National Library of Energy BETA

Sample records for rail shipment accident

  1. Naval Spent Fuel Rail Shipment Accident Exercise Objectives ...

    Office of Environmental Management (EM)

    Naval Spent Fuel Rail Shipment Accident Exercise Objectives Naval Spent Fuel Rail Shipment Accident Exercise Objectives PDF icon Naval Spent Fuel Rail Shipment Accident Exercise ...

  2. Moab Resumes Rail Shipments After Rockslide

    Broader source: Energy.gov [DOE]

    MOAB, Utah – EM’s Moab Uranium Mill Tailings Remedial Action Project recently resumed rail shipments after an almost two-month halt due to a major rockslide.

  3. 2015 EIA Energy Conference Crude Shipments and Rail Prioritization: A Shipper Perspective

    U.S. Energy Information Administration (EIA) Indexed Site

    Energy Conference Crude Shipments and Rail Prioritization: A Shipper Perspective Presented by: Jamie Heller Hellerworx, Inc. 301-654-1980 jamie@hellerworx.com Washington, DC, June 16, 2015 Presentation to: 2 * 2 Everyone Wants Flexibility! * Pipeline cheaper than rail, but ... * Shippers follow favorable basis differentials * Railroads redeploy assets as traffic shifts * Excess capacity costs money - no one wants to pay * Planning helps, but this is oil trading 3 Barge Movements of Crude 4

  4. Naval Spent Fuel Rail Shipment Accident Exercise Objectives

    Office of Environmental Management (EM)

    NAVAJO TRIBAL UTILITY NAVAJO TRIBAL UTILITY AUTHORITY AUTHORITY N a v a j o E l e c t r i f i c a t i o n D e m o n s t r a t i o n N a v a j o E l e c t r i f i c a t i o n D e m o n s t r a t i o n P r o g r a m P r o g r a m U.S. Department of Energy Tribal Energy Program 2004 Program Review Meeting Golden, Colorado October 20, 2004 Presented By: Paul Denetclaw Jr.- Electric Engineer Supervisor Larry Ahasteen- Renewable Energy Specialist Overview of NTUA Presentation Overview of NTUA

  5. Fall Protection Procedures for Sealing Bulk Waste Shipments by Rail Cars at Formerly Utilized Sites Remedial Action Program (FUSRAP) Sites - 13509

    SciTech Connect (OSTI)

    Boyle, J.D.; Fort, E. Joseph; Lorenz, William; Mills, Andy

    2013-07-01

    Rail-cars loaded with radioactive materials must be closed and fastened to comply with United States Department of Transportation (DOT) requirements before they shipped. Securing waste shipments in a manner that meets these regulations typically results in the use of a sealable rail-car liner. Workers accessing the tops of the 2.74 m high rail-cars to seal and inspect liners for compliance prior to shipment may be exposed to a fall hazard. Relatively recent revisions to the Fall Protection requirements in the Safety and Health Requirements Manual (EM385-1-1, U.S. Army Corps of Engineers) have necessitated modifications to the fall protection systems previously employed for rail-car loading at Formerly Utilized Sites Remedial Action Program (FUSRAP) sites. In response these projects have developed site-specific procedures to protect workers and maintain compliance with the improved fall protection regulations. (authors)

  6. Microsoft PowerPoint - Rail_Kneitel [Compatibility Mode]

    Office of Environmental Management (EM)

    1 Shipping Radioactive Waste by Rail from Brookhaven National Laboratory Terri Kneitel, PE, PMP U.S. Department of Energy National Transportation Stakeholders Forum May 14, 2014 2 Discussion Topics * Why Rail? * How is waste shipped? * What do we ship by rail? * DOT Requirements * Where does the waste go? * Logistics * BNL Rail Shipment Overview * Extensive Outreach - BNL Transportation Working Group * BNL Rail Shipment & Notification Protocols 5/16/2014 2 3 Why Rail? Rail * 1 car hauls

  7. Rail Coal Transportation Rates to the Electric Power Sector

    Gasoline and Diesel Fuel Update (EIA)

    modes, the Coal Waybill Data is based only on rail shipments. Due to the different nature of the data sources, users should exercise caution when attempting to combine the two...

  8. Microsoft Word - Unrelated Accident

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

    For Immediate Release Truck Accident Did Not Involve WIPP Shipment CARLSBAD, N.M., October 1, 2009 - A Wednesday night truck accident north of Albuquerque on Highway 165 that ...

  9. Overseas shipments of 48Y cylinders

    SciTech Connect (OSTI)

    Tanaka, R.T.; Furlan, A.S.

    1991-12-31

    This paper describes experiences with two incidents of overseas shipments of uranium hexafluoride (UF{sub 6}) cylinders. The first incident involved nine empty UF{sub 6} cylinders in enclosed sea containers. Three UF{sub 6} cylinders broke free from their tie-downs and damaged and contaminated several sea containers. This paper describes briefly how decontamination was carried out. The second incident involved a shipment of 14 full UF{sub 6} cylinders. Although the incident did not cause an accident, the potential hazard was significant. The investigation of the cause of the near accident is recounted. Recommendations to alleviate future similar incidents for both cases are presented.

  10. Assessment of the risk of transporting liquid chlorine by rail

    SciTech Connect (OSTI)

    Andrews, W.B.

    1980-03-01

    This report presents the risk of shipping liquid chlorine by rail. While chlorine is not an energy material, there are several benefits to studying chlorine transportation risks. First, chlorine, like energy materials, is widely used as a feedstock to industry. Second, it is the major purification agent in municipal water treatment systems and therefore, provides direct benefits to the public. Finally, other risk assessments have been completed for liquid chlorine shipments in the US and Europe, which provide a basis for comparison with this study. None of the previous PNL energy material risk assessments have had other studies for comparison. For these reasons, it was felt that a risk assessment of chlorine transportation by rail could provide information on chlorine risk levels, identify ways to reduce these risks and use previous studies on chlorine risks to assess the strengths and weaknesses of the PNL risk assessment methodology. The risk assessment methodology used in this study is summarized. The methodology is presented in the form of a risk assessment model which is constructed for ease of periodic updating of the data base so that the risk may be reevaluated as additional data become available. The report is sectioned to correspond to specific analysis steps identified in the model. The transport system and accident environment are described. The response of the transport system to accident environments is described. Release sequences are postulated and evaluated to determine both the likelihood and possible consequences of a release. Supportive data and analyses are given in the appendices. The risk assessment results are related to the year 1985 to allow a direct comparison with other reports in this series.

  11. 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.

    1999-04-15

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

  12. RAIL ROUTING PRACTICES AND PROPOSED ALTERNATIVES

    Office of Environmental Management (EM)

    on "Strawman" Report: RAIL ROUTING PRACTICES AND PROPOSED ALTERNATIVES Number Section Comment Response RTG-1-AAR SECTION II Safeguards Routing Regulations, Para. 2 The NRC has identified five types of route characteristics that receive special consideration when NRC staff review routes for approval pursuant to 10 CFR 73: (1) routes through highly populated areas; (2) routes that would place the shipment or escort vehicle in a significantly disadvantageous position (for example, tunnels

  13. SGP Shipment Notification Form

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

    PlainsShipment Notification Form SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric...

  14. AIR SHIPMENT OF SPENT NUCLEAR FUEL FROM THE BUDAPEST RESEARCH REACTOR

    SciTech Connect (OSTI)

    Dewes, J.

    2014-02-24

    The shipment of spent nuclear fuel is usually done by a combination of rail, road or sea, as the high activity of the SNF needs heavy shielding. Air shipment has advantages, e.g. it is much faster than any other shipment and therefore minimizes the transit time as well as attention of the public. Up to now only very few and very special SNF shipments were done by air, as the available container (TUK6) had a very limited capacity. Recently Sosny developed a Type C overpack, the TUK-145/C, compliant with IAEA Standard TS-R-1 for the VPVR/M type Skoda container. The TUK-145/C was first used in Vietnam in July 2013 for a single cask. In October and November 2013 a total of six casks were successfully shipped from Hungary in three air shipments using the TUK-145/C. The present paper describes the details of these shipments and formulates the lessons learned.

  15. HOW MANY DID YOU SAY? HISTORICAL AND PROJECTED SPENT NUCLEAR FUEL SHIPMENTS IN THE UNITED STATES, 1964 - 2048

    SciTech Connect (OSTI)

    Halstead, Robert J.; Dilger, Fred

    2003-02-27

    No comprehensive, up-to-date, official database exists for spent nuclear fuel shipments in the United States. The authors review the available data sources, and conclude that the absence of such a database can only be rectified by a major research effort, similar to that carried out by Oak Ridge National Laboratory (ORNL) in the early 1990s. Based on a variety of published references, and unpublished data from the U.S. Nuclear Regulatory Commission (NRC), the authors estimate cumulative U.S. shipments of commercial spent fuel for the period 1964-2001. The cumulative estimates include quantity shipped, number of cask-shipments, and shipment-miles, by truck and by rail. The authors review previous estimates of future spent fuel shipments, including contractor reports prepared for the U.S. Department of Energy (DOE), NRC, and the State of Nevada. The DOE Final Environmental Impact Statement (FEIS) for Yucca Mountain includes projections of spent nuclear fuel and high-level radioactive was te shipments for two inventory disposal scenarios (24 years and 38 years) and two national transportation modal scenarios (''mostly legal-weight truck'' and ''mostly rail''). Commercial spent fuel would compromise about 90 percent of the wastes shipped to the repository. The authors estimate potential shipments to Yucca Mountain over 38 years (2010-2048) for the DOE ''mostly legal-weight truck'' and ''mostly rail'' scenarios, and for an alternative modal mix scenario based on current shipping capabilities of the 72 commercial reactor sites. The cumulative estimates of future spent fuel shipments include quantity shipped, number of cask-shipments, and shipment-miles, by legal-weight truck, heavy-haul truck, rail and barge.

  16. Coal-by-Rail Business-as-Usual Reference Case

    Broader source: Energy.gov [DOE]

    As proposed carbon emission standards reduce domestic coal use, the role of coal in the U.S. energy mix may be expected to decline. If such a decline were to occur, how would it affect rail traffic? Today, coal represents a major share of rail tonnage and gross revenue. While growth in other traffic―most notably, crude oil―may offset some of any potential decline in coal shipments, would it be sufficient? This paper explores trends in coal production volumes and use, rail tonnage and revenue, and the distribution of traffic origins and destinations in order to consider the impact of potential changes in future coal traffic. Rather than modeling discrete flows, it draws on historical data and forecasts maintained by the U.S. Department of Energy’s Energy Information Administration (EIA), industry studies and analyses, and background knowledge of the rail industry, specific routes and service territories, and commodity-level traffic volumes.

  17. Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections...

    Office of Environmental Management (EM)

    of Spent Nuclear Fuel Task: Identify Shortline Railroads Serving Nuclear Power Plants Establish Contact Information with Railroads Officials Field Review of each ...

  18. Full-Scale Cask Testing and Public Acceptance of Spent Nuclear Fuel Shipments - 12254

    SciTech Connect (OSTI)

    Dilger, Fred; Halstead, Robert J.; Ballard, James D.

    2012-07-01

    Full-scale physical testing of spent fuel shipping casks has been proposed by the National Academy of Sciences (NAS) 2006 report on spent nuclear fuel transportation, and by the Presidential Blue Ribbon Commission (BRC) on America's Nuclear Future 2011 draft report. The U.S. Nuclear Regulatory Commission (NRC) in 2005 proposed full-scale testing of a rail cask, and considered 'regulatory limits' testing of both rail and truck casks (SRM SECY-05-0051). The recent U.S. Department of Energy (DOE) cancellation of the Yucca Mountain project, NRC evaluation of extended spent fuel storage (possibly beyond 60-120 years) before transportation, nuclear industry adoption of very large dual-purpose canisters for spent fuel storage and transport, and the deliberations of the BRC, will fundamentally change assumptions about the future spent fuel transportation system, and reopen the debate over shipping cask performance in severe accidents and acts of sabotage. This paper examines possible approaches to full-scale testing for enhancing public confidence in risk analyses, perception of risk, and acceptance of spent fuel shipments. The paper reviews the literature on public perception of spent nuclear fuel and nuclear waste transportation risks. We review and summarize opinion surveys sponsored by the State of Nevada over the past two decades, which show consistent patterns of concern among Nevada residents about health and safety impacts, and socioeconomic impacts such as reduced property values along likely transportation routes. We also review and summarize the large body of public opinion survey research on transportation concerns at regional and national levels. The paper reviews three past cask testing programs, the way in which these cask testing program results were portrayed in films and videos, and examines public and official responses to these three programs: the 1970's impact and fire testing of spent fuel truck casks at Sandia National Laboratories, the 1980's regulatory and demonstration testing of MAGNOX fuel flasks in the United Kingdom (the CEGB 'Operation Smash Hit' tests), and the 1980's regulatory drop and fire tests conducted on the TRUPACT II containers used for transuranic waste shipments to the Waste Isolation Pilot Plant in New Mexico. The primary focus of the paper is a detailed evaluation of the cask testing programs proposed by the NRC in its decision implementing staff recommendations based on the Package Performance Study, and by the State of Nevada recommendations based on previous work by Audin, Resnikoff, Dilger, Halstead, and Greiner. The NRC approach is based on demonstration impact testing (locomotive strike) of a large rail cask, either the TAD cask proposed by DOE for spent fuel shipments to Yucca Mountain, or a similar currently licensed dual-purpose cask. The NRC program might also be expanded to include fire testing of a legal-weight truck cask. The Nevada approach calls for a minimum of two tests: regulatory testing (impact, fire, puncture, immersion) of a rail cask, and extra-regulatory fire testing of a legal-weight truck cask, based on the cask performance modeling work by Greiner. The paper concludes with a discussion of key procedural elements - test costs and funding sources, development of testing protocols, selection of testing facilities, and test peer review - and various methods of communicating the test results to a broad range of stakeholder audiences. (authors)

  19. Longitudinal review of state-level accident statistics for carriers of interstate freight

    SciTech Connect (OSTI)

    Saricks, C.; Kvitek, T.

    1994-03-01

    State-level accident rates by mode of freight transport have been developed and refined for application to the US Department of Energy`s (DOE`s) environmental mitigation program, which may involve large-quantity shipments of hazardous and mixed wastes from DOE facilities. These rates reflect multi-year data for interstate-registered highway earners, American Association of Railroads member carriers, and coastal and internal waterway barge traffic. Adjustments have been made to account for the share of highway combination-truck traffic actually attributable to interstate-registered carriers and for duplicate or otherwise inaccurate entries in the public-use accident data files used. State-to-state variation in rates is discussed, as is the stability of rates over time. Computed highway rates have been verified with actual carriers of high- and low-level nuclear materials, and the most recent truck accident data have been used, to ensure that the results are of the correct order of magnitude. Study conclusions suggest that DOE use the computed rates for the three modes until (1) improved estimation techniques for highway combination-truck miles by state become available; (2) continued evolution of the railroad industry significantly increases the consolidation of interstate rail traffic onto fewer high-capacity trunk lines; or (3) a large-scale off-site waste shipment campaign is imminent.

  20. Rail Coal Transportation Rates

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    EIA uses the confidential version of the STB Waybill data, which includes actual revenue for shipments that originate and terminate at specific locations. The STB Waybill...

  1. WIPP Receives 200th Shipment

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

    200 th Shipment CARLSBAD, N.M., April 18, 2001 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) today received its 200 th shipment of defense- generated transuranic radioactive waste. The shipment came from DOE's Rocky Flats Environmental Technology Site (RFETS) in Colorado. "The arrival of the 200 th shipment of waste to WIPP exhibits the safety of our transportation system. This marks another major milestone for WIPP as we work toward cleanup of transuranic waste

  2. Radial arm strike rail

    DOE Patents [OSTI]

    McKeown, Mark H.; Beason, Steven C.

    1991-01-01

    The radial arm strike rail assembly is a system for measurement of bearings, directions, and stereophotography for geologic mapping, particularly where magnetic compasses are not appropriate. The radial arm, pivoting around a shaft axis, provides a reference direction determination for geologic mapping and bearing or direction determination. The centerable and levelable pedestal provide a base for the radial arm strike rail and the telescoping camera pedestal. The telescoping feature of the radial arm strike rail allows positioning the end of the rail for strike direction or bearing measurement with a goniometer.

  3. RH_SRS_Shipment

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

    WIPP Trucks Delivering First Remote-Handled Transuranic Waste from the Savannah River Site CARLSBAD, N.M., June 11, 2012- Photo caption: On June 7, 2012, Waste Isolation Pilot Plant (WIPP) trucks approach the WIPP facility near Carlsbad, New Mexico, with the first shipment of defense- related remote-handled transuranic (TRU) waste from Savannah River Site (SRS), near Aiken, South Carolina. TRU waste consists of materials contaminated with radioactive elements that have atomic numbers greater

  4. Air Shipment of Spent Nuclear Fuel from Romania to Russia

    SciTech Connect (OSTI)

    Igor Bolshinsky; Ken Allen; Lucian Biro; Alexander Buchelnikov

    2010-10-01

    Romania successfully completed the worlds first air shipment of spent nuclear fuel transported in Type B(U) casks under existing international laws and without shipment license special exceptions when the last Romanian highly enriched uranium (HEU) spent nuclear fuel was transported to the Russian Federation in June 2009. This air shipment required the design, fabrication, and licensing of special 20 foot freight containers and cask tiedown supports to transport the eighteen TUK 19 shipping casks on a Russian commercial cargo aircraft. The new equipment was certified for transport by road, rail, water, and air to provide multi modal transport capabilities for shipping research reactor spent fuel. The equipment design, safety analyses, and fabrication were performed in the Russian Federation and transport licenses were issued by both the Russian and Romanian regulatory authorities. The spent fuel was transported by truck from the VVR S research reactor to the Bucharest airport, flown by commercial cargo aircraft to the airport at Yekaterinburg, Russia, and then transported by truck to the final destination in a secure nuclear facility at Chelyabinsk, Russia. This shipment of 23.7 kg of HEU was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), as part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in close cooperation with the Rosatom State Atomic Energy Corporation and the International Atomic Energy Agency, and was managed in Romania by the National Commission for Nuclear Activities Control (CNCAN). This paper describes the planning, shipment preparations, equipment design, and license approvals that resulted in the safe and secure air shipment of this spent nuclear fuel.

  5. Waste Shipment Approval - Hanford Site

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

    About Us Hanford Site Wide Programs Hanford Site Solid Waste Acceptance Program Acceptance Process Waste Shipment Approval About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast and Funding Arrangements Waste Stream Approval Waste Shipment Approval Waste Receipt Quality Assurance Program Waste Specification Records Tools Points of Contact Waste Shipment Approval Email Email Page | Print Print

  6. AIR SHIPMENT OF HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL FROM ROMANIA AND LIBYA

    SciTech Connect (OSTI)

    Christopher Landers; Igor Bolshinsky; Ken Allen; Stanley Moses

    2010-07-01

    In June 2009 Romania successfully completed the worlds first air shipment of highly enriched uranium (HEU) spent nuclear fuel transported in Type B(U) casks under existing international laws and without special exceptions for the air transport licenses. Special 20-foot ISO shipping containers and cask tiedown supports were designed to transport Russian TUK 19 shipping casks for the Romanian air shipment and the equipment was certified for all modes of transport, including road, rail, water, and air. In December 2009 Libya successfully used this same equipment for a second air shipment of HEU spent nuclear fuel. Both spent fuel shipments were transported by truck from the originating nuclear facilities to nearby commercial airports, were flown by commercial cargo aircraft to a commercial airport in Yekaterinburg, Russia, and then transported by truck to their final destinations at the Production Association Mayak facility in Chelyabinsk, Russia. Both air shipments were performed under the Russian Research Reactor Fuel Return Program (RRRFR) as part of the U.S. National Nuclear Security Administration (NNSA) Global Threat Reduction Initiative (GTRI). The Romania air shipment of 23.7 kg of HEU spent fuel from the VVR S research reactor was the last of three HEU fresh and spent fuel shipments under RRRFR that resulted in Romania becoming the 3rd RRRFR participating country to remove all HEU. Libya had previously completed two RRRFR shipments of HEU fresh fuel so the 5.2 kg of HEU spent fuel air shipped from the IRT 1 research reactor in December made Libya the 4th RRRFR participating country to remove all HEU. This paper describes the equipment, preparations, and license approvals required to safely and securely complete these two air shipments of spent nuclear fuel.

  7. WIPP - Shipment & Disposal Information

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

    Shipment & Disposal Information Shipments Received As of February 11, 2014 Site Shipments Loaded Miles Argonne National Laboratory 193 331,333 Bettis Atomic Power Laboratory 5 10,955 GE Vallecitos Nuclear Center 32 44,800 Idaho National Laboratory 5,844 8,132,064 Los Alamos National Laboratory 1,344 459,648 Lawrence Livermore National Laboratory 18 24,804 Nevada Test Site 48 57,312 Oak Ridge National Laboratory 131 175,933 Rocky Flats Environmental Technology Site 2,045 1,446,444 Hanford

  8. WIPP Receives 100th Shipment

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

    Waste Isolation Pilot Plant Receives 100 th Shipment CARLSBAD, N.M., October 19, 2000 - The 100 th shipment of defense-generated transuranic radioactive waste has arrived safely at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). The shipment came from DOE's Rocky Flats Environmental Technology Site (RFETS) in Colorado. "This is a major milestone for WIPP as we work toward clean up of DOE sites across the country," said Dr. Inés Triay, Manager of the Carlsbad

  9. Milestone Shipment Arrives at WIPP

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M. – On Sept. 12, 2013, the 700th shipment of remote-handled (RH) transuranic (TRU) waste reached the gate at EM’s Waste Isolation Pilot Plant (WIPP).

  10. Waste shipment engineering data management plan

    SciTech Connect (OSTI)

    Marquez, D.L.

    1995-05-01

    This plan documents current data management practices and future data management improvements for TWRS Waste Shipment Engineering.

  11. User Shipments | Stanford Synchrotron Radiation Lightsource

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

    Shipments Shipping Equipment and Materials to SSRL Shipping Equipment and Materials from SSRL International User Shipments from SLAC - EXPORTS Require Power of Attorney Shipping Equipment and Materials to SSRL The following contact information should be included on all shipments to SSRL: Spokesperson's Name, Proposal #, and SSRL Beam Line SLAC, SSRL MS 99 2575 Sand Hill Rd. Menlo Park, CA 94025 If a contact number is required on carrier documentation, please use the SSRL Duty Operator's phone

  12. Rocky Flats resumes shipments to WIPP

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

    Rocky Flats Resumes Shipments to WIPP CARLSBAD, N.M., March 11, 2000 - The U.S. Department of Energy (DOE) has resumed transuranic radioactive waste shipments from DOE's Rocky Flats Environmental Technology Site (RFETS) to the Waste Isolation Pilot Plant (WIPP). A shipment consisting of 28 drums of transuranic waste today arrived safely at WIPP at 5:07 p.m. (Mountain Standard Time). The truck, carrying two TRUPACT-II (Transuranic Packaging Transporter Model II) shipping containers, departed

  13. User Shipments | Linac Coherent Light Source

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

    Shipments Check-In | Computer Accounts | Data Collection & Analysis | Policies | Proposals | Schedules | User Portal Shipping Equipment and Materials Hazardous Materials Shipments Getting Items through U.S. Customs Shipping User Samples/Equipment Outside of the U.S. Establishing User Financial Account The following contact information should be included on all shipments to LCLS: Spokesperson's Name and c/o Instrument Scientist SLAC, LCLS Bldg. 950 (specify instrument) 2575 Sand Hill Rd.

  14. Volume, Number of Shipments Surpass Goals

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

    shatters records in first year of accelerated shipping effort October 3, 2012 Los Alamos National Laboratory shatters records in first year of accelerated shipping effort Volume, Number of Shipments Surpass Goals LOS ALAMOS, NEW MEXICO, October 3, 2012-In the first year of an effort to accelerate shipments of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP), Los Alamos National Laboratory shattered its own record with 59 more shipments than planned, and became one of the largest

  15. Shipping Radioactive Waste by Rail from Brookhaven National Laboratory...

    Office of Environmental Management (EM)

    Shipping Radioactive Waste by Rail from Brookhaven National Laboratory Shipping Radioactive Waste by Rail from Brookhaven National Laboratory Shipping Radioactive Waste by Rail...

  16. TEC Working Group Topic Groups Rail Conference Call Summaries...

    Office of Environmental Management (EM)

    Rail Conference Call Summaries TEC Working Group Topic Groups Rail Conference Call Summaries CONFERENCE CALL SUMMARIES Rail Topic Group Inspections Subgroup Planning Subgroup...

  17. Segmented rail linear induction motor

    DOE Patents [OSTI]

    Cowan, M. Jr.; Marder, B.M.

    1996-09-03

    A segmented rail linear induction motor has a segmented rail consisting of a plurality of nonferrous electrically conductive segments aligned along a guideway. The motor further includes a carriage including at least one pair of opposed coils fastened to the carriage for moving the carriage. A power source applies an electric current to the coils to induce currents in the conductive surfaces to repel the coils from adjacent edges of the conductive surfaces. 6 figs.

  18. Segmented rail linear induction motor

    DOE Patents [OSTI]

    Cowan, Jr., Maynard; Marder, Barry M.

    1996-01-01

    A segmented rail linear induction motor has a segmented rail consisting of a plurality of nonferrous electrically conductive segments aligned along a guideway. The motor further includes a carriage including at least one pair of opposed coils fastened to the carriage for moving the carriage. A power source applies an electric current to the coils to induce currents in the conductive surfaces to repel the coils from adjacent edges of the conductive surfaces.

  19. WIPP Receives 500th Waste Shipment

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

    500 th Waste Shipment CARLSBAD, N.M., January 7, 2002 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) reached a new milestone Saturday with the safe arrival of its 500 th shipment of transuranic waste. The 500 th shipment arrived at WIPP at 6:38 p.m. Saturday from DOE's Rocky Flats Environmental Technology Site in Colorado. It was the 282 nd shipment to WIPP from Rocky Flats - one of five DOE sites sending defense-generated radioactive waste to WIPP for permanent

  20. Annual Transportation Report for Radioactive Waste Shipments...

    National Nuclear Security Administration (NNSA)

    ANNUAL TRANSPORTATION REPORT FY 2008 Radioactive Waste Shipments to and from the Nevada Test Site (NTS) February 2009 United States Department of Energy National Nuclear Security...

  1. Removing nuclear waste, one shipment at a time

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

    Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way...

  2. 3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Gregory, Louis

    2014-09-20

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS;  Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.

  3. 1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Gregory, Louis

    2015-02-20

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 1st quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report include minor volumes of non-radioactive classified waste/material that were approved for disposal (non-radioactive classified or nonradioactive classified hazardous). Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to rounding conventions for volumetric conversions from cubic meters to cubic feet.

  4. TEC Working Group Topic Groups Rail Conference Call Summaries...

    Office of Environmental Management (EM)

    Summaries Rail Topic Group TEC Working Group Topic Groups Rail Conference Call Summaries Rail Topic Group Rail Topic Group PDF icon May 17, 2007 PDF icon January 16, 2007 PDF icon...

  5. Hazardous Material Shipments | The Ames Laboratory

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

    Hazardous Material Shipments GET (General Employee Training): General Information: Materials and Transportation personnel perform domestic and international shipping activities associated with hazardous materials transported onsite and offsite. All activities are performed by personnel who have been trained for their respective transportation functions, as required by the Code of Federal Regulations (CFR) and International Air Transport Association (IATA). Shipments are made for the research and

  6. Table 6. Source and disposition of photovoltaic module shipments...

    U.S. Energy Information Administration (EIA) Indexed Site

    Source and disposition of photovoltaic module shipments, 2013" "(peak kilowatts)" "Module ... Administration, Form EIA-63B, 'Annual Photovoltaic CellModule Shipments Report.'rounding. ...

  7. Table 2. Value and average value of photovoltaic module shipments...

    U.S. Energy Information Administration (EIA) Indexed Site

    Value and average value of photovoltaic module shipments, 2013" "Module value, total ... Administration, Form EIA-63B, 'Annual Photovoltaic CellModule Shipments Report' Note: ...

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

    Office of Environmental Management (EM)

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

  9. TEC Working Group Topic Groups Rail

    Broader source: Energy.gov [DOE]

    The Rail Topic Group has the responsibility to identify and discuss current issues and concerns regarding rail transportation of radioactive materials by the Department of Energy (DOE). The group’s...

  10. Microsoft Word - Crude by rail July 2014

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

    Moving Crude Oil by Rail Page 1 of 10 Summary U.S. crude oil production has risen sharply in recent years, with much of the increased output moving by rail. In 2008, U.S. Class I ...

  11. Truck and rail charges for shipping spent fuel and nuclear waste

    SciTech Connect (OSTI)

    McNair, G.W.; Cole, B.M.; Cross, R.E.; Votaw, E.F.

    1986-06-01

    The Pacific Northwest Laboratory developed techniques for calculating estimates of nuclear-waste shipping costs and compiled a listing of representative data that facilitate incorporation of reference shipping costs into varius logistics analyses. The formulas that were developed can be used to estimate costs that will be incurred for shipping spent fuel or nuclear waste by either legal-weight truck or general-freight rail. The basic data for this study were obtained from tariffs of a truck carrier licensed to serve the 48 contiguous states and from various rail freight tariff guides. Also, current transportation regulations as issued by the US Department of Transportation and the Nuclear Regulatory Commission were investigated. The costs that will be incurred for shipping spent fuel and/or nuclear waste, as addressed by the tariff guides, are based on a complex set of conditions involving the shipment origin, route, destination, weight, size, and volume and the frequency of shipments, existing competition, and the length of contracts. While the complexity of these conditions is an important factor in arriving at a ''correct'' cost, deregulation of the transportation industry means that costs are much more subject to negotiation and, thus, the actual fee that will be charged will not be determined until a shipping contract is actually signed. This study is designed to provide the baseline data necessary for making comparisons of the estimated costs of shipping spent fuel and/or nuclear wastes by truck and rail transportation modes. The scope of the work presented in this document is limited to the costs incurred for shipping, and does not include packaging, cask purchase/lease costs, or local fees placed on shipments of radioactive materials.

  12. PRB rail loadings shatter record

    SciTech Connect (OSTI)

    Buchsbaum, L.

    2008-09-15

    Rail transport of coal in the Powder River Basin has expanded, with a record 2,197 trains loaded in a month. Arch Coal's Thunder basin mining complex has expanded by literally bridging the joint line railway. The dry fork mine has also celebrated its safety achievements. 4 photos.

  13. Microsoft Word - 10000th_shipment.doc

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

    For Immediate Release The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M.,...

  14. Volume, Number of Shipments Surpass Goals

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

    in the country."Our goal this fiscal year was to send 184 shipments to WIPP," said Lee Bishop, TRU waste manager at the U.S. Department of Energy's National - 2 - Nuclear Security...

  15. Removing nuclear waste, one shipment at a time

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

    Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way to a permanent repository near Carlsbad, NM. June 26, 2012 Governor Martinez applauding the 1014th TRU waste shipment New Mexico Governor Susana Martinez and other dignitaries applaud as the 1,014th shipment of transuranic waste leaves Los Alamos National Laboratory. Contact Patti Jones Communications Office (505)

  16. RAIL ROUTING - CURRENT PRACTICES FOR SPENT NUCLEAR FUEL AND HIGH-LEVEL WASTE SHIPMENTS,

    Office of Environmental Management (EM)

    Quality Control Inspector (QCI) Pre-Exam Quiz Quality Control Inspector (QCI) Pre-Exam Quiz This quiz is not representative of, nor related to the content of the actual QCI exam. While it is not an official indication as to whether or not someone can successfully pass the exam, it can be used as an assessment when deciding whether or not one is prepared to take the exam. This quiz was updated on 11/19/2014. PDF icon QCI Pre-Exam Quiz (Updated 11/19/2014) More Documents & Publications 1703

  17. Top-of-Rail lubricant

    SciTech Connect (OSTI)

    Alzoubi, M. F.; Fenske, G. R.; Erck, R. A.; Boparai, A. S.

    2000-07-14

    Analysis of the volatile and semivolatile fractions collected after use of the TOR lubricant indicated that other than contaminants in the collection laboratory, no compounds on the EPA's Target Compound Lists (Tables 2 and 5) were detected in these fractions. The data of these qualitative analyses, given in the various tables in the text, indicate only the relative amounts of the tentatively identified compounds. The authors recommend that quantitative analysis be performed on the volatile and semivolatile fractions to allow confirmation of the tentatively identified compounds and to obtain absolute amounts of the detected compounds. Additionally, the semivolatile fraction should be analyzed by liquid chromatography/mass spectrometry to identify compounds that are not chromatographable under the temperature program used for determination of semivolatile compounds. Introducing the top-of-rail (TOR) lubricant into the wheel/rail interface results in a reduction of almost 60% of lateral friction force over the forces encountered under dry conditions. This reveals good potential for energy savings, as well as wear reduction, for railroad companies. In TOR lubrication, an increase in the angle of attack and axle load results in increased lateral friction and rate of lubricant consumption. The most efficient TOR lubricant quantity to be used in the wheel/rail interface must be calculated precisely according to the number of cars, axle loads, train speed, and angle of attack.

  18. Rail-to-rail differential input amplification stage with main and surrogate differential pairs

    DOE Patents [OSTI]

    Britton, Jr., Charles Lanier; Smith, Stephen Fulton

    2007-03-06

    An operational amplifier input stage provides a symmetrical rail-to-rail input common-mode voltage without turning off either pair of complementary differential input transistors. Secondary, or surrogate, transistor pairs assume the function of the complementary differential transistors. The circuit also maintains essentially constant transconductance, constant slew rate, and constant signal-path supply current as it provides rail-to-rail operation.

  19. Microsoft Word - ORNL_first_shipment

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

    WIPP Receives First Shipment From Oak Ridge National Laboratory CARLSBAD, N.M., September 25, 2008 - Oak Ridge National Laboratory (ORNL) in Tennessee has become the latest site to ship defense-related transuranic waste directly to the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). A truck with three loaded TRUPACT-II shipping containers departed ORNL yesterday and arrived at WIPP this morning - the 6,894th safe shipment to WIPP since the project opened in 1999.

  20. WIPP receives 9,000th shipment

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

    WIPP receives 9,000th shipment CARLSBAD, N.M., October 7, 2010 � The U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) received its 9,000th shipment of transuranic (TRU) waste on Tuesday evening, marking an important milestone in the Department�s mission to clean up the legacy of the cold war. �This significant milestone represents our commitment to the nation to clean up the defense legacy TRU waste footprint,� said Interim Acting CBFO Manager Ed Ziemianski. �The WIPP

  1. Table 9. U.S. photovoltaic module shipments by state/territory...

    U.S. Energy Information Administration (EIA) Indexed Site

    photovoltaic module shipments by stateterritory, 2013 (peak kilowatts)" ... Administration, Form EIA-63B, 'Annual Photovoltaic CellModule Shipments Report.' ...

  2. Impacts of Rail Pressure and Biodiesel Composition on Soot Nanostructu...

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

    Rail Pressure and Biodiesel Composition on Soot Nanostructure Impacts of Rail Pressure and Biodiesel Composition on Soot Nanostructure Fractal dimensions of particle aggregates and ...

  3. Advanced Diesel Common Rail Injection System for Future Emission...

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

    Common Rail Injection System for Future Emission Legislation Advanced Diesel Common Rail Injection System for Future Emission Legislation 2004 Diesel Engine Emissions Reduction ...

  4. TEC Working Group Topic Groups Rail Archived Documents | Department...

    Office of Environmental Management (EM)

    Archived Documents TEC Working Group Topic Groups Rail Archived Documents ARCHIVED DOCUMENTS PDF icon Inspections Summary Matrix PDF icon TEC Transportation Safety WIPP-PIG Rail...

  5. TEC Working Group Topic Groups Rail Key Documents | Department...

    Office of Environmental Management (EM)

    Rail Key Documents TEC Working Group Topic Groups Rail Key Documents KEY DOCUMENTS Radiation Monitoring Subgroup Intermodal Subgroup Planning Subgroup PDF icon Current FRA State...

  6. TEC Working Group Topic Groups Rail Meeting Summaries | Department...

    Office of Environmental Management (EM)

    TEC Working Group Topic Groups Rail Meeting Summaries MEETING SUMMARIES PDF icon Kansas City TEC Meeting, Rail Topic Group Summary - July 25, 2007 PDF icon Atlanta TEC...

  7. Enhancements to System for Tracking Radioactive Waste Shipments Benefit

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

    Multiple Users | Department of Energy Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track shipments of

  8. Los Alamos National Laboratory resumes transuranic waste shipments

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

    LANL resumes transuranic waste shipments Los Alamos National Laboratory resumes transuranic waste shipments The waste was received at Waste Control Specialists in Andrews, Texas, where it will be temporarily staged until it can be shipped to the Waste Isolation Pilot Plant. April 2, 2014 Los Alamos sent the first shipment to Waste Control Specialists on April 1. Los Alamos sent the first shipment to Waste Control Specialists on April 1. Contact Patti Jones Communications Office (505) 665-7748

  9. ( Sample of Shipment Notice) Federal Records Center | Department of Energy

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

    ( Sample of Shipment Notice) Federal Records Center ( Sample of Shipment Notice) Federal Records Center This document instructs on how to ship records to the Federal Records Center PDF icon ( Sample of Shipment Notice) Federal Records Center More Documents & Publications Correspondence Style Guide Records Management Handbook Records Management Handbook

  10. Los Alamos National Laboratory celebrates 1000th transuranic waste shipment

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

    LANL celebrates 1000th transuranic waste shipment Los Alamos National Laboratory celebrates 1000th transuranic waste shipment LANL has sent record breaking numbers of shipments to WIPP each of the past three years and is on track to further surpass its record in 2012. June 26, 2012 The Los Alamos National Laboratory's 1000th shipment of transuranic waste leaves the Laboratory on its way to the Waste Isolation Pilot Plant near Carlsbad, N.M. The Los Alamos National Laboratory's 1000th shipment of

  11. Public information circular for shipments of irradiated reactor fuel

    SciTech Connect (OSTI)

    1996-07-01

    This circular provides information on shipment of spent fuel subject to regulation by US NRC. It provides a brief description of spent fuel shipment safety and safeguards requirement of general interest, a summary of data for 1979-1995 highway and railway shipments, and a listing, by State, of recent highway and railway shipment routes. The enclosed route information reflects specific NRC approvals that have been granted in response to requests for shipments of spent fuel. This publication does not constitute authority for carriers or other persons to use the routes described to ship spent fuel, other categories of nuclear waste, or other materials.

  12. Stakeholder Transportation Scorecard: Reviewing Nevada's Recommendations for Enhancing the Safety and Security of Nuclear Waste Shipments - 13518

    SciTech Connect (OSTI)

    Dilger, Fred C.; Ballard, James D.; Halstead, Robert J.

    2013-07-01

    As a primary stakeholder in the Yucca Mountain program, the state of Nevada has spent three decades examining and considering national policy regarding spent nuclear fuel and high-level radioactive waste transportation. During this time, Nevada has identified 10 issues it believes are critical to ensuring the safety and security of any spent nuclear fuel transportation program, and achieving public acceptance. These recommendations are: 1) Ship the oldest fuel first; 2) Ship mostly by rail; 3) Use dual-purpose (transportable storage) casks; 4) Use dedicated trains for rail shipments; 5) Implement a full-scale cask testing program; 6) Utilize a National Environmental Policy Act (NEPA) process for the selection of a new rail spur to the proposed repository site; 7) Implement the Western Interstate Energy Board (WIEB) 'straw man' process for route selection; 8) Implement Section 180C assistance to affected States, Tribes and localities through rulemaking; 9) Adopt safety and security regulatory enhancements proposed states; and 10) Address stakeholder concerns about terrorism and sabotage. This paper describes Nevada's proposals in detail and examines their current status. The paper describes the various forums and methods by which Nevada has presented its arguments and sought to influence national policy. As of 2012, most of Nevada's recommendations have been adopted in one form or another, although not yet implemented. If implemented in a future nuclear waste program, the State of Nevada believes these recommendations would form the basis for a successful national transportation plan for shipments to a geologic repository and/or centralized interim storage facility. (authors)

  13. Probabilistic assessment of spent fuel shipping cask response to severe transportation accident conditions. Report summary

    SciTech Connect (OSTI)

    Fischer, L.E.; Kimura, C.Y.; Witte, M.C.

    1985-01-01

    The licensing of commercial nuclear spent shipping casks in the United States is regulated by 10CFR71. In order to be licensed, casks must be designed not to fail under hypothetical test conditions specified in Appendix B of this regulation. Questions have been raised about the suitability of these tests in simulating actual transportation accident conditions. Our study addresses the adequacy of current regulations by comparing real-world accident conditions with regulatory test specifications using more complete accident statistics and more sophisticated structural analyses than have been used in studies to date. Our objective is to evaluate the protection provided by current regulations against severe accident conditions for commercial spent nuclear fuel casks that are transported by truck or rail. The complete spectrum of truck and rail accidents will be reviewed in order to determine the frequency (or infrequency) of cask failures during transportation accidents. 3 references, 1 figure.

  14. TEC Working Group Topic Groups Rail Conference Call Summaries Rail Topic

    Office of Environmental Management (EM)

    Group | Department of Energy Summaries Rail Topic Group TEC Working Group Topic Groups Rail Conference Call Summaries Rail Topic Group Rail Topic Group PDF icon May 17, 2007 PDF icon January 16, 2007 PDF icon August 31, 2006 PDF icon July 27, 2006 PDF icon June 8, 2006 PDF icon April 20, 2006 PDF icon March 9, 2006 PDF icon January 26, 2006 PDF icon November 9, 2005 PDF icon September 15, 2005 PDF icon April 28, 2005 PDF icon March 24, 2005 PDF icon February 24, 2005 PDF icon January 27,

  15. Solar Photovoltaic Cell/Module Shipments Report

    U.S. Energy Information Administration (EIA) Indexed Site

    Solar Photovoltaic Cell/Module Shipments Report February 2016 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Improving the Quality and Scope of EIA Data i This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or

  16. Trends in state-level freight accident rates: An enhancement of risk factor development for RADTRAN

    SciTech Connect (OSTI)

    Saricks, C.; Kvitek, T.

    1991-01-01

    Under the Nuclear Waste Policy Act, the Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) is concerned with understanding and managing risk as it applies to the shipment of spent commercial nuclear reactor fuel. Understanding risk in relation to mode and geography may provide opportunities to minimize radiological and non-radiological risks of transportation. To enhance such an understanding, a set of state-or waterway-specific accident, fatality, and injury rates (expressed as rates per shipment kilometer) by transportation mode and highway administrative class was developed, using publicly-available data bases. Adjustments made to accommodate miscoded or incomplete information in accident data are described, as well as the procedures for estimating state-level flow data. Results indicate that the shipping conditions under which spent fuel is likely to be transported should be less subject to accidents than the average'' shipment within mode. 10 refs., 3 tabs.

  17. Accident Investigations

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

    1996-04-26

    To prescribe requirements for conducting investigations of certain accidents occurring at Department of Energy (DOE) operations and sites; to improve the environment, safety and health for DOE, contractors, and the public; and to prevent the recurrence of such accidents. Chg 2, 4-26-96

  18. Accident Investigations

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

    1995-10-26

    To prescribe requirements for conducting investigations of certain accidents occurring at Department of Energy (DOE) operations and sites; to improve the environment , safety and health for DOE, contractors, and the public; and to prevent the recurrence of such accidents. Chg 1, 10-26-95. Cancels parts of DOE 5484.1

  19. PHOENIX ENERGIZES LIGHT RAIL CORRIDOR WITH UPGRADES

    Broader source: Energy.gov [DOE]

    Designed to promote energy efficiency in buildings in Phoenix, Arizona’s 10-mile-long Light Rail Corridor, Energize Phoenix focused on performing energy upgrades and reducing energy use in...

  20. A rationale for maintaining the double containment requirement for plutonium shipments

    SciTech Connect (OSTI)

    Channell, James K.; Anastas, George

    2003-12-31

    Current U.S. Nuclear Regulatory Commission (NRC) transportation regulations (10 CFR 71.63 (b)) require that all shipments containing more than 20 curies of plutonium must be transported in packages that provide double containment. On April 30, 2002 the NRC issued a proposed rule that would eliminate 71.63(b) and the double containment requirement. NRCs reasons for proposing elimination of 71.63(b) are: (1) compatibility with International Atomic Energy Agency Transportation Safety Standards (which do not have the requirement); (2) the current rule is inconsistent with the A1/A2 system since it applies only to plutonium; (3) double containment causes a heavier package and results in higher transportation costs; (4) the separate inner containment results in additional radiation exposure; and (5) while there would be additional protection from a separate inner container in an accident; this type of approach is not risk informed nor performance based. The Environmental Evaluation Group (EEG) has been a proponent of the double containment requirement for the Waste Isolation Pilot Plant (WIPP) shipments for twenty years. This requirement affects shipments to WIPP much more than any other current or planned shipping campaign because reactor fuel elements, metal or metal alloy, and vitrified high-level waste are exempt from 71.63(b). EEG submitted comments on the Proposed Rule on July 26, 2002 (Appendix C). This report is an update and expansion of the July 26, 2002 comments. Actual WIPP experience with shipments in the double contained TRUPACT-II package is used to respond to NRC arguments for deletion of 71.63(b) and offers a rationale for maintaining the current requirement.

  1. EIS-0250-S2: Supplemental EIS for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada- Nevada Rail Transportation Corridor

    Broader source: Energy.gov [DOE]

    This SEIS is to evaluate the potential environmental impacts of constructing and operating a railroad for shipments of spent nuclear fuel and high-level radioactive waste from an existing rail line in Nevada to a geologic repository at Yucca Mountain. The purpose of the evaluation is to assist the Department in deciding whether to construct and operate a railroad in Nevada, and if so, in which corridor and along which specific alignment within the selected corridor.

  2. Final Transuranic Waste Shipment Leaves Rocky Flats | Department of Energy

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

    Transuranic Waste Shipment Leaves Rocky Flats Final Transuranic Waste Shipment Leaves Rocky Flats April 19, 2005 - 12:23pm Addthis Cleanup Ahead of Schedule, On Track to Save Taxpayers Billions GOLDEN, CO. - A major environmental victory was achieved at the Rocky Flats Site in Golden, Colo., today when the final remaining shipment of radioactive, transuranic (TRU) waste left the property on a truck bound for an underground waste repository in New Mexico. This major milestone is another step

  3. Los Alamos National Laboratory Accelerates Transuranic Waste Shipments:

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

    Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan | Department of Energy Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan Los Alamos National Laboratory

  4. NEVADA NATIONAL SECURITY SITE (NNSS) DRIVERS ROUTE/SHIPMENT INFORMATION

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

    (NNSS) DRIVERS ROUTE/SHIPMENT INFORMATION (12/2014 Log No. 2014-229) NOTE: THIS FORM IS TWO (2) PAGES - YOU MUST COMPLETE BOTH PAGES NNSS SHIPMENT NUMBER: CARRIER NAME: TRACTOR NO.: TRAILER NO.: AT ORIGIN AT NNSS Main Gate NNSS OFFICE USE ONLY DEPARTURE DATE: ARRIVAL DATE: DESTINATION AREA: Area 5 DEPARTURE TIME: ARRIVAL TIME: NNSS DEPARTURE TIME: LOCATION: HELD OVER? No Yes REASON: ROUTE INFORMATION REVIEWED BY: ONSITE SHIPMENT (MAP NOT APPLICABLE) DROP YARD; LEAVE THIS FORM WITH SHIPPING

  5. First Shipment of Compressors Leaves Portsmouth | Department of Energy

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

    First Shipment of Compressors Leaves Portsmouth First Shipment of Compressors Leaves Portsmouth February 26, 2014 - 12:00pm Addthis EM employees Tim Emmons and Bill Lutz secure a compressor with tie downs to the truck bed in preparation for the first shipment of the components to a disposal facility. EM employees Tim Emmons and Bill Lutz secure a compressor with tie downs to the truck bed in preparation for the first shipment of the components to a disposal facility. Workers guide a compressor

  6. West Valley Demonstration Project Low-Level Waste Shipment |...

    Office of Environmental Management (EM)

    Project Low-Level Waste Shipment More Documents & Publications Indiana Department of Homeland Security - NNPP Exercise Transportation Security EIS-0337-SA-01: Supplement Analysis

  7. Packaging and Transportation for Offsite Shipment of Materials...

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

    1.1C Second Draft, Packaging and Transportation for Offsite Shipment of Materials of National Security Interests by Matthew Weber Functional areas: Defense Nuclear Facility Safety...

  8. Enhancements to System for Tracking Radioactive Waste Shipments...

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

    features are new mapping tools, multi-mode, two-way communication that automatically switches between terrestrial and satellite, in-depth shipment reporting, event alerts and a...

  9. Draft News Release: DOE Investigates Shipment of Wrong Drum to...

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

    site, and certifies transuranic waste shipments from that facility to WIPP. Before drums can be shipped to WIPP they have to be certified according to waste analysis...

  10. Laboratory increases shipments of waste to WIPP repository

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

    repository The campaign will eliminate LANL's existing backlog of approximately 1,500 drums of legacy transuranic waste awaiting shipment to WIPP. February 11, 2010 Los Alamos...

  11. Accident Investigations

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

    2011-03-04

    This Order prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and activities. Supersedes DOE O 225.1A. Cancels DOE G 225.1A-1.

  12. Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing |

    Office of Environmental Management (EM)

    Multiple Users | Department of Energy Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track shipments of

  13. Keeping Climate Change Solutions on Track: The Role of Rail ...

    Open Energy Info (EERE)

    Keeping Climate Change Solutions on Track: The Role of Rail Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Keeping Climate Change Solutions on Track: The Role of Rail...

  14. LNG shipments in 1994 set records

    SciTech Connect (OSTI)

    1996-01-15

    Worldwide LNG shipments by ocean-going vessels in 1994 increased to 1,619 voyages, according to an LNG shipping industry statistical annual. LNG Log 20 published the recently compiled 1994 data in the last quarter of 1995. The publication is from the Society of International Gas Tanker and Terminal Operators Ltd., London. The year`s total was 8.8% more than for 1993 and the most in 35 years of records. The trips were made and the vessels loaded and discharged without report of serious safety or environmental incident, says the publication. Of the voyages completed during the year, 596 were to European receiving terminals (up 2.8% over 1993), and 1,003 went to the Far East (an increase of 10.7%); shipments to the US, however, dropped to 20, from 32 in 1993. This paper shows that the 1,619 voyages represent 3.6 million nautical miles logged by 78 vessels active during the year. These ships pumped ashore record annual volumes of approximately 144.3 million cu m of LNG, 110.1 million cu m (76.3%) of which went to Far Eastern customers. The paper also summarizes containment systems in use in 1994 and since LNG began to be shipped in 1959.

  15. WIPP Receives First Shipment | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    WIPP Receives First Shipment WIPP Receives First Shipment Carlsbad, NM After more than two decades of political, legal, and bureaucratic delays, the first truckload of radioactive waste from Los Alamos National Laboratory arrives at the DOE Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico, 26 miles east of Carlsbad

  16. Tag: waste shipment | Y-12 National Security Complex

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

    waste shipment Tag: waste shipment Displaying 1 - 1 of 1... Category: News Y-12 completes waste removal project two years ahead of schedule Y-12 completed disposition of 2,247 containers of mixed waste more than two years ahead of the deadline

  17. Shipping container response to three severe railway accident scenarios

    SciTech Connect (OSTI)

    Mok, G.C.; Fischer, L.E.; Murty, S.S.; Witte, M.C.

    1998-04-01

    The probability of damage and the potential resulting hazards are analyzed for a representative rail shipping container for three severe rail accident scenarios. The scenarios are: (1) the rupture of closure bolts and resulting opening of closure lid due to a severe impact, (2) the puncture of container by an impacting rail-car coupler, and (3) the yielding of container due to side impact on a rigid uneven surface. The analysis results indicate that scenario 2 is a physically unreasonable event while the probabilities of a significant loss of containment in scenarios 1 and 3 are extremely small. Before assessing the potential risk for the last two scenarios, the uncertainties in predicting complex phenomena for rare, high- consequence hazards needs to be addressed using a rigorous methodology.

  18. TEC Working Group Topic Groups Rail Conference Call Summaries Inspections

    Office of Environmental Management (EM)

    Subgroup | Department of Energy Summaries Inspections Subgroup TEC Working Group Topic Groups Rail Conference Call Summaries Inspections Subgroup Inspections Subgroup PDF icon April 6, 2006 PDF icon February 23, 2006 Draft PDF icon January 24, 2006 More Documents & Publications TEC Working Group Topic Groups Rail Conference Call Summaries Planning Subgroup TEC Working Group Topic Groups Rail Conference Call Summaries Tracking Subgroup TEC Working Group Topic Groups Rail Conference Call

  19. TEC Working Group Topic Groups Rail Key Documents Radiation Monitoring

    Office of Environmental Management (EM)

    Subgroup | Department of Energy Radiation Monitoring Subgroup TEC Working Group Topic Groups Rail Key Documents Radiation Monitoring Subgroup Radiation Monitoring Subgroup PDF icon Draft Work Plan - February 4, 2008 More Documents & Publications TEC Working Group Topic Groups Rail Meeting Summaries TEC Working Group Topic Groups Rail Conference Call Summaries Radiation Monitoring Subgroup TEC Working Group Topic Groups Rail Key Documents Intermodal Subgroup

  20. Advanced Diesel Common Rail Injection System for Future Emission Legislation

    Broader source: Energy.gov [DOE]

    2004 Diesel Engine Emissions Reduction (DEER) Conference Presentation: Robert Bosch GMBH Common Rail System Engineering for PC Diesel Systems

  1. Radiological consequences of ship collisions that might occur in U.S. Ports during the shipment of foreign research reactor spent nuclear fuel to the United States in break-bulk freighters

    SciTech Connect (OSTI)

    Sprung, J.L.; Bespalko, S.J.; Massey, C.D.; Yoshimura, R.; Johnson, J.D.; Reardon, P.C.; Ebert, M.W.; Gallagher D.W.

    1996-08-01

    Accident source terms, source term probabilities, consequences, and risks are developed for ship collisions that might occur in U.S. ports during the shipment of spent fuel from foreign research reactors to the United States in break-bulk freighters.

  2. Offsite Shipment Campaign Readiness Assessment (OSCRA): A tool for offsite shipment campaigns

    SciTech Connect (OSTI)

    Michelhaugh, R.D.; Pope, R.B.; Bisaria, A.

    1995-12-31

    The Offsite Shipment Campaign Readiness Assessment (OSCRA) tool is designed to assist program managers in identifying, implementing, and verifying applicable transportation and disposal regulatory requirements for specific shipment campaigns. OSCRA addresses these issues and provides the program manager with a tool to support planning for safe and compliant transportation of waste and other regulated materials. Waste transportation and disposal requirements must be identified and addressed in the planning phase of a waste management project. In the past, in some cases, transportation and disposal requirements have not been included in overall project plans. These planning deficiencies have led to substantial delays and cost impacts. Additionally, some transportation regulatory requirements have not been properly implemented, resulting in substantial fines and public embarrassment for the U.S. Department of Energy (DOE). If a material has been processed and packaged for onsite storage (prior to offsite disposal) in a package that does not meet transportation requirements, it must be repackaged in U.S. Department of Transportation (DOT)-compliant packaging for transport. This repackaging can result in additional cost, time, and personnel radiation exposure. The original OSCRA concept was developed during the Pond Waste Project at the K-25 Site in Oak Ridge, Tennessee. The continued development of OSCRA as a user-friendly tool was funded in 1995 by the DOE Office of Environmental Management, Transportation Management Division (TMD). OSCRA is designed to support waste management managers, site remediation managers, and transportation personnel in defining applicable regulatory transportation and disposal requirements for offsite shipment of hazardous waste and other regulated materials. The need for this tool stems from increasing demands imposed on DOE and the need to demonstrate and document safe and compliant packaging and shipment of wastes from various DOE sites.

  3. Rail gun development for EOS research

    SciTech Connect (OSTI)

    Fowler, C.M.; Peterson, D.R.; Hawke, R.S.; Brooks, A.L.

    1981-01-01

    The status of a railgun program for EOS research in progress at Los Alamos and Livermore National Laboratories is described. The operating principle of rail guns, the power supplies used to drive them, diagnostic techniques used to monitor their performance and initial efforts to develop projectiles suitable for EOS research are discussed. (WHK)

  4. Rail Networks Are Getting Smarter | GE Global Research

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

    Rail Networks Are Getting Smarter Click to email this to a friend (Opens in new window) Share on Facebook (Opens in new window) Click to share (Opens in new window) Click to share on LinkedIn (Opens in new window) Click to share on Tumblr (Opens in new window) RailConnect 360 makes rail networks and operations smarter RailConnect 360 includes Movement Planner, Yard Planner and Trip Optimizer RailConnect 360 increases efficiency Freight trains moving faster could save railroads millions yearly

  5. Historical overview of domestic spent fuel shipments: Update

    SciTech Connect (OSTI)

    Not Available

    1991-07-01

    This report presents available historic data on most commercial and research reactor spent fuel shipments in the United States from 1964 through 1989. Data include sources of the spent fuel shipped, types of shipping casks used, number of fuel assemblies shipped, and number of shipments made. This report also addresses the shipment of spent research reactor fuel. These shipments have not been documented as well as commercial power reactor spent fuel shipment activity. Available data indicate that the greatest number of research reactor fuel shipments occurred in 1986. The largest campaigns in 1986 were from the Brookhaven National Laboratory, Brooklyn, New York, to the Idaho Chemical Processing Plant (ICPP) and from the Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR) in Tennessee and the Rockwell International Reactor in California to the Savannah River Plant near Aiken, South Carolina. For all years addressed in this report, DOE facilities in Idaho Falls and Savannah River were the major recipients of research reactor spent fuel. In 1989, 10 shipments were received at the Idaho facilities. These originated from universities in California, Michigan, and Missouri. 9 refs., 12 figs., 7 tabs.

  6. The Nevada railroad system: Physical, operational, and accident characteristics

    SciTech Connect (OSTI)

    1991-09-01

    This report provides a description of the operational and physical characteristics of the Nevada railroad system. To understand the dynamics of the rail system, one must consider the system`s physical characteristics, routing, uses, interactions with other systems, and unique operational characteristics, if any. This report is presented in two parts. The first part is a narrative description of all mainlines and major branchlines of the Nevada railroad system. Each Nevada rail route is described, including the route`s physical characteristics, traffic type and volume, track conditions, and history. The second part of this study provides a more detailed analysis of Nevada railroad accident characteristics than was presented in the Preliminary Nevada Transportation Accident Characterization Study (DOE, 1990).

  7. Hanford Shipment Arrives Safely At Waste Isolation Pilot Plant

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

    Hanford Shipment Arrives Safely At Waste Isolation Pilot Plant CARLSBAD, N.M., July 14, 2000 - A shipment of defense-generated transuranic radioactive waste from the U.S. Department of Energy's (DOE's) Hanford Site arrived safely today at the Waste Isolation Pilot Plant (WIPP). The shipment left the Richland, Wash. site at about 5 p.m. (Pacific Time) July 12 and arrived at WIPP today at about 2:10 p.m. (MT). Hanford is the fourth DOE site to ship waste to WIPP. Over the next 35-year period,

  8. Level: National Data; Row: Values of Shipments within NAICS Codes;

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Consumption Ratios of Fuel, 2006; Level: National Data; Row: Values of Shipments within NAICS Codes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption per Dollar of Value NAICS per Employee of Value Added of Shipments Code(a) Economic Characteristic(b) (million Btu) (thousand Btu) (thousand Btu) Total United States 311 - 339 ALL MANUFACTURING INDUSTRIES Value of Shipments and Receipts (million dollars) Under 20 330.6 3.6 2.0 20-49 550.0 4.5 2.2

  9. Level: National Data; Row: Values of Shipments within NAICS Codes;

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Consumption Ratios of Fuel, 2010; Level: National Data; Row: Values of Shipments within NAICS Codes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption per Dollar of Value NAICS per Employee of Value Added of Shipments Code(a) Economic Characteristic(b) (million Btu) (thousand Btu) (thousand Btu) Total United States 311 - 339 ALL MANUFACTURING INDUSTRIES Value of Shipments and Receipts (million dollars) Under 20 405.4 4.0 2.1 20-49 631.3 4.7 2.2

  10. USDOE Top-of-Rail Lubricant Project

    SciTech Connect (OSTI)

    Mohumad F. Alzoubi; George R. Fenske; Robert A. Erck; Amrit S. Boparai

    2002-02-01

    Lubrication of wheel/rail systems has been recognized for the last two decades as a very important issue for railroads. Energy savings and less friction and wear can be realized if a lubricant can be used at the wheel/rail interface. On the other hand, adverse influences are seen in operating and wear conditions if improper or excessive lubrication is used. Also, inefficiencies in lubrication need to be avoided for economic and environmental reasons. The top-of-rail (TOR) lubricant concept was developed by Texaco Corporation to lubricate wheels and rails effectively and efficiently. Tranergy Corporation has been developing its SENTRAEN 2000{trademark} lubrication system for the last ten years, and this revolutionary new high-tech on-board rail lubrication system promises to dramatically improve the energy efficiency, performance, safety, and track environment of railroads. The system is fully computer-controlled and ensures that all of the lubricant is consumed as the end of the train passes. Lubricant quantity dispensed is a function of grade, speed, curve, and axle load. Tranergy also has its LA4000{trademark} wheel and rail simulator, a lubrication and traction testing apparatus. The primary task of this project was collecting and analyzing the volatile and semivolatile compounds produced as the lubricant was used. The volatile organic compounds were collected by Carbotrap cartridges and analyzed by adsorption and gas chromatography/mass spectrometry (GC/MS). The semivolatile fraction was obtained by collecting liquid that dripped from the test wheel. The collected material was also analyzed by GC/MS. Both of these analyses were qualitative. The results indicated that in the volatile fraction, the only compounds on the Environmental Protection Agency's (EPA) Superfund List of Analytes detected were contaminants either in the room air or from other potential contamination sources in the laboratory. Similarly, in the semivolatile fraction none of the detected compounds are on the EPA's Superfund List of Analytes. The major compound in the semivolatile fraction is 1,2-propanediol, which was also found as the major component of the TOR lubricant before testing. Other compounds found in trace quantities either were present in the TOR lubricant or were small fragments from the polymeric component of the TOR lubricant. The second task for Argonne in this project was to investigate the effects of axle load, angle of attack, and quantity of lubricant on lateral friction forces, as well as the consumption time of the TOR lubricant. The second task was to collect and qualitatively identify any volatile and semivolatile compounds produced upon use of the TOR lubricant.

  11. Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – The Advanced Mixed Waste Treatment Project (AMWTP) recently completed the last of 25 shipments of waste bound for permanent disposal in New Mexico and Nevada, six months ahead of a regulatory deadline.

  12. Milestone reached: Waste shipment leaves Los Alamos National Laboratory

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

    Waste shipment leaves LANL Milestone reached: Waste shipment leaves Los Alamos National Laboratory The material, known as "remote-handled transuranic waste" (RH-TRU), has been stored at the Laboratory since 1995. June 2, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

  13. Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency |

    Energy Savers [EERE]

    Department of Energy Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency February 27, 2013 - 12:00pm Addthis This graphic shows how the radiofrequency identification technology tracks and monitors packages in transport, in-transit stops and storage. This graphic shows how the radiofrequency identification technology tracks and monitors packages in transport, in-transit stops and storage. The technology

  14. DOE Seeks Trucking Services for Transuranic Waste Shipments | Department of

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

    Energy Trucking Services for Transuranic Waste Shipments DOE Seeks Trucking Services for Transuranic Waste Shipments March 30, 2011 - 12:00pm Addthis Media Contact Bill Taylor 513-246-0539 william.taylor@emcbc.doe.gov Cincinnati -- The Department of Energy (DOE) today will issue a Request for Proposals for the continuation of carrier services to transport transuranic waste (TRU) between DOE sites and the Waste Isolation Pilot Plant (WIPP) site, near Carlsbad, New Mexico. The transportation

  15. Microsoft Word - First LANL Shipment Arrives at WCS

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

    NWP Media Contacts: Donavan Mager Nuclear Waste Partnership LLC (575) 234-7586 www.wipp.energy.gov For Immediate Release First LANL Shipment Arrives at Waste Control Specialists Facility ANDREWS, Texas, April 2, 2014 - The U.S. Department of Energy (DOE) and Nuclear Waste Partnership (NWP) today announced that the first transuranic waste shipment arrived at the Waste Control Specialists facility in Andrews, Texas. Defense-related transuranic waste will be temporarily staged at the commercial

  16. Non-destructive inspection protocol for reinforced concrete barriers and bridge railings

    SciTech Connect (OSTI)

    Chintakunta, Satish R.; Boone, Shane D.

    2014-02-18

    Reinforced concrete highway barriers and bridge railings serve to prevent errant vehicles from departing the travel way at grade separations. Despite the important role that they play in maintaining safety and their ubiquitous nature, barrier inspection rarely moves beyond visual inspection. In August 2008, a tractor-trailer fatally departed William Preston Lane, Jr. Memorial Bridge after it dislodged a section of the bridge barrier. Investigations following the accident identified significant corrosion of the anchor bolts attaching the bridge railing to the bridge deck. As a result of the information gathered during its investigation of the accident, the National Transportation Safety Board (NTSB) made recommendations to the Federal Highway Administration concerning Non-Destructive Evaluation (NDE) of concrete bridge railings. The Center for nondestructive evaluation (NDE) at Turner Fairbank Highway Research Center in McLean, VA is currently evaluating feasibility of using four technologies - ground penetrating radar (GPR), ultrasonic pulse-echo, digital radiography and infrared thermal imaging methods to develop bridge inspection methods that augment visual inspections, offer reliable measurement techniques, and are practical, both in terms of time and cost, for field inspection work. Controlled samples containing predefined corrosion levels in reinforcing steel were embedded at barrier connection points for laboratory testing. All four NDE techniques were used in the initial phase I testing. An inspection protocol for detecting and measuring the corrosion of reinforced steel embedded in the anchorage system will be developed as part of phase II research. The identified technologies shall be further developed for field testing utilizing a structure with a barrier in good condition and a structure with a barrier in poor condition.

  17. Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel

    Office of Environmental Management (EM)

    | Department of Energy Evaluation of Production of Oil & Gas From Oil Shale in the Piceance Basin Evaluation of Production of Oil & Gas From Oil Shale in the Piceance Basin The purpose of this paper is to provide the public and policy makers accurate estimates of energy efficiencies, water requirements, water availability, and CO2 emissions associated with the development of the 60 percent portion of the Piceance Basin where economic potential is the greatest, and where environmental

  18. Microsoft PowerPoint - Rail_Massaro

    Office of Environmental Management (EM)

    4 Annual Meeting of the National Transportation Stakeholders Forum May 13-15, 2014 in Bloomington, MN Safety Compliance Oversight Plan "SCOP" Tasks * Operational Integrity Train Crew, Train Dispatchers, etc. * Emergency Response Carrier Emergency Response Plans, Personnel Radioactive Awareness Training * Route Infrastructure Integrity Track Geometry, Bridge Inspection, etc. Hazardous Materials 2 Safety Compliance Oversight Plan "SCOP" Tasks * Highway-Rail Grade Crossing

  19. Automating Risk Assessments of Hazardous Material Shipments for Transportation Routes and Mode Selection

    SciTech Connect (OSTI)

    Barbara H. Dolphin; William D. RIchins; Stephen R. Novascone

    2010-10-01

    The METEOR project at Idaho National Laboratory (INL) successfully addresses the difficult problem in risk assessment analyses of combining the results from bounding deterministic simulation results with probabilistic (Monte Carlo) risk assessment techniques. This paper describes a software suite designed to perform sensitivity and cost/benefit analyses on selected transportation routes and vehicles to minimize risk associated with the shipment of hazardous materials. METEOR uses Monte Carlo techniques to estimate the probability of an accidental release of a hazardous substance along a proposed transportation route. A METEOR user selects the mode of transportation, origin and destination points, and charts the route using interactive graphics. Inputs to METEOR (many selections built in) include crash rates for the specific aircraft, soil/rock type and population densities over the proposed route, and bounding limits for potential accident types (velocity, temperature, etc.). New vehicle, materials, and location data are added when available. If the risk estimates are unacceptable, the risks associated with alternate transportation modes or routes can be quickly evaluated and compared. Systematic optimizing methods will provide the user with the route and vehicle selection identified with the lowest risk of hazardous material release. The effects of a selected range of potential accidents such as vehicle impact, fire, fuel explosions, excessive containment pressure, flooding, etc. are evaluated primarily using hydrocodes capable of accurately simulating the material response of critical containment components. Bounding conditions that represent credible accidents (i.e; for an impact event, velocity, orientations, and soil conditions) are used as input parameters to the hydrocode models yielding correlation functions relating accident parameters to component damage. The Monte Carlo algorithms use random number generators to make selections at the various decision points such as; crash, location, etc. For each pass through the routines, when a crash is randomly selected, crash parameters are then used to determine if failure has occurred using either external look up tables, correlations functions from deterministic calculations, or built in data libraries. The effectiveness of the software was recently demonstrated in safety analyses of the transportation of radioisotope systems for the US Dept. of Energy. These methods are readily adaptable to estimating risks associated with a variety of hazardous shipments such as spent nuclear fuel, explosives, and chemicals.

  20. DOE Shipment Activities: What We Accomplished and a Look Forward

    Office of Environmental Management (EM)

    Are We Shipping? * LLW and MLLW to NNSS * MOAB * LLW to EnergySolutions 3 Reportable ... and ARRA projects. 512011 10302011 Moab, UT Crescent Junction, UT Utah 4,901 Rail ...

  1. TEC Working Group Topic Groups Rail Key Documents Planning Subgroup...

    Office of Environmental Management (EM)

    Planning Subgroup Planning Subgroup PDF icon Rail Planning Timeline PDF icon Benchmarking Project: AREVA Trip Report More Documents & Publications TEC Meeting Summaries -...

  2. TEC Working Group Topic Groups Rail Key Documents Radiation Monitoring...

    Office of Environmental Management (EM)

    Radiation Monitoring Subgroup TEC Working Group Topic Groups Rail Key Documents Radiation Monitoring Subgroup Radiation Monitoring Subgroup PDF icon Draft Work Plan - February 4,...

  3. Hydrogen Assisted Diesel Combustion in a Common Rail Turbodiesel...

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

    a Compression Ignition Engine Advanced Diesel Combustion with Low Hydrocarbon and Carbon Monoxide Emissions Impacts of Rail Pressure and Biodiesel Composition on Soot Nanostructure

  4. TEC Working Group Topic Groups Rail Conference Call Summaries...

    Office of Environmental Management (EM)

    Summaries Inspections Subgroup TEC Working Group Topic Groups Rail Conference Call Summaries Inspections Subgroup Inspections Subgroup PDF icon April 6, 2006 PDF icon February 23,...

  5. TEC Working Group Topic Groups Rail Key Documents Intermodal...

    Office of Environmental Management (EM)

    Intermodal Subgroup TEC Working Group Topic Groups Rail Key Documents Intermodal Subgroup Intermodal Subgroup PDF icon Draft Work Plan More Documents & Publications TEC Working...

  6. Accident motivates scholarship recipient

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

    Accident motivates scholarship recipient Leyba encourages students: apply for Los Alamos ... Scholarship recipient not deterred by accident, inspired to help others October 26, 2010, ...

  7. Pipe overpack container for trasuranic waste storage and shipment

    DOE Patents [OSTI]

    Geinitz, Richard R. (Arvada, CO); Thorp, Donald T. (Broomfield, CO); Rivera, Michael A. (Boulder, CO)

    1999-01-01

    A Pipe Overpack Container for transuranic waste storage and shipment. The system consists of a vented pipe component which is positioned in a vented, insulated 55 gallon steel drum. Both the vented pipe component and the insulated drum are capable of being secured to prevent the contents from leaving the vessel. The vented pipe component is constructed of 1/4 inch stainless steel to provide radiation shielding. Thus, allowing shipment having high Americium-241 content. Several Pipe Overpack Containers are then positioned in a type B, Nuclear Regulatory Commission (NRC) approved, container. In the current embodiment, a TRUPACT-II container was employed and a maximum of fourteen Pipe Overpack Containers were placed in the TRUPACT-II. The combination received NRC approval for the shipment and storage of transuranic waste.

  8. SR-08-03 _LEU Shipments_.doc

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

    DOE Media CONTACTS: For Immediate Release Jim Giusti, (803) 952-7697 October, 2, 2008 james-r.giusti@srs.gov DOE's Savannah River Site Fulfills Uranium Shipment Contract with TVA Aiken, SC - The U.S. Department of Energy's (DOE) Savannah River Site (SRS) this week safely sent its final shipment of Cold War era uranium to the Tennessee Valley Authority (TVA), marking a significant step toward achieving the Department's goal of safely cleaning up the Site. As part of an interagency agreement with

  9. January 23, 2007: WIPP receives first shipment of waste | Department of

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

    Energy 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007 The Department's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, receives (pdf) its first shipment of remote-handled (RH) transuranic (TRU) radioactive waste. The waste, which consisted of three 30-gallon drums of radioactive debris waste and originated at DOE's Idaho National Laboratory, was

  10. Offset-free rail-to-rail derandomizing peak detect-and-hold circuit

    DOE Patents [OSTI]

    DeGeronimo, Gianluigi; O'Connor, Paul; Kandasamy, Anand

    2003-01-01

    A peak detect-and-hold circuit eliminates errors introduced by conventional amplifiers, such as common-mode rejection and input voltage offset. The circuit includes an amplifier, three switches, a transistor, and a capacitor. During a detect-and-hold phase, a hold voltage at a non-inverting in put terminal of the amplifier tracks an input voltage signal and when a peak is reached, the transistor is switched off, thereby storing a peak voltage in the capacitor. During a readout phase, the circuit functions as a unity gain buffer, in which the voltage stored in the capacitor is provided as an output voltage. The circuit is able to sense signals rail-to-rail and can readily be modified to sense positive, negative, or peak-to-peak voltages. Derandomization may be achieved by using a plurality of peak detect-and-hold circuits electrically connected in parallel.

  11. Implications of the Baltimore Rail Tunnel Fire for Full-Scale Testing of Shipping Casks

    SciTech Connect (OSTI)

    Halstead, R. J.; Dilger, F.

    2003-02-25

    The U.S. Nuclear Regulatory Commission (NRC) does not currently require full-scale physical testing of shipping casks as part of its certification process. Stakeholders have long urged NRC to require full-scale testing as part of certification. NRC is currently preparing a full-scale casktesting proposal as part of the Package Performance Study (PPS) that grew out of the NRC reexamination of the Modal Study. The State of Nevada and Clark County remain committed to the position that demonstration testing would not be an acceptable substitute for a combination of full-scale testing, scale-model tests, and computer simulation of each new cask design prior to certification. Based on previous analyses of cask testing issues, and on preliminary findings regarding the July 2001 Baltimore rail tunnel fire, the authors recommend that NRC prioritize extra-regulatory thermal testing of a large rail cask and the GA-4 truck cask under the PPS. The specific fire conditions and other aspects of the full-scale extra-regulatory tests recommended for the PPS are yet to be determined. NRC, in consultation with stakeholders, must consider past real-world accidents and computer simulations to establish temperature failure thresholds for cask containment and fuel cladding. The cost of extra-regulatory thermal testing is yet to be determined. The minimum cost for regulatory thermal testing of a legal-weight truck cask would likely be $3.3-3.8 million.

  12. Impact of commuter-rail services in Toronto region

    SciTech Connect (OSTI)

    Wells, S.S.; Hutchinson, B.G.

    1996-07-01

    Ridership of the commuter-rail system that was implemented in the Greater Toronto Area (GTA) in 1967 increased at an annual, average compound rate of 11.4% until 1989. Demand has leveled substantially during 1990--94 and has averaged only 2.1% per year, which probably reflects the suburbanization of employment. Urban economic theory is used to explain the way in which central-business-district (CBD) employees respond differently to suburban commuter-rail services and rapid transit services, mainly serving the inner intermediate suburbs. Travel data collected in 1986 and 1991 confirmed the effects suggested by the theory. Commuter-rail passengers are drawn from the larger suburban households, living principally in single-family houses, and commuter-rail passengers are more sensitive to access and egress distances than subway passengers. Policies that improve the quality of access and egress components of commuting trips from the suburbs stimulate passenger demand. Also, land-use policies that promote high-density, residential development at suburban commuter-rail stations are unlikely to contribute significantly to commuter-rail demand, and the lakeshore commuter-rail line that has been in service since 1967 has not had a significant impact on residential sorting and on the generation of additional demands.

  13. Accident Investigation of the June 17, 2012, Construction Accident...

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

    2012, Construction Accident - Structural Steel Collapse at The Over pack Storage ... Accident Investigation of the June 17, 2012, Construction Accident - Structural Steel ...

  14. Robotics virtual rail system and method

    DOE Patents [OSTI]

    Bruemmer, David J. (Idaho Falls, ID); Few, Douglas A. (Idaho Falls, ID); Walton, Miles C. (Idaho Falls, ID)

    2011-07-05

    A virtual track or rail system and method is described for execution by a robot. A user, through a user interface, generates a desired path comprised of at least one segment representative of the virtual track for the robot. Start and end points are assigned to the desired path and velocities are also associated with each of the at least one segment of the desired path. A waypoint file is generated including positions along the virtual track representing the desired path with the positions beginning from the start point to the end point including the velocities of each of the at least one segment. The waypoint file is sent to the robot for traversing along the virtual track.

  15. Microsoft PowerPoint - Rail_Kneitel [Compatibility Mode

    Office of Environmental Management (EM)

    * Some waste is transported as Class 7 per 49CFR173.401 - Low Specific Activity (LSA) is the "lowest category" of Class 7 waste. - BNL shipments are typically 3% to 5% of...

  16. Impacts of Rail Pressure and Biodiesel Composition on Soot Nanostructure

    Broader source: Energy.gov [DOE]

    Fractal dimensions of particle aggregates and the fringe lengths and fringe tortuosity within the primary soot particles has been assessed as functions of load, rail pressure, and biodiesel content.

  17. Proposed Work Scope for the Rail Topic Group

    Office of Environmental Management (EM)

    (TEC) Working Group's Rail Topic Group (RTG) is to provide stakeholder perspectives and ... or as necessary, reporting back to the full RTG on the bimonthly calls and at meetings. ...

  18. Enhanced Driver Requirements for WIPP Shipments - Fact Sheet

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

    . a critical step toward solving the nation's nuclear waste disposal problem Enhanced Driver Requirements for WIPP Shipments Waste Isolation Pilot Plant (WIPP), Driver Hiring Qualifications and Requirements WIPP drivers must meet very stringent requirements. To be hired, drivers: * Shall meet or exceed licensing, training, and physical qualification for set forth in the Code of Federal Regulations (CFR): "Qualifications of Drivers" 49 CFR 391; and the Commercial Motor Vehicle Safety

  19. Rail versus truck fuel efficiency: The relative fuel efficiency of truck-competitive rail freight and truck operations compared in a range of corridors. Final report

    SciTech Connect (OSTI)

    Not Available

    1991-04-01

    The report summarizes the findings of a study to evaluate the fuel efficiency of rail freight operations relative to competing truckload service. The objective of the study was to identify the circumstances in which rail freight service offers a fuel efficiency advantage over alternative truckload options, and to estimate the fuel savings associated with using rail service. The findings are based on computer simulations of rail and truck freight movements between the same origins and destinations. The simulation input assumptions and data are based on actual rail and truck operations. Input data was provided by U.S. regional and Class I railroads and by large truck fleet operators.

  20. The Rail Alignment Environmental Impact Statement: An Update

    SciTech Connect (OSTI)

    R. Sweeney

    2005-01-20

    On July 23,2002, the President of the United States signed into law a joint resolution of the United States Congress designating the Yucca Mountain site in Nye County, Nevada, for development as a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. If the US. Nuclear Regulatory Commission authorizes construction of the repository and receipt and possession of spent nuclear fuel and high-level radioactive at Yucca Mountain, the U.S. Department of Energy (DOE) would be responsible for transporting these materials to the Yucca Mountain repository as part of its obligation under the Nuclear Waste Policy Act. Part of the site recommendation decision included the analysis of a nation-wide shipping campaign to the proposed repository site. The ''Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada'' (February 2002) (Repository EIS) evaluated the potential impacts of the transportation of 70,000 Metric Tons of Heavy Metal spent nuclear fuel and high-level radioactive waste from 77 locations around the nation to the potential repository in Nevada over a 24 year shipping campaign. In the Repository EIS, DOE identified mostly rail as its preferred mode of transportation, both nationally and in the State of Nevada. In December 2003, based on public comments and the environmental analyses in the Repository EIS, DOE identified a preference for the Caliente rail corridor in Nevada. On April 8, 2004, DOE issued a Record of Decision (ROD) on the Mode of Transportation and Nevada Rail Corridor for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada. In this ROD, the DOE announced that it had decided to select the mostly rail scenario analyzed in the Repository EIS as the transportation mode both on a national basis and in the State of Nevada. Under the mostly rail scenario, the DOE would rely on a combination of rail, truck and possibly barge to transport to the repository site at Yucca Mountain up to 70,000 MTHM of spent nuclear fuel and high-level radioactive waste, with most of the spent nuclear fuel and high-level radioactive waste being transported by rail. This will ultimately require construction of a rail line in Nevada to the repository. In addition, the DOE has decided to select the Caliente rail corridor in which to examine potential alignments within which to construct that rail line. A corridor is a strip of land, approximately 400 meters (0.25 miles) wide, that encompasses one of several possible routes through which DOE could build a rail line. An alignment is the specific location of a rail line in a corridor, and would likely be 60 meters [200 feet] or less in width. Also on April 8, 2004, DOE issued a Notice of Intent to Prepare an Environmental Impact Statement for the Alignment, Construction, and Operation of a Rail Line to a Geologic Repository at Yucca Mountain, Nye County, NV. In the Notice of Intent, the Department announced its intent to prepare a Rail Alignment EIS to assist in selecting a possible alignment for construction of a rail line that would connect the repository at Yucca Mountain to an existing main rail line in Nevada. The Rail Alignment EIS also would consider the potential construction and operation of a rail-to-truck intermodal transfer facility, proposed to be located at the confluence of an existing mainline railroad and a highway, to support legal-weight truck transportation until the rail system is fully operational. This corridor is approximately 513 kilometers (319 miles) long and would cost an estimated $880 million (2001 dollars). Should DOE decide to build the Caliente corridor, it may be the longest rail line built in the United States since the Transcontinental Railroad was constructed in 1869. Some of the challenges in building this rail corridor are steep grades (the corridor crosses over 7 mountain ranges), isolated terrain, possible tunnels, and stakeholder acceptance.

  1. The First Recovery Act Funded Waste Shipment depart from the Advanced Mixed

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

    Waste Treatment Facility The First Recovery Act Funded Waste Shipment departs from the Advanced Mixed Waste Treatment Facility A shipment of mixed low-level waste left DOE�s Advanced Mixed Waste Treatment Project on May 6, years earlier than originally planned, due to funding received through the American Recovery and Reinvestment Act. The 36.5 cubic meter shipment consisted of radioactive and chemically contaminated waste that had been retrieved, characterized, packaged and shipped from

  2. Costs of Building Waste Facilities; Price Per Shipment to Recoup Costs

    Energy Science and Technology Software Center (OSTI)

    1993-05-14

    The Automated Pricing Schedule is a computer model for evaluating the economics of developing, operating, and closing a low-level radioactive waste disposal site. It provides pricing for individual shipments based on the characteristics of the shipment, and calculates a disposal fee to be charged for each shipment to recover the costs of the facility. It includes a sensitivity analysis module to evaluate the effect of varying the parameters of the model.

  3. WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs

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

    For immediate release WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs CARLSBAD, N.M., December 21, 2011 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote- handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble

  4. Table 10.7 Solar Thermal Collector Shipments by Market Sector...

    U.S. Energy Information Administration (EIA) Indexed Site

    Solar Thermal Collector Shipments by Market Sector, End Use, and Type, 2001-2009 (Thousand ... 8Medium-temperature collectors are solar thermal collectors that generally operate ...

  5. PTS 13.2 Packaging and Preparation for Shipment 4/10/95

    Broader source: Energy.gov [DOE]

    The objective of this surveillance is to evaluate the effectiveness of the contractor's programs for packaging radioactive and hazardous wastes for shipment.  The Facility Representative examines...

  6. 10,000th Waste Shipment Milestone is All in the Family | Department of

    Energy Savers [EERE]

    Energy 0,000th Waste Shipment Milestone is All in the Family 10,000th Waste Shipment Milestone is All in the Family August 29, 2011 - 12:00pm Addthis A Waste Isolation Pilot Plant facility shift manager inspects the shipping manifest of the 10,000th safe shipment to roll through the gates at the Department of Energy’s Waste Isolation Pilot Plant on Sept. 24, 2011. A Waste Isolation Pilot Plant facility shift manager inspects the shipping manifest of the 10,000th safe shipment to roll

  7. "Economic","per Employee","of Value Added","of Shipments" "Characteris...

    U.S. Energy Information Administration (EIA) Indexed Site

    ,,,"Consumption" ,,"Consumption","per Dollar" ,"Consumption","per Dollar","of Value" "Economic","per Employee","of Value Added","of Shipments" "Characteristic(a)","(million ...

  8. "Economic","per Employee","of Value Added","of Shipments" "Characteris...

    U.S. Energy Information Administration (EIA) Indexed Site

    " ",,"Consumption","per Dollar" " ","Consumption","per Dollar","of Value" "Economic","per Employee","of Value Added","of Shipments" "Characteristic(a)","(million ...

  9. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes

    U.S. Energy Information Administration (EIA) Indexed Site

    1.3 First Use of Energy for All Purposes (Fuel and Nonfuel), 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes Column: Energy Sources and Shipments; Unit: Trillion Btu. Shipments Economic Net Residual Distillate LPG and Coke and of Energy Sources Characteristic(a) Total(b) Electricity(c) Fuel Oil Fuel Oil(d) Natural Gas(e) NGL(f) Coal Breeze Other(g) Produced Onsite(h) Total United States Value of Shipments and Receipts (million dollars) Under 20 1,166 367 23

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

    Broader source: Energy.gov [DOE]

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

  11. Coal-by-Rail: A Business-as-Usual Reference Case | Argonne National...

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

    Coal-by-Rail: A Business-as-Usual Reference Case Title Coal-by-Rail: A Business-as-Usual Reference Case Publication Type Report Year of Publication 2015 Authors Mintz, MM, Saricks,...

  12. Crude Oil Movements of Crude of by Rail between PAD Districts

    U.S. Energy Information Administration (EIA) Indexed Site

    Notes: Rail movements of crude oil are estimates based on EIA analysis of data from the Surface Transportation Board and other information. See movements of crude oil by rail for ...

  13. Turbine blade squealer tip rail with fence members

    DOE Patents [OSTI]

    Little, David A

    2012-11-20

    A turbine blade includes an airfoil, a blade tip section, a squealer tip rail, and a plurality of chordally spaced fence members. The blade tip section includes a blade tip floor located at an end of the airfoil distal from the root. The blade tip floor includes a pressure side and a suction side joined together at chordally spaced apart leading and trailing edges of the airfoil. The squealer tip rail extends radially outwardly from the blade tip floor adjacent to the suction side and extends from a first location adjacent to the airfoil trailing edge to a second location adjacent to the airfoil leading edge. The fence members are located between the airfoil leading and trailing edges and extend radially outwardly from the blade tip floor and axially from the squealer tip rail toward the pressure side.

  14. Microsoft Word - Summary of Rail Comparison for Topic Group 7-1-02.doc

    Office of Environmental Management (EM)

    7/1/2002 1 Summary of the TEC Working Group Rail Topic Group report entitled "Transportation Safety WIPP-PIG Rail Comparison" In 1999, the Transportation External Coordination (TEC) Working Group developed a report entitled the "TEC/WG Transportation Safety Rail Comparison" to provide summary information to TEC participants concerning operational approaches, for rail transport in addressing a variety of transportation issues, objectives, approaches and procedures arising from

  15. USED FUEL RAIL SHOCK AND VIBRATION TESTING OPTIONS ANALYSIS

    SciTech Connect (OSTI)

    Ross, Steven B.; Best, Ralph E.; Klymyshyn, Nicholas A.; Jensen, Philip J.; Maheras, Steven J.

    2014-09-29

    The objective of the rail shock and vibration tests is to complete the framework needed to quantify loads of fuel assembly components that are necessary to guide materials research and establish a technical basis for review organizations such as the U.S. Nuclear Regulatory Commission (NRC). A significant body of experimental and numerical modeling data exists to quantify loads and failure limits applicable to normal conditions of transport (NCT) rail transport, but the data are based on assumptions that can only be verified through experimental testing. The test options presented in this report represent possible paths for acquiring the data that are needed to confirm the assumptions of previous work, validate modeling methods that will be needed for evaluating transported fuel on a case-by-case basis, and inform material test campaigns on the anticipated range of fuel loading. The ultimate goal of this testing is to close all of the existing knowledge gaps related to the loading of used fuel under NCT conditions and inform the experiments and analysis program on specific endpoints for their research. The options include tests that would use an actual railcar, surrogate assemblies, and real or simulated rail transportation casks. The railcar carrying the cradle, cask, and surrogate fuel assembly payload would be moved in a train operating over rail track modified or selected to impart shock and vibration forces that occur during normal rail transportation. Computer modeling would be used to help design surrogates that may be needed for a rail cask, a cask’s internal basket, and a transport cradle. The objective of the design of surrogate components would be to provide a test platform that effectively simulates responses to rail shock and vibration loads that would be exhibited by state-of-the-art rail cask, basket, and/or cradle structures. The computer models would also be used to help determine the placement of instrumentation (accelerometers and strain gauges) on the surrogate fuel assemblies, cask and cradle structures, and the railcar so that forces and deflections that would result in the greatest potential for damage to high burnup and long-cooled UNF can be determined. For purposes of this report we consider testing on controlled track when we have control of the track and speed to facilitate modeling.

  16. US and Dutch Governments Launch Effort to Detect Terrorist Shipments of

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

    Nuclear Material | National Nuclear Security Administration US and Dutch Governments Launch Effort to Detect Terrorist Shipments of Nuclear Material August 13, 2003 US and Dutch Governments Launch Effort to Detect Terrorist Shipments of Nuclear Material (PDF - 0.02Mb)~

  17. Rail assembly for use in a radioactive environment

    DOE Patents [OSTI]

    Watts, Ralph E.

    1989-01-01

    An improved rail assembly and method of construction thereof is disclosed herein that is particularly adapted for use with a crane trolley in a hot cell environment which is exposed to airborne and liquidborne radioactive contaminants. The rail assembly is generally comprised of a support wall having an elongated, rail-housing recess having a floor, side wall and ceiling. The floor of the recess is defined at least in part by the load-bearing surface of a rail, and is substantially flat, level and crevice-free to facilitate the drainage of liquids out of the recess. The ceiling of the recess overhangs and thereby captures trolley wheels within the recess to prevent them from becoming dislodged from the recess during a seismic disturbance. Finally, the interior of the recess includes a power track having a slot for receiving a sliding electrical connector from the crane trolley. The power track is mounted in an upper corner of the recess with its connector-receiving groove oriented downwardly to facilitate the drainage of liquidborne contaminants and to discourage the collection of airborne contaminants within the track.

  18. Full-Scale Accident Testing in Support of Used Nuclear Fuel Transportation.

    SciTech Connect (OSTI)

    Durbin, Samuel G.; Lindgren, Eric R.; Rechard, Rob P.; Sorenson, Ken B.

    2014-09-01

    The safe transport of spent nuclear fuel and high-level radioactive waste is an important aspect of the waste management system of the United States. The Nuclear Regulatory Commission (NRC) currently certifies spent nuclear fuel rail cask designs based primarily on numerical modeling of hypothetical accident conditions augmented with some small scale testing. However, NRC initiated a Package Performance Study (PPS) in 2001 to examine the response of full-scale rail casks in extreme transportation accidents. The objectives of PPS were to demonstrate the safety of transportation casks and to provide high-fidelity data for validating the modeling. Although work on the PPS eventually stopped, the Blue Ribbon Commission on America’s Nuclear Future recommended in 2012 that the test plans be re-examined. This recommendation was in recognition of substantial public feedback calling for a full-scale severe accident test of a rail cask to verify evaluations by NRC, which find that risk from the transport of spent fuel in certified casks is extremely low. This report, which serves as the re-assessment, provides a summary of the history of the PPS planning, identifies the objectives and technical issues that drove the scope of the PPS, and presents a possible path for moving forward in planning to conduct a full-scale cask test. Because full-scale testing is expensive, the value of such testing on public perceptions and public acceptance is important. Consequently, the path forward starts with a public perception component followed by two additional components: accident simulation and first responder training. The proposed path forward presents a series of study options with several points where the package performance study could be redirected if warranted.

  19. Accident resistant transport container

    DOE Patents [OSTI]

    Andersen, John A.; Cole, James K.

    1980-01-01

    The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident.

  20. Accident resistant transport container

    DOE Patents [OSTI]

    Anderson, J.A.; Cole, K.K.

    The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident.

  1. Accident management information needs

    SciTech Connect (OSTI)

    Hanson, D.J.; Ward, L.W.; Nelson, W.R.; Meyer, O.R. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

    1990-04-01

    In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, a methodology has been developed for identifying the plant information needs necessary for personnel involved in the management of an accident to diagnose that an accident is in progress, select and implement strategies to prevent or mitigate the accident, and monitor the effectiveness of these strategies. This report describes the methodology and presents an application of this methodology to a Pressurized Water Reactor (PWR) with a large dry containment. A risk-important severe accident sequence for a PWR is used to examine the capability of the existing measurements to supply the necessary information. The method includes an assessment of the effects of the sequence on the measurement availability including the effects of environmental conditions. The information needs and capabilities identified using this approach are also intended to form the basis for more comprehensive information needs assessment performed during the analyses and development of specific strategies for use in accident management prevention and mitigation. 3 refs., 16 figs., 7 tabs.

  2. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;

    U.S. Energy Information Administration (EIA) Indexed Site

    2 Consumption Ratios of Fuel, 2010; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption per Dollar of Value Economic per Employee of Value Added of Shipments Characteristic(a) (million Btu) (thousand Btu) (thousand Btu) Total United States Value of Shipments and Receipts (million dollars) Under 20 405.4 4.0 2.1 20-49 631.3 4.7 2.2 50-99 832.0 4.9 2.3 100-249 1,313.4 6.2

  3. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;

    U.S. Energy Information Administration (EIA) Indexed Site

    2 Consumption Ratios of Fuel, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption per Dollar of Value Economic per Employee of Value Added of Shipments Characteristic(a) (million Btu) (thousand Btu) (thousand Btu) Total United States Value of Shipments and Receipts (million dollars) Under 20 330.6 3.6 2.0 20-49 550.0 4.5 2.2 50-99 830.1 5.9 2.7 100-249 1,130.0 6.7

  4. Section 08: Approval Process for Waste Shipment From Waste Generator Sites

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

    for Disposal at the WIPP Approval Process for Waste Shipment From Waste Generator Sites for Disposal at the WIPP (40 CFR § 194.8) United States Department of Energy Waste Isolation Pilot Plant Carlsbad Field Office Carlsbad, New Mexico Compliance Recertification Application 2014 Approval Process for Waste Shipment From Waste Generator Sites for Disposal at the WIPP (40 CFR § 194.8) Table of Contents 8.0 Approval Process for Waste Shipment From Waste Generator Sites for Disposal at the WIPP

  5. EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE...

    Office of Environmental Management (EM)

    ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive ...

  6. The politics of Peacekeeper Rail Garrison. Doctoral thesis

    SciTech Connect (OSTI)

    Van Tassel, A.R.

    1992-01-01

    In 1985, the Congress capped at 50 the number of Peacekeeper ICBMs that could be deployed in vulnerable Minuteman silos, thereby sending the Reagan administration and the Air Force in search of another basing mode so that 100 of the ton-warhead missiles could be deployed as recommended by the Scowcroft Commission. The result was Peacekeeper rail garrison--a strategic nuclear weapon system that combined the Peacekeeper missile with railroad trains garrisoned at military installations. The missile trains would have dispersed across the nation's railways only during times of 'national need like the Cuban Missile Crisis. This case study examines the politics of that weapon system in order to contribute to the literature regarding weapons acquisition, test a number of propositions suggested by the bureaucratic politics model, and assess the influence of nonbureaucratic forces and actors on Peacekeeper rail garrison's fortunes.

  7. Dual-circuit segmented rail phased induction motor

    DOE Patents [OSTI]

    Marder, Barry M. (Albuquerque, NM); Cowan, Jr., Maynard (Albuquerque, NM)

    2002-01-01

    An improved linear motor utilizes two circuits, rather that one circuit and an opposed plate, to gain efficiency. The powered circuit is a flat conductive coil. The opposed segmented rail circuit is either a plurality of similar conductive coils that are shorted, or a plurality of ladders formed of opposed conductive bars connected by a plurality of spaced conductors. In each embodiment, the conductors are preferably cables formed from a plurality of intertwined insulated wires to carry current evenly.

  8. Accident Conditions versus Regulatory Test for NRC-Approved UF6 Packages

    SciTech Connect (OSTI)

    MILLS, G. SCOTT; AMMERMAN, DOUGLAS J.; LOPEZ, CARLOS

    2003-01-01

    The Nuclear Regulatory Commission (NRC) approves new package designs for shipping fissile quantities of UF{sub 6}. Currently there are three packages approved by the NRC for domestic shipments of fissile quantities of UF{sub 6}: NCI-21PF-1; UX-30; and ESP30X. For approval by the NRC, packages must be subjected to a sequence of physical tests to simulate transportation accident conditions as described in 10 CFR Part 71. The primary objective of this project was to relate the conditions experienced by these packages in the tests described in 10 CFR Part 71 to conditions potentially encountered in actual accidents and to estimate the probabilities of such accidents. Comparison of the effects of actual accident conditions to 10 CFR Part 71 tests was achieved by means of computer modeling of structural effects on the packages due to impacts with actual surfaces, and thermal effects resulting from test and other fire scenarios. In addition, the likelihood of encountering bodies of water or sufficient rainfall to cause complete or partial immersion during transport over representative truck routes was assessed. Modeled effects, and their associated probabilities, were combined with existing event-tree data, plus accident rates and other characteristics gathered from representative routes, to derive generalized probabilities of encountering accident conditions comparable to the 10 CFR Part 71 conditions. This analysis suggests that the regulatory conditions are unlikely to be exceeded in real accidents, i.e. the likelihood of UF{sub 6} being dispersed as a result of accident impact or fire is small. Moreover, given that an accident has occurred, exposure to water by fire-fighting, heavy rain or submersion in a body of water is even less probable by factors ranging from 0.5 to 8E-6.

  9. Table 10.6 Solar Thermal Collector Shipments by Type, Price,...

    U.S. Energy Information Administration (EIA) Indexed Site

    Solar Thermal Collector Shipments by Type, Price, and Trade, 1974-2009 (Thousand Square ... 1,577 1Low-temperature collectors are solar thermal collectors that generally operate ...

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

    SciTech Connect (OSTI)

    Nguyen, P.M.

    1994-08-19

    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.

  11. Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas

    Broader source: Energy.gov [DOE]

    PIKETON, Ohio — EM’s Portsmouth site this summer sent its first shipment of mixed low-level radioactive waste from its uranium enrichment operations to Waste Control Specialists (WCS) in Andrews, Texas for treatment and disposal.

  12. U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal

    Broader source: Energy.gov [DOE]

    On Tuesday, November 12, 2013, the U.S. Department of Energy (DOE) will host a press call to discuss Consolidated Edison Uranium Solidification Project (CEUSP) shipment and disposal plans in Nevada.

  13. EIA Energy Efficiency-Table 4a. Value of Shipments by Selected...

    Gasoline and Diesel Fuel Update (EIA)

    Table 4a Page Last Modified: May 2010 Table 4a. Value of Shipments1 by Selected Industries, 1998, 2002, and 2006 (Billion 2000 Dollars ) MECS Survey Years NAICS Subsector and...

  14. EIA Energy Efficiency-Table 3a. Value of Shipments by Selected...

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    a Page Last Modified: May 2010 Table 3a. Value of Shipments 1 by Selected Industries, 1998, 2002, and 2006 (Current Billion Dollars) MECS Survey Years NAICS Subsector and Industry...

  15. Award Spotlight Could Return to EM-Developed Technology for Tracking Shipments

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – EM’s James Shuler felt honored being named a technology innovation award finalist for developing radiofrequency identification (RFID) technology to track and monitor radioactive material shipments.

  16. Recovery Act Funding Leads to Record Year for Transuranic Waste Shipments

    Broader source: Energy.gov [DOE]

    With the help of American Recovery and Reinvestment Act funding, the Waste Isolation Pilot Plant (WIPP) received the most transuranic waste shipments in a single year since waste operations began...

  17. Under U.S.-Russia Partnership, Final Shipment of Fuel Converted...

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

    The final shipment also signals the beginning of a new era of U.S.-Russia collaborative work in the fields of nonproliferation, science, and nuclear research and development under ...

  18. U.S. and Bahamian Governments to Cooperate on Detecting Illicit Shipments

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

    of Nuclear Material | Department of Energy Bahamian Governments to Cooperate on Detecting Illicit Shipments of Nuclear Material U.S. and Bahamian Governments to Cooperate on Detecting Illicit Shipments of Nuclear Material January 11, 2005 - 9:46am Addthis Bahamas to Become First Caribbean Country to Use Detection Equipment NASSAU, BAHAMAS -- In an effort to work together in the war on terrorism, the United States and the Commonwealth of the Bahamas recently signed an agreement to install

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

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

    2010-12-20

    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. Supersedes DOE O 461.1A.

  20. Accident Response Group | National Nuclear Security Administration

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

    Accident Response Group NNSA's Accident Response Group (ARG) provides technical guidance and responds to U.S. nuclear weapons accidents. ARGLogo The team assists in assessing ...

  1. Federally Led Accident Investigation Reports | Department of...

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

    Federally Led Accident Investigation Reports Federally Led Accident Investigation Reports Includes Pre-March 2011 Type A Reports June 1, 1999 Type A Accident Investigation Board...

  2. Chernobyl Nuclear Accident | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Chernobyl Nuclear Accident Chernobyl Nuclear Accident Chernobyl, Ukraine A catastrophic nuclear accident occurs at Chernobyl Reactor 4 in the then Soviet Republic of Ukraine

  3. Rail transport of western coal: the history of rail deregulation and its influence on western coal resource development; prospects for legislative change

    SciTech Connect (OSTI)

    Smith, J.N.; Rose, R.R.

    1985-04-01

    The one major cloud on the horizon for the future of western coal outside the region is the high cost of transportation. With rail transportation costs running as much as 75% of the delivered price to some of the Gulf States, the ability to keep rail costs in check becomes critical to the future of western coal. Four years of experience with deregulation of the railroads and the performance of the Interstate Commerce Commission (ICC) under the new regulatory environment have led many shippers and buyers of rail transported commodities to the belief that national legislation is needed to give better protection to shippers in monopoly service areas. A tentative legislative effort began in the last Congress. Proposals for rail rate relief for captive shippers are taking more formidable shape in the 99th Congress with the organization of a well-financed and staffed coalition of coal and utility companies. They are seeking amendments to the Staggers Act which more explicitly define the protections and procedures available to captive shippers in advancing complaints through the ICC. Industrial shippers have formed a coalition of their own for fair rail service practices. Finally, another group has emerged in recent months seeking a bolder strategy for rail rate relief. This group asserts that unfair rail practices violate the antitrust laws. At the same time, the railroads are building their defenses and developing alliances with interests in the shipping community that would resist a return to greater rail regulation. While the outcome of this controversy is uncertain, the issue of rail rate equity and reregulation promises to become one of the more active and hotly debated issues in the 99th Congress. However it comes out, the results will have a lasting impact on many western states, their present economy and future development.

  4. Type B Accident Investigation, Subcontractor Employee Personal...

    Office of Environmental Management (EM)

    Park, Oak Ridge, Tennessee Type B Accident Investigation, Subcontractor Employee ... PDF icon Type B Accident Investigation, Subcontractor Employee Personal Protective ...

  5. 2011-07 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" |

    Office of Environmental Management (EM)

    Department of Energy 7 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" 2011-07 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" The intent of this recommendation is to ensure optimization of WIPP shipment schedules while helping to keep commitments to Consent Order milestones at MDA-G. PDF icon Rec 2011-07

  6. 4th Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Gregory, Louis

    2014-12-02

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. There was one shipment of two drums sent for offsite treatment and disposal. This report summarizes the 4th quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014.

  7. DRAFT - DOE O 461.1C, Packaging and Transportation for Offsite Shipment of Materials of National Security Interest

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

    The Order establishes requirements and responsibilities for ensuring the safety of packaging and transportation for offsite shipments of Materials of National Security Interest.

  8. Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania

    SciTech Connect (OSTI)

    K. J. Allen; I. Bolshinsky; L. L. Biro; M. E. Budu; N. V. Zamfir; M. Dragusin

    2010-07-01

    Romania safely air shipped 23.7 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel from the VVR S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the worlds first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in cooperation with the Romania National Commission for Nuclear Activities Control (CNCAN), the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), and the Russian Federation State Corporation Rosatom. The shipment was transported by truck to and from the respective commercial airports in Romania and the Russian Federation and stored at a secure nuclear facility in Russia where it will be converted into low enriched uranium. With this shipment, Romania became the 3rd country under the RRRFR program and the 14th country under the GTRI program to remove all HEU. This paper describes the work, equipment, and approvals that were required to complete this spent fuel air shipment.

  9. Research Reactor Preparations for the Air Shipment of Highly Enriched Uranium from Romania

    SciTech Connect (OSTI)

    K. J. Allen; I. Bolshinsky; L. L. Biro; M. E. Budu; N. V. Zamfir; M. Dragusin; C. Paunoiu; M. Ciocanescu

    2010-03-01

    In June 2009 two air shipments transported both unirradiated (fresh) and irradiated (spent) Russian-origin highly enriched uranium (HEU) nuclear fuel from two research reactors in Romania to the Russian Federation for conversion to low enriched uranium. The Institute for Nuclear Research at Pitesti (SCN Pitesti) shipped 30.1 kg of HEU fresh fuel pellets to Dimitrovgrad, Russia and the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH) shipped 23.7 kilograms of HEU spent fuel assemblies from the VVR S research reactor at Magurele, Romania, to Chelyabinsk, Russia. Both HEU shipments were coordinated by the Russian Research Reactor Fuel Return Program (RRRFR) as part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), were managed in Romania by the National Commission for Nuclear Activities Control (CNCAN), and were conducted in cooperation with the Russian Federation State Corporation Rosatom and the International Atomic Energy Agency. Both shipments were transported by truck to and from respective commercial airports in Romania and the Russian Federation and stored at secure nuclear facilities in Russia until the material is converted into low enriched uranium. These shipments resulted in Romania becoming the 3rd country under the RRRFR program and the 14th country under the GTRI program to remove all HEU. This paper describes the research reactor preparations and license approvals that were necessary to safely and securely complete these air shipments of nuclear fuel.

  10. Severe Accident Modeling

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

    Severe Accident Modeling - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  11. Accident Investigation of the June 17, 2012, Construction Accident -

    Energy Savers [EERE]

    Structural Steel Collapse at The Over pack Storage Expansion #2 at the Naval Reactors Facility at the Idaho National Laboratory, Idaho Falls, Idaho | Department of Energy 7, 2012, Construction Accident - Structural Steel Collapse at The Over pack Storage Expansion #2 at the Naval Reactors Facility at the Idaho National Laboratory, Idaho Falls, Idaho Accident Investigation of the June 17, 2012, Construction Accident - Structural Steel Collapse at The Over pack Storage Expansion #2 at the

  12. Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments

    U.S. Energy Information Administration (EIA) Indexed Site

    1.4 Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 2006; Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments Unit: Establishment Counts. Any Shipments NAICS Energy Net Residual Distillate LPG and Coke and of Energy Sources Code(a) Subsector and Industry Source(b) Electricity(c) Fuel Oil Fuel Oil(d) Natural Gas(e) NGL(f) Coal Breeze Other(g) Produced Onsite(h) Total United States 311 Food 14,128 14,113 326 1,475 11,399 2,947 67 15

  13. Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments;

    U.S. Energy Information Administration (EIA) Indexed Site

    .4 Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 2010; Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments; Unit: Establishment Counts. Any Shipments NAICS Energy Net Residual Distillate LPG and Coke and of Energy Sources Code(a) Subsector and Industry Source(b) Electricity(c) Fuel Oil Fuel Oil(d) Natural Gas(e) NGL(f) Coal Breeze Other(g) Produced Onsite(h) Total United States 311 Food 13,269 13,265 151 2,494 10,376 4,061 64 7

  14. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes

    U.S. Energy Information Administration (EIA) Indexed Site

    2.3 Nonfuel (Feedstock) Use of Combustible Energy, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes Column: Energy Sources Unit: Trillion Btu Economic Residual Distillate LPG and Coke and Characteristic(a) Total Fuel Oil Fuel Oil(b) Natural Gas(c) NGL(d) Coal Breeze Other(e) Total United States Value of Shipments and Receipts (million dollars) Under 20 47 0 3 5 Q 20 1 17 20-49 112 7 Q 20 1 12 1 64 50-99 247 29 Q 26 88 33 * 68 100-249 313 28 1 97 12 48 43 85

  15. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;

    U.S. Energy Information Administration (EIA) Indexed Site

    2 Electricity: Components of Net Demand, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Electricity Components; Unit: Million Kilowatthours. Sales and Net Demand Economic Total Onsite Transfers for Characteristic(a) Purchases Transfers In(b) Generation(c) Offsite Electricity(d) Total United States Value of Shipments and Receipts (million dollars) Under 20 107,618 56 1,447 28 109,094 20-49 97,570 181 5,220 307 102,664 50-99 104,082 Q 3,784 2,218

  16. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;

    U.S. Energy Information Administration (EIA) Indexed Site

    4 Electricity: Components of Onsite Generation, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Onsite-Generation Components; Unit: Million Kilowatthours. Renewable Energy (excluding Wood Economic Total Onsite and Characteristic(a) Generation Cogeneration(b) Other Biomass)(c) Other(d) Total United States Value of Shipments and Receipts (million dollars) Under 20 1,447 450 Q Q 20-49 5,220 5,106 29 Q 50-99 3,784 3,579 29 Q 100-249 17,821 17,115 484

  17. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;

    U.S. Energy Information Administration (EIA) Indexed Site

    6 Electricity: Sales to Utility and Nonutility Purchasers, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Utility and Nonutility Purchasers; Unit: Million Kilowatthours. Total of Economic Sales and Utility Nonutility Characteristic(a) Transfers Offsite Purchaser(b) Purchaser(c) Total United States Value of Shipments and Receipts (million dollars) Under 20 28 28 0 20-49 307 227 80 50-99 2,218 1,673 545 100-249 2,647 1,437 1,210 250-499 3,736 2,271

  18. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;

    U.S. Energy Information Administration (EIA) Indexed Site

    3.3 Fuel Consumption, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Energy Sources; Unit: Trillion Btu. Economic Net Residual Distillate LPG and Coke and Characteristic(a) Total Electricity(b) Fuel Oil Fuel Oil(c) Natural Gas(d) NGL(e) Coal Breeze Other(f) Total United States Value of Shipments and Receipts (million dollars) Under 20 1,139 367 23 45 535 14 21 3 131 20-49 1,122 333 13 19 530 8 93 5 122 50-99 1,309 349 22 17 549 10 157 8 197

  19. Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;

    U.S. Energy Information Administration (EIA) Indexed Site

    4.3 Offsite-Produced Fuel Consumption, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Energy Sources; Unit: Trillion Btu. Economic Residual Distillate Natural LPG and Coke and Characteristic(a) Total Electricity(b) Fuel Oil Fuel Oil(c) Gas(d) NGL(e) Coal Breeze Other(f) Total United States Value of Shipments and Receipts (million dollars) Under 20 1,066 367 23 45 535 13 21 3 59 20-49 1,063 334 13 18 530 8 93 5 63 50-99 1,233 357 22 16 549 10 157 8

  20. Public information circular for shipments of irradiated reactor fuel. Revision 9

    SciTech Connect (OSTI)

    Not Available

    1993-03-01

    This circular has been prepared to provide information on the shipment of irradiated reactor fuel (spent fuel) subject to regulation by the Nuclear Regulatory Commission (NRC), and to meet the requirements of Public Law 96--295. The report provides a brief description of NRC authority for certain aspects of transporting spent fuel. It provides descriptive statistics on spent fuel shipments regulated by the NRC from 1979 to 1992. It also lists detailed highway and railway segments used within each state from October 1, 1987 through December 31, 1992.

  1. Reducing the environmental impact of road and rail vehicles

    SciTech Connect (OSTI)

    Mayer, R.M.; Poulikakos, L.D.; Lees, A.R.; Heutschi, K.; Kalivoda, M.T.

    2012-01-15

    Methods have been developed to measure in situ the dynamic impact of both road and rail vehicles on the infrastructure and the environment. The resulting data sets have been analysed to quantify the environmental impacts in a transparent manner across both modes. A primary concern is that a small number of vehicles are being operated outside safe or regulatory limits which can have a disproportionate large impact. The analysis enables the various impacts to be ranked across both modes so enabling one to discern the benefits of intermodal transport. The impact of various policy options is considered and how to identify vehicles which can be classified as environmentally friendly. This would require European agreement as many heavy goods vehicle operate across country borders.

  2. Steering system for a train of rail-less vehicles

    DOE Patents [OSTI]

    Voight, Edward T.

    1983-01-01

    A steering system for use with a multiple vehicle train permits tracking without rails of one vehicle after another. This system is particularly useful for moving conveyor systems into and out of curved paths of room and pillar underground mine installations. The steering system features an elongated steering bar pivotally connected to each of adjacent vehicles at end portions of the bar permitting angular orientation of each vehicle in respect to the steering bar and other vehicles. Each end portion of the steering bar is linked to the near pair of vehicle wheels through wheel yoke pivot arms about king pin type pivots. Movement of the steering bar about its pivotal connection provides proportional turning of the wheels to effect steering and tracking of one vehicle following another in both forward and reverse directions.

  3. Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report' Note: Dollars are not

    U.S. Energy Information Administration (EIA) Indexed Site

    modules $3,754,813 Total modules $0.75 Table 2. Value and average value of photovoltaic module shipments, 2013 Module value, total shipments (thousand dollars) Module average value (dollars per peak watt) Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report' Note: Dollars are not adjusted for inflation.

  4. Table Definitions, Sources, and Explanatory Notes

    Gasoline and Diesel Fuel Update (EIA)

    Rail

  5. WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M. – The U.S. Department of Energy’s (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote-handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque.

  6. First Responders and Criticality Accidents

    SciTech Connect (OSTI)

    Valerie L. Putman; Douglas M. Minnema

    2005-11-01

    Nuclear criticality accident descriptions typically include, but do not focus on, information useful to first responders. We studied these accidents, noting characteristics to help (1) first responders prepare for such an event and (2) emergency drill planners develop appropriate simulations for training. We also provide recommendations to help people prepare for such events in the future.

  7. Fact #554: January 19, 2009 Energy Intensity of Light Rail Transit Systems

    Broader source: Energy.gov [DOE]

    According to the 2007 National Transit Databases, the energy intensity of light transit rail systems in the U.S. ranges from about 2,000 Btu per passenger-mile to about 31,000 Btu per passenger...

  8. DOE to Transport Moab Mill Tailings by Rail | Department of Energy

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

    of the U.S. Highway 191 transportation corridor that would be used to haul the material. ... The substantial rail infrastructure work is anticipated to begin in fall 2008 and is ...

  9. Cooled electronic system with thermal spreaders coupling electronics cards to cold rails

    DOE Patents [OSTI]

    Chainer, Timothy J; Gaynes, Michael A; Graybill, David P; Iyengar, Madhusudan K; Kamath, Vinod; Kochuparambil, Bejoy J; Schmidt, Roger R; Schultz, Mark D; Simco, Daniel P; Steinke, Mark E

    2013-07-23

    Liquid-cooled electronic systems are provided which include an electronic assembly having an electronics card and a socket with a latch at one end. The latch facilitates securing of the card within the socket or removal of the card from the socket. A liquid-cooled cold rail is disposed at the one end of the socket, and a thermal spreader couples the electronics card to the cold rail. The thermal spreader includes first and second thermal transfer plates coupled to first and second surfaces on opposite sides of the card, and thermally conductive extensions extending from end edges of the plates, which couple the respective transfer plates to the liquid-cooled cold rail. The thermally conductive extensions are disposed to the sides of the latch, and the card is securable within or removable from the socket using the latch without removing the cold rail or the thermal spreader.

  10. ORISE: REAC/TS Radiation Accident Registries

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

    Accident Registries The Radiation Emergency Assistance CenterTraining Site (REACTS) at ... (ORISE) maintains a number of radiation accident registries that provide medical ...

  11. DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING...

    Office of Environmental Management (EM)

    Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING ... related to emergency response to a transportation accident involving radioactive material. ...

  12. Table 10.8 Photovoltaic Cell and Module Shipments by Type, Trade, and Prices, 1982-2010

    U.S. Energy Information Administration (EIA) Indexed Site

    Photovoltaic Cell and Module Shipments by Type, Trade, and Prices, 1982-2010 Year U.S. Companies Reporting Shipments Shipments Trade Prices 1 Crystalline Silicon Thin-Film Total 2 Imports Exports Cells Modules Cells and Modules Modules Only Cells and Modules Modules Only Cells and Modules Modules Only Cells and Modules Modules Only Cells and Modules Modules Only Number Peak Kilowatts 3 Dollars 4 per Peak Watt 3 1982 19 NA NA NA NA 6,897 NA NA NA NA NA NA NA 1983 18 NA NA NA NA 12,620 NA NA NA

  13. 2011-02 "Accelerating TRU Waste Shipments from Area G to WIPP" | Department

    Office of Environmental Management (EM)

    of Energy 2 "Accelerating TRU Waste Shipments from Area G to WIPP" 2011-02 "Accelerating TRU Waste Shipments from Area G to WIPP" The intent of this recommendation is to help ensure that the rate of removal of Transuranic Waste from Area G is consistent with the completion of milestones in the 2005 Order on Consent. It is hoped that all agencies can work together and that all available funds can be used for WIPP shipments rather than some monies being diverted to pay

  14. ELUCIDATING THE DIFFERENCES BETWEEN ONSITE AND OFFSITE SHIPMENT OF RADIOACTIVE MATERIALS

    SciTech Connect (OSTI)

    Loftin, B.; Watkins, R.

    2013-06-19

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

  15. Request for One-Time Shipment of 32 Watt PU-328 Source in 9968 Packaging

    SciTech Connect (OSTI)

    Massey, W.M.

    1998-11-25

    The 9968 package is designed for surface shipment of fissile and other radioactive materials where a high degree of double containment is required. The use of the 9968 radioactive material package for a one time shipment of a 32 watt heat source versus the SARP approved maximum 30 watt heat source is addressed in this report. The analyses show that the small increase in heat load from 30 watts to 32 watts does not substantially increase internal temperatures or pressures that would approach limits for the package. Also, the weight of the content is within the current 9968 package limits. It is concluded that the 32-watt heat source can be safely shipped in the 9968 package and therefore a waiver to ship the source is justified.

  16. LOW-LEVEL RADIOACTIVE & MIXED WASTE SHIPMENTS TO THE NEVADA NATIONAL SECURITY SITE

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

    NV NY NY NV OH TN TN TN, WA, CA TN TN TN TX y ct 2 Plant Perma-Fix LOW-LEVEL RADIOACTIVE & MIXED WASTE SHIPMENTS TO THE NEVADA NATIONAL SECURITY SITE FIRST QUARTER REPORT, FY 2011 (OCTOBER, NOVEMBER, DECEMBER 2010) Livermore National Laboratory ergy Alliance onal Laboratory Mixed Waste Treatment Project gonne National Laboratory ational Laboratory Gaseous Diffusion Plant Proving Ground terra, LLC en National Laboratory y Environmental Services ecurity Technologies, Inc. h Gaseous Diffusion

  17. Radioactive Waste Shipments To And From The Nevada Test Site (NTS)

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

    688 ANNUAL REPORT - FY 2000 Radioactive Waste Shipments To And From The Nevada Test Site (NTS) March 2001 United States Department of Energy Nevada Operations Office Las Vegas, Nevada Availability for sale to the public from- U.S. Department of Commerce National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Phone 800.553.6847 Fax 703.605.6900 Email: orders@ntis.fedworld.gov Online ordering: http://www.ntis.gov/ordering.htm Available electronically at

  18. Radioactive Waste Shipments To And From The Nevada Test Site (NTS)

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

    947 ANNUAL REPORT - FY 2003 Radioactive Waste Shipments To And From The Nevada Test Site (NTS) January 2004 United States Department of Energy National Nuclear Security Administration Nevada Site Office Las Vegas, Nevada Available for sale to the public from- U.S. Department of Commerce National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Phone: 800.553.6847 Fax: 703.605.6900 Email: orders@ntis.gov Online ordering: http://www.ntis.gov/ordering.htm Available

  19. Accident tolerant fuel analysis

    SciTech Connect (OSTI)

    Smith, Curtis; Chichester, Heather; Johns, Jesse; Teague, Melissa; Tonks, Michael Idaho National Laboratory; Youngblood, Robert

    2014-09-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced ''RISMC toolkit'' that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional ''accident-tolerant'' (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  20. Accident Tolerant Fuel Analysis

    SciTech Connect (OSTI)

    Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood

    2014-09-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  1. Phase II Accident Investigation Board Briefing | Department of...

    Office of Environmental Management (EM)

    Phase II Accident Investigation Board Briefing Phase II Accident Investigation Board Briefing Topic: Ted Wyka DOE, Provided a Brief on the Findings in the WIPP Accident ...

  2. Type B Accident Investigation on the February 17, 2004, Personal...

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

    on the February 17, 2004, Personal Injury Accident, Bettis Atomic Power Laboratory Type B Accident Investigation on the February 17, 2004, Personal Injury Accident, Bettis Atomic ...

  3. The February 2014 Accidents at WIPP - What Happened and What...

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

    Comprehensive accident investigations resulted in significant planned changes to enhance ... ACCIDENT INVESTIGATIONS On February 7, 2014, the Department appointed an Accident ...

  4. Environment/Health/Safety (EHS): Monthly Accident Statistics

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

    Personal Protective Equipment (PPE) Injury Review & Analysis Worker Safety and Health Program: PUB-3851 Monthly Accident Statistics Latest Accident Statistics Accident...

  5. PROBABILISTIC SAFETY ASSESSMENT OF OPERATIONAL ACCIDENTS AT THE WASTE ISOLATION PILOT PLANT

    SciTech Connect (OSTI)

    Rucker, D.F.

    2000-09-01

    This report presents a probabilistic safety assessment of radioactive doses as consequences from accident scenarios to complement the deterministic assessment presented in the Waste Isolation Pilot Plant (WIPP) Safety Analysis Report (SAR). The International Council of Radiation Protection (ICRP) recommends both assessments be conducted to ensure that ''an adequate level of safety has been achieved and that no major contributors to risk are overlooked'' (ICRP 1993). To that end, the probabilistic assessment for the WIPP accident scenarios addresses the wide range of assumptions, e.g. the range of values representing the radioactive source of an accident, that could possibly have been overlooked by the SAR. Routine releases of radionuclides from the WIPP repository to the environment during the waste emplacement operations are expected to be essentially zero. In contrast, potential accidental releases from postulated accident scenarios during waste handling and emplacement could be substantial, which necessitates the need for radiological air monitoring and confinement barriers (DOE 1999). The WIPP Safety Analysis Report (SAR) calculated doses from accidental releases to the on-site (at 100 m from the source) and off-site (at the Exclusive Use Boundary and Site Boundary) public by a deterministic approach. This approach, as demonstrated in the SAR, uses single-point values of key parameters to assess the 50-year, whole-body committed effective dose equivalent (CEDE). The basic assumptions used in the SAR to formulate the CEDE are retained for this report's probabilistic assessment. However, for the probabilistic assessment, single-point parameter values were replaced with probability density functions (PDF) and were sampled over an expected range. Monte Carlo simulations were run, in which 10,000 iterations were performed by randomly selecting one value for each parameter and calculating the dose. Statistical information was then derived from the 10,000 iteration batch, which included 5%, 50%, and 95% dose likelihood, and the sensitivity of each assumption to the calculated doses. As one would intuitively expect, the doses from the probabilistic assessment for most scenarios were found to be much less than the deterministic assessment. The lower dose of the probabilistic assessment can be attributed to a ''smearing'' of values from the high and low end of the PDF spectrum of the various input parameters. The analysis also found a potential weakness in the deterministic analysis used in the SAR, a detail on drum loading was not taken into consideration. Waste emplacement operations thus far have handled drums from each shipment as a single unit, i.e. drums from each shipment are kept together. Shipments typically come from a single waste stream, and therefore the curie loading of each drum can be considered nearly identical to that of its neighbor. Calculations show that if there are large numbers of drums used in the accident scenario assessment, e.g. 28 drums in the waste hoist failure scenario (CH5), then the probabilistic dose assessment calculations will diverge from the deterministically determined doses. As it is currently calculated, the deterministic dose assessment assumes one drum loaded to the maximum allowable (80 PE-Ci), and the remaining are 10% of the maximum. The effective average of drum curie content is therefore less in the deterministic assessment than the probabilistic assessment for a large number of drums. EEG recommends that the WIPP SAR calculations be revisited and updated to include a probabilistic safety assessment.

  6. Impact of rail pressure and biodiesel fueling on the particulate morphology and soot nanostructures from a common-rail turbocharged direct injection diesel engine

    SciTech Connect (OSTI)

    Ye, Peng; Vander Wal, Randy; Boehman, Andre L.; Toops, Todd J.; Daw, C. Stuart; Sun, Chenxi; Lapuerta, Magin; Agudelo, John

    2014-12-26

    The effect of rail pressure and biodiesel fueling on the morphology of exhaust particulate agglomerates and the nanostructure of primary particles (soot) was investigated with a common-rail turbocharged direct injection diesel engine. The engine was operated at steady state on a dynamometer running at moderate speed with both low (30%) and medium–high (60%) fixed loads, and exhaust particulate was sampled for analysis. Ultra-low sulfur diesel and its 20% v/v blends with soybean methyl ester biodiesel were used. Fuel injection occurred in a single event around top dead center at three different injection pressures. Exhaust particulate samples were characterized with TEM imaging, scanning mobility particle sizing, thermogravimetric analysis, Raman spectroscopy, and XRD analysis. Particulate morphology and oxidative reactivity were found to vary significantly with rail pressure and with biodiesel blend level. Higher biodiesel content led to increases in the primary particle size and oxidative reactivity but did not affect nanoscale disorder in the as-received samples. For particulates generated with higher injection pressures, the initial oxidative reactivity increased, but there was no detectable correlation with primary particle size or nanoscale disorder.

  7. Impact of rail pressure and biodiesel fueling on the particulate morphology and soot nanostructures from a common-rail turbocharged direct injection diesel engine

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

    Ye, Peng; Vander Wal, Randy; Boehman, Andre L.; Toops, Todd J.; Daw, C. Stuart; Sun, Chenxi; Lapuerta, Magin; Agudelo, John

    2014-12-26

    The effect of rail pressure and biodiesel fueling on the morphology of exhaust particulate agglomerates and the nanostructure of primary particles (soot) was investigated with a common-rail turbocharged direct injection diesel engine. The engine was operated at steady state on a dynamometer running at moderate speed with both low (30%) and medium–high (60%) fixed loads, and exhaust particulate was sampled for analysis. Ultra-low sulfur diesel and its 20% v/v blends with soybean methyl ester biodiesel were used. Fuel injection occurred in a single event around top dead center at three different injection pressures. Exhaust particulate samples were characterized with TEMmore » imaging, scanning mobility particle sizing, thermogravimetric analysis, Raman spectroscopy, and XRD analysis. Particulate morphology and oxidative reactivity were found to vary significantly with rail pressure and with biodiesel blend level. Higher biodiesel content led to increases in the primary particle size and oxidative reactivity but did not affect nanoscale disorder in the as-received samples. For particulates generated with higher injection pressures, the initial oxidative reactivity increased, but there was no detectable correlation with primary particle size or nanoscale disorder.« less

  8. Impact of rail pressure and biodiesel fueling on the particulate morphology and soot nanostructures from a common-rail turbocharged direct injection diesel engine

    SciTech Connect (OSTI)

    Ye, Peng; Vander Wal, Randy; Boehman, Andre L.; Toops, Todd J.; Daw, C. Stuart; Sun, Chenxi; Lapuerta, Magin; Agudelo, John

    2014-12-26

    The effect of rail pressure and biodiesel fueling on the morphology of exhaust particulate agglomerates and the nanostructure of primary particles (soot) was investigated with a common-rail turbocharged direct injection diesel engine. The engine was operated at steady state on a dynamometer running at moderate speed with both low (30%) and mediumhigh (60%) fixed loads, and exhaust particulate was sampled for analysis. Ultra-low sulfur diesel and its 20% v/v blends with soybean methyl ester biodiesel were used. Fuel injection occurred in a single event around top dead center at three different injection pressures. Exhaust particulate samples were characterized with TEM imaging, scanning mobility particle sizing, thermogravimetric analysis, Raman spectroscopy, and XRD analysis. Particulate morphology and oxidative reactivity were found to vary significantly with rail pressure and with biodiesel blend level. Higher biodiesel content led to increases in the primary particle size and oxidative reactivity but did not affect nanoscale disorder in the as-received samples. For particulates generated with higher injection pressures, the initial oxidative reactivity increased, but there was no detectable correlation with primary particle size or nanoscale disorder.

  9. ORISE: REAC/TS Radiation Accident Registries

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

    Accident Registries The Radiation Emergency Assistance Center/Training Site (REAC/TS) at the Oak Ridge Institute for Science and Education (ORISE) maintains a number of radiation accident registries that provide medical professionals with up-to-date radiation accident information. Information for these accident registries is gathered from many sources, including the World Health Organization, International Atomic Energy Agency, U.S. Nuclear Regulatory Commission, state radiological health

  10. Net Movements of Crude Oil and Petroleum Products by Pipeline, Tanker, Barge, and Rail Between PAD Districts, January 2014

    U.S. Energy Information Administration (EIA) Indexed Site

    January 2014 (Thousand Barrels) Commodity PAD District 1 PAD District 2 PAD District 3 Receipts Shipments Net Receipts Receipts Shipments Net Receipts Receipts Shipments Net Receipts Crude Oil 1 ................................................................ 11,209 1,213 9,996 35,554 35,363 190 23,680 28,598 -4,918 Petroleum Products 2 .............................................. 106,990 8,669 107,347 29,831 18,055 -6,599 16,594 124,991 -103,885 Pentanes Plus

  11. NR-SRS TRU Waste Shipments Milestone June 4 2013.docx

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

    June 4, 2013 Bill Taylor, DOE-SR, (803) 952-8564 bill.taylor@srs.gov DT Townsend, SRNS, (803) 952-7566 Dt-lawrence.townsend@srs.gov Savannah River Site Exceeds Waste Shipment Goals AIKEN, S.C. - During the month of April, the Savannah River Site met two new milestone records towards analyzing, preparing, packaging and shipping radioactive transuranic (TRU) waste bound for a disposal site in New Mexico. The Savannah River Nuclear Solutions Solid Waste organization completed thirty-two TRU waste

  12. Packaging and Transportation for Offsite Shipment of Materials of National Security Interests

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

    2015-09-25

    The Order establishes requirements and responsibilities for ensuring the safety of packaging and transportation for offsite shipments of Materials of National Security Interest. DOE Order 461.1C received a significant number of major and suggested comments the first time it was reviewed in RevCom. As a result of the number of comments received, the OPI have a second RevCom review. This revision of DOE O 461.1C incorporates changes which resulted from the comment resolution process of the initial draft.

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

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

    2016-01-05

    The Order establishes requirements and responsibilities for ensuring the safety of packaging and transportation for offsite shipments of Materials of National Security Interest. DOE Order 461.1C received a significant number of major and suggested comments the first time it was reviewed in RevCom. As a result of the number of comments received, the OPI have a second RevCom review. This revision of DOE O 461.1C incorporates changes which resulted from the comment resolution process of the initial draft.

  14. Under U.S.-Russia Partnership, Final Shipment of Fuel Converted From 20,000

    National Nuclear Security Administration (NNSA)

    Russian Nuclear Warheads Arrives in United States and Will Be Used for U.S. Electricity | National Nuclear Security Administration Home / Library / Press Releases Under U.S.-Russia Partnership, Final Shipment of Fuel Converted From 20,000 Russian Nuclear Warheads Arrives in United States and Will Be Used for U.S. Electricity December 11, 2013 WASHINGTON, D.C. - The United States and Russia are today commemorating the completion of the 1993 U.S.-Russia HEU Purchase Agreement, commonly known

  15. Technical Review Report for the Justification for Shipment of Sodium-Bonded Carbide Fuel Pins in the T-3 Cask

    SciTech Connect (OSTI)

    West, M; DiSabatino, A

    2008-01-04

    This report documents the review of the Fluor Submittal (hereafter, the Submittal), prepared by Savannah River Packaging Technology (SRPT) of Savannah River National Laboratory (SRNL), at the request of the Department of Energy's (DOE) Richland Operations Office, for the shipment of unirradiated and irradiated sodium-bonded carbide fuel pins. The sodium-bonded carbide fuel pins are currently stored at the Fast Flux Test Facility (FFTF) awaiting shipment to Idaho National Laboratory (INL). Normally, modified contents are included into the next revision of the SARP. However, the contents, identified to be shipped from FFTF to Idaho National Laboratory, are a one-way shipment of 18 irradiated fuel pins and 7 unirradiated fuel pins, where the irradiated and unirradiated fuel pins are shipped separately, and can be authorized with a letter amendment to the existing Certificate of Compliance (CoC).

  16. Development of Green Box sensor module technologies for rail applications

    SciTech Connect (OSTI)

    Rey, D.; Breeding, R.; Hogan, J.; Mitchell, J.; McKeen, R.G.; Brogan, J.

    1996-04-01

    Results of a joint Sandia National Laboratories, University of New Mexico, and New Mexico Engineering Research Institute project to investigate an architecture implementing real-time monitoring and tracking technologies in the railroad industry is presented. The work, supported by the New Mexico State Transportation Authority, examines a family of smart sensor products that can be tailored to the specific needs of the user. The concept uses a strap-on sensor package, designed as a value-added component, integrated into existing industry systems and standards. Advances in sensor microelectronics and digital signal processing permit us to produce a class of smart sensors that interpret raw data and transmit inferred information. As applied to freight trains, the sensors` primary purpose is to minimize operating costs by decreasing losses due to theft, and by reducing the number, severity, and consequence of hazardous materials incidents. The system would be capable of numerous activities including: monitoring cargo integrity, controlling system braking and vehicle acceleration, recognizing component failure conditions, and logging sensor data. A cost-benefit analysis examines the loss of revenue resulting from theft, hazardous materials incidents, and accidents. Customer survey data are combined with the cost benefit analysis and used to guide the product requirements definition for a series of specific applications. A common electrical architecture is developed to support the product line and permit rapid product realization. Results of a concept validation, which used commercial hardware and was conducted on a revenue-generating train, are also reported.

  17. Accident analysis and DOE criteria

    SciTech Connect (OSTI)

    Graf, J.M.; Elder, J.C.

    1982-01-01

    In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied.

  18. DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M. – The Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste on Sept. 24, 2011. This marked an important milestone in the DOE Office of Environmental Management mission to clean up the country’s Cold War legacy.

  19. Parametric study of radiation dose rates from rail and truck spent fuel transport casks

    SciTech Connect (OSTI)

    Parks, C.V.; Hermann, O.W.; Knight, J.R.

    1985-08-01

    Neutron and gamma dose rates from typical rail and truck spent fuel transport casks are reported for a variety of spent PWR fuel sources and cask conditions. The IF 300 rail cask and NLI 1/2 truck cask were selected for use as appropriate cask models. All calculations (cross section preparation, generation of spent fuel source terms, radiation transport calculations, and dose evaluation) were performed using various modules of the SCALE computational system. Conditions or parameters for which there were variations between cases include: detector distance from cask, spent fuel cooling time, the setting of fuel or neutron shielding cavities to either wet or dry, the cobalt content of assembly materials, normal fuel assemblies and consolidated cannisters, the geometry mesh interval size, and the order of the angular quadrature set. 13 refs., 6 figs., 9 tabs.

  20. Level: National and Regional Data; Row: NAICS Codes; Column: Energy Sources and Shipments;

    U.S. Energy Information Administration (EIA) Indexed Site

    Coke and Shipments Net Residual Distillate Natural LPG and Coal Breeze of Energy Sources NAICS Total(b) Electricity(c) Fuel Oil Fuel Oil(d) Gas(e) NGL(f) (million (million Other(g) Produced Onsite(h) Code(a) Subsector and Industry (trillion Btu) (million kWh) (million bbl) (million bbl) (billion cu ft) (million bbl) short tons) short tons) (trillion Btu) (trillion Btu) Total United States RSE Column Factors: 0.9 1 1.2 1.8 1 1.6 0.8 0.9 1.2 0.4 311 Food 1,123 67,521 2 3 567 1 8 * 89 0 311221 Wet

  1. COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS

    SciTech Connect (OSTI)

    S.O. Bader

    1999-10-18

    The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be conservatively applied to confined CSNF assemblies.

  2. Accident Response Group | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Accident Response Group NNSA's Accident Response Group (ARG) provides technical guidance and responds to U.S. nuclear weapons accidents. ARG_Logo The team assists in assessing weapons damage and risk, and in developing and implementing procedures for safe weapon recovery, packaging, transportation, and disposal of damaged weapons. The ARG headquarters is located in Albuquerque, New Mexico and is supported by Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Sandia National

  3. HTGR severe accident sequence analysis

    SciTech Connect (OSTI)

    Harrington, R.M.; Ball, S.J.; Kornegay, F.C.

    1982-01-01

    Thermal-hydraulic, fission product transport, and atmospheric dispersion calculations are presented for hypothetical severe accident release paths at the Fort St. Vrain (FSV) high temperature gas cooled reactor (HTGR). Off-site radiation exposures are calculated for assumed release of 100% of the 24 hour post-shutdown core xenon and krypton inventory and 5.5% of the iodine inventory. The results show conditions under which dose avoidance measures would be desirable and demonstrate the importance of specific release characteristics such as effective release height. 7 tables.

  4. Calculation notes that support accident scenario and consequence development for the subsurface leak remaining subsurface accident

    SciTech Connect (OSTI)

    Ryan, G.W., Westinghouse Hanford

    1996-07-12

    This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Subsurface Leak Remaining Subsurface. The calculations needed to quantify the risk associated with this accident scenario are included within.

  5. Calculation notes that support accident scenario and consequence development for the subsurface leak remaining subsurface accident

    SciTech Connect (OSTI)

    Ryan, G.W., Westinghouse Hanford

    1996-09-19

    This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Subsurface Leak Remaining Subsurface. The calculations needed to quantify the risk associated with this accident scenario are included within.

  6. Life Cycle Assessment Comparing the Use of Jatropha Biodiesel in the Indian Road and Rail Sectors

    SciTech Connect (OSTI)

    Whitaker, M.; Heath, G.

    2010-05-01

    This life cycle assessment of Jatropha biodiesel production and use evaluates the net greenhouse gas (GHG) emission (not considering land-use change), net energy value (NEV), and net petroleum consumption impacts of substituting Jatropha biodiesel for conventional petroleum diesel in India. Several blends of biodiesel with petroleum diesel are evaluated for the rail freight, rail passenger, road freight, and road-passenger transport sectors that currently rely heavily on petroleum diesel. For the base case, Jatropha cultivation, processing, and use conditions that were analyzed, the use of B20 results in a net reduction in GHG emissions and petroleum consumption of 14% and 17%, respectively, and a NEV increase of 58% compared with the use of 100% petroleum diesel. While the road-passenger transport sector provides the greatest sustainability benefits per 1000 gross tonne kilometers, the road freight sector eventually provides the greatest absolute benefits owing to substantially higher projected utilization by year 2020. Nevertheless, introduction of biodiesel to the rail sector might present the fewest logistic and capital expenditure challenges in the near term. Sensitivity analyses confirmed that the sustainability benefits are maintained under multiple plausible cultivation, processing, and distribution scenarios. However, the sustainability of any individual Jatropha plantation will depend on site-specific conditions.

  7. Recommendations for Analyzing Accidents Under NEPA

    Broader source: Energy.gov [DOE]

    This DOE guidance clarifies and supplements "Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements." It focuses on principles of accident analyses under NEPA.

  8. Accident Investigation of the February 7, 2013, Scissor Lift Accident in

    Energy Savers [EERE]

    the West Hackberry Brine Tank-14 Resulting in Injury, Strategic Petroleum Reserve West Hackberry, LA | Department of Energy February 7, 2013, Scissor Lift Accident in the West Hackberry Brine Tank-14 Resulting in Injury, Strategic Petroleum Reserve West Hackberry, LA Accident Investigation of the February 7, 2013, Scissor Lift Accident in the West Hackberry Brine Tank-14 Resulting in Injury, Strategic Petroleum Reserve West Hackberry, LA February 7, 2013 On February 15, 2013, an Accident

  9. High-speed rail transportation. Hearing before the Subcommittee on Transportation and Hazardous Materials of the Committee on Energy and Commerce, US House of Representatives, One Hundred Second Congress, First Session, October 16, 1991

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    H.R. 1087 would authorize a high speed rail transportation development and commercialization program, establish a national high speed rail transportation policy, and promote development and commercialization of high speed rail transportation by providing Federal guarantees of certain investments in high speed rail transportation facilities. Testimony was heard from representatives of MAGLEV USA, Federal Railroad Administration, National Railroad Passenger Corporation (Amtrak), the Office of Technology Assessment, MAGLEV, Inc., National Maglev Initiative, High Speed Rail Association, and the Texas High-Speed Rail Association. Additional information was supplied by the Coalition of Northeastern Governors, Republic Locomotive, Washington State High Speed Ground Transportation, and the Texas High Speed Authority.

  10. Light-water reactor accident classification

    SciTech Connect (OSTI)

    Washburn, B.W.

    1980-02-01

    The evolution of existing classifications and definitions of light-water reactor accidents is considered. Licensing practice and licensing trends are examined with respect to terms of art such as Class 8 and Class 9 accidents. Interim definitions, consistent with current licensing practice and the regulations, are proposed for these terms of art.

  11. Commercial SNF Accident Release Fractions

    SciTech Connect (OSTI)

    J. Schulz

    2004-11-05

    The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M&O 1999). In contrast to bare unconfined fuel assemblies, the container that confines the fuel assemblies could provide an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. This analysis, however, does not take credit for the additional barrier and establishes only the total release fractions for bare unconfined intact commercial SNF assemblies, which may be conservatively applied to confined intact commercial I SNF assemblies.

  12. A Perspective on Long-Term Recovery Following the Fukushima Nuclear Accident - 12075

    SciTech Connect (OSTI)

    Chen, S.Y.

    2012-07-01

    The tragic events at the Fukushima Daiichi Nuclear Power Station began occurring on March 11, 2011, following Japan's unprecedented earthquake and tsunami. The subsequent loss of external power and on-site cooling capacity severely compromised the plant's safety systems, and subsequently, led to core melt in the affected reactors and damage to spent nuclear fuel in the storage pools. Together with hydrogen explosions, this resulted in a substantial release of radioactive material to the environment (mostly Iodine-131 and Cesium- 137), prompting an extensive evacuation effort. The latest release estimate places the event at the highest severity level (Level 7) on the International Nuclear Event Scale, the same as the Chernobyl accident of 1986. As the utility owner endeavored to stabilize the damaged facility, environmental contamination continued to propagate and affect every aspect of daily life in the affected region of Japan. Elevated levels of radioactivity (mostly dominated by Cs-137 with the passage of time) were found in soil, drinking water, vegetation, produce, seafood, and other foodstuffs. An estimated 80,000 to 90,000 people were evacuated; more evacuations are being contemplated months after the accident, and a vast amount of land has become contaminated. Early actions were taken to ban the shipment and sale of contaminated food and drinking water, followed by later actions to ban the shipment and sale of contaminated beef, mushrooms, and seafood. As the event continues to evolve toward stabilization, the long-term recovery effort needs to commence - a process that doubtless will involve rather complex decision-making interactions between various stakeholders. Key issues that may be encountered and considered in such a process include (1) socio-political factors, (2) local economic considerations, (3) land use options, (4) remediation approaches, (5) decontamination methods, (6) radioactive waste management, (7) cleanup levels and options, and (8) government policies, among others. This paper offers a perspective on this likely long and arduous journey toward establishing a 'new normal' that will ultimately take shape. Toward this end, it is important to evaluate the 'optimization' process advocated by the international community in achieving long-term recovery from this particularly fateful event in Fukushima. In the process, experience and lessons learned from past events will be fully evaluated and considered. (author)

  13. SAF-230DE- Web Based Course: Accident Investigation Overview

    Office of Energy Efficiency and Renewable Energy (EERE)

    This course that provides an overview of the fundamentals of accident investigation. The course is intended to meet the every five year refresher training requirement for DOE Federal Accident Investigators under DOE O 225.1B Accident Investigations.

  14. The Fukushima Daiichi Accident Study Information Portal

    SciTech Connect (OSTI)

    Shawn St. Germain; Curtis Smith; David Schwieder; Cherie Phelan

    2012-11-01

    This paper presents a description of The Fukushima Daiichi Accident Study Information Portal. The Information Portal was created by the Idaho National Laboratory as part of joint NRC and DOE project to assess the severe accident modeling capability of the MELCOR analysis code. The Fukushima Daiichi Accident Study Information Portal was created to collect, store, retrieve and validate information and data for use in reconstructing the Fukushima Daiichi accident. In addition to supporting the MELCOR simulations, the Portal will be the main DOE repository for all data, studies and reports related to the accident at the Fukushima Daiichi nuclear power station. The data is stored in a secured (password protected and encrypted) repository that is searchable and accessible to researchers at diverse locations.

  15. Table 10.9 Photovoltaic Cell and Module Shipments by Sector and End Use, 1989-2010 (Peak Kilowatts )

    U.S. Energy Information Administration (EIA) Indexed Site

    Photovoltaic Cell and Module Shipments by Sector and End Use, 1989-2010 (Peak Kilowatts 1 ) Year By Sector By End Use Total Residential Commercial 3 Industrial 4 Electric Power 5 Other 6 Grid-Connected 2 Off-Grid 2 Centralized 7 Distributed 8 Domestic 9 Non-Domestic 10 Total Shipments of Photovoltaic Cells and Modules 11<//td> 1989 1,439 6,057 [R] 3,993 785 551 [12] 1,251 [12] 2,620 8,954 12,825 1990 1,701 8,062 [R] 2,817 826 432 [12] 469 [12] 3,097 10,271 13,837 1991 3,624 5,715 [R] 3,947

  16. Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

    SciTech Connect (OSTI)

    D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

    2006-07-01

    In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

  17. Annual Transportation Report for Radioactive Waste Shipments to and from the Nevada Test Site, Fiscal Year 2009

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2010-02-01

    In February 1997, the U.S. Department of Energy (DOE), Nevada Operations Office (now known as the Nevada Site Office) issued the Mitigation Action Plan which addressed potential impacts described in the Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada (DOE/EIS 0243). The DOE, Nevada Operations Office committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada Test Site (NTS) Radioactive Waste Management Site (RWMS) at Area 5 and Area 3. Since 2006, the Area 3 RWMS has been in cold stand-by. This document satisfies requirements regarding low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to and from the NTS during FY 2009. In addition, this document provides shipment, volume, and route information on transuranic (TRU) waste shipped from the NTS to the Idaho National Laboratory, near Idaho Falls, Idaho.

  18. Type B Accident Investigation of the Arc Flash at Brookhaven...

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

    February 10, 2006 An accident at the Idaho National Laboratory (INL) was investigated in ... In conducting its investigation, the Accident Investigation Board (the Board) used various ...

  19. Accident Investigation of the October 1, 2013, Tice Electric...

    Energy Savers [EERE]

    Accident Investigation of the October 1, 2013, Tice Electric Company Employee Fatality ... (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to ...

  20. Accident Investigation of the September 20, 2012 Fatal Fall from...

    Office of Environmental Management (EM)

    Power Marketing Administration Accident Investigation of the September 20, 2012 ... (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to ...

  1. Accident Investigation of the February 7, 2013, Scissor Lift...

    Energy Savers [EERE]

    February 7, 2013, Scissor Lift Accident in the West Hackberry Brine Tank-14 Resulting in Injury, Strategic Petroleum Reserve West Hackberry, LA Accident Investigation of the ...

  2. Type B Accident Investigation Board Report Subcontractor Radioactive...

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

    Upon arrival, an incoming radiological survey was performed. PDF icon Type B Accident ... Preliminary Notice of Violation, Bechtel Jacobs Company, LLC - EA-2005-04 Type B Accident ...

  3. Type B Accident Investigation Board Report of the September 29...

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

    Type B Accident Investigation Board Report of the September 29, 2010, Radiological ... PDF icon Type B Accident Investigation Board Report of the September 29, 2010, ...

  4. Accident Investigation of the February 5, 2014, Underground Salt...

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

    Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM March 26, 2014 Accident Investigation of the ...

  5. Accident Investigation of the July 30, 2013, Electrical Fatality...

    Energy Savers [EERE]

    Accident Investigation of the July 30, 2013, Electrical Fatality on the Bandon-Rogue No. 1 ... (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to ...

  6. Los Alamos National Laboratory Accident Investigation Board Corrective...

    Office of Environmental Management (EM)

    Accident Investigation Board Corrective Action Plan Update Los Alamos National Laboratory Accident Investigation Board Corrective Action Plan Update Topic: Status of the Corrective ...

  7. Type B Accident Investigation At Washington Closure Hanford,...

    Office of Environmental Management (EM)

    Type B Accident Investigation At Washington Closure Hanford, LLC, Employee Fall Injury on ... PDF icon Type B Accident Investigation At Washington Closure Hanford, LLC, Employee Fall ...

  8. Type B Accident Investigation of the July 14, 2005, Americium...

    Energy Savers [EERE]

    14, 2005, Americium Contamination Accident at the Sigma Facility, Los Alamos National Laboratory Type B Accident Investigation of the July 14, 2005, Americium Contamination ...

  9. Type B Accident Investigation Board Report, May 8, 2004, Exothermic...

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

    metal reaction (exothermic reaction) accident occurred during heating of surplus ... PDF icon Type B Accident Investigation Board Report, May 8, 2004, Exothermic Metal Reactor ...

  10. Type B Accident Investigation Board Report of the Brookhaven...

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

    Type B Accident Investigation Board Report of the Brookhaven National Laboratory Employee ... Building 1005H. PDF icon Type B Accident Investigation Board Report of the ...

  11. Type B Accident Investigation on the June 27, 2002, Exothermic...

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

    PDF icon Type B Accident Investigation on the June 27, 2002, Exothermic Metal Reaction ... Preliminary Notice of Violation, BNFL, Inc - EA-2003-01 Type B Accident Investigation ...

  12. Accident Investigation of the June 1, 2013, Stairway Fall Resulting...

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

    On June 28, 2013, an Accident Investigation Board was appointed to investigate an accident at the Department of Energy Germantown Headquarters facility, on June 1, 2013 that ...

  13. Accident Investigation Report Phase II | Department of Energy

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

    On March 4, 2014, an Accident Investigation Board (the Board) was appointed by Matthew ... appointed an Accident Investigation Board to complete the investigation (Phase 2). ...

  14. ORISE: The Medical Basis for Radiation-Accident Preparedness...

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

    The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident ...

  15. Accident Investigation of the December 11, 2013, Integrated Device...

    Energy Savers [EERE]

    Accident Investigation of the December 11, 2013, Integrated Device Fireset and Detonator ... 9920, Albuquerque, NM March 16, 2014 Accident Investigation of the December 11, 2013, ...

  16. Type B Accident Investigation Board Report of the Bechtel Jacobs...

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

    Type B Accident Investigation Board Report of the Bechtel Jacobs Company, LLC Employee ... PDF icon Type B Accident Investigation Board Report of the Bechtel Jacobs Company, LLC ...

  17. Volume II - Accident and Operational Safety Analysis Handbook

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

    208-2012 July 2012 DOE HANDBOOK Accident and Operational Safety Analysis Volume II: ... This Department of Energy (DOE) Accident and Operational Safety Analysis Handbook ...

  18. Accident analysis of heavy water cooled thorium breeder reactor...

    Office of Scientific and Technical Information (OSTI)

    Accident analysis of heavy water cooled thorium breeder reactor Citation Details In-Document Search Title: Accident analysis of heavy water cooled thorium breeder reactor ...

  19. Accident Tolerant Fuels for LWRs: A Perspective (Journal Article...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Accident Tolerant Fuels for LWRs: A Perspective Citation Details In-Document Search Title: Accident Tolerant Fuels for LWRs: A Perspective Authors: Zinkle, Steven ...

  20. Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems...

    Office of Scientific and Technical Information (OSTI)

    Title: Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis The severe accident at Fukushima Daiichi nuclear plants illustrates the need for continuous ...

  1. Draft Supplement Analysis: Two Proposed Shipments of Commercial Spent Nuclear Fuel to Idaho National Laboratory for Research and Development Purposes

    Broader source: Energy.gov [DOE]

    DOE is proposing to transport, in two separate truck shipments, small quantities of commercial power spent nuclear fuel (SNF) to the Idaho National Laboratory (INL) Site for research purposes consistent with the mission of the DOE Office of Nuclear Energy. DOE is preparing a Supplement Analysis to determine whether an existing environmental impact statement should be supplemented, a new environmental impact statement should be prepared, or that no further NEPA documentation is required for this proposed action.

  2. Low-Level & Mixed Low-Level Radioactive Waste Shipments to NNSS, FY2010 2nd QTR

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

    NM NY NY NV OH TN TN TN, WA, CA TN TN TN TX Total Shipments by Route Lawrence Livermore National Laboratory Batelle Energy Alliance Idaho National Laboratory Advanced Mixed Waste Treatment Project Energx Argonne National Laboratory Argonne National Laboratory Paducah Gaseous Diffusion Plant Aberdeen Proving Ground Sandia National Laboratories Brookhaven National Laboratory West Valley Environmental Services National Security Technologies, Inc. Portsmouth Gaseous Diffusion Plant Duratek/Energy

  3. A National Tracking Center for Monitoring Shipments of HEU, MOX, and Spent Nuclear Fuel: How do we implement?

    SciTech Connect (OSTI)

    Mark Schanfein

    2009-07-01

    Nuclear material safeguards specialists and instrument developers at US Department of Energy (USDOE) National Laboratories in the United States, sponsored by the National Nuclear Security Administration (NNSA) Office of NA-24, have been developing devices to monitor shipments of UF6 cylinders and other radioactive materials , . Tracking devices are being developed that are capable of monitoring shipments of valuable radioactive materials in real time, using the Global Positioning System (GPS). We envision that such devices will be extremely useful, if not essential, for monitoring the shipment of these important cargoes of nuclear material, including highly-enriched uranium (HEU), mixed plutonium/uranium oxide (MOX), spent nuclear fuel, and, potentially, other large radioactive sources. To ensure nuclear material security and safeguards, it is extremely important to track these materials because they contain so-called “direct-use material” which is material that if diverted and processed could potentially be used to develop clandestine nuclear weapons . Large sources could be used for a dirty bomb also known as a radioactive dispersal device (RDD). For that matter, any interdiction by an adversary regardless of intent demands a rapid response. To make the fullest use of such tracking devices, we propose a National Tracking Center. This paper describes what the attributes of such a center would be and how it could ultimately be the prototype for an International Tracking Center, possibly to be based in Vienna, at the International Atomic Energy Agency (IAEA).

  4. Colorado STEP Training

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

    professionals what to do should they arrive at an accident involving a WIPP shipment. ... the unlikely event of a transportation accident involving a shipment headed for WIPP. ...

  5. Structural assessment of accident loads

    SciTech Connect (OSTI)

    Wagenblast, G.R., Westinghouse Hanford

    1996-05-28

    Structural assessments were made for specific accident loads for specific catch, receiver, and storage tanks. The evaluation herein represents level-of-effort order-of-magnitude estimates of limiting loads that would lead to collapse or rupture of the tank and unmitigated loss of confinement for the waste. Structural capacities were established using failure criteria. Compliance with codes such as ACI, ASCE, ASME, RCRA, UBC, WAC, and DOE Orders was `NOT` maintained. Normal code practice is to prevent failure with margins consistent with expected variations in loads and strengths and confidence in analysis techniques. The evaluation herein represent estimates of code limits without code load factors or code strength reduction factors, and loading beyond such a limit is considered as an onset of some failure mode. The exact nature of the failure mode and its relation to a safe condition is a judgment of the analyst. Consequently, these `RESULTS SHALL NOT BE USED TO ESTABLISH OPERATING OR SAFETY LOAD LIMITS FOR THESE TANKS`.

  6. Release fractions for Rocky Flats specific accidents

    SciTech Connect (OSTI)

    Weiss, R.C.

    1992-09-01

    As Rocky Flats and other DOE facilities begin the transition process towards decommissioning, the nature of the scenarios to be studied in safety analysis will change. Whereas the previous emphasis in safety accidents related to production, now the emphasis is shifting to accidents related tc decommissioning and waste management. Accident scenarios of concern at Rocky Flats now include situations of a different nature and different scale than are represented by most of the existing experimental accident data. This presentation will discuss approaches@to use for applying the existing body of release fraction data to this new emphasis. Mention will also be made of ongoing efforts to produce new data and improve the understanding of physical mechanisms involved.

  7. Crediting Tritium Deposition in Accident Analysis

    SciTech Connect (OSTI)

    Murphy, C.E. Jr.

    2001-06-20

    This paper describes the major aspects of tritium dispersion phenomenology, summarizes deposition attributes of the computer models used in the DOE Complex for tritium dispersion, and recommends an approach to account for deposition in accident analysis.

  8. Decontamination Dressdown at a Transportation Accident Involving

    Office of Environmental Management (EM)

    Radioactive Material | Department of Energy Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Decontamination Dressdown at a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to

  9. Radioactive waste shipments to Hanford Retrievable Storage from the General Electric Vallecitos Nuclear Center, Pleasanton, California

    SciTech Connect (OSTI)

    Vejvoda, E.J.; Pottmeyer, J.A.; DeLorenzo, D.S.; Weyns-Rollosson, M.I.; Duncan, D.R.

    1993-10-01

    During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Approximately 3.8% of the TRU waste to be retrieved for shipment to WIPP was generated at the General Electric (GE) Vallecitos Nuclear Center (VNC) in Pleasanton, California and shipped to the Hanford Site for storage. The purpose of this report is to characterize these radioactive solid wastes using process knowledge, existing records, and oral history interviews. The waste was generated almost exclusively from the activities, of the Plutonium Fuels Development Laboratory and the Plutonium Analytical Laboratory. Section 2.0 provides further details of the VNC physical plant, facility operations, facility history, and current status. The solid radioactive wastes were associated with two US Atomic Energy Commission/US Department of Energy reactor programs -- the Fast Ceramic Reactor (FCR) program, and the Fast Flux Test Reactor (FFTR) program. These programs involved the fabrication and testing of fuel assemblies that utilized plutonium in an oxide form. The types and estimated quantities of waste resulting from these programs are discussed in detail in Section 3.0. A detailed discussion of the packaging and handling procedures used for the VNC radioactive wastes shipped to the Hanford Site is provided in Section 4.0. Section 5.0 provides an in-depth look at this waste including the following: weight and volume of the waste, container types and numbers, physical description of the waste, radiological components, hazardous constituents, and current storage/disposal locations.

  10. DOE Accident Prevention and Investigation Program | Department of Energy

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

    DOE Accident Prevention and Investigation Program DOE Accident Prevention and Investigation Program The Department of Energy (DOE) Accident Prevention and Investigation Program serves as a key DOE corporate safety resource for promoting accident PREVENTION through exchange of lessons learned and information for improvement of our integrated safety management system. The techniques and tools utilized in the investigation of "accidents" can be valuable in looking at leading indicators

  11. Large Break LOCA Accident Management Strategies for Accidents With Large Containment Leaks

    SciTech Connect (OSTI)

    Sdouz, Gert

    2006-07-01

    The goal of this work is the investigation of the influence of different accident management strategies on the thermal-hydraulics in the containment during a Large Break Loss of Coolant Accident with a large containment leak from the beginning of the accident. The increasing relevance of terrorism suggests a closer look at this kind of severe accidents. Normally the course of severe accidents and their associated phenomena are investigated with the assumption of an intact containment from the beginning of the accident. This intact containment has the ability to retain a large part of the radioactive inventory. In these cases there is only a release via a very small leakage due to the un-tightness of the containment up to cavity bottom melt through. This paper represents the last part of a comprehensive study on the influence of accident management strategies on the source term of VVER-1000 reactors. Basically two different accident sequences were investigated: the 'Station Blackout'- sequence and the 'Large Break LOCA'. In a first step the source term calculations were performed assuming an intact containment from the beginning of the accident and no accident management action. In a further step the influence of different accident management strategies was studied. The last part of the project was a repetition of the calculations with the assumption of a damaged containment from the beginning of the accident. This paper concentrates on the last step in the case of a Large Break LOCA. To be able to compare the results with calculations performed years ago the calculations were performed using the Source Term Code Package (STCP), hydrogen explosions are not considered. In this study four different scenarios have been investigated. The main parameter was the switch on time of the spray systems. One of the results is the influence of different accident management strategies on the source term. In the comparison with the sequence with intact containment it was demonstrated that the accident management measures have quite lower consequences. In addition it was shown that in the case of a 'Large Break LOCA'-sequence the intact containment retains the nuclides up to a factor of 20 000. This is much more than in the case of a 'Station Blackout'-sequence. Within the frame of the study 17 source terms have been generated to evaluate in detail accident management strategies for VVER-1000 reactors. (authors)0.

  12. Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

    SciTech Connect (OSTI)

    Farmer, Mitchell T.; Bunt, R.; Corradini, M.; Ellison, Paul B.; Francis, M.; Gabor, John D.; Gauntt, R.; Henry, C.; Linthicum, R.; Luangdilok, W.; Lutz, R.; Paik, C.; Plys, M.; Rabiti, Cristian; Rempe, J.; Robb, K.; Wachowiak, R.

    2015-01-31

    The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy’s (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

  13. Second Draft - DOE O 461.1C, Packaging and Transportation for Offsite Shipment of Materials of National Security Interests

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

    The Order establishes requirements and responsibilities for ensuring the safety of packaging and transportation for offsite shipments of Materials of National Security Interest. DOE Order 461.1C received a significant number of major and suggested comments the first time it was reviewed in RevCom. As a result of the number of comments received, the OPI have a second RevCom review. This revision of DOE O 461.1C incorporates changes which resulted from the comment resolution process of the initial draft.

  14. Successful Completion of the Largest Shipment of Russian Research Reactor High-Enriched Uranium Spent Nuclear Fuel from Czech Republic to Russian Federation

    SciTech Connect (OSTI)

    Michael Tyacke; Dr. Igor Bolshinsky; Jeff Chamberlin

    2008-07-01

    On December 8, 2007, the largest shipment of high-enriched uranium spent nuclear fuel was successfully made from a Russian-designed nuclear research reactor in the Czech Republic to the Russian Federation. This accomplishment is the culmination of years of planning, negotiations, and hard work. The United States, Russian Federation, and the International Atomic Energy Agency have been working together on the Russian Research Reactor Fuel Return (RRRFR) Program in support of the Global Threat Reduction Initiative. In February 2003, RRRFR Program representatives met with the Nuclear Research Institute in Re, Czech Republic, and discussed the return of their high-enriched uranium spent nuclear fuel to the Russian Federation for reprocessing. Nearly 5 years later, the shipment was made. This paper discusses the planning, preparations, coordination, and cooperation required to make this important international shipment.

  15. Enhanced Accident Tolerant LWR Fuels: Metrics Development

    SciTech Connect (OSTI)

    Shannon Bragg-Sitton; Lori Braase; Rose Montgomery; Chris Stanek; Robert Montgomery; Lance Snead; Larry Ott; Mike Billone

    2013-09-01

    The Department of Energy (DOE) Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) is conducting research and development on enhanced Accident Tolerant Fuels (ATF) for light water reactors (LWRs). This mission emphasizes the development of novel fuel and cladding concepts to replace the current zirconium alloy-uranium dioxide (UO2) fuel system. The overall mission of the ATF research is to develop advanced fuels/cladding with improved performance, reliability and safety characteristics during normal operations and accident conditions, while minimizing waste generation. The initial effort will focus on implementation in operating reactors or reactors with design certifications. To initiate the development of quantitative metrics for ATR, a LWR Enhanced Accident Tolerant Fuels Metrics Development Workshop was held in October 2012 in Germantown, MD. This paper summarizes the outcome of that workshop and the current status of metrics development for LWR ATF.

  16. A Review of Criticality Accidents 2000 Revision

    SciTech Connect (OSTI)

    Thomas P. McLaughlin; Shean P. Monahan; Norman L. Pruvost; Vladimir V. Frolov; Boris G. Ryazanov; Victor I. Sviridov

    2000-05-01

    Criticality accidents and the characteristics of prompt power excursions are discussed. Sixty accidental power excursions are reviewed. Sufficient detail is provided to enable the reader to understand the physical situation, the chemistry and material flow, and when available the administrative setting leading up to the time of the accident. Information on the power history, energy release, consequences, and causes are also included when available. For those accidents that occurred in process plants, two new sections have been included in this revision. The first is an analysis and summary of the physical and neutronic features of the chain reacting systems. The second is a compilation of observations and lessons learned. Excursions associated with large power reactors are not included in this report.

  17. Type B Accident Investigation Board Report of the April 23, 1997...

    Office of Environmental Management (EM)

    April 23, 1997, Helicopter Accident at Raton Pass, Raton Pass, Colorado Type B Accident Investigation Board Report of the April 23, 1997, Helicopter Accident at Raton Pass, Raton ...

  18. Type B Accident Investigation on the August 5, 2003, Pu-238 Multiple...

    Energy Savers [EERE]

    Los Alamos National Laboratory Type B Accident Investigation on the August 5, 2003, ... The Accident Investigation Board concluded that the direct cause of the accident was the ...

  19. Accident progression event tree analysis for postulated severe accidents at N Reactor

    SciTech Connect (OSTI)

    Wyss, G.D.; Camp, A.L.; Miller, L.A.; Dingman, S.E.; Kunsman, D.M. ); Medford, G.T. )

    1990-06-01

    A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied.

  20. Fuel performance during severe accidents. [PWR

    SciTech Connect (OSTI)

    Buescher, B.J.; Gruen, G.E.; MacDonald, P.E.

    1982-01-01

    As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. This program is underway in the Power Burst Facility at the Idaho National Engineering Laboratory. In preparation for the first test, predictions have been performed using the TRAC-BD1 computer. This paper presents the calculated results showing a slow heatup to 2400 K over 5 hours, and the analysis includes accelerated oxidation of the zirconium cladding at temperatures above 1850 K.

  1. LESSONS LEARNED FROM A RECENT LASER ACCIDENT

    SciTech Connect (OSTI)

    Woods, Michael; /SLAC

    2011-01-26

    A graduate student received a laser eye injury from a femtosecond Ti:sapphire laser beam while adjusting a polarizing beam splitter optic. The direct causes for the accident included failure to follow safe alignment practices and failure to wear the required laser eyewear protection. Underlying root causes included inadequate on-the-job training and supervision, inadequate adherence to requirements, and inadequate appreciation for dimly visible beams outside the range of 400-700nm. This paper describes how the accident occurred, discusses causes and lessons learned, and describes corrective actions being taken.

  2. Status and use of the Rocky Flats Environmental Technology Site Pipe Overpack Container for TRU waste storage and shipments

    SciTech Connect (OSTI)

    Thorp, D.T.; Geinitz, R.R.; Rivera, M.A.

    1998-03-03

    The Pipe Overpack Container was designed to optimize shipments of high plutonium content transuranic waste from Rocky Flats Environmental Technology Site (RFETS) to Waste Isolation Pilot Plant (WIPP). The container was approved for use in the TRUPACT-II shipping container by the Nuclear Regulatory Commission in February 1997. The container optimizes shipments to WIPP by increasing the TRUPACT-II criticality limit from 325 fissile grams equivalent (FGE) to 2,800 FGE and provides additional shielding for handling wastes with high americium-241 (Am-241) content. The container was subsequently evaluated and approved for storage of highly dispersible TRU wastes and residues at RFETS. Thermal evaluation of the container shows that the container will mitigate the impact of a worst case thermal event from reactive or potentially pyrophoric materials. These materials contain hazards postulated by the Defense Nuclear Facilities Safety Board for interim storage. Packaging these reactive or potentially pyrophoric residues in the container without stabilizing the materials is under consideration at RFETS. The design, testing, and evaluations used in the approvals, and the current status of the container usage, will be discussed.

  3. Level 1 Accident Investigation Report of August 17, 2004, Fatal...

    Office of Environmental Management (EM)

    Investigation Report of August 17, 2004, Fatal Aircraft Accident on the Grand Coulee-Bell No.6, 500 kV Line Level 1 Accident Investigation Report of August 17, 2004, Fatal Aircraft ...

  4. Type B Accident Investigation of the October 9, 2008 Employee...

    Energy Savers [EERE]

    Sled Track, Sandia Site Office Type B Accident Investigation of the October 9, 2008 ... PDF icon Type B Accident Investigation of the October 9, 2008 Employee Injured when Rocket ...

  5. Type B Accident Investigation Board Report on the October 15...

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

    Type B Accident Investigation Board Report on the October 15, 2001, Grout Injection ... The board concluded that the direct cause of the accident was a failure of a 45 swivel ...

  6. Type B Accident Investigation Board Report BNFL, Inc. Employee...

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

    Type B Accident Investigation Board Report BNFL, Inc. Employee Foot Injury on December 17, ... On December 17, 2003, at approximately 7:15 a.m., an accident occurred at the U.S. ...

  7. Y-12's 1958 nuclear criticality accident and increased safety...

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

    accident and increased safety - 1958 brought accidents, more safety The first X-ray machine was brought to Y-12 in February, 1949. It was a 1,000 KV system installed in Building...

  8. PNNL Results from 2009 Silene Criticality Accident Dosimeter Intercomparison Exercise

    SciTech Connect (OSTI)

    Hill, Robin L.; Conrady, Matthew M.

    2010-06-30

    This document reports the results of testing of the Hanford Personnel Nuclear Accident Dosimeter (PNAD) during a criticality accident dosimeter intercomparison exercise at the CEA Valduc Center on October 13, 14, and 15, 2009.

  9. Severe Accident Test Station Activity Report

    SciTech Connect (OSTI)

    Pint, Bruce A.; Terrani, Kurt A.

    2015-06-01

    Enhancing safety margins in light water reactor (LWR) severe accidents is currently the focus of a number of international R&D programs. The current UO2/Zr-based alloy fuel system is particularly susceptible since the Zr-based cladding experiences rapid oxidation kinetics in steam at elevated temperatures. Therefore, alternative cladding materials that offer slower oxidation kinetics and a smaller enthalpy of oxidation can significantly reduce the rate of heat and hydrogen generation in the core during a coolant-limited severe accident. In the U.S. program, the high temperature steam oxidation performance of accident tolerant fuel (ATF) cladding solutions has been evaluated in the Severe Accident Test Station (SATS) at Oak Ridge National Laboratory (ORNL) since 2012. This report summarizes the capabilities of the SATS and provides an overview of the oxidation kinetics of several candidate cladding materials. A suggested baseline for evaluating ATF candidates is a two order of magnitude reduction in the steam oxidation resistance above 1000C compared to Zr-based alloys. The ATF candidates are categorized based on the protective external oxide or scale that forms during exposure to steam at high temperature: chromia, alumina, and silica. Comparisons are made to literature and SATS data for Zr-based alloys and other less-protective materials.

  10. Computerized Accident Incident Reporting System | Department of Energy

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

    Computerized Accident Incident Reporting System Computerized Accident Incident Reporting System CAIRS Database The Computerized Accident/Incident Reporting System is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE operations. CAIRS is a Government computer system and, as such, has security requirements that must be followed. Access to the database is open to DOE and DOE contractors. Additional information

  11. Development of Light Water Reactor Fuels with Enhanced Accident Tolerance

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

    - Report to Congress | Department of Energy Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to Congress Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to Congress This report provides DOE's plan to develop light water reactor (LWR) fuels with enhanced accident tolerance in response to 2012 Congressional direction and funding authorization. The result of the accident tolerant fuel development activities, if successful,

  12. Accident Investigation Reports - Type B | Department of Energy

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

    Accident Investigation Reports - Type B Accident Investigation Reports - Type B November 23, 2010 Type B Accident Investigation Board Report of the September 29, 2010, Radiological Contamination Event at the Separations Process Research Unit (SPRU), Building H2 Demolition, in Niskayuna, New, York This report is an independent product of the Type B Accident Investigation Board appointed by Mark A. Gilbertson, Deputy Assistant Secretary for Program and Site Support, U.S. Department of Energy.

  13. Recommendations for Analyzing Accidents Under NEPA (DOE, 2002) | Department

    Energy Savers [EERE]

    of Energy Analyzing Accidents Under NEPA (DOE, 2002) Recommendations for Analyzing Accidents Under NEPA (DOE, 2002) This DOE guidance clarifies and supplements "Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements." It focuses on principles of accident analyses under NEPA. PDF icon RECOMMENDATIONS for ANALYZING ACCIDENTS under the NATIONAL ENVIRONMENTAL POLICY ACT More Documents & Publications Recommendations for the Preparation

  14. Severe Accident Test Station Design Document

    SciTech Connect (OSTI)

    Snead, Mary A.; Yan, Yong; Howell, Michael; Keiser, James R.; Terrani, Kurt A.

    2015-09-01

    The purpose of the ORNL severe accident test station (SATS) is to provide a platform for evaluation of advanced fuels under projected beyond design basis accident (BDBA) conditions. The SATS delivers the capability to map the behavior of advanced fuels concepts under accident scenarios across various temperature and pressure profiles, steam and steam-hydrogen gas mixtures, and thermal shock. The overall facility will include parallel capabilities for examination of fuels and irradiated materials (in-cell) and non-irradiated materials (out-of-cell) at BDBA conditions as well as design basis accident (DBA) or loss of coolant accident (LOCA) conditions. Also, a supporting analytical infrastructure to provide the data-needs for the fuel-modeling components of the Fuel Cycle Research and Development (FCRD) program will be put in place in a parallel manner. This design report contains the information for the first, second and third phase of design and construction of the SATS. The first phase consisted of the design and construction of an out-of-cell BDBA module intended for examination of non-irradiated materials. The second phase of this work was to construct the BDBA in-cell module to test irradiated fuels and materials as well as the module for DBA (i.e. LOCA) testing out-of-cell, The third phase was to build the in-cell DBA module. The details of the design constraints and requirements for the in-cell facility have been closely captured during the deployment of the out-of-cell SATS modules to ensure effective future implementation of the in-cell modules.

  15. Calculation notes that support accident scenario and consequence development for the steam intrusion from interfacing systems accident

    SciTech Connect (OSTI)

    Ryan, G.W., Westinghouse Hanford

    1996-07-25

    This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Steam Intrusion from Interfacing Systems. The calculations needed to quantify the risk associated with this accident scenario are included within.

  16. Notice of Intent to Revise Department of Energy Order 461.1B, Packaging and Transportation for Offsite Shipment of Materials of National Security Interest

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

    2015-01-15

    The purpose of this memorandum is to provide justification for the proposed revision of DOE O 461.1B, Packaging and Transportation for Offsite Shipment of Materials of National Security Interest, dated 12-16-2010, as part of the the quadrennial review and recertification as required by DOE O 251.1C, Departmental Directives Program.

  17. Evaluation Metrics Applied to Accident Tolerant Fuels

    SciTech Connect (OSTI)

    Shannon M. Bragg-Sitton; Jon Carmack; Frank Goldner

    2014-10-01

    The safe, reliable, and economic operation of the nation’s nuclear power reactor fleet has always been a top priority for the United States’ nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry’s success. Decades of research combined with continual operation have produced steady advancements in technology and have yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. One of the current missions of the U.S. Department of Energy’s (DOE) Office of Nuclear Energy (NE) is to develop nuclear fuels and claddings with enhanced accident tolerance for use in the current fleet of commercial LWRs or in reactor concepts with design certifications (GEN-III+). Accident tolerance became a focus within advanced LWR research upon direction from Congress following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex. The overall goal of ATF development is to identify alternative fuel system technologies to further enhance the safety, competitiveness and economics of commercial nuclear power. Enhanced accident tolerant fuels would endure loss of active cooling in the reactor core for a considerably longer period of time than the current fuel system while maintaining or improving performance during normal operations. The U.S. DOE is supporting multiple teams to investigate a number of technologies that may improve fuel system response and behavior in accident conditions, with team leadership provided by DOE national laboratories, universities, and the nuclear industry. Concepts under consideration offer both evolutionary and revolutionary changes to the current nuclear fuel system. Mature concepts will be tested in the Advanced Test Reactor at Idaho National Laboratory beginning in Summer 2014 with additional concepts being readied for insertion in fiscal year 2015. This paper provides a brief summary of the proposed evaluation process that would be used to evaluate and prioritize the candidate accident tolerant fuel concepts currently under development.

  18. Radioactive waste shipments to Hanford retrievable storage from Westinghouse Advanced Reactors and Nuclear Fuels Divisions, Cheswick, Pennsylvania

    SciTech Connect (OSTI)

    Duncan, D.; Pottmeyer, J.A.; Weyns, M.I.; Dicenso, K.D.; DeLorenzo, D.S.

    1994-04-01

    During the next two decades the transuranic (TRU) waste now stored in the burial trenches and storage facilities at the Hanford Sits in southeastern Washington State is to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico for final disposal. Approximately 5.7 percent of the TRU waste to be retrieved for shipment to WIPP was generated by the decontamination and decommissioning (D&D) of the Westinghouse Advanced Reactors Division (WARD) and the Westinghouse Nuclear Fuels Division (WNFD) in Cheswick, Pennsylvania and shipped to the Hanford Sits for storage. This report characterizes these radioactive solid wastes using process knowledge, existing records, and oral history interviews.

  19. Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation.

    SciTech Connect (OSTI)

    Tentner, A. M.; Parma, E.; Wei, T.; Wigeland, R.; Nuclear Engineering Division; SNL; INL

    2010-03-01

    An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents for the SFR so that appropriate risk management measures can be implemented early in the design process. This report presents the results of a review of the SFR features and phenomena that directly influence the sequence of events during a postulated severe accident. The report identifies the safety features used or proposed for various SFR designs in the US and worldwide for the prevention and/or mitigation of Core Disruptive Accidents (CDA). The report provides an overview of the current SFR safety approaches and the role of severe accidents. Mutual understanding of these design features and safety approaches is necessary for future collaborations between the US and its international partners as part of the GEN IV program. The report also reviews the basis for an integrated safety approach to severe accidents for the SFR that reflects the safety design knowledge gained in the US during the Advanced Liquid Metal Reactor (ALMR) and Integral Fast Reactor (IFR) programs. This approach relies on inherent reactor and plant safety performance characteristics to provide additional safety margins. The goal of this approach is to prevent development of severe accident conditions, even in the event of initiators with safety system failures previously recognized to lead directly to reactor damage.

  20. Key regulatory drivers affecting shipments of mixed transuranic waste from Los Alamos National Laboratory to the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Schumann, P.B.; Bacigalupa, G.A.; Kosiewicz, S.T.; Sinkule, B.J.

    1997-02-01

    A number of key regulatory drivers affect the nature, scope, and timing of Los Alamos National Laboratory`s (LANL`s) plans for mixed transuranic (MTRU) waste shipments to the Waste Isolation Pilot Plant (WIPP), which are planned to commence as soon as possible following WIPP`s currently anticipated November, 1997 opening date. This paper provides an overview of some of the key drivers at LANL, particularly emphasizing those associated with the hazardous waste component of LANL`s MTRU waste (MTRU, like any mixed waste, contains both a radioactive and a hazardous waste component). The key drivers discussed here derive from the federal Resource Conservation and Recovery Act (RCRA) and its amendments, including the Federal Facility Compliance Act (FFCAU), and from the New Mexico Hazardous Waste Act (NMHWA). These statutory provisions are enforced through three major mechanisms: facility RCRA permits; the New Mexico Hazardous Waste Management Regulations, set forth in the New Mexico Administrative Code, Title 20, Chapter 4, Part 1: and compliance orders issued to enforce these requirements. General requirements in all three categories will apply to MTRU waste management and characterization activities at both WIPP and LANL. In addition, LANL is subject to facility-specific requirements in its RCRA hazardous waste facility permit, permit conditions as currently proposed in RCRA Part B permit applications presently being reviewed by the New Mexico Environment Department (NNED), and facility-specific compliance orders related to MTRU waste management. Likewise, permitting and compliance-related requirements specific to WIPP indirectly affect LANL`s characterization, packaging, record-keeping, and transportation requirements for MTRU waste. LANL must comply with this evolving set of regulatory requirements to begin shipments of MTRU waste to WIPP in a timely fashion.

  1. US Department of Energy Chernobyl accident bibliography

    SciTech Connect (OSTI)

    Kennedy, R A; Mahaffey, J A; Carr, F Jr

    1992-04-01

    This bibliography has been prepared by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Office of Health and Environmental Research to provide bibliographic information in a usable format for research studies relating to the Chernobyl nuclear accident that occurred in the Ukrainian Republic, USSR in 1986. This report is a product of the Chernobyl Database Management project. The purpose of this project is to produce and maintain an information system that is the official United States repository for information related to the accident. Two related products prepared for this project are the Chernobyl Bibliographic Search System (ChernoLit{trademark}) and the Chernobyl Radiological Measurements Information System (ChernoDat). This report supersedes the original release of Chernobyl Bibliography (Carr and Mahaffey, 1989). The original report included about 2200 references. Over 4500 references and an index of authors and editors are included in this report.

  2. Fire tests and analyses of a rail cask-sized calorimeter.

    SciTech Connect (OSTI)

    Figueroa, Victor G.; Lopez, Carlos; Suo-Anttila, Ahti Jorma; Greiner, Miles

    2010-10-01

    Three large open pool fire experiments involving a calorimeter the size of a spent fuel rail cask were conducted at Sandia National Laboratories Lurance Canyon Burn Site. These experiments were performed to study the heat transfer between a very large fire and a large cask-like object. In all of the tests, the calorimeter was located at the center of a 7.93-meter diameter fuel pan, elevated 1 meter above the fuel pool. The relative pool size and positioning of the calorimeter conformed to the required positioning of a package undergoing certification fire testing. Approximately 2000 gallons of JP-8 aviation fuel were used in each test. The first two tests had relatively light winds and lasted 40 minutes, while the third had stronger winds and consumed the fuel in 25 minutes. Wind speed and direction, calorimeter temperature, fire envelop temperature, vertical gas plume speed, and radiant heat flux near the calorimeter were measured at several locations in all tests. Fuel regression rate data was also acquired. The experimental setup and certain fire characteristics that were observed during the test are described in this paper. Results from three-dimensional fire simulations performed with the Cask Analysis Fire Environment (CAFE) fire code are also presented. Comparisons of the thermal response of the calorimeter as measured in each test to the results obtained from the CAFE simulations are presented and discussed.

  3. Preparation of the Second Shipment of Spent Nuclear Fuel from the Ustav Jaderneho Vyzkumu Rez (UJV Rez), a.s., Czech Republic to the Russian Federation for Reprocessing - 13478

    SciTech Connect (OSTI)

    Trtilek, Radek; Podlaha, Josef [UJV Rez, a. s., Hlavni 130, 25068 Husinec-Rez (Czech Republic)] [UJV Rez, a. s., Hlavni 130, 25068 Husinec-Rez (Czech Republic)

    2013-07-01

    After more than 50 years of operation of the LVR-15 research reactor operated by the UJV Rez, a. s. (formerly Nuclear Research Institute - NRI), a large amount of the spent nuclear fuel (SNF) of Russian origin has been accumulated. In 2005 UJV Rez, a. s. jointed the Russian Research Reactor Fuel Return (RRRFR) program under the United States (US) - Russian Global Threat Reduction Initiative (GTRI) and started the process of SNF shipment from the LVR-15 research reactor back to the Russian Federation (RF). In 2007 the first shipment of SNF was realized. In 2011, preparation of the second shipment of spent fuel from the Czech Republic started. The experience obtained from the first shipment will be widely used, but some differences must be taken into the account. The second shipment will be realized in 2013 and will conclude the return transport of all, both fresh and spent, high-enriched nuclear fuel from the Czech Republic to the Russian Federation. After the shipment is completed, there will be only low-enriched nuclear fuel on the territory of the Czech Republic, containing maximum of 20% of U-235, which is the conventionally recognized limit between the low- and high-enriched nuclear materials. The experience (technical, organizational, administrative, logistic) obtained from the each SNF shipment as from the Czech Republic as from other countries using the Russian type research reactors are evaluated and projected onto preparation of next shipment of high enriched nuclear fuel back to the Russian Federation. The results shown all shipments provided by the UJV Rez, a. s. in the frame of the GTRI Program have been performed successfully and safely. It is expected the experience and results will be applied to preparation and completing of the Chinese Miniature Neutron Source Reactors (MNSR) Spent Nuclear Fuel Repatriation in the near future. (authors)

  4. Risk Estimation Methodology for Launch Accidents.

    SciTech Connect (OSTI)

    Clayton, Daniel James; Lipinski, Ronald J.; Bechtel, Ryan D.

    2014-02-01

    As compact and light weight power sources with reliable, long lives, Radioisotope Power Systems (RPSs) have made space missions to explore the solar system possible. Due to the hazardous material that can be released during a launch accident, the potential health risk of an accident must be quantified, so that appropriate launch approval decisions can be made. One part of the risk estimation involves modeling the response of the RPS to potential accident environments. Due to the complexity of modeling the full RPS response deterministically on dynamic variables, the evaluation is performed in a stochastic manner with a Monte Carlo simulation. The potential consequences can be determined by modeling the transport of the hazardous material in the environment and in human biological pathways. The consequence analysis results are summed and weighted by appropriate likelihood values to give a collection of probabilistic results for the estimation of the potential health risk. This information is used to guide RPS designs, spacecraft designs, mission architecture, or launch procedures to potentially reduce the risk, as well as to inform decision makers of the potential health risks resulting from the use of RPSs for space missions.

  5. Hanford waste tank bump accident analysis

    SciTech Connect (OSTI)

    MALINOVIC, B.

    2003-03-21

    This report provides a new evaluation of the Hanford tank bump accident analysis (HNF-SD-Wh4-SAR-067 2001). The purpose of the new evaluation is to consider new information and to support new recommendations for final safety controls. This evaluation considers historical data, industrial failure modes, plausible accident scenarios, and system responses. A tank bump is a postulated event in which gases, consisting mostly of water vapor, are suddenly emitted from the waste and cause tank headspace pressurization. A tank bump is distinguished from a gas release event in two respects: First, the physical mechanism for release involves vaporization of locally superheated liquid, and second, gases emitted to the head space are not flammable. For this reason, a tank bump is often called a steam bump. In this report, even though non-condensible gases may be considered in bump models, flammability and combustion of emitted gases are not. The analysis scope is safe storage of waste in its current configuration in single-shell tanks (SSTs) and double-shell tanks (DSTs). The analysis considers physical mechanisms for tank bump to formulate criteria for bump potential, application of the criteria to the tanks, and accident analysis of bump scenarios. The result of consequence analysis is the mass of waste released from tanks for specific scenarios where bumps are credible; conversion to health consequences is performed elsewhere using standard Hanford methods (Cowley et al. 2000). The analysis forms a baseline for future extension to consider waste retrieval.

  6. Investigations on optimization of accident management measures following a station blackout accident in a VVER-1000 pressurized water reactor

    SciTech Connect (OSTI)

    Tusheva, P.; Schaefer, F.; Kliem, S.

    2012-07-01

    The reactor safety issues are of primary importance for preserving the health of the population and ensuring no release of radioactivity and fission products into the environment. A part of the nuclear research focuses on improvement of the safety of existing nuclear power plants. Studies, research and efforts are a continuing process at improving the safety and reliability of existing and newly developed nuclear power plants at prevention of a core melt accident. Station blackout (loss of AC power supply) is one of the dominant accidents taken into consideration at performing accident analysis. In case of multiple failures of safety systems it leads to a severe accident. To prevent an accident to turn into a severe one or to mitigate the consequences, accident management measures must be performed. The present paper outlines possibilities for application and optimization of accident management measures following a station blackout accident. Assessed is the behaviour of the nuclear power plant during a station blackout accident without accident management measures and with application of primary/secondary side oriented accident management measures. Discussed are the possibilities for operators ' intervention and the influence of the performed accident management measures on the course of the accident. Special attention has been paid to the effectiveness of the passive feeding and physical phenomena having an influence on the system behaviour. The performed simulations show that the effectiveness of the secondary side feeding procedure can be limited due to an early evaporation or flashing effects in the feed water system. The analyzed cases show that the effectiveness of the accident management measures strongly depends on the initiation criteria applied for depressurization of the reactor coolant system. (authors)

  7. Severe Accident Scoping Simulations of Accident Tolerant Fuel Concepts for BWRs

    SciTech Connect (OSTI)

    Robb, Kevin R.

    2015-08-01

    Accident-tolerant fuels (ATFs) are fuels and/or cladding that, in comparison with the standard uranium dioxide Zircaloy system, can tolerate loss of active cooling in the core for a considerably longer time period while maintaining or improving the fuel performance during normal operations [1]. It is important to note that the currently used uranium dioxide Zircaloy fuel system tolerates design basis accidents (and anticipated operational occurrences and normal operation) as prescribed by the US Nuclear Regulatory Commission. Previously, preliminary simulations of the plant response have been performed under a range of accident scenarios using various ATF cladding concepts and fully ceramic microencapsulated fuel. Design basis loss of coolant accidents (LOCAs) and station blackout (SBO) severe accidents were analyzed at Oak Ridge National Laboratory (ORNL) for boiling water reactors (BWRs) [2]. Researchers have investigated the effects of thermal conductivity on design basis accidents [3], investigated silicon carbide (SiC) cladding [4], as well as the effects of ATF concepts on the late stage accident progression [5]. These preliminary analyses were performed to provide initial insight into the possible improvements that ATF concepts could provide and to identify issues with respect to modeling ATF concepts. More recently, preliminary analyses for a range of ATF concepts have been evaluated internationally for LOCA and severe accident scenarios for the Chinese CPR1000 [6] and the South Korean OPR-1000 [7] pressurized water reactors (PWRs). In addition to these scoping studies, a common methodology and set of performance metrics were developed to compare and support prioritizing ATF concepts [8]. A proposed ATF concept is based on iron-chromium-aluminum alloys (FeCrAl) [9]. With respect to enhancing accident tolerance, FeCrAl alloys have substantially slower oxidation kinetics compared to the zirconium alloys typically employed. During a severe accident, FeCrAl would tend to generate heat and hydrogen from oxidation at a slower rate compared to the zirconium-based alloys in use today. The previous study, [2], of the FeCrAl ATF concept during station blackout (SBO) severe accident scenarios in BWRs was based on simulating short term SBO (STSBO), long term SBO (LTSBO), and modified SBO scenarios occurring in a BWR-4 reactor with MARK-I containment. The analysis indicated that FeCrAl had the potential to delay the onset of fuel failure by a few hours depending on the scenario, and it could delay lower head failure by several hours. The analysis demonstrated reduced in-vessel hydrogen production. However, the work was preliminary and was based on limited knowledge of material properties for FeCrAl. Limitations of the MELCOR code were identified for direct use in modeling ATF concepts. This effort used an older version of MELCOR (1.8.5). Since these analyses, the BWR model has been updated for use in MELCOR 1.8.6 [10], and more representative material properties for FeCrAl have been modeled. Sections 2 4 present updated analyses for the FeCrAl ATF concept response during severe accidents in a BWR. The purpose of the study is to estimate the potential gains afforded by the FeCrAl ATF concept during BWR SBO scenarios.

  8. Probe characterization of high-current driven metal plasma in a vacuum-arc rail gun

    SciTech Connect (OSTI)

    Vijayan, T.; Roychowdhury, P.; Venkatramani, N.

    2004-10-15

    The characteristics of metal plasma launched by high-current electric arc in a vacuum-arc rail gun are determined by employing electrical and magnetic probes. These measurements are validated by results from theoretical simulations. The arc coupled nonlinear circuit equations are solved simultaneously with the Newtonian arc motion and revealed the undercritically damped behavior of the arc current identical to the arc-current signal recorded by the Rogowski magnetic probe. Similarly the arc velocity and displacement derived from the signatures of B-dot probes are shown to concur closely with the results of JxB propulsion from simulation. The heating of plasma is formulated in a three-electron population regime with direct arc energy coupling through magnetohydrodynamic, ion-acoustic, Coulomb, and neutral interactions. This results in high temperature (T{sub e}) of hundreds of eV in the arc as revealed by the simulation. Hence T{sub e} of the rapidly cooling and equilibrating plasma that emerged from the muzzle is high around 80-90 eV, which is confirmed by Langmuir electric probe measurements. Density n{sub e} of this metal plasma is shown to be in the range 4x10{sup 21}-6x10{sup 21} m{sup -3} and includes multiple ion charge states. The exit velocity of the plasma measured by a pair of Langmuir probes is close to 2.2x10{sup 6} cm/s and matched well with the arc velocity determined by the B-dot probes and the results from simulation.

  9. Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis Citation Details In-Document Search Title: Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis The severe accident at Fukushima Daiichi nuclear plants illustrates the need for continuous improvements through developing and implementing technologies that contribute to safe, reliable and cost-effective operation of the nuclear fleet. Development of enhanced

  10. Accident Investigation Report - Fire Report | Department of Energy

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

    Fire Report Accident Investigation Report - Fire Report On February 7, 2014, Deputy Assistant Secretary, Safety, Security, and Quality Programs Environmental Management, DOE, formally appointed an Accident Investigation Board to investigate an underground mine fire involving a salt haul truck occurred at DOE's WIPP near Carlsbad, New Mexico. The Board began the investigation on February 10, 2014, and the report is now final and available for the public. PDF icon Accident Investigation Report

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

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

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

  12. ORISE: The Medical Basis for Radiation-Accident Preparedness: Medical

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

    Management (Published by REAC/TS) The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness and the Biodosimetry Workshop As part of its mission to provide continuing education for personnel responsible for treating radiation injuries, REAC/TS hosted the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness symposium and

  13. Los Alamos National Laboratory Accident Investigation Board Corrective

    Office of Environmental Management (EM)

    Action Plan Update | Department of Energy Accident Investigation Board Corrective Action Plan Update Los Alamos National Laboratory Accident Investigation Board Corrective Action Plan Update Topic: Status of the Corrective Actions that were identified by the Accident Investigation Board. It was noted that there are 22 Judgments of Need that were assessed against the Los Alamos Site. PDF icon AIB-CAP-Update - January 13, 2016

  14. Type A Accident Investigation of the March 16, 2000, Plutonium...

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

    New Mexico Type A Accident Investigation of the March 16, 2000, Plutonium-238 Multiple Intake Event at the Plutonium Facility, Los Alamos National Laboratory, New Mexico July ...

  15. Accident Investigation of the August 21, 2012, Contamination...

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

    PDF icon Accident Investigation of the August 21, 2012, Contamination Incident at the Los Alamos Neutron Science Center at the Los Alamos National Laboratory More Documents & ...

  16. Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts...

    Office of Scientific and Technical Information (OSTI)

    Concepts in Light Water Reactors Citation Details In-Document Search Title: Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors Authors: ...

  17. Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts...

    Office of Scientific and Technical Information (OSTI)

    in Pressurized Water Reactors Citation Details In-Document Search Title: Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors ...

  18. Accident Investigation Reports - Type B | Department of Energy

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

    is an independent product of the Type B Accident Investigation Board appointed by John Kennedy, Acting Manager, Chicago Operations Office, U.S. Department of Energy (DOE). October...

  19. Sandia Assists NASA in Understanding Launch-Area Accidents

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

    Assists NASA in Understanding Launch-Area Accidents - Sandia Energy Energy Search Icon ... Twitter Google + Vimeo GovDelivery SlideShare Sandia Assists NASA in Understanding ...

  20. Improvement of Design Codes to Account for Accident Thermal Effects...

    Office of Environmental Management (EM)

    IMPROVEMENT OF DESIGN CODES TO ACCOUNT FOR ACCIDENT THERMAL EFFECTS ON SEISMIC PERFORMANCE Amit H. Varma, Kadir Sener, Saahas Bhardwaj Purdue University Andrew Whittaker: Univ. of...

  1. Accident Investigations of the February 14, 2014, Radiological...

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

    Because of this, the Accident Investigation Board established a Fire Forensic Analysis Team. The results of the fire forensic analysis are documented in the Fire Forensic Analysis ...

  2. Type B Accident Investigation of the August 22, 2000, Injury...

    Office of Environmental Management (EM)

    Chemical Reaction at the Portsmouth Gaseous Diffusion Plant, X-701B Site Type B Accident Investigation of the August 22, 2000, Injury Resulting From Violent Exothermic Chemical ...

  3. Type B Accident Investigation Board Report for the January 11...

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

    barrier analysis, change analysis, and event and causal factor analysis. PDF icon Type B Accident Investigation Board Report for the January 11, 2006, Personal Injury During ...

  4. Accident Investigation Report - Fire Report | Department of Energy

    Office of Environmental Management (EM)

    an Accident Investigation Board to investigate an underground mine fire involving a salt haul truck occurred at DOE's WIPP near Carlsbad, New Mexico. The Board began the...

  5. Development of Light Water Reactor Fuels with Enhanced Accident...

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

    This report provides DOE's plan to develop light water reactor (LWR) fuels with enhanced ... PDF icon Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - ...

  6. Type B Accident Investigation Report of the October 28, 2004...

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

    of the October 28, 2004, Burn Injuries Sustained During an Office of Secure Transportation Joint Training Exercise at Fort Hunter-Liggett, CA Type B Accident Investigation Report ...

  7. Sandia Energy - Waste Isolation Pilot Plant Accident Investigation...

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

    Home Energy Nuclear Energy News News & Events Research & Capabilities Systems Analysis Materials Science Computational Modeling & Simulation Waste Isolation Pilot Plant Accident...

  8. Hazard Categorization and Accident Analysis Techniques for Compliance...

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

    Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports by Diane Johnson he purpose of this DOE Standard is to...

  9. Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems...

    Office of Scientific and Technical Information (OSTI)

    The severe accident at Fukushima Daiichi nuclear plants illustrates the need for ... Subject: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS Develop; fuels; Fukushima Daiichi; Low ...

  10. Type B Accident Investigation Report on the Exertional Heat Illnesses...

    Office of Environmental Management (EM)

    Heat Illnesses during SPOTC 2006 at the National Training Center in Albuquerque, New Mexico, July 13, 2006 Type B Accident Investigation Report on the Exertional Heat Illnesses ...

  11. Financial assistance to states and tribes to support emergency preparedness and response and the safe transportation of hazardous shipments: 1996 Update

    SciTech Connect (OSTI)

    Bradbury, J.A.; Leyson, J.; Lester, M.K.

    1996-07-01

    This report revises and updates the 1995 report Financial Assistance to States and Tribes to Support Emergency Preparedness and Response and the Safe Transportation of Hazardous Shipments, PNL-10260 (UC-620). The presentation of data and some of the data reported have been changed; these data supersede those presented in the earlier publication. All data have been updated to fiscal year 1995, with the exception of FEMA data that are updated to fiscal year 1994 only. The report identifies and summarizes existing sources of financial assistance to States and Tribes in preparing and responding to transportation emergencies and ensuring the safe transportation of hazardous shipments through their jurisdictions. It is intended for use as an information resource for the U.S. Department of Energy`s Office of Environmental Management (EM), Office of Transportation, Emergency Management, and Analytical Services (EM-76).

  12. Assessment of the risk of transporting propane by truck and train

    SciTech Connect (OSTI)

    Geffen, C.A.

    1980-03-01

    The risk of shipping propane is discussed and the risk assessment methodology is summarized. The risk assessment model has been constructed as a series of separate analysis steps to allow the risk to be readily reevaluated as additional data becomes available or as postulated system characteristics change. The transportation system and accident environment, the responses of the shipping system to forces in transportation accidents, and release sequences are evaluated to determine both the likelihood and possible consequences of a release. Supportive data and analyses are given in the appendices. The risk assessment results are related to the year 1985 to allow a comparison with other reports in this series. Based on the information presented, accidents involving tank truck shipments of propane will be expected to occur at a rate of 320 every year; accidents involving bobtails would be expected at a rate of 250 every year. Train accidents involving propane shipments would be expected to occur at a rate of about 60 every year. A release of any amount of material from propane trucks, under both normal transportation and transport accident conditions, is to be expected at a rate of about 110 per year. Releases from propane rail tank cars would occur about 40 times a year. However, only those releases that occur during a transportation accident or involve a major tank defect will include sufficient propane to present the potential for danger to the public. These significant releases can be expected at the lower rate of about fourteen events per year for truck transport and about one event every two years for rail tank car transport. The estimated number of public fatalities resulting from these significant releases in 1985 is fifteen. About eleven fatalities per year result from tank truck operation, and approximately half a death per year stems from the movement of propane in rail tank cars.

  13. Preliminary analysis of loss-of-coolant accident in Fukushima nuclear accident

    SciTech Connect (OSTI)

    Su'ud, Zaki; Anshari, Rio

    2012-06-06

    Loss-of-Coolant Accident (LOCA) in Boiling Water Reactor (BWR) especially on Fukushima Nuclear Accident will be discussed in this paper. The Tohoku earthquake triggered the shutdown of nuclear power reactors at Fukushima Nuclear Power station. Though shutdown process has been completely performed, cooling process, at much smaller level than in normal operation, is needed to remove decay heat from the reactor core until the reactor reach cold-shutdown condition. If LOCA happen at this condition, it will cause the increase of reactor fuel and other core temperatures and can lead to reactor core meltdown and exposure of radioactive material to the environment such as in the Fukushima Dai Ichi nuclear accident case. In this study numerical simulation has been performed to calculate pressure composition, water level and temperature distribution on reactor during this accident. There are two coolant regulating system that operational on reactor unit 1 at this accident, Isolation Condensers (IC) system and Safety Relief Valves (SRV) system. Average mass flow of steam to the IC system in this event is 10 kg/s and could keep reactor core from uncovered about 3,2 hours and fully uncovered in 4,7 hours later. There are two coolant regulating system at operational on reactor unit 2, Reactor Core Isolation Condenser (RCIC) System and Safety Relief Valves (SRV). Average mass flow of coolant that correspond this event is 20 kg/s and could keep reactor core from uncovered about 73 hours and fully uncovered in 75 hours later. There are three coolant regulating system at operational on reactor unit 3, Reactor Core Isolation Condenser (RCIC) system, High Pressure Coolant Injection (HPCI) system and Safety Relief Valves (SRV). Average mass flow of water that correspond this event is 15 kg/s and could keep reactor core from uncovered about 37 hours and fully uncovered in 40 hours later.

  14. Type B Accident Investigation of the March 20, 2003, Stair Installation Accident at Building 752, Sandia National Laboratories

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type B Accident Investigation Board appointed by Karen L. Boardman, Manager, Sandia Site Office (SSO), National Nuclear Security Administration (NNSA).

  15. Calculation notes that support accident scenario and consequence development for the steam intrusion from interfacing systems accident

    SciTech Connect (OSTI)

    Van Vleet, R.J.; Ryan, G.W.; Crowe, R.D.; Lindberg, S.E., Fluor Daniel Hanford

    1997-03-04

    This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report (FSAR): Steam Intrusion From Interfacing Systems. The calculations needed to quantify the risk associated with this accident scenario are included in the following sections to aid in the understanding of this accident scenario. Information validation forms citing assumptions that were approved for use specifically in this analysis are included in Appendix A. Copies of these forms are also on file with TWRS Project Files. Calculations performed in this document, in general, are expressed in traditional (English) units to aid understanding of the accident scenario and related parameters.

  16. Logistical concepts associated with international shipments using the USA/9904/B(U)F RTG Transportation System (RTGTS)

    SciTech Connect (OSTI)

    Barklay, C.D.; Miller, R.G.; Pugh, B.K.; Howell, E.I.

    1997-01-01

    Over the last 30 years, radioisotopes have provided heat from which electrical power is generated. For space missions, the isotope of choice has generally been {sup 238}PuO{sub 2}, its long half-life making it ideal for supplying power to remote satellites and spacecraft like the Voyager, Pioneer, and Viking missions, as well as the recently launched Galileo and Ulysses missions, and the presently planned Cassini mission. Electric power for future space missions will be provided by either radioisotopic thermoelectric generators (RTG), radioisotope thermophotovoltaic systems (RTPV), alkali metal thermal to electrical conversion (AMTEC) systems, radioisotope Stirling systems, or a combination of these. The type of electrical power system has yet to be specified for the {open_quotes}Pluto Express{close_quotes} mission. However, the current plan does incorporate the use of Russian launch platforms for the spacecraft. The implied tasks associated with this plan require obtaining international certification for the transport of the radioisotopic power system, and resolving any logistical issues associated with the actual shipment of the selected radioisotopic power system. This paper presents a conceptual summary of the logistical considerations associated with shipping the selected radioisotopic power system using the USA/9904/B(U)F-85, Radioisotope Thermoelectric Generator Transportation System (RTGTS). {copyright} {ital 1997 American Institute of Physics.}

  17. Logistical concepts associated with international shipments using the USA/9904/B(U)F RTG Transportation System (RTGTS)

    SciTech Connect (OSTI)

    Barklay, Chadwick D.; Miller, Roger G.; Pugh, Barry K.; Howell, Edwin I.

    1997-01-10

    Over the last 30 years, radioisotopes have provided heat from which electrical power is generated. For space missions, the isotope of choice has generally been {sup 238}PuO{sub 2}, its long half-life making it ideal for supplying power to remote satellites and spacecraft like the Voyager, Pioneer, and Viking missions, as well as the recently launched Galileo and Ulysses missions, and the presently planned Cassini mission. Electric power for future space missions will be provided by either radioisotopic thermoelectric generators (RTG), radioisotope thermophotovoltaic systems (RTPV), alkali metal thermal to electrical conversion (AMTEC) systems, radioisotope Stirling systems, or a combination of these. The type of electrical power system has yet to be specified for the 'Pluto Express' mission. However, the current plan does incorporate the use of Russian launch platforms for the spacecraft. The implied tasks associated with this plan require obtaining international certification for the transport of the radioisotopic power system, and resolving any logistical issues associated with the actual shipment of the selected radioisotopic power system. This paper presents a conceptual summary of the logistical considerations associated with shipping the selected radioisotopic power system using the USA/9904/B(U)F-85, Radioisotope Thermoelectric Generator Transportation System (RTGTS)

  18. BWR containment failure analysis during degraded-core accidents

    SciTech Connect (OSTI)

    Yue, D.D.

    1982-06-06

    This paper presents a containment failure mode analysis during a spectrum of postulated degraded core accident sequences in a typical 1000-MW(e) boiling water reactor (BWR) with a Mark-I wetwell containment. Overtemperature failure of containment electric penetration assemblies (CEPAs) has been found to be the major failure mode during such accidents.

  19. Accident response group (ARG) containers for recovery of damaged warheads

    SciTech Connect (OSTI)

    York, A.R. II; Hoffman, J.P.

    1993-09-01

    This report provides an overview of the containers that are currently stored at Pantex and available for use in response to an accident or for use in any other application where a sealed containment vessel and accident resistant overpack may be needed.

  20. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    1999-10-20

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

  1. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.; PIEPHO, M.G.

    2000-03-23

    This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  2. Canister storage building design basis accident analysis documentation

    SciTech Connect (OSTI)

    KOPELIC, S.D.

    1999-02-25

    This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  3. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    1999-09-09

    This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  4. Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video

    Office of Energy Efficiency and Renewable Energy (EERE)

    This course that provides an overview of the fundamentals of accident investigation. The course is intended to meet the every five year refresher training requirement for DOE Federal Accident Investigators under DOE O 225.1B, Accident Investigations.

  5. GPHS-RTG launch accident analysis for Galileo and Ulysses

    SciTech Connect (OSTI)

    Bradshaw, C.T. )

    1991-01-01

    This paper presents the safety program conducted to determine the response of the General Purpose Heat Source (GPHS) Radioisotope Thermoelectric Generator (RTG) to potential launch accidents of the Space Shuttle for the Galileo and Ulysses missions. The National Aeronautics and Space Administration (NASA) provided definition of the Shuttle potential accidents and characterized the environments. The Launch Accident Scenario Evaluation Program (LASEP) was developed by GE to analyze the RTG response to these accidents. RTG detailed response to Solid Rocket Booster (SRB) fragment impacts, as well as to other types of impact, was obtained from an extensive series of hydrocode analyses. A comprehensive test program was conducted also to determine RTG response to the accident environments. The hydrocode response analyses coupled with the test data base provided the broad range response capability which was implemented in LASEP.

  6. MELCOR accident analysis for ARIES-ACT

    SciTech Connect (OSTI)

    Paul W. Humrickhouse; Brad J. Merrill

    2012-08-01

    We model a loss of flow accident (LOFA) in the ARIES-ACT1 tokamak design. ARIES-ACT1 features an advanced SiC blanket with LiPb as coolant and breeder, a helium cooled steel structural ring and tungsten divertors, a thin-walled, helium cooled vacuum vessel, and a room temperature water-cooled shield outside the vacuum vessel. The water heat transfer system is designed to remove heat by natural circulation during a LOFA. The MELCOR model uses time-dependent decay heats for each component determined by 1-D modeling. The MELCOR model shows that, despite periodic boiling of the water coolant, that structures are kept adequately cool by the passive safety system.

  7. Graphite Oxidation Simulation in HTR Accident Conditions

    SciTech Connect (OSTI)

    El-Genk, Mohamed

    2012-10-19

    Massive air and water ingress, following a pipe break or leak in steam-generator tubes, is a design-basis accident for high-temperature reactors (HTRs). Analysis of these accidents in both prismatic and pebble bed HTRs requires state-of-the-art capability for predictions of: 1) oxidation kinetics, 2) air “helium gas mixture stratification and diffusion into the core following the depressurization, 3) transport of multi-species gas mixture, and 4) graphite corrosion. This project will develop a multi-dimensional, comprehensive oxidation kinetics model of graphite in HTRs, with diverse capabilities for handling different flow regimes. The chemical kinetics/multi-species transport model for graphite burning and oxidation will account for temperature-related changes in the properties of graphite, oxidants (O2, H2O, CO), reaction products (CO, CO2, H2, CH4) and other gases in the mixture (He and N2). The model will treat the oxidation and corrosion of graphite in geometries representative of HTR core component at temperatures of 900°C or higher. The developed chemical reaction kinetics model will be user-friendly for coupling to full core analysis codes such as MELCOR and RELAP, as well as computational fluid dynamics (CFD) codes such as CD-adapco. The research team will solve governing equations for the multi-dimensional flow and the chemical reactions and kinetics using Simulink, an extension of the MATLAB solver, and will validate and benchmark the model's predictions using reported experimental data. Researchers will develop an interface to couple the validated model to a commercially available CFD fluid flow and thermal-hydraulic model of the reactor , and will perform a simulation of a pipe break in a prismatic core HTR, with the potential for future application to a pebble-bed type HTR.

  8. Level 1 Accident Report of the March 1, 2010 Bobcat Fatality...

    Energy Savers [EERE]

    at BPA's White Bluffs Substation Level 1 Accident Report of the March 1, 2010 Bobcat ... (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to ...

  9. Type A Accident Investigation Board Report on the April 19, 1999...

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

    Type A Accident Investigation Board Report on the April 19, 1999, Special Agent Fatality ... responsibility for conducting a Type A accident investigation to the AL Manager on April ...

  10. Type B Accident Investigation of the July 31, 2006, Fall from...

    Office of Environmental Management (EM)

    31, 2006, Fall from Ladder Accident at the Lawrence Livermore National Laboratory, Livermore, California Type B Accident Investigation of the July 31, 2006, Fall from Ladder ...

  11. Reactor safety study. An assessment of accident risks in U. S...

    Office of Scientific and Technical Information (OSTI)

    An assessment of accident risks in U. S. commercial nuclear power plants. Executive ... An assessment of accident risks in U. S. commercial nuclear power plants. Executive ...

  12. Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy...

    Office of Scientific and Technical Information (OSTI)

    Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding Citation Details In-Document Search Title: Improving Accident Tolerance of Nuclear Fuel with Coated ...

  13. The Accident at Fukushima: What Happened?

    SciTech Connect (OSTI)

    Fujie, Takao

    2012-07-01

    At 2:46 PM, on the coast of the Pacific Ocean in eastern Japan, people were spending an ordinary afternoon. The earthquake had a magnitude of 9.0, the fourth largest ever recorded in the world. Avery large number of aftershocks were felt after the initial earthquake. More than 100 of them had a magnitude of over 6.0. There were very few injured or dead at this point. The large earthquake caused by this enormous crustal deformation spawned a rare and enormous tsunami that crashed down 30-40 minutes later. It easily cleared the high levees, washing away cars and houses and swallowing buildings of up to three stories in height. The largest tsunami reading taken from all regions was 40 meters in height. This tsunami reached the West Coast of the United States and the Pacific coast of South America, with wave heights of over two meters. It was due to this tsunami that the disaster became one of a not imaginable scale, which saw the number of dead or missing reach about 20,000 persons. The enormous tsunami headed for 15 nuclear power plants on the Pacific coast, but 11 power plants withstood the tsunami and attained cold shutdown. The flood height of the tsunami that struck each power station ranged to a maximum of 15 meters. The Fukushima Daiichi Nuclear Power Plant Units experienced the largest and the cores of three reactors suffered meltdown. As a result, more than 160,000 residents were forced to evacuate, and are still living in temporary accommodation. The main focus of this presentation is on what happened at the Fukushima Daiichi, and how station personnel responded to the accident, with considerable international support. A year after the Fukushima Daiichi accident, Japan is in the process of leveraging the lessons learned from the accident to further improve the safety of nuclear power facilities and regain the trust of society. In this connection, not only international organizations, including IAEA, and WANO, but also governmental organizations and nuclear industry representatives from various countries, have been evaluating what happened at Fukushima Daiichi. Support from many countries has contributed to successfully stabilizing the Fukushima Daiichi Nuclear Power Station. International cooperation is required as Japan started along the long road to decommissioning the reactors. Such cooperation with the international community would achieve the decommissioning of the damaged reactors. Finally, recovery plans by the Japanese government to decontaminate surrounding regions have been started in order to get residents back to their homes as early as possible. Looking at the world's nuclear power industry, there are currently approximately 440 reactors in operation and 60 under construction. Despite the dramatic consequences of the Fukushima Daiichi catastrophe it is expected that the importance of nuclear power generation will not change in the years to come. Newly accumulated knowledge and capabilities must be passed on to the next generation. This is the duty put upon us and which is one that we must embrace.

  14. Guidance manual for the identification of hazardous wastes delivered to publicly owned treatment works by truck, rail, or dedicated pipe

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    The manual is directed towards two types of facilities: First, guidance is to POTWs that wish to preclude the entry of hazardous wastes into their facilities and avoid regulation and liability under RCRA. Administrative/technical recommendations for control of such wastes is provided, many of which are already in use by POTWs. Second, the responsibilities of POTWs that choose to accept hazardous wastes from truck, rail, or dedicated pipeline are discussed, including relevant regulatory provisions, strict liability and corrective action requirements for releases, and recommended procedures for waste acceptance/management. The manual describes the RCRA regulatory status of wastes that POTW operators typically may encounter. The manual includes a Waste Monitoring Plan. Appendices give the following: RCRA lists; RCRA listed hazardous wastes; examples of POTW sewer use ordinance language, waste hauler permit; waste tracking form, notification of hazardous waste activity; uniform hazardous waste manifest; biennial hazardous waste report; and state hazardous waste contacts.

  15. Verification Test Suite (VERTS) For Rail Gun Applications using ALE3D: 2-D Hydrodynamics & Thermal Cases

    SciTech Connect (OSTI)

    Najjar, F M; Solberg, J; White, D

    2008-04-17

    A verification test suite has been assessed with primary focus on low reynolds number flow of liquid metals. This is representative of the interface between the armature and rail in gun applications. The computational multiphysics framework, ALE3D, is used. The main objective of the current study is to provide guidance and gain confidence in the results obtained with ALE3D. A verification test suite based on 2-D cases is proposed and includes the lid-driven cavity and the Couette flow are investigated. The hydro and thermal fields are assumed to be steady and laminar in nature. Results are compared with analytical solutions and previously published data. Mesh resolution studies are performed along with various models for the equation of state.

  16. MELCOR Accident Consequence Code System (MACCS)

    SciTech Connect (OSTI)

    Chanin, D.I. ); Sprung, J.L.; Ritchie, L.T.; Jow, Hong-Nian )

    1990-02-01

    This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previous CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projection, dose accumulation by a number of pathways including food and water ingestion, early and latent health effects, and economic costs. The MACCS code can be used for a variety of applications. These include (1) probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, (2) sensitivity studies to gain a better understanding of the parameters important to PRA, and (3) cost-benefit analysis. This report is composed of three volumes. This document, Volume 1, the Users's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems.

  17. Material selection for accident tolerant fuel cladding

    SciTech Connect (OSTI)

    Pint, B. A.; Terrani, K. A.; Yamamoto, Y.; Snead, L. L.

    2015-09-14

    Alternative cladding materials are being investigated for accident tolerance, which can be defined as >100X improvement (compared to current Zr-based alloys) in oxidation resistance in steam environments at ?1200C for short (?4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800C could not be reproduced. Both FeCrAl and MAX phase Ti2AlC form a protective alumina scale in steam. Therefore, commercial Ti2AlC that is not single phase, formed a much thicker oxide at 1200C in steam and significant TiO2, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich ? formation. The composition effects and critical limits to retaining protective scale formation at >1400C are still being evaluated.

  18. Material selection for accident tolerant fuel cladding

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

    Pint, B. A.; Terrani, K. A.; Yamamoto, Y.; Snead, L. L.

    2015-09-14

    Alternative cladding materials are being investigated for accident tolerance, which can be defined as >100X improvement (compared to current Zr-based alloys) in oxidation resistance in steam environments at ≥1200°C for short (≤4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800°C could not be reproduced. Both FeCrAl and MAX phase Ti2AlC form a protective alumina scale in steam. Therefore, commercial Ti2AlC that is not single phase, formed a much thicker oxide at 1200°C in steammore » and significant TiO2, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475°C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich α’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated.« less

  19. Type B Accident Investigation Of The February 25, 2009 Injury...

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

    New Mexico Type B Accident Investigation Of The February 25, 2009 Injury To A Passenger In An Electric Cart At The Waste Isolation Pilot Plant, Carlsbad, New Mexico April 1, ...

  20. Type B Accident Investigation Board Report on the Head Injury...

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

    New Mexico - August 25, 2004 Type B Accident Investigation Board Report on the Head Injury to a Miner at the Waste Isolation Pilot Plant, Carlsbad, New Mexico - August 25, ...

  1. Accident Investigation Reports - Type B | Department of Energy

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

    independent product of the Type B Accident Investigation Board appointed by James M. Turner, Ph.D., Manager of the U.S. Department of Energy, Oakland Operations Office. July 7,...

  2. Type A Accident Investigation of the June 21, 2001, Drilling...

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

    struck by part of the drilling rig (a "tong") that he was operating. PDF icon Type A Accident Investigation of the June 21, 2001, Drilling Rig Operator Injury at the Fermi ...

  3. Accidents and Intentional Destructive Acts Guidance and Requirements

    Broader source: Energy.gov [DOE]

    Accidents, as they relate to public and occupational health issues, include the determination of potential adverse effects on human health. The effects of Intentional Destructive Acts (IDAs), more...

  4. Type B Accident Investigation Board Report of the Savannah River...

    Energy Savers [EERE]

    Savannah River Site Hand Injury at the Salt Waste Processing Facility on October 6, 2009 Type B Accident Investigation Board Report of the Savannah River Site Hand Injury at the ...

  5. Type B Accident Investigation of the Savannah River Site Arc...

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

    of the Savannah River Site Arc Flash Burn Injury on September 23, 2009, in the D Area Powerhouse Type B Accident Investigation of the Savannah River Site Arc Flash Burn Injury on ...

  6. Type B Accident Investigation of the January 10, 2006, Flash...

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

    January 10, 2006, Flash Fire and Injury at the Savannah River National Laboratory Type B Accident Investigation of the January 10, 2006, Flash Fire and Injury at the Savannah River ...

  7. Type B Accident Investigation Board Report Grout Injection Operator...

    Energy Savers [EERE]

    and no damage to any structures inside the calvareum (i.e., no evidence of brain injury). Page 16 2.4. Investigation Readiness and Accident Scene Preservation The...

  8. Core coolability following loss-of-heat sink accidents. [LMFBR

    SciTech Connect (OSTI)

    Khatib-Rahbar, M.

    1983-01-01

    Most investigations of core meltdown scenarios in liquid metal fast breeder reactors (LMFBRs) have focused on accidents resulting from unprotected transients. In comparison, protected accidents which may lead to loss of core coolability and subsequent meltdown have received considerably less attention until recently. The sequence of events leading to the protected loss-of-heat sink (LOHS) accident is among other things dependent on plant type and design. The situation is vastly different in pool-type LMFBRs as compared to the loop-type design; this is as a result of major differences in the primary system configuration, coolant inventory and the structural design. The principal aim of the present paper is to address LOHS accidents in a loop-type LMFBR in regard to physical sequences of events which could lead to loss-of-core coolability and subsequent meltdown.

  9. Corrective Action Plan Addressing the Accident Investigation Report

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

    Corrective Action Plan Addressing the Accident Investigation Report of the February 5, 2014 Fire Event and the February 14, 2014 Radiological Release Event, Rev 1 Page 2 of 89 Table of Contents 1 Purpose ................................................................................................................................................................................................ 7 2 Summary of the

  10. Volume II - Accident and Operational Safety Analysis Handbook

    Energy Savers [EERE]

    208-2012 July 2012 DOE HANDBOOK Accident and Operational Safety Analysis Volume II: Operational Safety Analysis Techniques U.S. Department of Energy Washington, D.C. 20585 NOT MEASUREMENT SENSITIVE DOE-HDBK-1208-2012 i ACKNOWLEDGEMENTS This Department of Energy (DOE) Accident and Operational Safety Analysis Handbook was prepared under the sponsorship of the DOE Office of Health Safety and Security (HSS), Office of Corporate Safety Programs, and the Energy Facility Contractors Operating Group

  11. Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in

    Office of Scientific and Technical Information (OSTI)

    Pressurized Water Reactors (Journal Article) | SciTech Connect Journal Article: Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors Citation Details In-Document Search Title: Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors Authors: George, Nathan M [1] ; Terrani, Kurt A [1] ; Powers, Jeffrey J [1] ; Worrall, Andrew [1] ; Maldonado, G Ivan [1] + Show Author Affiliations ORNL Publication Date:

  12. Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in

    Office of Scientific and Technical Information (OSTI)

    Light Water Reactors (Conference) | SciTech Connect Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors Citation Details In-Document Search Title: Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors Authors: George, Nathan M [1] ; Maldonado, G Ivan [1] ; Terrani, Kurt A [1] ; Worrall, Andrew [1] + Show Author Affiliations ORNL Publication Date: 2014-01-01 OSTI Identifier: 1185572 DOE Contract Number:

  13. Emergency Response to a Transportation Accident Involving Radioactive

    Office of Environmental Management (EM)

    Material | Department of Energy Response to a Transportation Accident Involving Radioactive Material Emergency Response to a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown

  14. Accident analysis of heavy water cooled thorium breeder reactor (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect SciTech Connect Search Results Journal Article: Accident analysis of heavy water cooled thorium breeder reactor Citation Details In-Document Search Title: Accident analysis of heavy water cooled thorium breeder reactor Thorium has lately attracted considerable attention because it is accumulating as a by-product of large scale rare earth mining. The objective of research is to analyze transient behavior of a heavy water cooled thorium breeder that is designed by

  15. Severe accident progression perspectives based on IPE results

    SciTech Connect (OSTI)

    Lehner, J.R.; Lin, C.C.; Pratt, W.T.; Drouin, M.

    1996-08-01

    Accident progression perspectives were gathered from the level 2 PRA analyses (the analysis of the accident after core damage has occurred involving the containment performance and the radionuclide release from the containment) described in the IPE submittals. Insights related to the containment failure modes, the releases associated with those failure modes, and the factors responsible for the types of containment failures and release sizes reported were obtained. Complete results are discussed in NUREG-1560 and summarized here.

  16. Type B Accident Investigation of the July 14, 2005, Americium Contamination Accident at the Sigma Facility, Los Alamos National Laboratory

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type B Accident Investigation Board appointed by Edwin L. Wilmot, Manager of the Los Alamos Site Office of the National Nuclear Security Administration, U.S. Department of Energy.

  17. Type B Accident Investigation Board Report on the March 27, 1998, Rotating Shaft Accident at the Ames Laboratory, Ames, Iowa

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type B Accident Investigation Board appointed by John Kennedy, Acting Manager, Chicago Operations Office, U.S. Department of Energy (DOE).

  18. Surrogate Spent Nuclear Fuel Vibration Integrity Investigation

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Bevard, Bruce Balkcom; Howard, Rob L

    2014-01-01

    Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading encountered during road or rail shipment. ORNL has been developing testing capabilities that can be used to improve our understanding of the impacts of vibration loading on SNF integrity, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet nuclear industry and U.S. Nuclear Regulatory Commission needs in the area of safety of SNF storage and transportation operations.

  19. Railroad accident report: Head-on collision between Iowa Interstate Railroad Extra 470 West and Extra 406 East with release of hazardous materials near Altoona, Iowa, on July 30, 1988. Irregular report

    SciTech Connect (OSTI)

    Not Available

    1989-07-06

    About 11:40 a.m. central daylight saving time on July 30, 1988, Iowa Interstate Railroad Ltd. (IAIS) freight trains Extra 470 West and Extra 406 East collided head on within the yard limits of Altoona, Iowa, about 10 miles east of Des Moines, Iowa. All 5 locomotive units from both trains; 11 cars of Extra 406 East; and 3 cars, including two tank cars containing denatured alcohol, of Extra 470 West derailed. The denatured alcohol, which was released through the pressure relief valves and the manway domes of the two derailed tank cars, was ignited by the fire resulting from the collision of the locomotives. Both crew members of Extra 470 West were fatally injured; the two crew members of Extra 406 East were only slightly injured. The estimated damage (including lading) as a result of this accident exceeded $1 million. The major safety issues in the accident include operational methods employed by the IAIS, training and selection of train and engine personnel, supervisory oversight by the IAIS, design of closure fittings on hazardous materials rail tanks, and oversight of regional railroads by the Federal Railroad Administration.

  20. Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident

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

    Safety after a Traffic Accident to someone by E-mail Share Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Facebook Tweet about Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Twitter Bookmark Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Google Bookmark Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Delicious Rank Alternative Fuels Data Center: Natural Gas Safety after a

  1. Page

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

    Packaging and Transportation Packaging and Transportation Packaging and Transportation Radiological shipments are accomplished safely. Annually, about 400 million hazardous materials shipments occur in the United States by rail, air, sea, and land. Of these shipments, about three million are radiological shipments. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material/waste. Please click here to see Office of Packaging and Transportation Fiscal Year 2012

  2. Packaging and Transportation | Department of Energy

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

    Packaging and Transportation Packaging and Transportation Packaging and Transportation Radiological shipments are accomplished safely. Annually, about 400 million hazardous materials shipments occur in the United States by rail, air, sea, and land. Of these shipments, about three million are radiological shipments. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material/waste. Please click here to see Office of Packaging and Transportation Fiscal Year 2012

  3. Radiological Impact Assessment (RIA) following a postulated accident in PHWRS

    SciTech Connect (OSTI)

    Soni, N.; Kansal, M.; Rammohan, H. P.; Malhotra, P. K.

    2012-07-01

    Radiological Impact Assessment (RIA) following postulated accident i.e Loss of Coolant Accident (LOCA) with failed Emergency Core Cooling System (ECCS), performed as part of the reactor safety analysis of a typical 700 MWe Indian Pressurized Heavy Water Reactor(PHWR). The rationale behind the assessment is that the public needs to be protected in the event that the postulated accident results in radionuclide release outside containment. Radionuclides deliver dose to the human body through various pathways namely, plume submersion, exposure due to ground deposition, inhalation and ingestion. The total exposure dose measured in terms of total effective dose equivalent (TEDE) is the sum of doses to a hypothetical adult human at exclusion zone boundary by all the exposure pathways. The analysis provides the important inputs to decide upon the type of emergency counter measures to be adopted during the postulated accident. The importance of the various pathways in terms of contribution to the total effective dose equivalent(TEDE) is also assessed with respect to time of exposure. Inhalation and plume gamma dose are the major contributors towards TEDE during initial period of accident whereas ingestion and ground shine dose start dominating in TEDE in the extended period of exposure. Moreover, TEDE is initially dominated by I-131, Kr-88, Te-132, I-133 and Sr-89, whereas, as time progresses, Xe-133,I-131 and Te-132 become the main contributors. (authors)

  4. Literature Survey of Crude Oil Properties Relevant to Handling and Fire Safety in Transport.

    SciTech Connect (OSTI)

    Lord, David; Luketa, Anay; Wocken, Chad; Schlasner, Steve; Aulich, Ted; Allen, Ray; Rudeen, David Keith

    2015-03-01

    Several fiery rail accidents in 2013-2015 in the U.S. and Canada carrying crude oil produced from the Bakken region of North Dakota have raised questions at many levels on the safety of transporting this, and other types of crude oil, by rail. Sandia National Laboratories was commissioned by the U.S. Department of Energy to investigate the material properties of crude oils, and in particular the so-called "tight oils" like Bakken that comprise the majority of crude oil rail shipments in the U.S. at the current time. The current report is a literature survey of public sources of information on crude oil properties that have some bearing on the likelihood or severity of combustion events that may occur around spills associated with rail transport. The report also contains background information including a review of the notional "tight oil" field operating environment, as well a basic description of crude oils and potential combustion events in rail transport. This page intentionally blank

  5. ATWS at Browns Ferry Unit One - accident sequence analysis

    SciTech Connect (OSTI)

    Harrington, R.M.; Hodge, S.A.

    1984-07-01

    This study describes the predicted response of Unit One at the Browns Ferry Nuclear Plant to a postulated complete failure to scram following a transient occurrence that has caused closure of all Main Steam Isolation Valves (MSIVs). This hypothetical event constitutes the most severe example of the type of accident classified as Anticipated Transient Without Scram (ATWS). Without the automatic control rod insertion provided by scram, the void coefficient of reactivity and the mechanisms by which voids are formed in the moderator/coolant play a dominant role in the progression of the accident. Actions taken by the operator greatly influence the quantity of voids in the coolant and the effect is analyzed in this report. The progression of the accident sequence under existing and under recommended procedures is discussed. For the extremely unlikely cases in which equipment failure and wrongful operator actions might lead to severe core damage, the sequence of emergency action levels and the associated timing of events are presented.

  6. Multiscale Multiphysics Developments for Accident Tolerant Fuel Concepts

    SciTech Connect (OSTI)

    Gamble, K. A.; Hales, J. D.; Yu, J.; Zhang, Y.; Bai, X.; Andersson, D.; Patra, A.; Wen, W.; Tome, C.; Baskes, M.; Martinez, E.; Stanek, C. R.; Miao, Y.; Ye, B.; Hofman, G. L.; Yacout, A. M.; Liu, W.

    2015-09-01

    U3Si2 and iron-chromium-aluminum (Fe-Cr-Al) alloys are two of many proposed accident tolerant fuel concepts for the fuel and cladding, respectively. The behavior of these materials under normal operating and accident reactor conditions is not well known. As part of the Department of Energy’s Accident Tolerant Fuel High Impact Problem program significant work has been conducted to investigate the U3Si2 and FeCrAl behavior under reactor conditions. This report presents the multiscale and multiphysics effort completed in fiscal year 2015. The report is split into four major categories including Density Functional Theory Developments, Molecular Dynamics Developments, Mesoscale Developments, and Engineering Scale Developments. The work shown here is a compilation of a collaborative effort between Idaho National Laboratory, Los Alamos National Laboratory, Argonne National Laboratory and Anatech Corp.

  7. REAC/TS Radiation Accident Registry: An Overview

    SciTech Connect (OSTI)

    Doran M. Christensen, DO, REAC /TS Associate Director and Staff Physician Becky Murdock, REAC/TS Registry and Health Physics Technician

    2012-12-12

    Over the past four years, REAC/TS has presented a number of case reports from its Radiation Accident Registry. Victims of radiological or nuclear incidents must meet certain dose criteria for an incident to be categorized as an “accident” and be included in the registry. Although the greatest numbers of “accidents” in the United States that have been entered into the registry involve radiation devices, the greater percentage of serious accidents have involved sealed sources of one kind or another. But if one looks at the kinds of accident scenarios that have resulted in extreme consequence, i.e., death, the greater share of deaths has occurred in medical settings.

  8. DOE - NNSA/NFO -- News & Views Accident Trap

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

    Accident Traps Four Workers 1,800 Feet below Ground Photo - rescue from 1,800 feet below Over the past 42 years the Nevada Test Site has earned an excellent safety record. Thousands of workers have completed millions of accident-free hours at this heavy industry site. Since 1957 (no accurate records exist for 1951-56) there have been 46 fatalities on the Test Site, and six fatalities at other Test-Site-related locations. Being safety conscious and prepared minimizes the impact of the occasional

  9. Type A Accident Investigation of the July 15, 2004, Hanford 200...

    Energy Savers [EERE]

    July 15, 2004, Hanford 200 East Area Fall Fatality Type A Accident Investigation of the ... PDF icon Type A Accident Investigation of the July 15, 2004, Hanford 200 East Area Fall ...

  10. Type A Accident Investigation Board Report on the April 3, 1995...

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

    1, 1995 The accident under investigation occurred on April 3, 1995, at approximately 10:46 a.m. As a result of the accident, a Wackenhut Services, Incorporated-Savannah River Site ...

  11. Type A Accident Report of the June 26, 2009 Vehicle Fatality...

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

    Type A Accident Report of the June 26, 2009 Vehicle Fatality at Lawrence Livermore ... PDF icon Type A Accident Report of the June 26, 2009 Vehicle Fatality at Lawrence ...

  12. Calculation notes for surface leak resulting in pool, TWRS FSAR accident analysis

    SciTech Connect (OSTI)

    Hall, B.W.

    1996-09-25

    This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Surface Leaks Resulting in Pool.

  13. Calculation Notes for Subsurface Leak Resulting in Pool, TWRS FSAR Accident Analysis

    SciTech Connect (OSTI)

    Hall, B.W.

    1996-09-25

    This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Subsurface Leaks Resulting in Pool.

  14. Source terms for plutonium aerosolization from nuclear weapon accidents

    SciTech Connect (OSTI)

    Stephens, D.R.

    1995-07-01

    The source term literature was reviewed to estimate aerosolized and respirable release fractions for accidents involving plutonium in high-explosive (HE) detonation and in fuel fires. For HE detonation, all estimates are based on the total amount of Pu. For fuel fires, all estimates are based on the amount of Pu oxidized. I based my estimates for HE detonation primarily upon the results from the Roller Coaster experiment. For hydrocarbon fuel fire oxidation of plutonium, I based lower bound values on laboratory experiments which represent accident scenarios with very little turbulence and updraft of a fire. Expected values for aerosolization were obtained from the Vixen A field tests, which represent a realistic case for modest turbulence and updraft, and for respirable fractions from some laboratory experiments involving large samples of Pu. Upper bound estimates for credible accidents are based on experiments involving combustion of molten plutonium droplets. In May of 1991 the DOE Pilot Safety Study Program established a group of experts to estimate the fractions of plutonium which would be aerosolized and respirable for certain nuclear weapon accident scenarios.

  15. Evaluation of severe accident risks: Surry Unit 1

    SciTech Connect (OSTI)

    Breeding, R.J. ); Helton, J.C. ); Murfin, W.B. ); Smith, L.N. )

    1990-10-01

    In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe accidents at commercial nuclear power plants in the US reported in NUREG-1150, the Severe Accident Risk Reduction Program (SARRP) has completed a revised calculation of the risk to the general public from severe accidents at the Surry Power Station, Unit 1. This power plant, located in southeastern Virginia, is operated by the Virginia Electric Power Corp. The emphasis in this risk analysis was not on determining a so-called'' point estimate of risk. Rather, it was to determine the distribution of risk, and to discover the uncertainties that account for the breadth of this distribution. Off-site risk initiation by events, both internal to the power station and external to the power station were assessed. This document, Volume 3, Revision 1, Part 2, provides Appendices A through E to this report. These appendices contain: supporting information for the accident progression analysis; the source term analysis; the consequence analysis; risk results; and sampling information.

  16. Accident analysis of heavy water cooled thorium breeder reactor

    SciTech Connect (OSTI)

    Yulianti, Yanti; Su’ud, Zaki; Takaki, Naoyuki

    2015-04-16

    Thorium has lately attracted considerable attention because it is accumulating as a by-product of large scale rare earth mining. The objective of research is to analyze transient behavior of a heavy water cooled thorium breeder that is designed by Tokai University and Tokyo Institute of Technology. That is oxide fueled, PWR type reactor with heavy water as primary coolant. An example of the optimized core has relatively small moderator to fuel volume ratio (MFR) of 0.6 and the characteristics of the core are burn-up of 67 GWd/t, breeding ratio of 1.08, burn-up reactivity loss during cycles of < 0.2% dk/k, and negative coolant reactivity coefficient. One of the nuclear reactor accidents types examined here is Unprotected Transient over Power (UTOP) due to withdrawing of the control rod that result in the positive reactivity insertion so that the reactor power will increase rapidly. Another accident type is Unprotected Loss of Flow (ULOF) that caused by failure of coolant pumps. To analyze the reactor accidents, neutron distribution calculation in the nuclear reactor is the most important factor. The best expression for the neutron distribution is the Boltzmann transport equation. However, solving this equation is very difficult so that the space-time diffusion equation is commonly used. Usually, space-time diffusion equation is solved by employing a point kinetics approach. However, this approach is less accurate for a spatially heterogeneous nuclear reactor and the nuclear reactor with quite large reactivity input. Direct method is therefore used to solve space-time diffusion equation which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference method is solved by using iterative methods. The indication of UTOP accident is decreasing macroscopic absorption cross-section that results large external reactivity, and ULOF accident is indicated by decreasing coolant flow. The power reactor has a peak value before reactor has new balance condition. The analysis showed that temperatures of fuel and claddings during accident are still below limitations which are in secure condition.

  17. Level 1 Accident Report of the March 1, 2010 Bobcat Fatality at BPA's White

    Energy Savers [EERE]

    Bluffs Substation | Department of Energy Report of the March 1, 2010 Bobcat Fatality at BPA's White Bluffs Substation Level 1 Accident Report of the March 1, 2010 Bobcat Fatality at BPA's White Bluffs Substation March 31, 2010 On March 2, 2010 at the request of the Bonneville Power Administration (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to investigate an accident in which a supplemental labor contractor was fatally injured in a Bobcat/backhoe accident at the

  18. Type A Accident Investigation Board Report on the July 1, 2008, of the

    Energy Savers [EERE]

    Vehicle Fatality Accident-Western Area Power Marketing Administration | Department of Energy July 1, 2008, of the Vehicle Fatality Accident-Western Area Power Marketing Administration Type A Accident Investigation Board Report on the July 1, 2008, of the Vehicle Fatality Accident-Western Area Power Marketing Administration August 29, 2008 At approximately 1210 CDT, July 1, 2008, three Western Area Power Administration (Western) employees were traveling south on North Dakota gravel road 59th

  19. Type B Accident Investigation Board Report of the April 23, 1997,

    Energy Savers [EERE]

    Helicopter Accident at Raton Pass, Raton Pass, Colorado | Department of Energy April 23, 1997, Helicopter Accident at Raton Pass, Raton Pass, Colorado Type B Accident Investigation Board Report of the April 23, 1997, Helicopter Accident at Raton Pass, Raton Pass, Colorado May 1997 On April 23, 1997, a helicopter belonging to the Western Area Power Administration (Western) crashed near the summit of Raton Pass in southern Colorado. On April 24, 1997, Michael S. Cowan, Western's Chief Program

  20. Type B Accident Investigation of the July 12, 2007, Forklift and Pedestrian

    Energy Savers [EERE]

    Accident at the Paducah Gaseous Diffusion Plant, Portsmouth/Paducah Project Office | Department of Energy 2, 2007, Forklift and Pedestrian Accident at the Paducah Gaseous Diffusion Plant, Portsmouth/Paducah Project Office Type B Accident Investigation of the July 12, 2007, Forklift and Pedestrian Accident at the Paducah Gaseous Diffusion Plant, Portsmouth/Paducah Project Office April 14, 2008 On July 12, 2007, an employee at the Paducah Gaseous Diffusion Plant (PGDP) was walking alone during

  1. Type B Accident Investigation of the July 31, 2006, Fall from Ladder

    Energy Savers [EERE]

    Accident at the Lawrence Livermore National Laboratory, Livermore, California | Department of Energy 31, 2006, Fall from Ladder Accident at the Lawrence Livermore National Laboratory, Livermore, California Type B Accident Investigation of the July 31, 2006, Fall from Ladder Accident at the Lawrence Livermore National Laboratory, Livermore, California October 25, 2006 Early on the morning of July 31, 2006, an electrician in the Plant Engineering (PE) Department of the Lawrence Livermore

  2. Type B Accident Investigation on the February 17, 2004, Personal Injury

    Energy Savers [EERE]

    Accident, Bettis Atomic Power Laboratory | Department of Energy on the February 17, 2004, Personal Injury Accident, Bettis Atomic Power Laboratory Type B Accident Investigation on the February 17, 2004, Personal Injury Accident, Bettis Atomic Power Laboratory August 16, 2004 Prime contractors need to provide a safe work environment for the entire facility site, including parking lots and outdoor pedestrian walkways. Particular attention needs to be given to areas that must be traversed by

  3. Identification and evaluation of PWR in-vessel severe accident management strategies

    SciTech Connect (OSTI)

    Dukelow, J S [Pacific Northwest Lab., Richland, WA (United States); Harrison, D G [Jason Associates, Idaho Falls, ID (United States); Morgenstern, M [Battelle Human Affairs Research Center, Seattle, WA (United States)

    1992-03-01

    This reports documents work performed the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents. The selection and evaluation of strategies was limited to the in-vessel phase of the severe accident, i.e., after the initiation of core degradation and prior to RPV failure. A parallel project at BNL has been considering strategies applicable to the ex-vessel phase of PWR severe accidents.

  4. Accident Investigation Board (AIB) findings about the drum breach at WIPP

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

    Accident Investigation Board findings Accident Investigation Board (AIB) findings about the drum breach at WIPP WHEN: Apr 23, 2015 5:30 PM - 7:00 PM WHERE: Fuller Lodge 2132 Central Avenue, Los Alamos CATEGORY: Community TYPE: Meeting INTERNAL: Calendar Login Event Description The Department of Energy will host a town hall meeting to discuss the Accident Investigation Board findings from the Feb. 14, 2014, drum breach at the Waste Isolation Pilot Plant. Members of the Accident Investigation

  5. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    RITTMANN, P.D.

    1999-10-07

    Three bounding accidents postdated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing, and a hydrogen explosion. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  6. Microsoft Word - 2015.06.22 - Report to Congress - Accident Tolerant Fuels

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

    ROADMAP: DEVELOPMENT OF LWR FUELS WITH ENHANCED ACCIDENT TOLERANCE Page i Development of Light Water Reactor Fuels with Enhanced Accident Tolerance Report to Congress April 2015 United States Department of Energy Washington, DC 20585 _____________________________________________________________________________ ROADMAP: DEVELOPMENT OF LWR FUELS WITH ENHANCED ACCIDENT TOLERANCE Page i Message from the Assistant Secretary for Nuclear Energy In the Senate Appropriations Committee Report (Senate

  7. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    2000-01-10

    Four bounding accidents postulated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing a hydrogen explosion, and a fire breaching filter vessel and enclosure. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  8. Agenda of critical issues: coal price and availability. Final report. [Includes effect of legislation, sulfur content and rail transport costs

    SciTech Connect (OSTI)

    Tennican, M.L.; Wayland, R.E.; Weinstein, D.M.

    1984-10-01

    Temple, Barker, and Sloane, Inc. developed an agenda of critical issues regarding future coal prices and coal availability for EPRI. TBS interviewed nearly 50 utility, coal company, and railroad officials, academic experts, and coal consultants; held a one-day participatory workshop; and conducted a literature review and follow-up interviews with selected utilities. TBS found four causes of uncertainty in the utility industry over future coal prices. First, the acid deposition proposals in Congress vary in terms of the structure of the legislation, the costs of compliance, and the impact on coal prices; in turn these uncertainties impede utility fuel planning and decision making. Second, powerplant-specific factors will have a major impact on whether utilities switch or scrub in response to acid deposition legislation; existing analyses do not capture these factors. The most important powerplant-specific factors are matching unit characteristics with coal specifications, retrofit scrubber costs, and differing state regulatory environments. Third, TBS found that utility fuel managers have great uncertainty over the availability and future cost of compliance coal. TBS estimated that the existing production capacity of eastern compliance coal is at least twice as high as current production. Fourth, TBS concluded that uncertainty over future coal transportation rates was a major reason for utilities' uncertainty over future delivered prices of coal. Critical transportation-related issues are the strategic and tactical response of eastern coal producers to the Staggers Act; the impact on rail rates of the sale of Conrail, of possible transcontinental mergers, and of multi-modal mergers; and the future pricing policies that eastern railroads will adopt in response to imports of Colombian coal. 21 references.

  9. A Fully Automated Method for CT-on-Rails-Guided Online Adaptive Planning for Prostate Cancer Intensity Modulated Radiation Therapy

    SciTech Connect (OSTI)

    Li, Xiaoqiang; Quan, Enzhuo M.; Li, Yupeng; Pan, Xiaoning; Zhou, Yin; Wang, Xiaochun; Du, Weiliang; Kudchadker, Rajat J.; Johnson, Jennifer L.; Kuban, Deborah A.; Lee, Andrew K.; Zhang, Xiaodong

    2013-08-01

    Purpose: This study was designed to validate a fully automated adaptive planning (AAP) method which integrates automated recontouring and automated replanning to account for interfractional anatomical changes in prostate cancer patients receiving adaptive intensity modulated radiation therapy (IMRT) based on daily repeated computed tomography (CT)-on-rails images. Methods and Materials: Nine prostate cancer patients treated at our institution were randomly selected. For the AAP method, contours on each repeat CT image were automatically generated by mapping the contours from the simulation CT image using deformable image registration. An in-house automated planning tool incorporated into the Pinnacle treatment planning system was used to generate the original and the adapted IMRT plans. The cumulative dosevolume histograms (DVHs) of the target and critical structures were calculated based on the manual contours for all plans and compared with those of plans generated by the conventional method, that is, shifting the isocenters by aligning the images based on the center of the volume (COV) of prostate (prostate COV-aligned). Results: The target coverage from our AAP method for every patient was acceptable, while 1 of the 9 patients showed target underdosing from prostate COV-aligned plans. The normalized volume receiving at least 70 Gy (V{sub 70}), and the mean dose of the rectum and bladder were reduced by 8.9%, 6.4 Gy and 4.3%, 5.3 Gy, respectively, for the AAP method compared with the values obtained from prostate COV-aligned plans. Conclusions: The AAP method, which is fully automated, is effective for online replanning to compensate for target dose deficits and critical organ overdosing caused by interfractional anatomical changes in prostate cancer.

  10. Analysis of the FeCrAl Accident Tolerant Fuel Concept Benefits during BWR Station Blackout Accidents

    SciTech Connect (OSTI)

    Robb, Kevin R

    2015-01-01

    Iron-chromium-aluminum (FeCrAl) alloys are being considered for fuel concepts with enhanced accident tolerance. FeCrAl alloys have very slow oxidation kinetics and good strength at high temperatures. FeCrAl could be used for fuel cladding in light water reactors and/or as channel box material in boiling water reactors (BWRs). To estimate the potential safety gains afforded by the FeCrAl concept, the MELCOR code was used to analyze a range of postulated station blackout severe accident scenarios in a BWR/4 reactor employing FeCrAl. The simulations utilize the most recently known thermophysical properties and oxidation kinetics for FeCrAl. Overall, when compared to the traditional Zircaloy-based cladding and channel box, the FeCrAl concept provides a few extra hours of time for operators to take mitigating actions and/or for evacuations to take place. A coolable core geometry is retained longer, enhancing the ability to stabilize an accident. Finally, due to the slower oxidation kinetics, substantially less hydrogen is generated, and the generation is delayed in time. This decreases the amount of non-condensable gases in containment and the potential for deflagrations to inhibit the accident response.

  11. Type B Accident Investigation Board Report of the January 20, 1998, Electrical Accident at the Casa Grande Substation,South of Phoenix, Arizona

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type-B Accident Investigation Board appointed by Michael S.Cowan, Chief Program Officer, Western Area Power Administration.

  12. Mitigation of Severe Accident Consequences Using Inherent Safety Principles

    SciTech Connect (OSTI)

    R. A. Wigeland; J. E. Cahalan

    2009-12-01

    Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability of occurrence are typically handled without consequence through reliable engineering systems and good design practices. For accidents of lower probability, the initiating events are characterized by larger and more numerous challenges to the reactor system, such as failure of one or more major engineered systems and can also include a failure to scram the reactor in response. As the initiating conditions become more severe, they have the potential for creating serious consequences of potential safety significance, including fuel melting, fuel pin disruption and recriticality. If the progression of such accidents is not mitigated by design features of the reactor, energetic events and dispersal of radioactive materials may result. For severe accidents, there are several approaches that can be used to mitigate the consequences of such severe accident initiators, which typically include fuel pin failures and core disruption. One approach is to increase the reliability of the reactor protection system so that the probability of an ATWS event is reduced to less than 1 x 10-6 per reactor year, where larger accident consequences are allowed, meeting the U.S. NRC goal of relegating such accident consequences as core disruption to these extremely low probabilities. The main difficulty with this approach is to convincingly test and guarantee such increased reliability. Another approach is to increase the redundancy of the reactor scram system, which can also reduce the probability of an ATWS event to a frequency of less than 1 x 10-6 per reactor year or lower. The issues with this approach are more related to reactor core design, with the need for a greater number of control rod positions in the reactor core and the associated increase in complexity of the reactor protection system. A third approach is to use the inherent reactivity feedback that occurs in a fast reactor to automatically respond to the change in reactor conditions and to result in a benign response to these events. This approach has the advantage of being relatively simple to implement, and does not face the issue of reliability since only fundamental physical phenomena are used in a passive manner, not active engineered systems. However, the challenge is to present a convincing case that such passive means can be implemented and used. The purpose of this paper is to describe this third approach in detail, the technical basis and experimental validation for the approach, and the resulting reactor performance that can be achieved for ATWS events.

  13. Electrical equipment performance under severe accident conditions (BWR/Mark 1 plant analysis): Summary report

    SciTech Connect (OSTI)

    Bennett, P.R.; Kolaczkowski, A.M.; Medford, G.T.

    1986-09-01

    The purpose of the Performance Evaluation of Electrical Equipment during Severe Accident States Program is to determine the performance of electrical equipment, important to safety, under severe accident conditions. In FY85, a method was devised to identify important electrical equipment and the severe accident environments in which the equipment was likely to fail. This method was used to evaluate the equipment and severe accident environments for Browns Ferry Unit 1, a BWR/Mark I. Following this work, a test plan was written in FY86 to experimentally determine the performance of one selected component to two severe accident environments.

  14. INDUSTRIAL/MILITARY ACTIVITY-INITIATED ACCIDENT SCREENING ANALYSIS

    SciTech Connect (OSTI)

    D.A. Kalinich

    1999-09-27

    Impacts due to nearby installations and operations were determined in the Preliminary MGDS Hazards Analysis (CRWMS M&O 1996) to be potentially applicable to the proposed repository at Yucca Mountain. This determination was conservatively based on limited knowledge of the potential activities ongoing on or off the Nevada Test Site (NTS). It is intended that the Industrial/Military Activity-Initiated Accident Screening Analysis provided herein will meet the requirements of the ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987) in establishing whether this external event can be screened from further consideration or must be included as a design basis event (DBE) in the development of accident scenarios for the Monitored Geologic Repository (MGR). This analysis only considers issues related to preclosure radiological safety. Issues important to waste isolation as related to impact from nearby installations will be covered in the MGR performance assessment.

  15. Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report

    SciTech Connect (OSTI)

    Lori Braase

    2013-01-01

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: • Give “priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools.” • Give “special technical emphasis and funding priority…to activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors.” • Report “to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020.” Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and Commercialization. The activities performed during the feasibility assessment phase include laboratory scale experiments; fuel performance code updates; and analytical assessment of economic, operational, safety, fuel cycle, and environmental impacts of the new concepts. The development and qualification stage will consist of fuel fabrication and large scale irradiation and safety basis testing, leading to qualification and ultimate NRC licensing of the new fuel. The commercialization phase initiates technology transfer to industry for implementation. Attributes for fuels with enhanced accident tolerance include improved reaction kinetics with steam and slower hydrogen generation rate, while maintaining acceptable cladding thermo-mechanical properties; fuel thermo-mechanical properties; fuel-clad interactions; and fission-product behavior. These attributes provide a qualitative guidance for parameters that must be considered in the development of fuels and cladding with enhanced accident tolerance. However, quantitative metrics must be developed for these attributes. To initiate the quantitative metrics development, a Light Water Reactor Enhanced Accident Tolerant Fuels Metrics Development Workshop was held October 10-11, 2012, in Germantown, Maryland. This document summarizes the structure and outcome of the two-day workshop. Questions regarding the content can be directed to Lori Braase, 208-526-7763, lori.braase@inl.gov.

  16. In a mining accident, first responders are working against

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

    a mining accident, first responders are working against the clock and against a myriad of dangers such as debris, poisonous gases, flooding, explosive vapors, and unstable structures to assess the situation and rescue trapped miners. These unknown and potentially deadly conditions create a challenge for first responders and often limit their ability to assess the situation and respond in a timely matter. There is a need for a robotic system that could be used to support a mine rescue team,

  17. Ion irradiation testing of Improved Accident Tolerant Cladding Materials

    SciTech Connect (OSTI)

    Anderoglu, Osman; Tesmer, Joseph R.; Maloy, Stuart A.

    2014-01-14

    This report summarizes the results of ion irradiations conducted on two FeCrAl alloys (named as ORNL A&B) for improving the accident tolerance of LWR nuclear fuel cladding. After irradiation with 1.5 MeV protons to ~0.5 to ~1 dpa and 300°C nanoindentations were performed on the cross-sections along the ion range. An increase in hardness was observed in both alloys. Microstructural analysis shows radiation induced defects.

  18. Accident Investigation of the October 1, 2013, Tice Electric Company

    Energy Savers [EERE]

    Employee Fatality near Patrick's Knob Radio Station, Bonneville Power Administration | Department of Energy October 1, 2013, Tice Electric Company Employee Fatality near Patrick's Knob Radio Station, Bonneville Power Administration Accident Investigation of the October 1, 2013, Tice Electric Company Employee Fatality near Patrick's Knob Radio Station, Bonneville Power Administration November 22, 2013 On October 2, 2013, at the request of the Bonneville Power Administration (BPA) Chief Safety

  19. Type B Accident Investigation At Washington Closure Hanford, LLC, Employee

    Energy Savers [EERE]

    Fall Injury on July 1, 2009, At The 336 Building, Hanford Site, Washington | Department of Energy At Washington Closure Hanford, LLC, Employee Fall Injury on July 1, 2009, At The 336 Building, Hanford Site, Washington Type B Accident Investigation At Washington Closure Hanford, LLC, Employee Fall Injury on July 1, 2009, At The 336 Building, Hanford Site, Washington July 30, 2009 During D4 project demolition preparation work on the morning of July 1, 2009, in Hanford's 300 Area, a millwright

  20. Type B Accident Investigation Board Report Subcontractor Radioactive

    Energy Savers [EERE]

    Release During Transportation Activities on May 14, 2004, Bechtel Jacobs Company LLC, Oak Ridge, Tennessee (Amended) | Department of Energy Subcontractor Radioactive Release During Transportation Activities on May 14, 2004, Bechtel Jacobs Company LLC, Oak Ridge, Tennessee (Amended) Type B Accident Investigation Board Report Subcontractor Radioactive Release During Transportation Activities on May 14, 2004, Bechtel Jacobs Company LLC, Oak Ridge, Tennessee (Amended) August 17, 2004 On Friday,

  1. Type B Accident Investigation Board Report of the Brookhaven National

    Energy Savers [EERE]

    Laboratory Employee Injury at Building 1005H on October 9, 2009 | Department of Energy of the Brookhaven National Laboratory Employee Injury at Building 1005H on October 9, 2009 Type B Accident Investigation Board Report of the Brookhaven National Laboratory Employee Injury at Building 1005H on October 9, 2009 December 11, 2009 On the afternoon of October 9, 2009, a Lead Rigger for Brookhaven Science Associates (BSA), LLC at the Brookhaven National laboratory (BNL) wasinjured while at the

  2. Type B Accident Investigation Report on the Exertional Heat Illnesses

    Energy Savers [EERE]

    during SPOTC 2006 at the National Training Center in Albuquerque, New Mexico, July 13, 2006 | Department of Energy on the Exertional Heat Illnesses during SPOTC 2006 at the National Training Center in Albuquerque, New Mexico, July 13, 2006 Type B Accident Investigation Report on the Exertional Heat Illnesses during SPOTC 2006 at the National Training Center in Albuquerque, New Mexico, July 13, 2006 July 13, 2006 This Report addresses three injuries that occurred on June 15, 2006 during the

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

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

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

  4. Cold Vacuum Drying facility design basis accident analysis documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  5. Cofrentes NPP activities on PSA and severe accident analysis

    SciTech Connect (OSTI)

    Suarez, J.; Borondo, L.; Garcia, P.J.

    1996-07-01

    Cofrentes NPP (CNPP) has developed a Level 1 PSA with the following scope: analysis of internal events, with the reactor initially operating at power, internal and external flooding risk analysis; internal fire risk analysis; reliability analysis of the containment heat removal and containment isolation systems. Level 1 CNPP-PSA results reveal that total core damage frequency in CNPP is less than other similar BWR/6 plants. The CNPP-PSA related activities and applications being carried out currently are: adjusting of MAAP 3.0B, revision 10, on VAX and PC; acquisition of MAAP 4; development of Level1/Level2-PSA interface; seismic site categorization for the IPEEE; prioritization of motor operated valves related to GL-89/10, complementary analysis for exemption to some 10CFR50 App. J requirements; Q-List grading; reliability-centered maintenance; maintenance rule support; on-line maintenance support, off-line risk-monitor development, PSA applicability to the 10CFR50 App. R requirements, analysis of the frequency of mis-oriented fuel bundle event, etc. About severe accident management, CNPP, as part of the Spanish-BWROG, is currently analyzing the generic products of the US-BWROG AMG in order to generate their specific ones. Also, in this group BWR, the development of tools to simulate accident scenarios beyond core damage will be studied and a training process oriented to warrant the optimum use of new EOP/AMG in accident scenarios will be implemented.

  6. Analysis of PWR RCS Injection Strategy During Severe Accident

    SciTech Connect (OSTI)

    Wang, S.-J. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, K.-S. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, S.-C. [Taiwan Power Company, Taiwan (China)

    2004-05-15

    Reactor coolant system (RCS) injection is an important strategy for severe accident management of a pressurized water reactor (PWR) system. Maanshan is a typical Westinghouse PWR nuclear power plant (NPP) with large, dry containment. The severe accident management guideline (SAMG) of Maanshan NPP is developed based on the Westinghouse Owners Group (WOG) SAMG.The purpose of this work is to analyze the RCS injection strategy of PWR system in an overheated core condition. Power is assumed recovered as the vessel water level drops to the bottom of active fuel. The Modular Accident Analysis Program version 4.0.4 (MAAP4) code is chosen as a tool for analysis. A postulated station blackout sequence for Maanshan NPP is cited as a reference case for this analysis. The hot leg creep rupture occurs during the mitigation action with immediate injection after power recovery according to WOG SAMG, which is not desired. This phenomenon is not considered while developing the WOG SAMG. Two other RCS injection methods are analyzed by using MAAP4. The RCS injection strategy is modified in the Maanshan SAMG. These results can be applied for typical PWR NPPs.

  7. KERENA safety concept in the context of the Fukushima accident

    SciTech Connect (OSTI)

    Zacharias, T.; Novotny, C.; Bielor, E.

    2012-07-01

    Within the last three years AREVA NP and E.On KK finalized the basic design of KERENA which is a medium sized innovative boiling water reactor, based on the operational experience of German BWR nuclear power plants (NPPs). It is a generation III reactor design with a net electrical output of about 1250 MW. It combines active safety equipment of service-proven designs with new passive safety components, both safety classified. The passive systems utilize basic laws of physics, such as gravity and natural convection, enabling them to function without electric power. Even actuation of these systems is performed thanks to basic physic laws. The degree of diversity in component and system design, achieved by combining active and passive equipment, results in a very low core damage frequency. The Fukushima accident enhanced the world wide discussion about the safety of operating nuclear power plants. World wide stress tests for operating nuclear power plants are being performed embracing both natural and man made hazards. Beside the assessment of existing power plants, also new designs are analyzed regarding the system response to beyond design base accidents. KERENA's optimal combination of diversified cooling systems (active and passive) allows passing efficiently such tests, with a high level of confidence. This paper describes the passive safety components and the KERENA reactor behavior after a Fukushima like accident. (authors)

  8. Environmental Assessment for the Transfer of 1100 AREA, Southern Rail Connection and Rolling Stock, Hanford Site, Richland, Washington

    SciTech Connect (OSTI)

    N /A

    1998-08-01

    This environmental assessment (EA) has been prepared to assess potential environmental impacts associated with the U.S. Department of Energy's proposed action: the transfer of the 1100 Area, southern rail connection and rolling stock to a non-federal entity. Impact information contained herein will be used by the U.S. Department of Energy, Richland Operations Office Manager, to determine if the proposed action is a major federal action significantly affecting the quality of the human environment. If the proposed action is determined to be major and significant, an environmental impact statement will be prepared. If the proposed action is determined not to be major and significant, a Finding of No Significant Impact (FONSI) will be issued and the action can proceed. Criteria used to evaluate significance can be found in Title 40, Code of Federal Regulations (CFR) 1508.27. This EA was prepared in compliance with the ''National Environmental Policy Act'' (NEPA) of 1969, as amended, the Council on Environmental Quality (CEQ) Regulations for Implementing the Procedural Provisions of NEPA (40 CFR 1500-1508), and the U.S. Department of Energy Implementing Procedures for NEPA (10 CFR 1021). The following is a description of each section of the EA. (1) Purpose and Need for Action. This provides a brief statement concerning the problem or opportunity the U.S. Department of Energy is addressing with the proposed action. As necessary, background information is provided. (2) Description of the Proposed Action. A description with sufficient detail to identify potential environmental impacts is provided. (3) Alternatives to the Proposed Action. Reasonable alternative actions, which would address the Purpose and Need, are described. A no action alternative, as required by 10 CFR 1021, also is described. (4) Affected Environment. This provides a brief description of the locale in which the proposed action takes place, and which may be environmentally impacted. (5) Environmental Impacts. The range of environmental impacts, beneficial and adverse, are described for the proposed action. Impacts of alternatives briefly are discussed. (6) Permits and Regulatory Requirements. A brief description of permits and regulatory requirements for the proposed action is provided. (7) Organizations Consulted. Any outside agencies, groups, or individuals contacted as part of environmental assessment documentation preparation are listed. (8) References. Documents used to provide information or data are listed. The appendices contain additional information necessary to support an understanding of the proposed action, alternatives, and potential impacts is provided. Comments resulting from review of the environmental assessment by states and tribes or other stakeholders and the response to those comments will be included in the appendices.

  9. Another Look at the Relationship Between Accident- and Encroachment-Based Approaches to Run-Off-the-Road Accidents Modeling

    SciTech Connect (OSTI)

    Miaou, Shaw-Pin

    1997-08-01

    The purpose of this study was to look for ways to combine the strengths of both approaches in roadside safety research. The specific objectives were (1) to present the encroachment-based approach in a more systematic and coherent way so that its limitations and strengths can be better understood from both statistical and engineering standpoints, and (2) to apply the analytical and engineering strengths of the encroachment-based thinking to the formulation of mean functions in accident-based models.

  10. AN EVALUATION OF PYROLYSIS OIL PROPERTIES AND CHEMISTRY AS RELATED TO PROCESS AND UPGRADE CONDITIONS WITH SPECIAL CONSIDERATION TO PIPELINE SHIPMENT

    SciTech Connect (OSTI)

    Bunting, Bruce G; Boyd, Alison C

    2012-01-01

    One factor limiting the development of commercial biomass pyrolysis is challenges related to the transportation of the produced pyrolysis oil. The oil has different chemical and physical properties than crude oil, including more water and oxygen and has lower H/C ratio, higher specific gravity and density, higher acidity, and lower energy content. These differences could limit its ability to be transported by existing petroleum pipelines. Pyrolysis oil can also be treated, normally by catalytic hydrodeoxygenation, and approaches crude oil and petroleum condensates at higher severity levels. This improvement also results in lower liquid yield and high hydrogen consumption. Biomass resources for pyrolysis are expected to become plentiful and widely distributed in the future, mainly through the use of crop residuals and growing of energy crops such as perennial grasses, annual grasses, and woody crops. Crude oil pipelines are less well distributed and, when evaluated on a county level, could access about 18% of the total biomass supply. States with high potential include Texas, Oklahoma, California, and Louisiana. In this study, published data on pyrolysis oil was compiled into a data set along with bio-source source material, pyrolysis reactor conditions, and upgrading conditions for comparison to typical crude oils. Data of this type is expected to be useful in understanding the properties and chemistry and shipment of pyrolysis oil to refineries, where it can be further processed to fuel or used as a source of process heat.

  11. Transportation risk assessment for the shipment of irradiated FFTF tritium target assemblies from the Hanford Site to the Savannah River Site

    SciTech Connect (OSTI)

    Nielsen, D. L.

    1997-11-19

    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 report examines the potential health and safety impacts associated with transportation of irradiated tritium targets from FFTF to the Savannah River Site for processing at the Tritium Extraction Facility. Potential risks to workers and members of the public during normal transportation and accident conditions are assessed.

  12. Rail Coal Transportation Rates

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Recurring Reserves Stocks All reports Browse by Tag Alphabetical Frequency Tag Cloud Data For: 2001 Next Release Date: October 2003 U. S. Coal-Producing Districts...

  13. Rail Coal Transportation Rates

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Previous Data Years Year: 2013 2011 2010 2008 2002 Go Background and Methodology The data ... The initial report on coal transportation rates covered the years 2001 through 2008, ...

  14. Rail Coal Transportation Rates

    Gasoline and Diesel Fuel Update (EIA)

    their confidential Carload Waybill Sample. While valuable, due to the statistical nature of the Waybill data, much of the information had to be withheld for confidentiality...

  15. Rail Coal Transportation Rates

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    on research by the U.S. Department of Energy and was only incorporated into the GIS analysis below; it is not in any other elements of this report. See Methodology for greater...

  16. Key Parameters for Operator Diagnosis of BWR Plant Condition during a Severe Accident

    SciTech Connect (OSTI)

    Clayton, Dwight A.; Poore, III, Willis P.

    2015-01-01

    The objective of this research is to examine the key information needed from nuclear power plant instrumentation to guide severe accident management and mitigation for boiling water reactor (BWR) designs (specifically, a BWR/4-Mark I), estimate environmental conditions that the instrumentation will experience during a severe accident, and identify potential gaps in existing instrumentation that may require further research and development. This report notes the key parameters that instrumentation needs to measure to help operators respond to severe accidents. A follow-up report will assess severe accident environmental conditions as estimated by severe accident simulation model analysis for a specific US BWR/4-Mark I plant for those instrumentation systems considered most important for accident management purposes.

  17. Safety evaluation of MHTGR licensing basis accident scenarios

    SciTech Connect (OSTI)

    Kroeger, P.G.

    1989-04-01

    The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

  18. Markov Model of Accident Progression at Fukushima Daiichi

    SciTech Connect (OSTI)

    Cuadra A.; Bari R.; Cheng, L-Y; Ginsberg, T.; Lehner, J.; Martinez-Guridi, G.; Mubayi, V.; Pratt, T.; Yue, M.

    2012-11-11

    On March 11, 2011, a magnitude 9.0 earthquake followed by a tsunami caused loss of offsite power and disabled the emergency diesel generators, leading to a prolonged station blackout at the Fukushima Daiichi site. After successful reactor trip for all operating reactors, the inability to remove decay heat over an extended period led to boil-off of the water inventory and fuel uncovery in Units 1-3. A significant amount of metal-water reaction occurred, as evidenced by the quantities of hydrogen generated that led to hydrogen explosions in the auxiliary buildings of the Units 1 & 3, and in the de-fuelled Unit 4. Although it was assumed that extensive fuel damage, including fuel melting, slumping, and relocation was likely to have occurred in the core of the affected reactors, the status of the fuel, vessel, and drywell was uncertain. To understand the possible evolution of the accident conditions at Fukushima Daiichi, a Markov model of the likely state of one of the reactors was constructed and executed under different assumptions regarding system performance and reliability. The Markov approach was selected for several reasons: It is a probabilistic model that provides flexibility in scenario construction and incorporates time dependence of different model states. It also readily allows for sensitivity and uncertainty analyses of different failure and repair rates of cooling systems. While the analysis was motivated by a need to gain insight on the course of events for the damaged units at Fukushima Daiichi, the work reported here provides a more general analytical basis for studying and evaluating severe accident evolution over extended periods of time. This work was performed at the request of the U.S. Department of Energy to explore 'what-if' scenarios in the immediate aftermath of the accidents.

  19. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    SciTech Connect (OSTI)

    Bertini, H.W.

    1980-04-01

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

  20. Accident Investigation of the February 5, 2014, Underground Salt Haul Truck

    Energy Savers [EERE]

    Fire at the Waste Isolation Pilot Plant, Carlsbad NM | Department of Energy 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM March 26, 2014 Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM The U.S. Department of Energy (DOE) Accident Prevention

  1. Accident Investigation of the June 1, 2013, Stairway Fall Resulting in a

    Energy Savers [EERE]

    Federal Employee Fatality at DOE Headquarters Germantown, Maryland | Department of Energy , 2013, Stairway Fall Resulting in a Federal Employee Fatality at DOE Headquarters Germantown, Maryland Accident Investigation of the June 1, 2013, Stairway Fall Resulting in a Federal Employee Fatality at DOE Headquarters Germantown, Maryland On June 28, 2013, an Accident Investigation Board was appointed to investigate an accident at the Department of Energy Germantown Headquarters facility, on June

  2. Temperature of aircraft cargo flame exposure during accidents involving fuel spills

    SciTech Connect (OSTI)

    Mansfield, J.A.

    1993-01-01

    This report describes an evaluation of flame exposure temperatures of weapons contained in alert (parked) bombers due to accidents that involve aircraft fuel fires. The evaluation includes two types of accident, collisions into an alert aircraft by an aircraft that is on landing or take-off, and engine start accidents. Both the B-1B and B-52 alert aircraft are included in the evaluation.

  3. Next-generation nuclear fuel withstands high-temperature accident

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

    conditions U.S. DEPARTMENT OF ENERGY IDAHO FALLS, IDAHO, 83403 For Immediate Release: Sept. 25, 2013 Media Contacts: Teri Ehresman, 208-526-7785 teri.ehresman@inl.gov Bill Cabage (ORNL), 865-574-4399, cabagewh@ornl.gov Next-generation nuclear fuel withstands high-temperature accident conditions IDAHO FALLS - A safer and more efficient nuclear fuel is on the horizon. A team of researchers at the U.S. Department of Energy's Idaho National Laboratory (INL) and Oak Ridge National Laboratory

  4. Analysis of Three Mile Island-Unit 2 accident

    SciTech Connect (OSTI)

    Not Available

    1980-03-01

    The Nuclear Safety Analysis Center (NSAC) of the Electric Power Research Institute has analyzed the Three Mile Island-2 accident. Early results of this analysis were a brief narrative summary, issued in mid-May 1979 and an initial version of this report issued later in 1979 as noted in the Foreword. The present report is a revised version of the 1979 report, containing summaries, a highly detailed sequence of events, a comparison of that sequence of events with those from other sources, 25 appendices, references and a list of abbreviations and acronyms. A matrix of equipment and system actions is included as a folded insert.

  5. Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario

    SciTech Connect (OSTI)

    Rempe, J. L.; Knudson, D. L.; Lutz, R. J.

    2015-09-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) and Fukushima Daiichi Units 1, 2, and 3 nuclear power plants demonstrate the critical importance of accurate, relevant, and timely information on the status of reactor systems during a severe accident. These events also highlight the critical importance of understanding and focusing on the key elements of system status information in an environment where operators may be overwhelmed with superfluous and sometimes conflicting data. While progress in these areas has been made since TMI-2, the events at Fukushima suggests that there may still be a potential need to ensure that critical plant information is available to plant operators. Recognizing the significant technical and economic challenges associated with plant modifications, it is important to focus on instrumentation that can address these information critical needs. As part of a program initiated by the Department of Energy, Office of Nuclear Energy (DOE-NE), a scoping effort was initiated to assess critical information needs identified for severe accident management and mitigation in commercial Light Water Reactors (LWRs), to quantify the environment instruments monitoring this data would have to survive, and to identify gaps where predicted environments exceed instrumentation qualification envelop (QE) limits. Results from the Pressurized Water Reactor (PWR) scoping evaluations are documented in this report. The PWR evaluations were limited in this scoping evaluation to quantifying the environmental conditions for an unmitigated Short-Term Station BlackOut (STSBO) sequence in one unit at the Surry nuclear power station. Results were obtained using the MELCOR models developed for the US Nuclear Regulatory Commission (NRC)-sponsored State of the Art Consequence Assessment (SOARCA) program project. Results from this scoping evaluation indicate that some instrumentation identified to provide critical information would be exposed to conditions that significantly exceeded QE limits for extended time periods for the low frequency STSBO sequence evaluated in this study. It is recognized that the core damage frequency (CDF) of the sequence evaluated in this scoping effort would be considerably lower if evaluations considered new FLEX equipment being installed by industry. Nevertheless, because of uncertainties in instrumentation response when exposed to conditions beyond QE limits and alternate challenges associated with different sequences that may impact sensor performance, it is recommended that additional evaluations of instrumentation performance be completed to provide confidence that operators have access to accurate, relevant, and timely information on the status of reactor systems for a broad range of challenges associated with risk important severe accident sequences.

  6. Fission product release from irradiated LWR fuel under accident conditions

    SciTech Connect (OSTI)

    Strain, R.V.; Sanecki, J.E.; Osborne, M.F.

    1984-01-01

    Fission product release from irradiated LWR fuel is being studied by heating fuel rod segments in flowing steam and an inert carrier gas to simulate accident conditions. Fuels with a range of irradiation histories are being subjected to several steam flow rates over a wide range of temperatures. Fission product release during each test is measured by gamma spectroscopy and by detailed examination of the collection apparatus after the test has been completed. These release results are complemented by a detailed posttest examination of samples of the fuel rod segment. Results of release measurements and fuel rod characterizations for tests at 1400 through 2000/sup 0/C are presented in this paper.

  7. Advance plant severe accident/thermal hydraulic issues for ACRS

    SciTech Connect (OSTI)

    Kress, T.S.

    1994-09-01

    The ACRS has been reviewing various advance plant designs for certification. The most active reviews have been for the ABWR, AP600, and System 80+. We have completed the reviews for ABWR and System 80+ and are presently concentrating on AP600. The ACRS gave essentially unqualified certification approval for the two completed reviews, yet,,during the process of review a number of issues arose and the plant designs changed somewhat to accommodate some of the ACRS concerns. In this talk, I will describe some of the severe accident and thermal hydraulic related issues we discussed in our reviews.

  8. Level 1 Accident Investigation Report of August 17, 2004, Fatal Aircraft

    Energy Savers [EERE]

    Accident on the Grand Coulee-Bell No.6, 500 kV Line | Department of Energy Investigation Report of August 17, 2004, Fatal Aircraft Accident on the Grand Coulee-Bell No.6, 500 kV Line Level 1 Accident Investigation Report of August 17, 2004, Fatal Aircraft Accident on the Grand Coulee-Bell No.6, 500 kV Line OCTOBER 1, 2004 On August 17, 2004, at approximately 0940, a Bonneville Power Administration (BPA) pilot was killed in the crash of a Bell 206BIII helicopter while stringing "sock

  9. Summary of the SRS Severe Accident Analysis Program, 1987--1992

    SciTech Connect (OSTI)

    Long, T.A.; Hyder, M.L.; Britt, T.E.; Allison, D.K.; Chow, S.; Graves, R.D.; DeWald, A.B. Jr.; Monson, P.R. Jr.; Wooten, L.A.

    1992-11-01

    The Severe Accident Analysis Program (SAAP) is a program of experimental and analytical studies aimed at characterizing severe accidents that might occur in the Savannah River Site Production Reactors. The goals of the Severe Accident Analysis Program are: To develop an understanding of severe accidents in SRS reactors that is adequate to support safety documentation for these reactors, including the Safety Analysis Report (SAR), the Probabilistic Risk Assessment (PRA), and other studies evaluating the safety of reactor operation; To provide tools and bases for the evaluation of existing or proposed safety related equipment in the SRS reactors; To provide bases for the development of accident management procedures for the SRS reactors; To develop and maintain on the site a sufficient body of knowledge, including documents, computer codes, and cognizant engineers and scientists, that can be used to authoritatively resolve questions or issues related to reactor accidents. The Severe Accident Analysis Program was instituted in 1987 and has already produced a substantial amount of information, and specialized calculational tools. Products of the Severe Accident Analysis Program (listed in Section 9 of this report) have been used in the development of the Safety Analysis Report (SAR) and the Probabilistic Risk Assessment (PRA), and in the development of technical specifications for the SRS reactors. A staff of about seven people is currently involved directly in the program and in providing input on severe accidents to other SRS activities.

  10. Portsmouth Site Plant Surpasses Five Years Without Lost-Time Accident |

    Energy Savers [EERE]

    Department of Energy Site Plant Surpasses Five Years Without Lost-Time Accident Portsmouth Site Plant Surpasses Five Years Without Lost-Time Accident November 26, 2013 - 12:00pm Addthis BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident. BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident. Russ Hall, environment,

  11. A comparative analysis of accident risks in fossil, hydro, and nuclear energy chains

    SciTech Connect (OSTI)

    Burgherr, P.; Hirschberg, S.

    2008-07-01

    This study presents a comparative assessment of severe accident risks in the energy sector, based on the historical experience of fossil (coal, oil, natural gas, and LPG (Liquefied Petroleum Gas)) and hydro chains contained in the comprehensive Energy-related Severe Accident Database (ENSAD), as well as Probabilistic Safety Assessment (PSA) for the nuclear chain. Full energy chains were considered because accidents can take place at every stage of the chain. Comparative analyses for the years 1969-2000 included a total of 1870 severe ({>=} 5 fatalities) accidents, amounting to 81,258 fatalities. Although 79.1% of all accidents and 88.9% of associated fatalities occurred in less developed, non-OECD countries, industrialized OECD countries dominated insured losses (78.0%), reflecting their substantially higher insurance density and stricter safety regulations. Aggregated indicators and frequency-consequence (F-N) curves showed that energy-related accident risks in non-OECD countries are distinctly higher than in OECD countries. Hydropower in non-OECD countries and upstream stages within fossil energy chains are most accident-prone. Expected fatality rates are lowest for Western hydropower and nuclear power plants; however, the maximum credible consequences can be very large. Total economic damages due to severe accidents are substantial, but small when compared with natural disasters. Similarly, external costs associated with severe accidents are generally much smaller than monetized damages caused by air pollution.

  12. DOE-STD-3014-96; DOE Standard Accident Analysis For Aircraft...

    Office of Environmental Management (EM)

    DOE STANDARD October 1 996 Reaffirmation May 2006 ACCIDENT CRASH INTO ANALYSIS HAZARDOUS FACILITIES U.S. Department of Energy Washington, DC 20585 AREA SAFT DISTRIBUTION STATEMENT ...

  13. Type B Accident Investigation Board Report on the March 27, 1998...

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

    More Documents & Publications Type A Accident Investigation Board Report on the August 13, 1996, Electrical Shock at TRA-609, Test Reactor Area, Idaho National Engineering ...

  14. Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS

    Broader source: Energy.gov [DOE]

    DOE O 225.1B prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and...

  15. 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.

    2003-02-27

    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.

  16. Estimating vehicle roadside encroachment frequency using accident prediction models

    SciTech Connect (OSTI)

    Miaou, S.-P.

    1996-07-01

    The existing data to support the development of roadside encroachment- based accident models are extremely limited and largely outdated. Under the sponsorship of the Federal Highway Administration and Transportation Research Board, several roadside safety projects have attempted to address this issue by providing rather comprehensive data collection plans and conducting pilot data collection efforts. It is clear from the results of these studies that the required field data collection efforts will be expensive. Furthermore, the validity of any field collected encroachment data may be questionable because of the technical difficulty to distinguish intentional from unintentional encroachments. This paper proposes an alternative method for estimating the basic roadside encroachment data without actually field collecting them. The method is developed by exploring the probabilistic relationships between a roadside encroachment event and a run-off-the-road event With some mild assumptions, the method is capable of providing a wide range of basic encroachment data from conventional accident prediction models. To illustrate the concept and use of such a method, some basic encroachment data are estimated for rural two-lane undivided roads. In addition, the estimated encroachment data are compared with the existing collected data. The illustration shows that the method described in this paper can be a viable approach to estimating basic encroachment data without actually collecting them which can be very costly.

  17. Novel Accident-Tolerant Fuel Meat and Cladding

    SciTech Connect (OSTI)

    Robert D. Mariani; Pavel G Medvedev; Douglas L Porter; Steven L Hayes; James I. Cole; Xian-Ming Bai

    2013-09-01

    A novel accident-tolerant fuel meat and cladding are here proposed. The fuel meat design incorporates annular fuel with inserts and discs that are fabricated from a material having high thermal conductivity, for example niobium. The inserts are rods or tubes. Discs separate the fuel pellets. Using the BISON fuel performance code it was found that the peak fuel temperature can be lowered by more than 600 degrees C for one set of conditions with niobium metal as the thermal conductor. In addition to improved safety margin, several advantages are expected from the lower temperature such as decreased fission gas release and fuel cracking. Advantages and disadvantages are discussed. An enrichment of only 7.5% fully compensates the lost reactivity of the displaced UO2. Slightly higher enrichments, such as 9%, allow uprates and increased burnups to offset the initial costs for retooling. The design has applications for fast reactors and transuranic burning, which may accelerate its development. A zirconium silicide coating is also described for accident tolerant applications. A self-limiting degradation behavior for this coating is expected to produce a glassy, self-healing layer that becomes more protective at elevated temperature, with some similarities to MoSi2 and other silicides. Both the fuel and coating may benefit from the existing technology infrastructure and the associated wide expertise for a more rapid development in comparison to other, more novel fuels and cladding.

  18. Advanced sodium fast reactor accident source terms : research needs.

    SciTech Connect (OSTI)

    Powers, Dana Auburn; Clement, Bernard; Ohno, Shuji; Zeyen, Roland

    2010-09-01

    An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic eventEnergetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolantEntrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached claddingRates of radionuclide leaching from fuel by liquid sodiumSurface enrichment of sodium pools by dissolved and suspended radionuclidesThermal decomposition of sodium iodide in the containment atmosphereReactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model of radionuclide release progressed.

  19. Accident consequence calculations for project W-058 safetyanalysis

    SciTech Connect (OSTI)

    Van Keuren, J.C.

    1997-06-10

    Accident consequence analyses have been performed for Project W-058, the Replacement Cross Site Transfer System. using the assumption and analysis techniques developed for the Tank Remediation Waste system Basis for Interim Operation. most potential accident involving the FISTS are bounded by the TWRS BIO analysis. However, the spray leak and pool leak scenarios require revised analyses since the RCSTS design utilizes larger diameter pipe and higher pressures than those analyzed in the TWRS BIO. Also the volume of diversion box and vent station are larger than that assumed for the valve pits in the TWRS BIO, which effects results of sprays or spills into the pits. the revised analysis for the spray leak is presented in Section 2, for the above ground spill in Section 3, for the presented in Section 2, for the above ground spill in Section 3, for the subsurface spill forming a pool in Section 4, and for the subsurface pool remaining subsurface in Section 5. The conclusion from these sections are summarized below.

  20. Accident Fault Trees for Defense Waste Processing Facility

    SciTech Connect (OSTI)

    Sarrack, A.G.

    1999-06-22

    The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses to calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).

  1. Thermohydraulic and Safety Analysis for CARR Under Station Blackout Accident

    SciTech Connect (OSTI)

    Wenxi Tian; Suizheng Qiu; Guanghui Su; Dounan Jia [Xi'an Jiaotong University, 28 Xianning Road, Xi'an 710049 (China); Xingmin Liu - China Institute of Atomic Energy

    2006-07-01

    A thermohydraulic and safety analysis code (TSACC) has been developed using Fortran 90 language to evaluate the transient thermohydraulic behaviors and safety characteristics of the China Advanced Research Reactor(CARR) under Station Blackout Accident(SBA). For the development of TSACC, a series of corresponding mathematical and physical models were considered. Point reactor neutron kinetics model was adopted for solving reactor power. All possible flow and heat transfer conditions under station blackout accident were considered and the optional models were supplied. The usual Finite Difference Method (FDM) was abandoned and a new model was adopted to evaluate the temperature field of core plate type fuel element. A new simple and convenient equation was proposed for the resolution of the transient behaviors of the main pump instead of the complicated four-quadrant model. Gear method and Adams method were adopted alternately for a better solution to the stiff differential equations describing the dynamic behaviors of the CARR. The computational result of TSACC showed the enough safety margin of CARR under SBA. For the purpose of Verification and Validation (V and V), the simulated results of TSACC were compared with those of Relap5/Mdo3. The V and V result indicated a good agreement between the results by the two codes. Because of the adoption of modular programming techniques, this analysis code is expected to be applied to other reactors by easily modifying the corresponding function modules. (authors)

  2. ATMOSPHERIC MODELING IN SUPPORT OF A ROADWAY ACCIDENT

    SciTech Connect (OSTI)

    Buckley, R.; Hunter, C.

    2010-10-21

    The United States Forest Service-Savannah River (USFS) routinely performs prescribed fires at the Savannah River Site (SRS), a Department of Energy (DOE) facility located in southwest South Carolina. This facility covers {approx}800 square kilometers and is mainly wooded except for scattered industrial areas containing facilities used in managing nuclear materials for national defense and waste processing. Prescribed fires of forest undergrowth are necessary to reduce the risk of inadvertent wild fires which have the potential to destroy large areas and threaten nuclear facility operations. This paper discusses meteorological observations and numerical model simulations from a period in early 2002 of an incident involving an early-morning multicar accident caused by poor visibility along a major roadway on the northern border of the SRS. At the time of the accident, it was not clear if the limited visibility was due solely to fog or whether smoke from a prescribed burn conducted the previous day just to the northwest of the crash site had contributed to the visibility. Through use of available meteorological information and detailed modeling, it was determined that the primary reason for the low visibility on this night was fog induced by meteorological conditions.

  3. PERSPECTIVES ON A DOE CONSEQUENCE INPUTS FOR ACCIDENT ANALYSIS APPLICATIONS

    SciTech Connect (OSTI)

    , K; Jonathan Lowrie, J; David Thoman , D; Austin Keller , A

    2008-07-30

    Department of Energy (DOE) accident analysis for establishing the required control sets for nuclear facility safety applies a series of simplifying, reasonably conservative assumptions regarding inputs and methodologies for quantifying dose consequences. Most of the analytical practices are conservative, have a technical basis, and are based on regulatory precedent. However, others are judgmental and based on older understanding of phenomenology. The latter type of practices can be found in modeling hypothetical releases into the atmosphere and the subsequent exposure. Often the judgments applied are not based on current technical understanding but on work that has been superseded. The objective of this paper is to review the technical basis for the major inputs and assumptions in the quantification of consequence estimates supporting DOE accident analysis, and to identify those that could be reassessed in light of current understanding of atmospheric dispersion and radiological exposure. Inputs and assumptions of interest include: Meteorological data basis; Breathing rate; and Inhalation dose conversion factor. A simple dose calculation is provided to show the relative difference achieved by improving the technical bases.

  4. Mike West Potomac Hudson Engineering Sandy Enyeart SAIC

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

    West Potomac Hudson Engineering Sandy Enyeart SAIC August 11, 2011 Nevada National Security Site (NNSS) Site-Wide Environmental Impact Statement (SWEIS) Transportation Analysis Page 2 Page 2Title 117FY11 - 08/11/2011 - Page 2 Current Transportation Practices * Recognizes previous agreements * Primarily all truck transport - FY 2008: 11% of shipments were rail-to-truck - FY 2009: 3% of shipments were rail-to-truck - FY 2010: less than 1% of shipments were rail-to-truck Page 3 Page 3Title 117FY11

  5. Type B Accident Investigation Board Report on the August 5, 1998, Load Haul Dump Accident at U16b Tunnel, Nevada Test Site

    Broader source: Energy.gov [DOE]

    Thisis theType B Accident Investigation Board report of an industrial accident at the Nevada Test site (NTS), U16b tunnel in which a Bechtel Nevada (BN) employee suffered a compressed skull fracture as a result of being struck onthe head by a valve and fitting assembly on the end of a hose whichhad been broken from a water pipe by a moving piece of construction equipment.

  6. ASN Aircraft accident Beechcraft 1900C N27RA Tonopah-Test Range...

    National Nuclear Security Administration (NNSA)

    Accident description languages: Share 0 Statd,LB:5E)(WEWkNF75WLEW)w(Ni7wkE.(wnNa75WLEW)w(... According to the Air Force Materiel Command Accident Investigation Board report, the pilot ...

  7. Recovery sequences for a station blackout accident at the Grand Gulf Nuclear Station

    SciTech Connect (OSTI)

    Carbajo, J.J. [Martin Marietta Energy Systems, Oak Ridge, TN (United States)

    1995-12-31

    Recovery sequences for a low-pressure, short term, station blackout severe accident at the Grand Gulf power plant have been investigated using the computer code MELCOR, version 1.8.3 PN. This paper investigates the effect of reflood timing and mass flow rate on accident recovery.

  8. A statistical description of the types and severities of accidents involving tractor semi-trailers

    SciTech Connect (OSTI)

    Clauss, D.B.; Wilson, R.K.; Blower, D.F.; Campbell, K.L.

    1994-06-01

    This report provides a statistical description of the types and severities of tractor semi-trailer accidents involving at least one fatality. The data were developed for use in risk assessments of hazardous materials transportation. Several accident databases were reviewed to determine their suitability to the task. The TIFA (Trucks Involved in Fatal Accidents) database created at the University of Michigan Transportation Research Institute was extensively utilized. Supplementary data on collision and fire severity, which was not available in the TIFA database, were obtained by reviewing police reports for selected TIFA accidents. The results are described in terms of frequencies of different accident types and cumulative distribution functions for the peak contact velocity, rollover skid distance, fire temperature, fire size, fire separation, and fire duration.

  9. Decontamination analysis of the NUWAX-83 accident site using DECON

    SciTech Connect (OSTI)

    Tawil, J.J.

    1983-11-01

    This report presents an analysis of the site restoration options for the NUWAX-83 site, at which an exercise was conducted involving a simulated nuclear weapons accident. This analysis was performed using a computer program deveoped by Pacific Northwest Laboratory. The computer program, called DECON, was designed to assist personnel engaged in the planning of decontamination activities. The many features of DECON that are used in this report demonstrate its potential usefulness as a site restoration planning tool. Strategies that are analyzed with DECON include: (1) employing a Quick-Vac option, under which selected surfaces are vacuumed before they can be rained on; (2) protecting surfaces against precipitation; (3) prohibiting specific operations on selected surfaces; (4) requiring specific methods to be used on selected surfaces; (5) evaluating the trade-off between cleanup standards and decontamination costs; and (6) varying of the cleanup standards according to expected exposure to surface.

  10. Hypothetical accident conditions thermal analysis of the 5320 package

    SciTech Connect (OSTI)

    Hensel, S.J.; Gromada, R.J.

    1995-12-31

    An axisymmetric model of the 5320 package was created to perform hypothetical accident conditions (HAC) thermal calculations. The analyses assume the 5320 package contains 359 grams of plutonium-238 (203 Watts) in the form of an oxide powder at a minimum density of 2.4 g/cc or at a maximum density of 11.2 g/cc. The solution from a non-solar 100 F ambient steady-state analysis was used as the initial conditions for the fire transient. A 30 minute 1,475 F fire transient followed by cooling via natural convection and thermal radiation to a 100 F non-solar environment was analyzed to determine peak component temperatures and vessel pressures. The 5320 package was considered to be horizontally suspended within the fire during the entire transient.

  11. Technical evaluation: 300 Area steam line valve accident

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    On June 7, 1993, a journeyman power operator (JPO) was severely burned and later died as a result of the failure of a 6-in. valve that occurred when he attempted to open main steam supply (MSS) valve MSS-25 in the U-3 valve pit. The pit is located northwest of Building 331 in the 300 Area of the Hanford Site. Figure 1-1 shows a layout of the 300 Area steam piping system including the U-3 steam valve pit. Figure 1-2 shows a cutaway view of the approximately 10- by 13- by 16-ft-high valve pit with its various steam valves and connecting piping. Valve MSS-25, an 8-in. valve, is located at the bottom of the pit. The failed 6-in. valve was located at the top of the pit where it branched from the upper portion of the 8-in. line at the 8- by 8- by 6-in. tee and was then ``blanked off`` with a blind flange. The purpose of this technical evaluation was to determine the cause of the accident that led to the failure of the 6-in. valve. The probable cause for the 6-in. valve failure was determined by visual, nondestructive, and destructive examination of the failed valve and by metallurgical analysis of the fractured region of the valve. The cause of the accident was ultimately identified by correlating the observed failure mode to the most probable physical phenomenon. Thermal-hydraulic analyses, component stress analyses, and tests were performed to verify that the probable physical phenomenon could be reasonably expected to produce the failure in the valve that was observed.

  12. LANL Resumes Shipments to WIPP

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

    Administration Produces First Plutonium Pit in 14 Years LANL Produces First Plutonium Pit in 14 Years Los Alamos, NM NNSA's Los Alamos National Laboratory (LANL) announced that it has successfully made the first nuclear weapons "pit" in 14 years that meets specifications for use in the U.S. stockpile. The plutonium pit, called Qual-1 because it was built with and fully met qualified processes, is for the W88 warhead, which is carried on the Trident II D5 Submarine-Launched Cruise

  13. Operations start and shipments begin

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

    and the original group returned to Oak Ridge by way of Knoxville. In The New World, by Richard G. Hewlett and Oscar E. Anderson Jr., the following description is provided...

  14. LANL reaches waste shipment milestone

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

    "The repository has a proven record of safe and secure operations." As remaining drums are shipped, the Laboratory is demolishing unused storage facilities in a multiyear...

  15. WHEN MODEL MEETS REALITY – A REVIEW OF SPAR LEVEL 2 MODEL AGAINST FUKUSHIMA ACCIDENT

    SciTech Connect (OSTI)

    Zhegang Ma

    2013-09-01

    The Standardized Plant Analysis Risk (SPAR) models are a set of probabilistic risk assessment (PRA) models used by the Nuclear Regulatory Commission (NRC) to evaluate the risk of operations at U.S. nuclear power plants and provide inputs to risk informed regulatory process. A small number of SPAR Level 2 models have been developed mostly for feasibility study purpose. They extend the Level 1 models to include containment systems, group plant damage states, and model containment phenomenology and accident progression in containment event trees. A severe earthquake and tsunami hit the eastern coast of Japan in March 2011 and caused significant damages on the reactors in Fukushima Daiichi site. Station blackout (SBO), core damage, containment damage, hydrogen explosion, and intensive radioactivity release, which have been previous analyzed and assumed as postulated accident progression in PRA models, now occurred with various degrees in the multi-units Fukushima Daiichi site. This paper reviews and compares a typical BWR SPAR Level 2 model with the “real” accident progressions and sequences occurred in Fukushima Daiichi Units 1, 2, and 3. It shows that the SPAR Level 2 model is a robust PRA model that could very reasonably describe the accident progression for a real and complicated nuclear accident in the world. On the other hand, the comparison shows that the SPAR model could be enhanced by incorporating some accident characteristics for better representation of severe accident progression.

  16. Analysis of Kuosheng Station Blackout Accident Using MELCOR 1.8.4

    SciTech Connect (OSTI)

    Wang, S.-J.; Chien, C.-S.; Wang, T.-C.; Chiang, K.-S

    2000-11-15

    The MELCOR code, developed by Sandia National Laboratories, is a fully integrated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs).A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simulated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng NPP is established based on Kuosheng NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the fission product release fractions associated with the SBO accident were simulated. The predicted results are plausible and as expected in light of current understanding of severe accident phenomena. The uncertainty of this analysis is briefly discussed. The important features of the MELCOR 1.8.4 are described. The estimated results provide useful information for the probabilistic risk assessment (PRA) of Kuosheng NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Kuosheng NPP in the near future.

  17. Type A Accident Investigation Board Report on the April 3, 1995, Security

    Energy Savers [EERE]

    Rappel Tower Fatality at the DOE Savannah River Site | Department of Energy 3, 1995, Security Rappel Tower Fatality at the DOE Savannah River Site Type A Accident Investigation Board Report on the April 3, 1995, Security Rappel Tower Fatality at the DOE Savannah River Site August 1, 1995 The accident under investigation occurred on April 3, 1995, at approximately 10:46 a.m. As a result of the accident, a Wackenhut Services, Incorporated-Savannah River Site (WSI-SRS) Special Response Team

  18. The response of BWR Mark II containments to station blackout severe accident sequences

    SciTech Connect (OSTI)

    Greene, S.R.; Hodge, S.A.; Hyman, C.R.; Tobias, M.L. (Oak Ridge National Lab., TN (USA))

    1991-05-01

    This report describes the results of a series of calculations conducted to investigate the response of BWR Mark 2 containments to short-term and long-term station blackout severe accident sequences. The BWR-LTAS, BWRSAR, and MELCOR codes were employed to conduct quantitative accident sequence progression and containment response analyses for several station blackout scenarios. The accident mitigation effectiveness of automatic depressurization system actuation, drywell flooding via containment spray operation, and debris quenching in Mark 2 suppression pools is assessed. 27 refs., 16 figs., 21 tabs.

  19. Study on the Accidental Rupture of Hot Leg or Surge Line in SBO Accident

    SciTech Connect (OSTI)

    Kun Zhang; Xuewu Cao [Shanghai Jiaotong University, Shanghai (China)

    2006-07-01

    The postulated total station blackout accident (SBO) of PWR NPP with 600 MWe in China is analyzed as the base case using SCDAP/RELAP5 code. Then the hot leg or surge line are assumed to rupture before the lower head of Reactor Pressure Vessel (RPV) ruptures, and the progressions are analyzed in detail comparing with the base case. The results show that the accidental rupture of hot leg or surge line will greatly influence the progression of accident. The probability of hot leg or surge line rupture in intentional depressurization is also studied in this paper, which provides a suggestion to the development of Severe Accident Management Guidelines (SAMG). (authors)

  20. WIPP Workers Reach Two Million Man-Hours Without a Lost-Time Accident

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

    Workers Reach Two Million Man-Hours Without a Lost-Time Accident CARLSBAD, N.M., February 22, 2001 - Workers at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) reached a safety milestone Feb. 19 by working two million man-hours without a lost-time accident. According to the National Safety Council, facilities with the same industry code as WIPP lose an average of 20.6 workdays (or 164.8 man-hours) a year to accidents. "Safety is at the core of all WIPP