, C. Barry [XCEL Engineering, Inc.

    2013-01-01T23:59:59.000Z

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply with pressure safety requirements in 10 CFR 851. It also describes actions taken to develop and implement ORNL’s Pressure Safety Program.

  20. Appendix A. Material Safety Data Sheets for Drilling Mud MATERIAL SAFETY DATA SHEET

    E-Print Network [OSTI]

    Torgersen, Christian

    -contained breathing apparatus required for fire fighting personnel. NFPA Ratings: Health 1, Flammability 0, Reactivity: Off white Odor: Odorless pH: 7.75 (1%) Specific Gravity @ 20 C (Water=1): 0.8-1.0 Density @ 20 C (lbs