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. Naval Spent Fuel Rail Shipment Accident Exercise Objectives

    Office of Environmental Management (EM)

    NAVAL SPENT FUEL RAIL SHIPMENT ACCIDENT EXERCISE OBJECTIVES * Familiarize stakeholders with the Naval spent fuel ACCIDENT EXERCISE OBJECTIVES Familiarize stakeholders with the ...

  3. 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.

  4. 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

  5. No Recordable Accidents in 17,000 Waste Shipments Across 3.4 Million Miles

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – No U.S. Department of Transportation recordable accidents resulted from DOE’s nearly 17,000 radioactive, hazardous material and waste shipments across 3.4 million miles in fiscal 2015.

  6. 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)

  7. 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

  8. 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...

  9. 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 ...

  10. TEC Working Group Topic Groups Rail Key Documents Planning Subgroup |

    Office of Environmental Management (EM)

    Department of Energy Planning Subgroup TEC Working Group Topic Groups Rail Key Documents Planning Subgroup Planning Subgroup Rail Planning Timeline (135.57 KB) Benchmarking Project: AREVA Trip Report (651.92 KB) More Documents & Publications TEC Meeting Summaries - July 2007 Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel Federal Railroad Administration

  11. 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.

  12. 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.

  13. 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.

  14. 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

  15. 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...

  16. 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.

  17. 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.

  18. 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.

  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. Site Specific Analyses of a Spent Nuclear Fuel Transportation Accident

    SciTech Connect (OSTI)

    Biwer, B. M.; Chen, S. Y.

    2003-02-24

    The number of spent nuclear fuel (SNF) shipments is expected to increase significantly during the time period that the United States' inventory of SNF is sent to a final disposal site. Prior work estimated that the highest accident risks of a SNF shipping campaign to the proposed geologic repository at Yucca Mountain were in the corridor states, such as Illinois. The largest potential human health impacts would be expected to occur in areas with high population densities such as urban settings. Thus, our current study examined the human health impacts from the most plausible severe SNF transportation accidents in the Chicago metropolitan area. The RISKIND 2.0 program was used to model site-specific data for an area where the largest impacts might occur. The results have shown that the radiological human health consequences of a severe SNF rail transportation accident on average might be similar to one year of exposure to natural background radiation for those persons living a nd working in the most affected areas downwind of the actual accident location. For maximally exposed individuals, an exposure similar to about two years of exposure to natural background radiation was estimated. In addition to the accident probabilities being very low (approximately 1 chance in 10,000 or less during the entire shipping campaign), the actual human health impacts are expected to be lower if any of the accidents considered did occur, because the results are dependent on the specific location and weather conditions, such as wind speed and direction, that were selected to maximize the results. Also, comparison of the results of longer duration accident scenarios against U.S. Environmental Protection Agency guidelines was made to demonstrate the usefulness of this site-specific analysis for emergency planning purposes.

  1. 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

  2. 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 Railroad's ...

  3. 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...

  4. 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...

  5. 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...

  6. 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.

  7. 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 world’s 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.

  8. 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

  9. 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

  10. LANL reaches waste shipment milestone

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

    LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communications Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important

  11. 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 world’s 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.

  12. 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

  13. RUSSIAN-ORIGIN HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL SHIPMENT FROM BULGARIA

    SciTech Connect (OSTI)

    Kelly Cummins; Igor Bolshinsky; Ken Allen; Tihomir Apostolov; Ivaylo Dimitrov

    2009-07-01

    In July 2008, the Global Threat Reduction Initiative and the IRT 2000 research reactor in Sofia, Bulgaria, operated by the Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped 6.4 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel (SNF) to the Russian Federation. The shipment, which resulted in the removal of all HEU from Bulgaria, was conducted by truck, barge, and rail modes of transport across two transit countries before reaching the final destination at the Production Association Mayak facility in Chelyabinsk, Russia. This paper describes the work, equipment, organizations, and approvals that were required to complete the spent fuel shipment and provides lessons learned that might assist other research reactor operators with their own spent nuclear fuel shipments.

  14. Lab sets new record for waste shipments

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

    New record for waste shipments Lab sets new record for waste shipments LANL completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. August 20, 2010 LANL's shipment of transuranic waste leaves Los Alamos. LANL's shipment of transuranic waste leaves Los Alamos. Contact Fred deSousa Communications Office (505) 500-5672 Email "Removing this waste from Los Alamos is crucial to our plans for overall

  15. Los Alamos shipments to Waste Control Specialists

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

    8, 2014 Los Alamos shipments to Waste Control Specialists To date, Waste Control Specialists (WCS), a facility in Andrews, Texas, has received and processed seven shipments of defense-generated transuranic waste from Los Alamos National Laboratory. Members of WIPP's Central Characterization Project mobile loading unit and crew went to WCS to safely unload the disposal containers. Plans include completing up to 10 shipments per week to WCS. All shipments are using WIPP's transportation protocols

  16. 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.

  17. 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

  18. 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

  19. 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...

  20. 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 Current FRA State Rail Safety ...

  1. 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 ...

  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. 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...

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

    Office of Environmental Management (EM)

    Low-Level Waste Shipment West Valley Demonstration Project Low-Level Waste Shipment West Valley Demonstration Project Low-Level Waste Shipment (406.16 KB) More Documents & ...

  6. 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.

  7. 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.

  8. WIPP Receives First Remote-Handled Waste Shipment From Sandia...

    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 ... (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. ...

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

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

    Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users ...

  10. The First Recovery Act Funded Waste Shipment depart from the...

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

    The First Recovery Act Funded Waste Shipment departs from the Advanced Mixed Waste Treatment Facility A shipment of mixed low-level waste left DOEs Advanced Mixed Waste ...

  11. Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency...

    Office of Environmental Management (EM)

    Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency February 27, 2013 - 12:00pm Addthis This ...

  12. DOE Seeks Trucking Services for Transuranic Waste Shipments ...

    Office of Environmental Management (EM)

    Seeks Trucking Services for Transuranic Waste Shipments DOE Seeks Trucking Services for Transuranic Waste Shipments March 30, 2011 - 12:00pm Addthis Media Contact Bill Taylor ...

  13. 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...

  14. 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

  15. 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...

  16. 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.

  17. 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)

  18. First Savannah River Shipment Arrives At WIPP

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

    First Savannah River Site Shipment Arrives At WIPP CARLSBAD, N.M., May 10, 2001 - The U.S. ... from DOE's Savannah River Site has arrived at the Waste Isolation Pilot Plant (WIPP). ...

  19. 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...

  20. 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.

  1. Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments

    SciTech Connect (OSTI)

    Doerge, D. H.; Haffner, D. R.

    1988-06-01

    This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

  2. Module Shipments Total Inventory, Start-of-Year

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

    Module Shipments Total Inventory, Start-of-Year 906,914 Manufactured During Reporting Year 726,915 Imported During Reporting Year 5,858,676 Purchased from U.S. OEM 33,951 Total Available for Shipment 7,526,456 U.S. Shipments and Sales for Resale 6,054,538 Export Shipments 182,985 Total Shipments 6,237,524 Inventory, End-of-Year 1,288,933 Table 6. Source and disposition of photovoltaic module shipments, 2014 (peak kilowatts) Source Disposition Source: U.S. Energy Information Administration, Form

  3. TEC Working Group Topic Groups Rail Key Documents Intermodal Subgroup |

    Office of Environmental Management (EM)

    Department of Energy Intermodal Subgroup TEC Working Group Topic Groups Rail Key Documents Intermodal Subgroup Intermodal Subgroup Draft Work Plan (206.83 KB) More Documents & Publications TEC Working Group Topic Groups Rail Key Documents Radiation Monitoring Subgroup TEC Working Group Topic Groups Rail Conference Call Summaries Intermodal Subgroup TEC Working Group Topic Groups Rail Conference Call Summaries Rail Topic Group

  4. 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.

  5. 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.

  6. Final Transuranic Waste Shipment Leaves Rocky Flats | Department...

    Office of Environmental Management (EM)

    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 ...

  7. TEC Working Group Topic Groups Rail Conference Call Summaries | Department

    Office of Environmental Management (EM)

    of Energy Rail Conference Call Summaries TEC Working Group Topic Groups Rail Conference Call Summaries CONFERENCE CALL SUMMARIES Rail Topic Group Inspections Subgroup Planning Subgroup Tracking Subgroup TRAGIS Subgroup Radiation Monitoring Subgroup Intermodel Subgroup

  8. 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

  9. 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.

  10. 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., September 28, 2011 - The U.S. Department of Energy today announced that the Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste over the weekend. This marks an important milestone in DOE's mission to clean up the country's Cold War legacy. "This accomplishment reflects the hard

  11. 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

  12. Portsmouth, Paducah Project Leaps Past Shipment Milestone, Delivering

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

    Economic Benefit to U.S. | Department of Energy Portsmouth, Paducah Project Leaps Past Shipment Milestone, Delivering Economic Benefit to U.S. Portsmouth, Paducah Project Leaps Past Shipment Milestone, Delivering Economic Benefit to U.S. September 1, 2012 - 12:00pm Addthis Pictured here are railcars carrying tanks of hydrofluoric acid for shipment from the Portsmouth site to Solvay Fluorides for industrial use. Pictured here are railcars carrying tanks of hydrofluoric acid for shipment from

  13. 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

  14. ( 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 ( Sample of Shipment Notice) Federal Records Center (196.84 KB) More Documents & Publications Correspondence Style Guide Records Management Handbook Records Management Handbook

  15. 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.

  16. 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 ...

  17. 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 ...

  18. 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...

  19. 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

  20. 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

  1. 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.

  2. Cell Shipments Total Inventory, Start-of-Year

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

    Cell Shipments Total Inventory, Start-of-Year 628,668 Manufactured and Purchased During Reporting Year 652,696 Imported During Reporting Year 233,377 Total Available for Shipment 1,514,740 Cells Assembled into Modules and Sold for Resale 1,129,525 Export Shipments 106,472 Total Shipments 1,235,997 Inventory, End-of-Year 278,744 Table 5. Source and disposition of photovoltaic cell shipments, 2014 (peak kilowatts) Source Disposition Source: U.S. Energy Information Administration, Form EIA-63B,

  3. 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

  4. 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.

  5. Rail transportation of Fernald remediation waste

    SciTech Connect (OSTI)

    Fellman, R.T.; Lojek, D.A.; Motl, G.P.; Weddendorf, W.K.

    1995-01-24

    Remediation of the Department of Energy (DOE) Fernald site located north of Cincinnati will generate large quantities of low-level radwaste. This volume includes approximately 1,050,000 tons of material to be removed from eight waste pits comprising Operable Unit 1 (OU-1). The remedial alternative selected includes waste material excavation, drying and transportation by rail to a burial site in the arid west for disposal. Rail transportation was selected not only because rail transportation is safer than truck transportation, but also because of the sheer magnitude of the project and the availability of bulk rail car unloading facilities at a representative disposal site. Based upon current waste quantity estimates as presented in the Feasibility Study for OUI, a fully-loaded 47-car unit train would depart the Fernald site weekly for five years. This paper illustrates the steps taken to obtain agency and public acceptance of the Record of Decision for the remedy which hinged on rail transportation. A preliminary, but detailed, rail transportation plan was prepared for the project to support a series of CERCLA public meetings conducted in late 1994. Some of the major issues addressed in the plan included the following: (1) Scope of project leading to selection of rail transportation; (2) Waste classification; (3) Rail Company overview; (4) Train configuration and rail car selection; (5) Routing; (6) Safety; (7) Prior Notification Requirements (8) Emergency Response. A series of three public meetings identified a number of issues of prime concern to Fernald stakeholders. Following resolution of these issues during the public comment period, a Record of Decision (ROD) approving implementation of the rail transportation strategy was approved pending incorporation of EPA and State of Ohio comments on December 22, 1994.

  6. 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)

  7. 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.

  8. CNG Imports by Rail into the U.S. | Department of Energy

    Office of Environmental Management (EM)

    Rail into the U.S. CNG Imports by Rail into the U.S. CNG Imports by Rail Form (Excel) (40.5 KB) CNG Imports by Rail Form (pdf) (11.18 KB) More Documents & Publications LNG Exports by Rail out of the U.S. Other Imports by Rail into the U.S. Other Exports by Rail out of

  9. 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.

  10. 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...

  11. 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.

  12. 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

  13. 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

  14. Laboratory increases shipments of waste to WIPP repository

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

    Lab increases shipments to WIPP repository Laboratory increases shipments of waste to WIPP 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 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

  15. Reminder: Jefferson Lab Shipment Import and Export Requirements | Jefferson

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

    Lab Reminder: Jefferson Lab Shipment Import and Export Requirements Reminder: Jefferson Lab Shipment Import and Export Requirements For any shipment being imported to Jefferson Lab, it is mandatory that the lab's customs broker, Team Worldwide, be contacted by the vendors' shipper to arrange all shipping from their facility to the lab (Team Worldwide contact information is listed below). Contacting Jefferson Lab's customs broker will save time and facilitate movement of the property to

  16. 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...

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

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

    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 ...

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

    Gasoline and Diesel Fuel Update (EIA)

    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 ...

  19. 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 ...

  20. Level: National and Regional Data; Row: Values of Shipments and...

    Gasoline and Diesel Fuel Update (EIA)

    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 ...

  1. 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...

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

    Office of Environmental Management (EM)

    Accomplished and a Look Forward Presented by Stephen O'Connor, Director of Office of Packaging and Transportation. PDF icon DOE Shipment Activities: What We Accomplished and a...

  3. 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.

  4. 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

  5. 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).

  6. WIPP Receives First Shipment | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (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

  7. 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.

  8. 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.

  9. 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...

  10. 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

  11. TEC Working Group Topic Groups Rail Archived Documents | Department of

    Office of Environmental Management (EM)

    Energy Archived Documents TEC Working Group Topic Groups Rail Archived Documents ARCHIVED DOCUMENTS Inspections Summary Matrix (49.36 KB) TEC Transportation Safety WIPP-PIG Rail Comparison (130.46 KB) Regulatory Summary Matrix (62.08 KB) More Documents & Publications TEC Working Group Topic Groups Rail Key Documents TEC Working Group Topic Groups Rail Meeting Summaries TEC Meeting Summaries - September 2005 Presentations

  12. 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 April 6, 2006 (14.05 KB) February 23, 2006 Draft (20.29 KB) January 24, 2006 (27.44 KB) 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

  13. 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 Draft Work Plan - February 4, 2008 (114.02 KB) 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

  14. 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.

  15. 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.

  16. 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 May 17, 2007 (10.98 KB) January 16, 2007 (14.41 KB) August 31, 2006 (16.39 KB) July 27, 2006 (19.28 KB) June 8, 2006 (15.79 KB) April 20, 2006 (19.91 KB) March 9, 2006 (19.65 KB) January 26, 2006 (20.86 KB) November 9, 2005 (24.38 KB) September 15, 2005 (32.13 KB) April 28, 2005 (19.16 KB) March 24, 2005 (28.33 KB) February 24, 2005 (32.77

  17. 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,

  18. 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

  19. 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)

  20. CNG Exports by Rail out of the U.S. | Department of Energy

    Office of Environmental Management (EM)

    Rail out of the U.S. CNG Exports by Rail out of the U.S. CNG Exports by Rail Form (Excel) (40.5 KB) CNG Exports by Rail Form (pdf) (11.06 KB) More Documents & Publications CNG Imports by Rail into the U.S. Other Exports by Rail out of the U.S. LNG Exports by Rail out of the U.S.

  1. Solar Photovoltaic Cell/Module Shipments - Energy Information...

    Gasoline and Diesel Fuel Update (EIA)

    Solar Photovoltaic CellModule Shipments Report With data for 2014 | Release Date: July ... changes to strategic planning of companies in the U.S. solar photovoltaic (PV) industry. ...

  2. Milestone Shipment Arrives at WIPP | Department of Energy

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

    the EM program at DOE's Idaho site. "Safety is the most ... CBFO has responsibility for WIPP and the National TRU ... Waste Shipment From Sandia Labs DOE Completes TRU Waste ...

  3. 50th Anniversary of First Fuel Shipment Highlights EM's Role...

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

    ... The SNF shipment was part of the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. This Atoms for Peace initiative was designed to recover and store U.S. origin ...

  4. 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.

  5. Accident Investigation Handbook

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

    Accident Investigations (AI) and Operational Safety Reviews (OSR) are valuable for ... in conducting Department of Energy (DOE) accident investigations over the past many years. ...

  6. 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

  7. Solar Photovoltaic Cell/Module Shipments Report July 2016

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

    Photovoltaic Cell/Module Shipments Report July 2016 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Solar Photovoltaic Cell/Module Shipments Report 1 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 employee

  8. 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

  9. 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.

  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

  11. 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 ...

  12. Microsoft Word - Summary of Rail Comparison for Topic Group 7...

    Office of Environmental Management (EM)

    ... National planning and coordination for emergency response is accomplished through ... a WIPP shipment poses unique problems for emergency response personnel not usually ...

  13. 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 Natural Gas Pipeline Materials for Hydrogen Science Evaluation of Natural Gas Pipeline Materials for Hydrogen Science Presentation by 04-Adams to DOE Hydrogen Pipeline R&D Project Review Meeting held January 5-6, 2005 at Oak Ridge National Laboratory in Oak Ridge, Tennessee. 04_adams_nat_gas.pdf (9.97 MB) More Documents & Publications Evalutation of Natural Gas Pipeline Materials and Infrastructure for Hydrogen/Mixed Gas Service Hydrogen

  14. Chicago-St. Louis high speed rail plan

    SciTech Connect (OSTI)

    Stead, M.E.

    1994-12-31

    The Illinois Department of Transportation (IDOT), in cooperation with Amtrak, undertook the Chicago-St. Louis High Speed Rail Financial and Implementation Plan study in order to develop a realistic and achievable blueprint for implementation of high speed rail in the Chicago-St. Louis corridor. This report presents a summary of the Price Waterhouse Project Team`s analysis and the Financial and Implementation Plan for implementing high speed rail service in the Chicago-St. Louis corridor.

  15. TEC Working Group Topic Groups Rail | Department of Energy

    Office of Environmental Management (EM)

    The group's current task is to examine different aspects of rail transportation including inspections, tracking and radiation monitoring, planning and process, and review of ...

  16. 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,...

  17. 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,...

  18. 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

  19. PHOENIX ENERGIZES LIGHT RAIL CORRIDOR WITH UPGRADES | Department...

    Energy Savers [EERE]

    in Phoenix, Arizona's 10-mile-long Light Rail Corridor, Energize Phoenix focused on performing energy upgrades and reducing energy use in commercial and residential spaces. ...

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

    Office of Environmental Management (EM)

    7, 2012, Construction Accident - Structural Steel Collapse at The Over pack Storage ... Accident Investigation of the June 17, 2012, Construction Accident - Structural Steel ...

  1. Pipe overpack container for trasuranic waste storage and shipment

    DOE Patents [OSTI]

    Geinitz, Richard R.; Thorp, Donald T.; Rivera, Michael A.

    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.

  2. Rocky Flats 100th Shipments Arrives at WIPP

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

    RELEASE Rocky Flats For Immediate Release Contact: Karen Lutz, DOE RFFO, 303/966-4546 01-08 Jennifer Thompson, Kaiser-Hill, 303/966-6285 Kate Foster, Westinghouse TRU Solutions, 505/234-7589 Rocky Flats' 100 th Shipment Arrives at Waste Isolation Pilot Plant DENVER, Colo., March 14, 2001- The 100 th shipment of transuranic waste from the U.S. Department of Energy's (DOE) Rocky Flats Environmental Technology Site (RFETS) has arrived at DOE's Waste Isolation Pilot Plant (WIPP) in New Mexico. Rocky

  3. SUPPLEMENT ANALYSIS PROPOSED SHIPMENT OF COMMERCIAL SPENT NUCLEAR FUEL

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

    SUPPLEMENT ANALYSIS PROPOSED SHIPMENT OF COMMERCIAL SPENT NUCLEAR FUEL TO DOE NATIONAL LABORATORIES FOR RESEARCH AND DEVELOPMENT PURPOSES Office of Nuclear Energy U.S. DEPARTMENT OF ENERGY DECEMBER 2015 DOE/EIS-0203-SA-07 DOE/EIS-0250F-S-1-SA-02 Commercial Fuel Shipment SA DOE/EIS-0203-SA-07 December 2015 CONVERSION FACTORS Metric to English English to Metric Multiply by To get Multiply by To get Area Square kilometers 247.1 Acres Square kilometers 0.3861 Square miles Square meters 10.764 Square

  4. 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

  5. All aboard for high-speed rail

    SciTech Connect (OSTI)

    Herman, D.

    1996-09-01

    A sleek, bullet-nosed train whizzing across the countryside is a fairly common sight in many nations. Since the Train a Grande Vitesse (TGV)--the record-setting ``train with great speed``--was introduced in France in 1981, Germany, Japan, and other countries have joined the high-speed club. In addition, the Eurostar passenger train, which travels between Great Britain and France through the Channel Tunnel, can move at 186 miles per hour once it reaches French tracks. Despite the technology`s growth elsewhere, rapid rail travel has not been seen on US shores beyond a few test runs by various manufacturers. Before the end of the century, however, American train spotters will finally be able to see some very fast trains here too. In March, Washington, DC-based Amtrak announced the purchase of 18 American Flyer high-speed train sets for the Northeast Corridor, which stretches from Boston through new York to the nation`s capital. Furthermore, Florida will get its own system by 2004, and other states are now taking a look at the technology. The American Flyer--designed by Montreal-based Bombardier and TGV manufacturer GEC Alsthom Transport in Paris--should venture onto US rails by 1999. Traveling at up to 150 miles per hour, the American Flyer will cut the New York-Boston run from 4 1/2 hours to 3 hours and reduce New York-Washington trip time from 3 hours to less than 2 3/4. Amtrak hopes the new trains and better times will earn it a greater share of travelers from air shuttles and perhaps from Interstate 95. This article describes how technologies that tilt railcars and propel the world`s fastest trains will be merged into one train set for the American Flyer, Amtrak`s first trip along high-speed rails.

  6. 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

  7. 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.

  8. LNG Imports by Rail into the U.S. | Department of Energy

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

    Rail into the U.S. LNG Imports by Rail into the U.S. LNG Imports by Rail Form (Excel) (54.5 KB) LNG Imports by Rail Form (pdf) (11.21 KB) More Documents & Publications LNG Imports by Truck into the U.S. Form LNG Imports by Vessel into the U.S. Form LNG Exports by Truck

  9. 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.

  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. Robotics virtual rail system and method

    DOE Patents [OSTI]

    Bruemmer, David J.; Few, Douglas A.; Walton, Miles C.

    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.

  12. Accident motivates scholarship recipient

    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. 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

  13. 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. ...

  14. 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.

  15. Microsoft PowerPoint - Rail_Kneitel [Compatibility Mode

    Office of Environmental Management (EM)

    Super Sacks * Sometimes waste is loaded into Super Sacks (IP-1 Packages) * Then the sacks are loaded into a railcar with a crane. 5162014 5 9 What do we ship by rail? * Waste ...

  16. The Environmental Injector: Beyond Common Rail and Hydraulic

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

    Intensificatiion | Department of Energy The Environmental Injector: Beyond Common Rail and Hydraulic Intensificatiion The Environmental Injector: Beyond Common Rail and Hydraulic Intensificatiion The Environmental Injector System increases injection pressure, reduces parasitic losses, allows for a wide range of alternative fuels, reduces costs, and improves safety. deer08_vollmer.pdf (233.3 KB) More Documents & Publications Preparation, Injection and Combustion of Supercritical Fluids

  17. Hydrogen Assisted Diesel Combustion in a Common Rail Turbodiesel Engine |

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

    Department of Energy Assisted Diesel Combustion in a Common Rail Turbodiesel Engine Hydrogen Assisted Diesel Combustion in a Common Rail Turbodiesel Engine This study measured the effects of hydrogen substitution on engine performance and reducing NOx emissions in a diesel engine deer09_boehman.pdf (150.76 KB) More Documents & Publications Particulate Produced from Advanced Combustion Operation in a Compression Ignition Engine Advanced Diesel Combustion with Low Hydrocarbon and Carbon

  18. 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.

  19. Table 2. Value and average value of photovoltaic module shipments, 2014

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

    Value and average value of photovoltaic module shipments, 2014" "Module value, total shipments (thousand dollars)" "Total Modules ",5425417 "Module average value (dollars per peak watt)" "Total Modules ",0.87 "Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report' Note: Dollars are not adjusted for inflation.

  20. Uraninum-233 Inventory in Oak Ridge Lightened with First Shipment of

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

    Material from Building 3019 | Department of Energy Uraninum-233 Inventory in Oak Ridge Lightened with First Shipment of Material from Building 3019 Uraninum-233 Inventory in Oak Ridge Lightened with First Shipment of Material from Building 3019 January 5, 2012 - 12:00pm Addthis OAK RIDGE, Tenn. - The first shipment of inventory from Building 3019 at the Oak Ridge National Laboratory arrived at the Nevada Nuclear Security Site (NNSS) on December 22, marking the beginning of the end for the

  1. 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.

  2. 10,000th Waste Shipment Milestone is All in the Family | Department of

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

    Energy 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 through

  3. 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...

  4. 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

  5. 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,...

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

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

    2010 2011 2012 2013 2014 2015 View History From PADD 1 to PADD 2 0 0 0 0 0 0 2010-2015 ... See movements of crude oil by rail for movements by rail within PADDs and tofrom Canada. ...

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. Annual Report - FY 1998, Shipments to and from the Nevada Test Site (NTS)

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office

    1999-02-01

    This report summarizes waste shipments to the Nevada Test Site Radioactive Waste Management Sites at Area 3 and Area 5 during fiscal year 1998. In addition this report provides a summary evaluation of each shipping campaign by source (waste generator) which identifies observable incidents, if any, associated with the actual waste shipments.

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

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

    2016-07-20

    The purpose of this Order is to make clear that the packaging and transportation of all offsite shipments of Materials of National Security Interest (MNSI) for DOE must be conducted in accordance with Department of Transportation (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.

  14. 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 ...

  15. U.S. Energy-by-Rail Data Methodology

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

    by-Rail Data Methodology June 2016 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | U.S. Energy-by-Rail Data Methodology 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 employee of the United States

  16. 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

  17. 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.

  18. 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.

  19. 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...

  20. 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

  1. 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

  2. 10,000th Shipment Celebrated at WIPP | Department of Energy

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

    Shipment Celebrated at WIPP 10,000th Shipment Celebrated at WIPP October 24, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - Approximately 130 people gathered at the U.S. Department of Energy's (DOE's) Waste Isolation Pilot Plant (WIPP) on October 22, to celebrate the 10,000th shipment of transuranic (TRU) waste to WIPP, which arrived safely late last month. The event was attended by elected and appointed officials, state and local leaders, WIPP

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

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

    Department of Energy First Remote-Handled Waste Shipment From Sandia Labs WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs December 21, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 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. The

  4. Remarks on Rail Transportation of Energy Resources John R. Birge

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

    Crude oil is a small but increasing component f. Public externalities: Accidents, ... Competition i. Taxes and subsidies for trucking ii. Pipeline regulation: construction and ...

  5. 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.

  6. 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.

  7. 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.

  8. 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...

  9. 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...

  10. 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...

  11. 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.

  12. Idaho Site Achieves Successful Nuclear Shipment on Newly Constructed Haul Road

    Office of Energy Efficiency and Renewable Energy (EERE)

    IDAHO FALLS, Idaho – Close coordination among operations, security and transportation teams at the Idaho site helped ensure the recent success of the first nuclear shipment on a newly constructed haul road.

  13. " 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"

  14. " 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"

  15. 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

  16. 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.

  17. 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.

  18. Dual-circuit segmented rail phased induction motor

    DOE Patents [OSTI]

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

    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.

  19. 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 Energy Defense Waste Management Programs Advanced

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

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

    to Transport Moab Mill Tailings by Rail DOE to Transport Moab Mill Tailings by Rail August 5, 2008 - 2:40pm Addthis Department Approves Project Baseline and Obtains Nuclear Regulatory Commission Nod WASHINGTON, DC - The U.S. Department of Energy (DOE) today reaffirmed its prior decision to relocate mill tailings predominantly by rail from the former uranium-ore processing site near Moab, Utah, 30 miles north to Crescent Junction, Utah. As determined previously, oversized material that is not

  1. "Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report.' Note: Includes both U.S. Shipments and Exports."

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

    Annual photovoltaic module shipments, 2004-2014 (peak kilowatts)" "Year","Modules" 2004,143274 2005,204996 2006,320208 2007,494148 2008,920693 2009,1188879 2010,2644498 2011,3772075 2012,4655005 2013,4984881 2014,6237524 "Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report.' Note: Includes both U.S. Shipments and Exports.

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

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

    | Department of Energy 4: January 19, 2009 Energy Intensity of Light Rail Transit Systems Fact #554: January 19, 2009 Energy Intensity of Light Rail Transit Systems 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-mile. There are only four light rail systems with energy intensity over 10,000 Btu per passenger-mile. These systems may have improved

  3. CNG-Hybrid: A Practical Path to "Net Zero Emissions" in Commuter Rail

    Broader source: Energy.gov [DOE]

    This 3-stage project proposes modernizing and hybridizing commuter rail locomotives by conversion to natural gas, using waste heat recovery, and employing intercooled gas turbine engines.

  4. 2011-07 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" |

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

    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. Rec 2011-07 - July 27, 2011 (78.0

  5. 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.

  6. 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.

  7. 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.

  8. Guidance for Radiation Accident Management

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

    Procedure Demonstration Introduction Radioactive materials are among the many kinds of hazardous substances emergency responders might have to deal with in an accident. It is ...

  9. Accident Investigation Report- Fire Report

    Broader source: Energy.gov [DOE]

    On February 7, 2014, Deputy Assistant Secretary, Safety, Security, and Quality Programs Environmental Management, DOE, formally appointed an Accident Investigation Board to investigate an...

  10. 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 world’s 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.

  11. 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.

  12. 2011-03 "Using Rail transport for Moving Waste" | Department of Energy

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

    3 "Using Rail transport for Moving Waste" 2011-03 "Using Rail transport for Moving Waste" The intent of this NNMCAB recommendation is to see that the required cleanup at LANL is completed in the safest way, specifically relative to movement of waste. Rec 2011-03 - January 26, 2011 (158.28

  13. 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.

  14. 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. ...

  15. DOE Accident Prevention and Investigation Program | Department...

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

    Additionally, HSS has developed: SAF-230 - 40 hour Accident Investigator, and the online SAF-230DE Accident Investigation Orientation, training courses. For more information see ...

  16. Severe Accident Studies | Department of Energy

    Office of Environmental Management (EM)

    accidents and safety. PDF icon Severe Accident Studies More Documents & Publications Spent Fuel Transportation Risk Assessment DOE-STD-101-92 EIS-0218-SA-07: Supplement Analysis

  17. Microsoft Word - 10,000th Shipment Commemoration Release Final.doc

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

    10,000 th Shipment Celebrated at WIPP CARLSBAD, N.M., October 27, 2011 - Approximately 130 people gathered at the U.S. Department of Energy's (DOE's) Waste Isolation Pilot Plant (WIPP) on October 22, to celebrate the 10,000 th shipment of transuranic (TRU) waste to WIPP, which arrived safely late last month. The event was attended by elected and appointed officials, state and local leaders, WIPP employees and representatives of the carriers who transport TRU waste to WIPP. "People in D.C.

  18. 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.

  19. "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than

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

    5,000 Cubic Meters of Nuclear Waste to WIPP | Department of Energy "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues to safely treat and dispose of radioactive waste created while producing

  20. 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

  1. 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

  2. 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 $5,425,417 Total Modules $0.87 Table 2. Value and average value of photovoltaic module shipments, 2014 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.

  3. Table Definitions, Sources, and Explanatory Notes

    Gasoline and Diesel Fuel Update (EIA)

    Rail

  4. Recent experience in planning, packaging and preparing noncommercial spent fuel for shipment in the United States

    SciTech Connect (OSTI)

    Shappert, L.B.; Parks, C.V.; Turner, D.W.; Aramayo, G.A.

    1998-05-01

    The US Department of Energy-Headquarters (DOE-HQ) has issued a Record of Decision (ROD) which identified the plan to be followed in managing spent nuclear fuel (SNF) belonging to the Department. As a result, the aluminum-clad fuels stored at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, were directed to be shipped to the Savannah River Site (SRS) near Aiken, South Carolina. The BMI-1 cask was chosen to make the shipments of SNF from dry storage that had to be placed in canisters. However, the Certificate of Compliance (COC) for the BMI-1 cask limited the fissile material loading to 800 g of unirradiated fissile material for the cask configuration chosen. Because about half of the canisters were already filled and sealed with more fissile material than was permitted by the COC, approval to make these shipments in the BMI-1 was requested from the Nuclear Regulatory Commission (NRC). A safety analysis showed that the shipments could be made safely under the conditions identified. The waiver was granted in September 1997 and the three shipments were successfully completed in January 1998.

  5. Savannah River Site offsite hazardous waste shipment data validation report. Revision 1

    SciTech Connect (OSTI)

    Casey, C.; Kudera, D.E.; Page, L.A.; Rohe, M.J.

    1995-05-01

    The objective of this data validation is to verify that waste shipments reported in response to the US Department of Energy Headquarters data request are properly categorized according to DOE-HQ definitions. This report documents all findings and actions resulting from the independent review of the Savannah River Site data submittal, and provides a summary of the SRS data submittal and data validation strategy. The overall hazardous waste management and offsite release process from 1987--1991 is documented, along with an identification and description of the hazardous waste generation facilities. SRS did not ship any hazardous waste offsite before 1987. Sampling and analysis and surface surveying procedures and techniques used in determining offsite releasability of the shipments are also described in this report. SRS reported 150 manifested waste shipments from 1984 to 1991 that included 4,755 drums or lab packs and 13 tankers. Of these waste items, this report categorizes 4,251 as clean (including 12 tankers), 326 as likely clean, 138 as likely radioactive, and 55 as radioactive (including one tanker). Although outside the original scope of this report, 14 manifests from 1992 and 1993 are included, covering 393 drums or lab packs and seven tankers. From the 1992--1993 shipments, 58 drums or lab packs are categorized as radioactive and 16 drums are categorized as likely radioactive. The remainder are categorized as clean.

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 2011-02 "Accelerating TRU Waste Shipments from Area G to WIPP" | Department

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

    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

  12. 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.

  13. Type B Accident Investigation Board Report on the October 8,...

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

    Type B Accident Investigation on the February 17, 2004, Personal Injury Accident, Bettis Atomic Power Laboratory Type B Accident Investigation of the Arc Flash at Brookhaven ...

  14. 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 ...

  15. 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...

  16. ENVIRONMENTAL ASSESSMENT FOR THE PROPOSED WITHDRAWAL OF PUBLIC LANDS WITHIN AND SURROUNDING THE CALIENTE RAIL CORRIDOR, NEVADA

    SciTech Connect (OSTI)

    DOE

    2005-12-01

    The purpose for agency action is to preclude surface entry and the location of new mining claims, subject to valid existing rights, within and surrounding the Caliente rail corridor as described in the Yucca Mountain FEIS (DOE 2002). This protective measure is needed to enhance the safe, efficient, and uninterrupted evaluation of land areas for potential rail alignments within the Caliente rail corridor. The evaluation will assist the DOE in determining, through the Rail Alignment environmental impact statement (EIS) process, whether to construct a branch rail line, and to provide support to the BLM in deciding whether or not to reserve a ROW for the rail line under the Federal Land Policy and Management Act (FLPMA). The BLM participated as a cooperating agency in preparing this EA because it is the responsible land manager and BLM staff could contribute resource specific expertise.

  17. 2011-09 "New Urgency for Increased TRU Shipments from MDA G" | Department

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

    of Energy 9 "New Urgency for Increased TRU Shipments from MDA G" 2011-09 "New Urgency for Increased TRU Shipments from MDA G" The intent of this recommendation is to provide confidence to the Northern New Mexico communities that DOE is responding to the need to protect their health and safety. Rec 2011-09 - July 27, 2011 (80.7

  18. 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.

  19. 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.

  20. " Row: NAICS Codes, Value of Shipments and Employment Sizes;"

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

    2 Capability to Switch Natural Gas to Alternative Energy Sources, 2010;" " Level: National and Regional Data;" " Row: NAICS Codes, Value of Shipments and Employment Sizes;" " Column: Energy Sources;" " Unit: Billion Cubic Feet." ,,"Natural Gas",,,"Alternative Energy Sources(b)" ,,,,,,,,,,"Coal Coke" "NAICS"," ","Total","

  1. " Row: NAICS Codes, Value of Shipments and Employment Sizes;"

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

    6 Capability to Switch Electricity to Alternative Energy Sources, 2010; " " Level: National and Regional Data;" " Row: NAICS Codes, Value of Shipments and Employment Sizes;" " Column: Energy Sources;" " Unit: Million Kilowatthours." ,,"Electricity Receipts",,,"Alternative Energy Sources(b)" ,,,,,,,,,,"Coal Coke" "NAICS"," ","Total","

  2. 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

  3. 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

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

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

    871 ANNUAL REPORT - FY 2002 Radioactive Waste Shipments To And From The Nevada Test Site (NTS) January 2003 United States Department of Energy National Nuclear Security Administration Nevada Operations 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.fedworld.gov Online ordering: http://www.ntis.gov/ordering.htm

  5. 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

  6. 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

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

    Office of Environmental Management (EM)

    Investigation, Subcontractor Employee Personal Protective Equipment Ignition Incident on ... Type B Accident Investigation, Subcontractor Employee Personal Protective Equipment ...

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

    SciTech Connect (OSTI)

    Rucker, D.F.

    2000-09-01

    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.

  9. Table 10.6 Solar Thermal Collector Shipments by Type, Price, and Trade, 1974-2009 (Thousand Square Feet, Except as Noted)

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

    Solar Thermal Collector Shipments by Type, Price, and Trade, 1974-2009 (Thousand Square Feet, Except as Noted) Year Low-Temperature Collectors 1 Medium-Temperature Collectors 2 High-Temperature Collectors 3 Total Shipments Trade Number of U.S. Manu- facturers Quantity Shipped Shipments per Manu- facturer Price 4 (dollars 5 per square foot) Number of U.S. Manu- facturers Quantity Shipped Shipments per Manu- facturer Price 4 (dollars 5 per square foot) Quantity Shipped Price 4 (dollars 5 per

  10. Analysis of the D0 Crane Rail as a Support for a Horizontal Lifeline

    SciTech Connect (OSTI)

    Cease, H.; /Fermilab

    2000-03-02

    The D-Zero crane rail is analyzed for use as an anchor support for a one person Horizon{trademark} Horizontal Lifeline system that will span the pit area at D-Zero assembly hall. The lifeline will span 75 ft across the pit area, will be located out of the travel of the crane and above the concrete lentil wall. The crane rail is a suitable anchor for a one person Horizon TM Horizontal Lifeline system. The expected stress on the rail is 1,995 psi which has a factor of safety of 5.5 on the allowable stress. The anchor position is located 18 feet away from the concrete lentil wall and out of the travel of the overhead crane.

  11. 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.

  12. Physical Protection of Spent Fuel Shipments: Resolution of Stakeholder Concerns Through Rulemaking - 12284

    SciTech Connect (OSTI)

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

    2012-07-01

    In 1999, the State of Nevada brought its concerns about physical protection of current spent nuclear fuel (SNF) shipments, and future SNF shipments to a federal repository, before the NRC in a 1999 petition for rulemaking (PRM-73-10). In October 2010, the NRC published a rulemaking decision which would significantly strengthen physical protection of SNF in transit. The newest articulation of the rule (10 CFR 73.37) incorporates regulatory clarifications and security enhancements requested in Nevada's 1999 petition for rulemaking, codifies the findings of the Nuclear NRC and DOE consequence analyses into policy guidance documents and brings forward into regulations the agency and licensee experience gained since the terrorist attacks of September 11, 2001. Although at present DOE SNF shipments would continue to be exempt from these NRC regulations, Nevada considers the rule to constitute a largely satisfactory resolution to stakeholder concerns raised in the original petition and in subsequent comments submitted to the NRC. This paper reviews the process of regulatory changes, assesses the specific improvements contained in the new rules and briefly describes the significance of the new rule in the context of a future national nuclear waste management program. Nevada's petition for rulemaking led to a generally satisfactory resolution of the State's concerns. The decade plus timeframe from petition to rulemaking conclusion saw a sea change in many aspects of the relevant issues - perhaps most importantly the attacks on 9/11 led to the recognition by regulatory bodies that a new threat environment exists wherein shipments of SNF and HLW pose a viable target for human initiated events. The State of Nevada has always considered security a critical concern for the transport of these highly radioactive materials. This was one of the primary reasons for the original rulemaking petition and subsequent advocacy by Nevada on related issues. NRC decisions on the majority of

  13. 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

  14. " Row: NAICS Codes; Column: Energy Sources and Shipments;"

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

    .1. Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" " Level: National Data; " " Row: NAICS Codes; Column: Energy Sources and Shipments;" " Unit: Establishment Counts." " "," "," "," "," "," "," "," "," "," "," ",," " " "," ","Any",," "," ",,"

  15. " Row: Selected SIC Codes; Column: Energy Sources and Shipments;"

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

    1. First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" " Level: National Data; " " Row: Selected SIC Codes; Column: Energy Sources and Shipments;" " Unit: Physical Units or Btu." " "," "," "," "," "," "," "," "," "," "," ",," " " "," "," ",," "," ",," ","

  16. " Row: Selected SIC Codes; Column: Energy Sources and Shipments;"

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

    2. First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" " Level: National Data; " " Row: Selected SIC Codes; Column: Energy Sources and Shipments;" " Unit: Trillion Btu." " "," "," "," "," "," "," "," "," "," "," ",," " " "," "," ",," "," ",," "," ",,"

  17. 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.

  18. 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.

  19. Level: National Data and Regional Totals; Row: NAICS Codes, Value of Shipments and Employment Sizes;

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

    0 Capability to Switch Coal to Alternative Energy Sources, 2006; Level: National Data and Regional Totals; Row: NAICS Codes, Value of Shipments and Employment Sizes; Column: Energy Sources; Unit: Thousand Short Tons. NAICS Total Not Electricity Natural Distillate Residual Code(a) Subsector and Industry Consumed(c) Switchable Switchable Receipts(d) Gas Fuel Oil Fuel Oil LPG Other(e) Total United States 311 Food 6,603 1,013 5,373 27 981 303 93 271 86 3112 Grain and Oilseed Milling 5,099 658 4,323

  20. Level: National and Regional Data; Row: NAICS Codes, Value of Shipments and Employment Sizes;

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

    6 Capability to Switch Electricity to Alternative Energy Sources, 2010; Level: National and Regional Data; Row: NAICS Codes, Value of Shipments and Employment Sizes; Column: Energy Sources; Unit: Million Kilowatthours. Coal Coke NAICS Total Not Natural Distillate Residual and Code(a) Selected Subsectors and Industry Receipts(c) Switchable Switchable Gas Fuel Oil Fuel Oil Coal LPG Breeze Other(d) Total United States 311 Food 75,673 2,403 70,987 666 1,658 Q 406 Q Q 141 3112 Grain and Oilseed

  1. 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.

  2. 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

  3. 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.

  4. 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).

  5. 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

  6. 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

  7. 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.

  8. 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.

  9. 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.

  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 the Oak Ridge Institute for Science and Education (ORISE) maintains a number of radiation ...

  11. 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.

  12. 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.

  13. 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.

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

    Broader source: Energy.gov [DOE]

    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.

  15. 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

  16. Examining Supply Chain Resilience for the Intermodal Shipment of Spent Nuclear Fuel and High Level Radioactive Materials

    SciTech Connect (OSTI)

    Peterson, Steven K

    2016-01-01

    The U.S. Department of Energy (DOE) has a significant programmatic interest in the safe and secure routing and transportation of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States, including shipments entering the country from locations outside U.S borders. In any shipment of SNF/HLW, there are multiple chains; a jurisdictional chain as the material moves between jurisdictions (state, federal, tribal, administrative), a physical supply chain (which mode), as well as a custody chain (which stakeholder is in charge/possession) of the materials being transported. Given these interconnected networks, there lies vulnerabilities, whether in lack of communication between interested stakeholders or physical vulnerabilities such as interdiction. By identifying key links and nodes as well as administrative weaknesses, decisions can be made to harden the physical network and improve communication between stakeholders. This paper examines the parallel chains of oversight and custody as well as the chain of stakeholder interests for the shipments of SNF/HLW and the potential impacts on systemic resiliency. Using the Crystal River shutdown location as well as a hypothetical international shipment brought into the United States, this paper illustrates the parallel chains and maps them out visually.

  17. 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.

  18. 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

  19. 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 ...

  20. 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 ...

  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. 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 ...

  4. 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 ...

  5. 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 ...

  6. 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). ...

  7. 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 ...

  8. Type B Accident Investigation Board Report of the Savannah River...

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

    Processing Facility on October 6, 2009 Type B Accident Investigation Board Report of the ... This report documents the results of the Type B Accident Investigation Board (Board) ...

  9. 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 ... Type B Accident Investigation Board Report on the October 15, 2001, Grout Injection ...

  10. 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 ...

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

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

    (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to investigate an accident that resulted in the fatality of a Wilson Construction Company Crew Foreman. ...

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

    Energy Savers [EERE]

    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 ...

  13. Table 9. U.S. photovoltaic module shipments by state/territory, 2014 (peak kilow

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

    photovoltaic module shipments by state/territory, 2014 (peak kilowatts)" "State","Total","Percent of U.S. total" "Alabama",482,0 "Alaska",81,0 "Arizona",194476,0.033 "Arkansas",336,0 "California",3163120,0.53 "Colorado",47240,0.008 "Connecticut",50745,0.009 "Delaware",6600,0.001 "District of Columbia",751,0 "Florida",18593,0.003 "Georgia",47660,0.008

  14. 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

  15. 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.

  16. 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.

  17. 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`.

  18. 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.

  19. 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.

  20. Chernobyl accident: A comprehensive risk assessment

    SciTech Connect (OSTI)

    Vargo, G.J.; Poyarkov, V.; Baryakhtar, V.; Kukhar, V.; Los, I.

    1999-01-01

    The authors, all of whom are Ukrainian and Russian scientists involved with Chernobyl nuclear power plant since the April 1986 accident, present a comprehensive review of the accident. In addition, they present a risk assessment of the remains of the destroyed reactor and its surrounding shelter, Chernobyl radioactive waste storage and disposal sites, and environmental contamination in the region. The authors explore such questions as the risks posed by a collapse of the shelter, radionuclide migration from storage and disposal facilities in the exclusion zone, and transfer from soil to vegetation and its potential regional impact. The answers to these questions provide a scientific basis for the development of countermeasures against the Chernobyl accident in particular and the mitigation of environmental radioactive contamination in general. They also provide an important basis for understanding the human health and ecological risks posed by the accident.

  1. 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.

  2. 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

  3. 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)

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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.

  9. 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).

  10. NIF: Impacts of chemical accidents and comparison of chemical/radiological accident approaches

    SciTech Connect (OSTI)

    Lazaro, M.A.; Policastro, A.J.; Rhodes, M.

    1996-01-12

    The US Department of Energy (DOE) proposes to construct and operate the National Ignition Facility (NIF). The goals of the NIF are to (1) achieve fusion ignition in the laboratory for the first time by using inertial confinement fusion (ICF) technology based on an advanced-design neodymium glass solid-state laser, and (2) conduct high-energy-density experiments in support of national security and civilian applications. The primary focus of this paper is worker-public health and safety issues associated with postulated chemical accidents during the operation of NIF. The key findings from the accident analysis will be presented. Although NIF chemical accidents will be emphasized, the important differences between chemical and radiological accident analysis approaches and the metrics for reporting results will be highlighted. These differences are common EIS facility and transportation accident assessments.

  11. 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).

  12. 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 ...

  13. 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 ...

  14. 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.

  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. 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.

  17. 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.

  18. 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.

  19. 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.

  20. Accident Investigation Board (AIB) findings about the drum breach...

    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 ...

  1. 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 ... Thousands of workers have completed millions of accident-free hours at this heavy industry ...

  2. 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...

  3. 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.

  4. 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 1000ºC 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.

  5. ANS severe accident program overview & planning document

    SciTech Connect (OSTI)

    Taleyarkhan, R.P.

    1995-09-01

    The Advanced Neutron Source (ANS) severe accident document was developed to provide a concise and coherent mechanism for presenting the ANS SAP goals, a strategy satisfying these goals, a succinct summary of the work done to date, and what needs to be done in the future to ensure timely licensability. Guidance was received from various bodies [viz., panel members of the ANS severe accident workshop and safety review committee, Department of Energy (DOE) orders, Nuclear Regulatory Commission (NRC) requirements for ALWRs and advanced reactors, ACRS comments, world-wide trends] were utilized to set up the ANS-relevant SAS goals and strategy. An in-containment worker protection goal was also set up to account for the routine experimenters and other workers within containment. The strategy for achieving the goals is centered upon closing the severe accident issues that have the potential for becoming certification issues when assessed against realistic bounding events. Realistic bounding events are defined as events with an occurrency frequency greater than 10{sup {minus}6}/y. Currently, based upon the level-1 probabilistic risk assessment studies, the realistic bounding events for application for issue closure are flow blockage of fuel element coolant channels, and rapid depressurization-related accidents.

  6. 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

  7. 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 phases 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.

  8. Phase II Accident Investigation Board Briefing | Department of Energy

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

    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 Investigation. Information Provided included the Judgments of NEED and Causes That Contributed to the Incident. AIB Brief - May 20, 2015 (1.98

  9. 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.

  10. 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.

  11. 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 Rež, 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.

  12. 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

  13. Table 10.7 Solar Thermal Collector Shipments by Market Sector, End Use, and Type, 2001-2009 (Thousand Square Feet)

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

    Solar Thermal Collector Shipments by Market Sector, End Use, and Type, 2001-2009 (Thousand Square Feet) Year and Type By Market Sector By End Use Total Residential Commercial 1 Industrial 2 Electric Power 3 Other 4 Pool Heating Water Heating Space Heating Space Cooling Combined Heating 5 Process Heating Electricity Generation Total Shipments 6<//td> 2001 Total 10,125 1,012 17 1 35 10,797 274 70 0 12 34 2 11,189 Low 7 9,885 987 12 0 34 10,782 42 61 0 0 34 0 10,919 Medium 8 240 24 5 0 1 16

  14. "Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report.'"

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

    Destination of photovoltaic module export shipments, 2014" "peak kilowatts" "Country/Continent","Total","Percent of U.S. Total" "Africa/Europe",53898,0.29 "Asia/Australia",107460,0.59 "South/Central America",11692,0.06 "Canada",4378,0.02 "Mexico",5556,0.03 "Total",182984,1 "Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report.'

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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)

  1. 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, Fe

  2. 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.

  3. A framework for the assessment of severe accident management strategies

    SciTech Connect (OSTI)

    Kastenberg, W.E.; Apostolakis, G.; Dhir, V.K.

    1993-09-01

    Severe accident management can be defined as the use of existing and/or altemative resources, systems and actors to prevent or mitigate a core-melt accident. For each accident sequence and each combination of severe accident management strategies, there may be several options available to the operator, and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrumentation behavior during an accident. A framework based on decision trees and influence diagrams has been developed which incorporates such criteria as feasibility, effectiveness, and adverse effects, for evaluating potential severe accident management strategies. The framework is also capable of propagating both data and model uncertainty. It is applied to several potential strategies including PWR cavity flooding, BWR drywell flooding, PWR depressurization and PWR feed and bleed.

  4. Assessment of light water reactor accident management programs and experience

    SciTech Connect (OSTI)

    Hammersley, R.J.

    1992-03-01

    The objective of this report is to provide an assessment of the current light water reactor experience regarding accident management programs and associated technology developments. This assessment for light water reactor (LWR) designs is provided as a resource and reference for the development of accident management capabilities for the production reactors at the Savannah River Site. The specific objectives of this assessment are as follows: 1. Perform a review of the NRC, utility, and industry (NUMARC, EPRI) accident management programs and implementation experience. 2. Provide an assessment of the problems and opportunities in developing an accident management program in conjunction or following the Individual Plant Examination process. 3. Review current NRC, utility, and industry technological developments in the areas of computational tools, severe accident predictive tools, diagnostic aids, and severe accident training and simulation.

  5. 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

  6. Federally Led Accident Investigation Reports | Department of Energy

    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 April 21, 2015 Accident Investigations of the February 14, 2014, Radiological Release at the Waste Isolation Pilot Plant, Carlsbad, NM On Friday, February 14, 2014, there was a release of radioactive material in the underground repository at the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Following initial visual inspections

  7. Accident Response Group | National Nuclear Security Administration | (NNSA)

    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

  8. 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.

  9. 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.

  10. 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...

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

    Energy Savers [EERE]

    IMPROVEMENT OF DESIGN CODES TO ACCOUNT FOR ACCIDENT THERMAL EFFECTS ON SEISMIC PERFORMANCE ... PROJECT OBJECTIVES (CONT'D) Develop design guidelines and recommendations for ...

  12. Type B Accident Investigation of the January 10, 2006, Flash...

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

    Independent Oversight Follow-up Review, Savannah River National Laboratory - January 2012 Type B Accident Investigation of the Arc Flash at Brookhaven National Laboratory, April ...

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

    Energy Savers [EERE]

    Arc Flash at Brookhaven National Laboratory, April 14, 2006 Type B Accident Investigation of the Arc Flash at Brookhaven National Laboratory, April 14, 2006 February 10, 2006 An ...

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

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

    Power Marketing Administration Accident Investigation of the September 20, 2012 Fatal Fall from the Dworshak-Taft 1 Transmission Tower, at the Bonneville Power Marketing ...

  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. 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...

  17. Recommendations for Analyzing Accidents Under NEPA (DOE, 2002)

    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.

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

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

    Sandia National Laboratory Site 9920, Albuquerque, NM Accident Investigation of the December 11, 2013, Integrated Device Fireset and Detonator Accidental Discharge at the Sandia ...

  19. Code System to Model LWR Meltdown Accident Response.

    Energy Science and Technology Software Center (OSTI)

    2001-04-25

    MARCH2 describes the response of water cooled reactors to severe accidents, including consideration of the primary coolant system as well as the containment.

  20. 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 ...

  1. 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...

  2. 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...

  3. 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: ...

  4. 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 ...

  5. 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...

  6. 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 ...

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

    Office of Environmental Management (EM)

    September 1, 2010 Type B Accident Investigation Board Report Employee Puncture Wound at ... investigation of the June 14, 2010, employee puncture wound at the Department of ...

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

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

    Employee Foot Injury on December 17, 2003, at the East Tennessee Technology Park Building K-31 Type B Accident Investigation Board Report BNFL, Inc. Employee Foot Injury on ...

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

    Energy Savers [EERE]

    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 ...

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

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

    Company Employee Fatality near Patrick's Knob Radio Station, Bonneville Power Administration Accident Investigation of the October 1, 2013, Tice Electric Company Employee Fatality ...

  11. Type B Accident Investigation Board Report Employee Puncture...

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

    investigation of the June 14, 2010, employee puncture wound at the Department of ... TYPE B ACCIDENT INVESTIGATION BOARD REPORT EMPLOYEE PUNCTURE WOUND AT THE F-TRU WASTE ...

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

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

    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 ...

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

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

    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 ...

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

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

    Report, May 8, 2004, Exothermic Metal Reactor Event During Sodium Transfer Activities, ... Type B Accident Investigation Board Report, May 8, 2004, Exothermic Metal Reactor Event ...

  15. 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 ...

  16. 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 ...

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

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

    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 ...

  18. Type A Accident Investigation of the June 21, 2001, Drilling...

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

    June 21, 2001, Drilling Rig Operator Injury at the Fermi National Accelerator Laboratory, August 2001 Type A Accident Investigation of the June 21, 2001, Drilling Rig Operator ...

  19. 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)

  20. 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.

  1. 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.

  2. 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).

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

    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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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 ...

  17. 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 ...

  18. 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 ...

  19. 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).

  20. 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.

  1. 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

  2. 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.}

  3. 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)

  4. The Y-12 Plant No Rad-Added Program for off-site shipment of nonradioactive hazardous waste

    SciTech Connect (OSTI)

    Cooper, K.H.; Mattie, B.K.; Williams, J.L.; Jacobs, D.G.; Roberts, K.A.

    1994-02-14

    On May 17, 1991, the US Department of Energy (DOE) issued a directive for DOE operations to cease off-site shipments of non-radioactive hazardous waste pending further clarification and approvals. A DOE Performance Objective for Certification of Non-Radioactive Hazardous Waste was issued in November 1991. In response to these directives, the Waste Management Division of Oak Ridge Y-12 Plant, with assistance from Roy F. Weston, Inc., has developed a No Rad-Added Program to provide small programmatic guidance and a set of procedures, approved by DOE, which will permit hazardous waste to be shipped from the Y-12 Plant to commercial treatment, storage, or disposal facilities after ensuring and certifying that hazardous waste has no radioactivity added as a result of DOE operations. There are serious legal and financial consequences of shipping waste containing radioactivity to an off-site facility not licensed to receive radioactive materials. Therefore, this program is designed with well-defined responsibilities and stringent documentation requirements.

  5. Biofuels Task Force.pdf

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

    ... Brian Hazen-Manager, Advanced Technologies & Alternative ... import volumes, Flex-Fuel Vehicle (FFV) production, and ... Figure 4 shows recent trends in rail shipments of ethanol ...

  6. ,"Total Crude Oil and Petroleum Products Net Receipts by Pipeline, Tanker, Barge and Rail between PAD Districts"

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

    Net Receipts by Pipeline, Tanker, Barge and Rail between PAD Districts" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Total Crude Oil and Petroleum Products Net Receipts by Pipeline, Tanker, Barge and Rail between PAD Districts",5,"Monthly","6/2016","1/15/1981" ,"Release

  7. 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 ≥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 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 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.

  8. 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.

  9. Material Selection for Accident Tolerant Fuel Cladding

    SciTech Connect (OSTI)

    Pint, Bruce A.; Terrani, Kurt A.; Yamamoto, Yukinori; Snead, Lance Lewis

    2015-01-01

    Alternative cladding materials to Zr-based alloys are being investigated for accident tolerance, which can be defined as > 100X improvement (compared to Zr-based alloys) in oxidation resistance to steam or steam-H2 environments at ≥ 1200°C for short 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. However, commercial Ti2AlC that was not single phase, formed a much thicker oxide at 1200°C in steam and significant TiO2, and therefore Ti2AlC may be challenging to form 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 α´ formation. The composition effects and critical limits to retaining protective scale formation at > 1400°C are still being evaluated.

  10. 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

  11. Next-generation nuclear fuel withstands high-temperature accident...

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

    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 ...

  12. 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 ...

  13. 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...

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

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

    Bechtel Jacobs Company, LLC Employee Fall Injury on January 3, 2006, at the K-25 Building, ... Type B Accident Investigation Board Report of the Bechtel Jacobs Company, LLC Employee ...

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

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

    of the October 9, 2008 Employee Injured when Rocket Motor Unexpectedly Fired at the Sandia ... Type B Accident Investigation of the October 9, 2008 Employee Injured when Rocket Motor ...

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

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

    wire on the Grand Coulee-Bell 6 500-kV line between tower 842 and BPA's Bell Substation in Mead, Washington. (See Appendix 7, Site Map.) Level 1 Accident Investigation ...

  17. 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...

  18. 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, ...

  19. 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, ...

  20. 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,...

  1. 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.

  2. 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.

  3. Volume II - Accident and Operational Safety Analysis Handbook

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

    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

  4. Revised accident source terms for light-water reactors

    SciTech Connect (OSTI)

    Soffer, L.

    1995-02-01

    This paper presents revised accident source terms for light-water reactors incorporating the severe accident research insights gained in this area over the last 15 years. Current LWR reactor accident source terms used for licensing date from 1962 and are contained in Regulatory Guides 1.3 and 1.4. These specify that 100% of the core inventory of noble gases and 25% of the iodine fission products are assumed to be instantaneously available for release from the containment. The chemical form of the iodine fission products is also assumed to be predominantly elemental iodine. These assumptions have strongly affected present nuclear air cleaning requirements by emphasizing rapid actuation of spray systems and filtration systems optimized to retain elemental iodine. A proposed revision of reactor accident source terms and some im implications for nuclear air cleaning requirements was presented at the 22nd DOE/NRC Nuclear Air Cleaning Conference. A draft report was issued by the NRC for comment in July 1992. Extensive comments were received, with the most significant comments involving (a) release fractions for both volatile and non-volatile species in the early in-vessel release phase, (b) gap release fractions of the noble gases, iodine and cesium, and (c) the timing and duration for the release phases. The final source term report is expected to be issued in late 1994. Although the revised source terms are intended primarily for future plants, current nuclear power plants may request use of revised accident source term insights as well in licensing. This paper emphasizes additional information obtained since the 22nd Conference, including studies on fission product removal mechanisms, results obtained from improved severe accident code calculations and resolution of major comments, and their impact upon the revised accident source terms. Revised accident source terms for both BWRS and PWRS are presented.

  5. 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).

  6. 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.

  7. 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

  8. 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.

  9. 08FFL-0020Influence of High Fuel Rail Pressure and Urea Selective Catalytic Reduction on PM Formation in an Off-Highway Heavy-Duty Diesel Engine

    SciTech Connect (OSTI)

    Kass, Michael D; Domingo, Norberto; Storey, John Morse; Lewis Sr, Samuel Arthur

    2008-01-01

    The influence of fuel rail pressure (FRP) and urea-selective catalytic reduction (SCR) on particulate matter (PM) formation is investigated in this paper along with notes regarding the NOx and other emissions. Increasing FRP was shown to reduce the overall soot and total PM mass for four operating conditions. These conditions included two high speed conditions (2400 rpm at 540 and 270 Nm of torque) and two moderated speed conditions (1400 rpm at 488 and 325 Nm). The concentrations of CO2 and NOx increased with fuel rail pressure and this is attributed to improved fuel-air mixing. Interestingly, the level of unburned hydrocarbons remained constant (or increased slightly) with increased FRP. PM concentration was measured using an AVL smoke meter and scanning mobility particle sizer (SMPS); and total PM was collected using standard gravimetric techniques. These results showed that the smoke number and particulate concentrations decrease with increasing FRP. However the decrease becomes more gradual as very high rail pressures. Additionally, the total PM decreased with increasing FRP; however, the soluble organic fraction (SOF) reaches a maximum after which it declines with higher rail pressure. The total PM was collected for the two 1400 rpm conditions downstream of the engine, diesel oxidation catalyst, and a urea-SCR catalyst. The results show that significant PM reduction occurs in the SCR catalyst even during high rates of urea dosage. Analysis of the PM indicates that residual SOF is burned up in the SCR catalyst.

  10. 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.

  11. 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)

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. "Economic","per Employee","of Value Added","of Shipments" "Characteristic(a)","(million Btu)","(thousand Btu)","(thousand Btu)"

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

    2 Relative Standard Errors for Table 6.2;" " Unit: Percents." ,,,"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

  17. 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

  18. 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

  19. 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

  20. 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 ...

  1. DOE-ID FOIA Type A Accident Investigation Board Report - July...

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

    Research Library You are here: DOE-ID Home > FOIA > Type A Accident Investigation Board Report - July 28, 1998 Type A Accident Investigation Board Report - July 28, 1998 Fatality ...

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. Environmental radionuclide distribution in Georgia after the Chernobyl accident

    SciTech Connect (OSTI)

    Mosulishvili, L.M.; Shoniya, N.I.; Katamadze, N.M.

    1994-01-01

    Atmospheric Chernobyl-released radioactivity, assessed at about 2 x 10{sup 18} Bq, caused global environmental contamination. Contaminated air masses appeared in the Transcaucasian region in early May, 1986. Rains that month promoted intense radionuclide deposition all over Georgia. The contamination level of western Georgia considerably exceeded the contamination level of eastern Georgia. The Black Sea coast of Georgia suffered from the Chernobyl accident as much as did strongly contaminated areas of the Ukraine and Belarus`. Unfortunately, governmental decrees on countermeasures against the consequences of the Chernobyl accident at that time did not even refer to the coast of Georgia. The authors observed the first increase in radioactivity background in rainfall samples collected on May 2, 1986, in Tbilisi. {gamma}-Spectrometric measurements of aerosol filters, vegetation, food stuffs, and other objects, in addition to rainfall, persistently confirmed the occurrence of short-lived radionuclides, including {sup 131}I. At first, this fact seemed unbelievable, because the Chernobyl accident had occurred only 4-5 days earlier and far from Georgia. However, these arguments proved to be faulty. Soon, environmental monitoring of radiation in Georgia became urgent. Environmental radionuclide distribution in Georgia shortly after the Chernobyl accident, as well as the methods of analysis, are reported in this paper.

  7. 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.

  8. Type B Accident Investigation of the July 31, 2006, Fall from Ladder

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

    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

  9. 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

  10. Radionuclide release calculations for selected severe accident scenarios

    SciTech Connect (OSTI)

    Denning, R.S.; Leonard, M.T.; Cybulskis, P.; Lee, K.W.; Kelly, R.F.; Jordan, H.; Schumacher, P.M.; Curtis, L.A. )

    1990-08-01

    This report provides the results of source term calculations that were performed in support of the NUREG-1150 study. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants.'' This is the sixth volume of a series of reports. It supplements results presented in the earlier volumes. Analyses were performed for three of the NUREG-1150 plants: Peach Bottom, a Mark I, boiling water reactor; Surry, a subatmospheric containment, pressurized water reactor; and Sequoyah, an ice condenser containment, pressurized water reactor. Complete source term results are presented for the following sequences: short term station blackout with failure of the ADS system in the Peach Bottom plant; station blackout with a pump seal LOCA for the Surry plant; station blackout with a pump seal LOCA in the Sequoyah plant; and a very small break with loss of ECC and spray recirculation in the Sequoyah plant. In addition, some partial analyses were performed which did not require running all of the modules of the Source Term Code Package. A series of MARCH3 analyses were performed for the Surry and Sequoyah plants to evaluate the effects of alternative emergency operating procedures involving primary and secondary depressurization on the progress of the accident. Only thermal-hydraulic results are provided for these analyses. In addition, three accident sequences were analyzed for the Surry plant for accident-induced failure of steam generator tubes. In these analyses, only the transport of radionuclides within the primary system and failed steam generator were examined. The release of radionuclides to the environment is presented for the phase of the accident preceding vessel meltthrough. 17 refs., 176 figs., 113 tabs.

  11. 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.

  12. Level 1 Accident Report of the March 1, 2010 Bobcat Fatality at BPA's White Bluffs Substation

    Broader source: Energy.gov [DOE]

    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 White Bluffs Substation near Richland, Washington on March 1, 2010.

  13. 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

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. 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.

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

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

    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

  2. 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 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 Energy Defense Waste

  3. 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,

  4. 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.

  5. Type B Accident Investigation At Washington Closure Hanford, LLC, Employee

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

    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

  6. Type B Accident Investigation Board Report Subcontractor Radioactive

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

    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,

  7. Type B Accident Investigation Board Report of the Brookhaven National

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

    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

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

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

    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

  9. Estimated long term health effects of the Chernobyl accident

    SciTech Connect (OSTI)

    Cardis, E.

    1996-07-01

    Apart from the dramatic increase in thyroid cancer in those exposed as children, there is no evidence to date of a major public health impact as a result of radiation exposure due to the Chernobyl accident in the three most affected countries (Belarus, Russia, and Ukraine). Although some increases in the frequency of cancer in exposed populations have been reported ,these results are difficult to interpret, mainly because of differences in the intensity and method of follow-up between exposed populations and the general population with which they are compared. If the experience of the survivors of the atomic bombing of Japan and of other exposed populations is applicable, the major radiological impact of the accident will be cases of cancer. The total lifetime numbers of excess cancers will be greatest among the `liquidators` (emergency and recovery workers) and among the residents of `contaminated` territories, of the order of 2000 to 2500 among each group (the size of the exposed populations is 200,000 liquidators and 3,700,000 residents of `contaminated` areas). These increases would be difficult to detect epidemiologically against an expected background number of 41500 and 433000 cases of cancer respectively among the two groups. The exposures for populations due to the Chernobyl accident are different in type and pattern from those of the survivors of the atomic bombing of Japan. Thus predictions derived from studies of these populations are uncertain. The extent of the incidence of thyroid cancer was not envisaged. Since only ten years have lapsed since the accident, continued monitoring of the health of the population is essential to assess the public health impact.

  10. 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.

  11. 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.

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

    SciTech Connect (OSTI)

    Gilles Youinou; R. Sonat Sen

    2013-09-01

    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 accident tolerant fuel contributes to this effort. These fuels, in comparison with the standard zircaloy – UO2 system currently used by the LWR industry, should be designed such that they tolerate loss of active cooling in the core for a longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, and design-basis events. This report presents a preliminary systems analysis related to most of these concepts. The potential impacts of these innovative LWR fuels on the front-end of the fuel cycle, on the reactor operation and on the back-end of the fuel cycle are succinctly described without having the pretension of being exhaustive. Since the design of these various concepts is still a work in progress, this analysis can only be preliminary and could be updated as the designs converge on their respective final version.

  13. 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)

  14. 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.

  15. Radionuclide mass balance for the TMI-2 accident: data-base system and preliminary mass balance. Volume 2

    SciTech Connect (OSTI)

    Goldman, M I; Davis, R J; Strahl, J F; Arcieri, W C; Tonkay, D W

    1983-04-01

    Tables are presented which represent the radionuclide levels following the Three Mile Island-2 reactor accident.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  2. Interface requirements to couple thermal hydraulics codes to severe accident codes: ICARE/CATHARE

    SciTech Connect (OSTI)

    Camous, F.; Jacq, F.; Chatelard, P.

    1997-07-01

    In order to describe with the same code the whole sequence of severe LWR accidents, up to the vessel failure, the Institute of Protection and Nuclear Safety has performed a coupling of the severe accident code ICARE2 to the thermalhydraulics code CATHARE2. The resulting code, ICARE/CATHARE, is designed to be as pertinent as possible in all the phases of the accident. This paper is mainly devoted to the description of the ICARE2-CATHARE2 coupling.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  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. 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

  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. Type B Accident Investigation of the Arc Flash at Brookhaven National Laboratory, April 14, 2006

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type B Accident Investigation Board appointed by Elizabeth D. Sellers, Manager, Idaho Operations Office, U.S. Department of Energy.

  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. 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 ...

  13. Portsmouth Site Plant Surpasses Five Years Without Lost-Time Accident |

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

    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,

  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. Microsoft Word - 2015.06.22 - Report to Congress - Accident Tolerant...

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

    ... Performance improvement may improve the overall economics of the nuclear fuel cycle. RD&D strategy for enhanced accident tolerant fuels The overall strategy for development, ...

  16. Type A Accident Report of the June 26, 2009 Vehicle Fatality...

    Office of Environmental Management (EM)

    Report of the June 26, 2009 Vehicle Fatality at Lawrence Livermore National Laboratory Type A Accident Report of the June 26, 2009 Vehicle Fatality at Lawrence Livermore National ...

  17. 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

    Broader source: Energy.gov [DOE]

    On February 15, 2013, an Accident Investigation Board (the Board) was appointed to investigate an accident that resulted in serious injuries caused when a scissor lift tipped over in Brine Tank-14 (WHT-14) at the Strategic Petroleum Reserve, West Hackberry, Louisiana, site on February 7, 2013. The Board’s responsibilities have been completed with respect to this investigation. The analysis and the identification of the direct cause, root causes, contributing causes, and judgments of need resulting from this investigation were performed in accordance with the Department of Energy (DOE) Order 225.1B, Accident Investigations.

  18. 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.

  19. 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.

  20. 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.