Sample records for transportation accident involving

  1. Accident resistant transport container

    DOE Patents [OSTI]

    Andersen, John A. (Albuquerque, NM); Cole, James K. (Albuquerque, NM)

    1980-01-01T23:59:59.000Z

    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.

  2. Probability of spent fuel transportation accidents

    SciTech Connect (OSTI)

    McClure, J. D.

    1981-07-01T23:59:59.000Z

    The transported volume of spent fuel, incident/accident experience and accident environment probabilities were reviewed in order to provide an estimate of spent fuel accident probabilities. In particular, the accident review assessed the accident experience for large casks of the type that could transport spent (irradiated) nuclear fuel. This review determined that since 1971, the beginning of official US Department of Transportation record keeping for accidents/incidents, there has been one spent fuel transportation accident. This information, coupled with estimated annual shipping volumes for spent fuel, indicated an estimated annual probability of a spent fuel transport accident of 5 x 10/sup -7/ spent fuel accidents per mile. This is consistent with ordinary truck accident rates. A comparison of accident environments and regulatory test environments suggests that the probability of truck accidents exceeding regulatory test for impact is approximately 10/sup -9//mile.

  3. Improving Transportation Safety Through Accident

    E-Print Network [OSTI]

    Minnesota, University of

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

  4. DEVELOPMENT AND USE OF A DIRECTORY OF ACCIDENT DATABASES INVOLVING

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    DEVELOPMENT AND USE OF A DIRECTORY OF ACCIDENT DATABASES INVOLVING CHEMICALS J.P.Pineau Institut from end-users of accident data who need validated data for dealing with risk assessment in which Data collection Data analysis, Reliability, Uncertainty, Accident, Hazardous material, Risk analysis

  5. accidents involving external: Topics by E-print Network

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

    25 Next Page Last Page Topic Index 1 Development and use of the ESReDA directory of accident databases involving chemicals Computer Technologies and Information Sciences Websites...

  6. Potential importance of water pathways for spent fuel transportation accident risk

    SciTech Connect (OSTI)

    Ostmeyer, R.M.

    1986-01-01T23:59:59.000Z

    This paper analyzes the potential importance of water pathway contamination for spent fuel transportation accident risk using a ''worst-case'' water contamination scenario. The scenario used for the analysis involves an accident release that occurs near a reservoir. Water pathway doses are compared to doses for accident releases in urban or agricultural areas. The results of the analysis indicate that water pathways are not important for assessing the risk of transporting spent reactor fuel by truck or by rail.

  7. Decontamination Dressdown at a Transportation Accident Involving

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office of Policy, OAPMMilestone |Procurement of, 2011Department of

  8. Accident Procedure Outline the procedures for accidents involving University of Michigan (U-M) vehicles.

    E-Print Network [OSTI]

    Kirschner, Denise

    owned by U-M are covered by the U-M self insurance program administered by Risk Management. Procedure 1. An accident is defined as any incident that causes damage to people or property. 2. In the event. 4. If the accident causes personal injury to the driver, occupants and/or pedestrian, contact Risk

  9. Temperature of aircraft cargo flame exposure during accidents involving fuel spills

    SciTech Connect (OSTI)

    Mansfield, J.A.

    1993-01-01T23:59:59.000Z

    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.

  10. Examination of offsite radiological emergency protective measures for nuclear reactor accidents involving core melt

    E-Print Network [OSTI]

    Aldrich, David C.

    1979-01-01T23:59:59.000Z

    Evacuation, sheltering followed by population relocation, and iodine prophylaxis are evaluated as offsite public protective measures in response to nuclear reactor accidents involving core-melt. Evaluations were conducted ...

  11. Fatal accidents involving roof falls in coal mining, 1996--1998

    SciTech Connect (OSTI)

    Not Available

    1999-01-01T23:59:59.000Z

    This publication presents information on fatalities involving roof and rib falls that occurred in coal mining operations from January 1996 through December 1998. It includes statistics for the fatalities, as well as abstracts, best practices and illustrations. Conclusion statements have been substituted for best practices where no Title 30 Code of Regulations violations were cited during the accident investigation. From January 1996 through December 1998, 36 miners died at coal operations from accidents classified as roof falls. The information in the report is based on statistics taken from the 1996 through 1998 MSHA Fatal Illustration Programs: Roof Fall Fatalities by District.

  12. Fatal accidents involving roof falls in coal mining, 1996--1998

    SciTech Connect (OSTI)

    NONE

    1999-11-01T23:59:59.000Z

    This publication presents information on fatalities involving roof and rib falls that occurred in coal mining operations from January 1996 through December 1998. It includes statistics for the fatalities, as well as abstracts, best practices and illustrations. Conclusion statements have been substituted for best practices where no Title 30 Code of Regulations violations were cited during the accident investigation. From January 1996 through December 1998, 36 miners died at coal operations from accidents classified as roof falls. The information in the report is based on statistics taken from the 1996 through 1998 MSHA Fatal Illustration Programs: Roof Fall Fatalities by District.

  13. Emergency Response to a Transportation Accident Involving Radioactive

    Office of Environmental Management (EM)

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

  14. Modeling requirements for full-scope reactor simulators of fission-product transport during severe accidents

    SciTech Connect (OSTI)

    Ellison, P.G.; Monson, P.R. (Westinghouse Savannah River Co., Aiken, SC (United States)); Mitchell, H.A. (Concord Associates, Inc., Knoxville, TN (United States))

    1990-01-01T23:59:59.000Z

    This paper describes in the needs and requirements to properly and efficiently model fission product transport on full scope reactor simulators. Current LWR simulators can be easily adapted to model severe accident phenomena and the transport of radionuclides. Once adapted these simulators can be used as a training tool during operator training exercises for training on severe accident guidelines, for training on containment venting procedures, or as training tool during site wide emergency training exercises.

  15. Modeling requirements for full-scope reactor simulators of fission-product transport during severe accidents

    SciTech Connect (OSTI)

    Ellison, P.G.; Monson, P.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Mitchell, H.A. [Concord Associates, Inc., Knoxville, TN (United States)

    1990-12-31T23:59:59.000Z

    This paper describes in the needs and requirements to properly and efficiently model fission product transport on full scope reactor simulators. Current LWR simulators can be easily adapted to model severe accident phenomena and the transport of radionuclides. Once adapted these simulators can be used as a training tool during operator training exercises for training on severe accident guidelines, for training on containment venting procedures, or as training tool during site wide emergency training exercises.

  16. Development and use of the ESReDA directory of accident databases involving chemicals

    E-Print Network [OSTI]

    Boyer, Edmond

    , Data analysis, Reliability, Uncertainty, Accident, Hazardous material, Risk analysis. INTRODUCTION to the quality of data collected from accident investigations and their subsequent analysis. Many frameworks, a working group ofEuropean Safety, Reliability and Data Association (ESReDA) "Accident Analysis" (AA

  17. Control of Major-Accident Hazards Involving Land Transmission Charlotte BOUISSOU, Project Manager for Pipelines Risk Assessment

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    aims to help authorities to balance the requirement of the new pipeline regulation with regardsControl of Major-Accident Hazards Involving Land Transmission Pipelines Charlotte BOUISSOU, Project Manager for Pipelines Risk Assessment Sandrine DESCOURRIERE, Project Manager for Plants Risk Assessment

  18. Using Software Development Standards to Analyse Accidents Involving Electrical, Electronic or Programmable, Electronic Systems: The Blade Mill PLC Case Study

    E-Print Network [OSTI]

    Johnson, Chris

    -1- Using Software Development Standards to Analyse Accidents Involving Electrical, Electronic developed by the US Department of Energy (1992). The intention is that both the lightweight flowcharts's (HSE) mission is to ensure that risks to people's health and safety from work activities are properly

  19. 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.

    2014-09-01T23:59:59.000Z

    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.

  20. TRENDS (Transport and Retention of Nuclides in Dominant Sequences): A code for modeling iodine behavior in containment during severe accidents

    SciTech Connect (OSTI)

    Weber, C.F.; Beahm, E.C.; Kress, T.S.; Daish, S.R.; Shockley, W.E.

    1989-01-01T23:59:59.000Z

    The ultimate aim of a description of iodine behavior in severe LWR accidents is a time-dependent accounting of iodine species released into containment and to the environment. Factors involved in the behavior of iodine can be conveniently divided into four general categories: (1) initial release into containment, (2) interaction of iodine species in containment not directly involving water pools, (3) interaction of iodine species in, or with, water pools, and (4) interaction with special systems such as ice condensers or gas treatment systems. To fill the large gaps in knowledge and to provide a means for assaying the iodine source term, this program has proceeded along two paths: (1) Experimental studies of the chemical behavior of iodine under containment conditions. (2) Development of TRENDS (Transport and Retention of Nuclides in Dominant Sequences), a computer code for modeling the behavior of iodine in containment and its release from containment. The main body of this report consists of a description of TRENDS. These two parts to the program are complementary in that models within TRENDS use data that were produced in the experimental program; therefore, these models are supported by experimental evidence that was obtained under conditions expected in severe accidents. 7 refs., 1 fig., 2 tabs.

  1. Technical basis for the transportation related handling representative accidents and associated hazards condition

    SciTech Connect (OSTI)

    TOMASZEWSKI, T.A.

    2003-03-21T23:59:59.000Z

    This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process and the technical basis for assigning risk bins for the handling and movement of tank farm waste sample containers, and mixed, low-level, and hazardous operational waste containers incidental to onsite vehicle transportation representative accident and associated hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls. See RPP-14286, Facility Worker Technical Basis Document, for these considerations. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described in this report.

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

    SciTech Connect (OSTI)

    Marsha Keister

    2001-02-01T23:59:59.000Z

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

  3. Threat of Hydride Re-orientation to Spent Fuel Integrity During Transportation Accidents: Myth or Reality?

    SciTech Connect (OSTI)

    Rashid, Joe [ANATECH, 5435 Oberlin Drive, San Diego, CA 92121 (United States); Machiels, Albert [EPRI, 3420 Hillview Avenue, Palo Alto, CA 94304 (United States)

    2007-07-01T23:59:59.000Z

    The source-term study conducted by Sandia National Laboratories nearly two decades ago for the spent fuel inventory known at the time, which was in the low-to-medium burnup range ({approx}35 GWd/MTU), showed that the effects of transportation accidents on spent fuel failures, and consequential radioactivity release to the environment, were relatively benign. However, with today's discharged fuel burnups routinely greater than 45 GWd/MTU, potential hydride reorientation during interim dry storage, and its effects on cladding properties, has become one of the primary concerns for spent fuel transportation. Laboratory tests of un-irradiated cladding specimens subjected to heat treatments promoting hydride dissolution followed by re-precipitation in the radial direction have shown that relatively moderate concentrations ({approx}70 ppm) of radial hydrides can significantly degrade cladding ductility, at least at room temperature. The absence of specific data that are relevant to high-burnup spent fuel under dry storage conditions have led to the conjecture, deduced from those tests, that massive cladding failures, possibly resulting in fuel reconfiguration, can be expected during cask drop events. Such conclusions are not borne out by the findings in this paper. The analysis results indicate that cladding failure is bi-modal: a state of failure initiation at the cladding ID remaining as part-wall damage with less than 2% probability of occurrence, and a through-wall failure at a probability of 1 E-5. These results indicate that spent fuel conditions that could promote the formation of radial hydrides during dry storage are not sufficient to produce radial hydrides concentrations of significant levels to cause major threat to spent fuel integrity. It is important to note in this regard that the through-wall cladding failure probability of 1 E-5 is of the same order of magnitude as calculated in the cited Sandia study for low burnup fuel. (authors)

  4. Contribution of Case Based Reasoning (CBR) in the Exploitation of Return of Experience. Application to Accident Scenarii in Railroad Transport

    E-Print Network [OSTI]

    Maalel, Ahmed

    2012-01-01T23:59:59.000Z

    The study is from a base of accident scenarii in rail transport (feedback) in order to develop a tool to share build and sustain knowledge and safety and secondly to exploit the knowledge stored to prevent the reproduction of accidents / incidents. This tool should ultimately lead to the proposal of prevention and protection measures to minimize the risk level of a new transport system and thus to improve safety. The approach to achieving this goal largely depends on the use of artificial intelligence techniques and rarely the use of a method of automatic learning in order to develop a feasibility model of a software tool based on case based reasoning (CBR) to exploit stored knowledge in order to create know-how that can help stimulate domain experts in the task of analysis, evaluation and certification of a new system.

  5. Dose estimates in a loss of lead shielding truck accident.

    SciTech Connect (OSTI)

    Dennis, Matthew L.; Osborn, Douglas M.; Weiner, Ruth F.; Heames, Terence John (Alion Science & Technology Albuquerque, NM)

    2009-08-01T23:59:59.000Z

    The radiological transportation risk & consequence program, RADTRAN, has recently added an updated loss of lead shielding (LOS) model to it most recent version, RADTRAN 6.0. The LOS model was used to determine dose estimates to first-responders during a spent nuclear fuel transportation accident. Results varied according to the following: type of accident scenario, percent of lead slump, distance to shipment, and time spent in the area. This document presents a method of creating dose estimates for first-responders using RADTRAN with potential accident scenarios. This may be of particular interest in the event of high speed accidents or fires involving cask punctures.

  6. Transportation of Dangerous Goods Anyone involved with the Transportation of Dangerous Goods must be trained. This includes shipping

    E-Print Network [OSTI]

    TDG Transportation of Dangerous Goods Anyone involved with the Transportation of Dangerous Goods must be trained. This includes shipping and receiving. All receiving of Dangerous Goods for the Science in Departmental Offices or labs. How do you know if the package is a dangerous goods shipment? Parcels containing

  7. Using Software Development Standards to Analyse Accidents Involving Electrical, Electronic or Programmable Electronic Systems: The Blade Mill Case Study

    E-Print Network [OSTI]

    Johnson, C.W.

    Johnson,C.W. Bowell,M. In C.J. Hayhurst, C.M.Holloway and B. Strauch (eds), Proceedings of the 2nd Workshop on the Investigation and Reporting of Incidents and Accidents, Published as NASA Technical Report NASA/CP-2003-212642 pp 111-128

  8. The potential consequences and risks of highway accidents involving gamma-emitting low specific activity (LSA) waste

    SciTech Connect (OSTI)

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

    1988-08-01T23:59:59.000Z

    This report documents an analysis of the potential risks and consequences of highway accidents that lead to the release of gamma-emitting low specific activity (LSA) materials from their packagings. Of particular concern is LSA waste with a specific activity level near the existing regulatory limit. The results of the analysis are intended primarily to provide a basis for evaluating limits on the quantity of radionuclides that can be contained in a single LSA waste shipment. 81 refs., 39 figs., 52 tabs.

  9. Development of an Ontology to Assist the Modeling of Accident Scenarii "Application on Railroad Transport "

    E-Print Network [OSTI]

    Maalel, Ahmed; Mejri, Lassad; Ghezela, Henda Hajjami Ben

    2012-01-01T23:59:59.000Z

    In a world where communication and information sharing are at the heart of our business, the terminology needs are most pressing. It has become imperative to identify the terms used and defined in a consensual and coherent way while preserving linguistic diversity. To streamline and strengthen the process of acquisition, representation and exploitation of scenarii of train accidents, it is necessary to harmonize and standardize the terminology used by players in the security field. The research aims to significantly improve analytical activities and operations of the various safety studies, by tracking the error in system, hardware, software and human. This paper presents the contribution of ontology to modeling scenarii for rail accidents through a knowledge model based on a generic ontology and domain ontology. After a detailed presentation of the state of the art material, this article presents the first results of the developed model.

  10. NORTHWESTERN UNIVERSITY ACCIDENT REPORT FORM

    E-Print Network [OSTI]

    Shahriar, Selim

    NORTHWESTERN UNIVERSITY ACCIDENT REPORT FORM Whenever a University vehicle sustains damage of any kind, or is involved in an accident which results in personal injury or property damage, this accident that this form is for University Use Only and is not meant to supersede the official state accident report form

  11. Unavoidable Accident

    E-Print Network [OSTI]

    Grady, Mark F.

    2009-01-01T23:59:59.000Z

    463. _____. 1987. Economic Analysis of Accident Law. _____.2005. “Liability for Accidents”, NBER Working Paper No.possibility is that the accident wasn’t under the defendant’

  12. Pore scale modeling of reactive transport involved in geologic CO2 sequestration

    SciTech Connect (OSTI)

    Kang, Qinjin [Los Alamos National Laboratory; Lichtner, Peter C [Los Alamos National Laboratory; Viswanathan, Hari S [Los Alamos National Laboratory; Abdel-fattah, Amr I [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    We apply a multi-component reactive transport lattice Boltzmann model developed in previolls studies to modeling the injection of a C02 saturated brine into various porous media structures at temperature T=25 and 80 C. The porous media are originally consisted of calcite. A chemical system consisting of Na+, Ca2+, Mg2+, H+, CO2(aq), and CI-is considered. The fluid flow, advection and diHusion of aqueous species, homogeneous reactions occurring in the bulk fluid, as weB as the dissolution of calcite and precipitation of dolomite are simulated at the pore scale. The effects of porous media structure on reactive transport are investigated. The results are compared with continuum scale modeling and the agreement and discrepancy are discussed. This work may shed some light on the fundamental physics occurring at the pore scale for reactive transport involved in geologic C02 sequestration.

  13. Accident Response Group

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

    1991-09-20T23:59:59.000Z

    To establish Department of Energy (DOE) policy for DOE response to accidents and significant incidents involving nuclear weapons or nuclear weapon components. Cancels DOE O 5530.1. Canceled by DOE O 153.1.

  14. Type B Accident Investigation Board Report on the February 27, 1998, Shipping Violations Involving the Corehole 8 Project at the Oak Ridge National Laboratory, Oak Ridge, Tennesee

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type B Investigation Board appointed by James C. Hall, Manager, Oak Ridge Operations Office, U.S. Department of Energy. The Board was appointed to perform a Type B investigation of these incidents and to prepare an investigation report in accordance with DOE Order 225.1A, Accident Investigations.

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

    E-Print Network [OSTI]

    Barkan, Christopher P.L.

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

  16. Accident Investigations

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

    2011-03-04T23:59:59.000Z

    This Order prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and activities.

  17. COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS

    SciTech Connect (OSTI)

    S.O. Bader

    1999-10-18T23:59:59.000Z

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

  18. In-vessel thermohydraulics evaluation of an unprotected transient overpower accident and delayed neutron precursor concentration transport analysis using a multidimensional code

    SciTech Connect (OSTI)

    Muramatsu, T.; Ninokata, H. (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan))

    1992-02-01T23:59:59.000Z

    This paper reports on a three-dimensional in-vessel thermohydraulics analysis that is carried out for the early phase of an unprotected transient overpower (UTOP) accident and delayed neutron precursor concentration transport in a typical loop-type fast breeder reactor plant. In the UTOP calculations, the time at which the sodium temperature reaches the reactor trip level is evaluated based on calculated upper plenum flow and temperature distributions. For fission product release from the core assemblies, the delayed neutron precursor concentration in the sodium that reaches the detectors depends on the location of the faulted assembly. Three-dimensional flow patterns, and hence, the residence time in the upper plenum. Delayed neutron precursors that bypassed the recirculation flow to appear in the plenum primarily contribute to the peak concentration.

  19. Accident Investigations

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

    1996-04-26T23:59:59.000Z

    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)]

    1995-10-26T23:59:59.000Z

    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. STATE OF CALIFORNIA -DGS ORIM VEHICLE ACCIDENT REPORT

    E-Print Network [OSTI]

    Ponce, V. Miguel

    STATE OF CALIFORNIA - DGS ORIM VEHICLE ACCIDENT REPORT STD. 270 (REV. 2/2002c) ACCIDENT PREVIOUSLY REPORTED TO ORIM? (If Yes, give date) YES NO THIS REPORT MUST BE MAILED WITHIN 48 HOURS AFTER ACCIDENT (ACCIDENTS INVOLVING INJURY SHOULD FIRST BE CALLED OR FAXED TO ORIM AT (916) 376-5302 - CALNET 480-5302 - FAX

  2. Recherche Transport Scurit -DOI 10.1007/s13547-012-0043-7 Tlphoner au volant : impact sur la conduite et risque d'accident

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    conduite et risque d'accident une revue de la littérature Phoning while driving: impact on the driving and risk of accident a literature review Marie-Pierre Bruyas1 et Jean-Louis Martin2&3 IFSTTAR-LESCOT1'une part, l'impact de l'usage du téléphone sur la conduite automobile et, d'autre part, le risque d'accident

  3. Date of Accident: _____/_____/________ Day of Week: __________________ Hour: _____:______ AM / PM TIME VEHICLE ACCIDENT REPORT

    E-Print Network [OSTI]

    Farritor, Shane

    Page 1/2 Date of Accident: _____/_____/________ Day of Week: __________________ Hour: _____:______ AM / PM TIME VEHICLE ACCIDENT REPORT TO BE USED BY ALL STATE AGENCIES to make immediate report of all motor vehicle accidents involving State employees, vehicles, equipment or where highways could result

  4. The MacArthur Maze Fire and Roadway Collapse: A "Worst Case Scenario" for Spent Nuclear Fuel Transportation?

    SciTech Connect (OSTI)

    Bajwa, Christopher S.; Easton, Earl P.; Adkins, Harold E.; Cuta, Judith M.; Klymyshyn, Nicholas A.; Suffield, Sarah R.

    2012-07-06T23:59:59.000Z

    In 2007, a severe transportation accident occurred near Oakland, California, at the interchange known as the "MacArthur Maze." The accident involved a double tanker truck of gasoline overturning and bursting into flames. The subsequent fire reduced the strength of the supporting steel structure of an overhead interstate roadway causing the collapse of portions of that overpass onto the lower roadway in less than 20 minutes. The US Nuclear Regulatory Commission has analyzed what might have happened had a spent nuclear fuel transportation package been involved in this accident, to determine if there are any potential regulatory implications of this accident to the safe transport of spent nuclear fuel in the United States. This paper provides a summary of this effort, presents preliminary results and conclusions, and discusses future work related to the NRC's analysis of the consequences of this type of severe accident.

  5. Risk Estimation Methodology for Launch Accidents.

    SciTech Connect (OSTI)

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

    2014-02-01T23:59:59.000Z

    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.

  6. Commercial SNF Accident Release Fractions

    SciTech Connect (OSTI)

    J. Schulz

    2004-11-05T23:59:59.000Z

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

  7. STUDENT / VISITOR ACCIDENT REPORT FORM nco/revised 10/06/03

    E-Print Network [OSTI]

    Azevedo, Ricardo

    STUDENT / VISITOR ACCIDENT REPORT FORM nco/revised 10/06/03 (To Be Completed By Individual Involved In Accident) 1. Name: ________________________________________ Student ID or DL No.: _______________________ 2 No - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6. Date of Accident: ___________________ Day of Week: _______________________ Time: ____________ 7

  8. accident survival time: Topics by E-print Network

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

    person(s) involved in IncidentAccident: 1) Name New Hampshire, University of 2 Does Daylight Savings Time Affect Traffic Accidents? Texas A&M University - TxSpace Summary: This...

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

    Energy Savers [EERE]

    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...

  10. Simulation of transportation of low enriched uranium solutions

    SciTech Connect (OSTI)

    Hope, E.P.; Ades, M.J.

    1996-08-01T23:59:59.000Z

    A simulation of the transportation by truck of low enriched uranium solutions has been completed for NEPA purposes at the Savannah River Site. The analysis involves three distinct source terms, and establishes the radiological risks of shipment to three possible destinations. Additionally, loading accidents were analyzed to determine the radiological consequences of mishaps during handling and delivery. Source terms were developed from laboratory measurements of chemical samples from low enriched uranium feed materials being stored at SRS facilities, and from manufacturer data on transport containers. The transportation simulations were accomplished over the INTERNET using the DOE TRANSNET system at Sandia National Laboratory. The HIGHWAY 3.3 code was used to analyze routing scenarios, and the RADTRAN 4 code was used to analyze incident free and accident risks of transporting radiological materials. Loading accidents were assessed using the Savannah River Site AXAIR89Q and RELEASE 2 codes.

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

    SciTech Connect (OSTI)

    Geffen, C.A.

    1980-03-01T23:59:59.000Z

    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.

  12. Transportation

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

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

  13. Transportation

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

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

  14. REAC/TS Radiation Accident Registry: An Overview

    SciTech Connect (OSTI)

    Doran M. Christensen, DO, REAC /TS Associate Director and Staff Physician Becky Murdock, REAC/TS Registry and Health Physics Technician

    2012-12-12T23:59:59.000Z

    Over the past four years, REAC/TS has presented a number of case reports from its Radiation Accident Registry. Victims of radiological or nuclear incidents must meet certain dose criteria for an incident to be categorized as an “accident” and be included in the registry. Although the greatest numbers of “accidents” in the United States that have been entered into the registry involve radiation devices, the greater percentage of serious accidents have involved sealed sources of one kind or another. But if one looks at the kinds of accident scenarios that have resulted in extreme consequence, i.e., death, the greater share of deaths has occurred in medical settings.

  15. Employee Accident / Incident Investigation Report Employee Name _________________________________________________________________

    E-Print Network [OSTI]

    Long, Nicholas

    Employee Accident / Incident Investigation Report Employee Name's Title _________________________________________________________________ Date and Time of Accident accident occurred

  16. 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. (Battelle Columbus Div., OH (USA))

    1990-08-01T23:59:59.000Z

    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.

  17. Transportation

    SciTech Connect (OSTI)

    Murphy, E.E

    1990-01-01T23:59:59.000Z

    The author discusses how, in a reversal of the usual pattern, the Federal Aviation Administration (FAA) turned this year to equipment dating back 20 years while several U.S. railroads and transit authorities invested in new designs. Also, the aviation industry adopted a new maintenance philosophy in the wake of several aircraft accidents attributed to the effects of aging.

  18. Estimating Pedestrian Accident Exposure: Protocol Report

    E-Print Network [OSTI]

    Greene-Roesel, Ryan; Diogenes, Mara Chagas; Ragland, David R

    2007-01-01T23:59:59.000Z

    Pedestrian Accident Risk. Accident Analysis and Prevention,Pedestrian Accidents. Accident Analysis and Prevention, Vol.in New Zealand. Accident Analysis and Prevention, Vol. 27,

  19. Utilizing an encroachment probability benefit-cost model to estimate accident reduction factors

    E-Print Network [OSTI]

    Hayes, Carolyn A

    1997-01-01T23:59:59.000Z

    Improving safety on Texas roadways is a major public concern. Over the years, the Texas Department of Transportation and other highway agencies have become interested in reducing society's accident cost while maximizing returns on accident...

  20. RESEARCH FOUNDATION -STATE UNIVERSITY OF NEW YORK REPORT OF ACCIDENT OR INJURY

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    RESEARCH FOUNDATION - STATE UNIVERSITY OF NEW YORK REPORT OF ACCIDENT OR INJURY (OTHER THAN A MOTOR VEHICLE ACCIDENT) Revised: July 2008 1. Date and T ime of accident: Date: T ime: 2. Date of Report: 3. T o be completed by Safety Supervisor: YEAR: NO.: SEQUENCE: FILE ID: 4. Did accident involve personal injury? Yes

  1. Placental findings in cord accidents

    E-Print Network [OSTI]

    Parast, Mana M

    2012-01-01T23:59:59.000Z

    Placental findings in cord accidents. BMC Pregnancy andPlacental findings in cord accidents Mana M Parast Fromfor stillbirth. “Cord accident,” defined by obstruction of

  2. The Accident Externality from Driving

    E-Print Network [OSTI]

    Edlin, Aaron S.; Karaca-Mandic, Pinar

    2007-01-01T23:59:59.000Z

    Sex-Divided Mile- age, Accident, and Insurance Cost DataMandic. 2003. “The Accident Externality from Driving. ”Insurance Res. Council. accident externality from driving

  3. Transportation

    E-Print Network [OSTI]

    Vinson, Steve

    2013-01-01T23:59:59.000Z

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

  4. Interpreting Accident Statistics

    E-Print Network [OSTI]

    Ferreira, Joseph Jr.

    Accident statistics have often been used to support the argument that an abnormally small proportion of drivers account for a large proportion of the accidents. This paper compares statistics developed from six-year data ...

  5. A Road Accident

    E-Print Network [OSTI]

    G.yu lha

    tracks (include description/relationship if appropriate) NA Title of track A Road Accident Translation of title Description (to be used in archive entry) Shel ko shares his experience of a serious road accident in which the truck he...

  6. Biohazardous Laboratory Incidence/Accident Response and Reporting Protocol UGA Office of Biosafety

    E-Print Network [OSTI]

    Arnold, Jonathan

    Biohazardous Laboratory Incidence/Accident Response and Reporting Protocol UGA Office of Biosafety Biohazardous laboratory incident or accident involves the following: 1. Any potential or known exposure-related accidents or illnesses involving work described under the NIH Guidelines for Recombinant DNA Research (NIH

  7. NO NAME:Accident reporting and Auto Insurance.doc July 15, 2014

    E-Print Network [OSTI]

    Kelly, Scott David

    NO NAME:Accident reporting and Auto Insurance.doc July 15, 2014 STATEMENT OF RESOURCES TO ADDRESS CLAIMS ARISING FROM ACCIDENTS INVOLVING VEHICLES OPERATED ON UNIVERSITY BUSINESS This statement contains a general description of resources available in connection with claims arising from accidents involving

  8. Resonant charge-exchange involving excited helium atoms and reactive transport of local thermodynamic equilibrium helium plasma

    SciTech Connect (OSTI)

    Kosarim, A. V.; Smirnov, B. M. [Joint Institute for High Temperatures RAS, Moscow (Russian Federation); Laricchiuta, A. [CNR IMIP Bari, Bari (Italy); Capitelli, M. [CNR IMIP Bari, Bari (Italy); Department of Chemistry, University of Bari, Bari (Italy)

    2012-06-15T23:59:59.000Z

    The cross sections for charge-exchange and charge-transfer processes are evaluated for collisions of helium ions with parent-atoms in ground and excited states, with the principal quantum number n= 1-5, in the collision energy range from thermal up to 10 eV. Corresponding diffusion-type collision integrals are derived, and the role of 'abnormal' transport of electronically excited states on the reactive thermal conductivity of equilibrium helium plasma, at atmospheric pressure, estimated in the frame of a simplified approach.

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

    SciTech Connect (OSTI)

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

    1993-12-31T23:59:59.000Z

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

  10. Accidents, engineering and history at NASA: 1967-2003

    E-Print Network [OSTI]

    Brown, Alexander F. G. (Alexander Frederic Garder), 1970-

    2009-01-01T23:59:59.000Z

    The manned spaceflight program of the National Aeronautics and Space Administration (NASA) has suffered three fatal accidents: one in the Apollo program and two in the Space Transportation System (the Shuttle). These were ...

  11. Accident motivates scholarship recipient

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

    Accident motivates scholarship recipient Leyba encourages students: apply for Los Alamos Employees' Scholarship Fund Life-changing experience: springboard to a career in exercise,...

  12. ASU SUPERVISOR'S ACCIDENT/ILLNESS INVESTIGATION FORM Return to: ASU Office of Human Resources, Workers' Comp Office,

    E-Print Network [OSTI]

    Thaxton, Christopher S.

    ASU SUPERVISOR'S ACCIDENT/ILLNESS INVESTIGATION FORM Return to: ASU Office of Human Resources or as soon as possible after the accident/illness. IMMEDIATELY report all accidents involving serious bodily injury or death to the HR Workers' Comp Office (X 6488) ACCIDENT DATA 1. Name of Employee: SS#: SEX: Male

  13. The Accident Externality from Driving

    E-Print Network [OSTI]

    Edlin, Aaron S.; Karaca-Mandic, Pinar

    2005-01-01T23:59:59.000Z

    a given state could a?ect accident risk and could correlateVolume on Motor-Vehicle Accidents on Two-Lane Tangents. ”Laurie. “Sex-Divided Mileage Accident and In- surance Cost

  14. The Accident Externality from Driving

    E-Print Network [OSTI]

    Edlin, Aaron S.; Karaca-Mandic, Pinar

    2003-01-01T23:59:59.000Z

    to which this externality results from increases in accidentrates, accident severity or both remains unclear. Itpertains to underinsured accident costs like fatality risk.

  15. Radiological Release Accident Investigation Report

    Broader source: Energy.gov [DOE]

    Phase 1 of this accident investigation report is an independent product of the Accident Investigation Board appointed by Matthew Moury, Deputy Assistant Secretary, Safety, Security, and Quality...

  16. APS Guideline for Accident Investigations

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

    APS Guideline for Accident Investigations Introduction Purpose The primary purpose of an incident or accident investigation is to identify the hazard control systems that either...

  17. Accident causation study on roadways with limited sight distance crest vertical curves

    E-Print Network [OSTI]

    Stoddard, Angela May

    1994-01-01T23:59:59.000Z

    reflect the driver and vehicle population currently on the transportation network. An accident causation study was conducted to determine if roadways with limited stopping sight distance present a safety hazard for the transportation network. Rural two...

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

    SciTech Connect (OSTI)

    Kastenberg, W.E. [ed.; Apostolakis, G.; Dhir, V.K. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering] [and others

    1993-09-01T23:59:59.000Z

    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.

  19. Transportation scenarios for risk analysis.

    SciTech Connect (OSTI)

    Weiner, Ruth F.

    2010-09-01T23:59:59.000Z

    Transportation risk, like any risk, is defined by the risk triplet: what can happen (the scenario), how likely it is (the probability), and the resulting consequences. This paper evaluates the development of transportation scenarios, the associated probabilities, and the consequences. The most likely radioactive materials transportation scenario is routine, incident-free transportation, which has a probability indistinguishable from unity. Accident scenarios in radioactive materials transportation are of three different types: accidents in which there is no impact on the radioactive cargo, accidents in which some gamma shielding may be lost but there is no release of radioactive material, and accident in which radioactive material may potentially be released. Accident frequencies, obtainable from recorded data validated by the U.S. Department of Transportation, are considered equivalent to accident probabilities in this study. Probabilities of different types of accidents are conditional probabilities, conditional on an accident occurring, and are developed from event trees. Development of all of these probabilities and the associated highway and rail accident event trees are discussed in this paper.

  20. TIPS ON ACCIDENT/INCIDENT REPORTING Accident Reporting Why?

    E-Print Network [OSTI]

    Lennard, William N.

    TIPS ON ACCIDENT/INCIDENT REPORTING Accident Reporting ­ Why? Obligation to report Health Care of the accident ­ if not, the organization (i.e. the department) can be fined Obligation under Section 51, 52 happened? When did it happen? (Date, Time and Place) When was the accident/incident reported? Any

  1. Accident tolerant fuel analysis

    SciTech Connect (OSTI)

    Smith, Curtis [Idaho National Laboratory; Chichester, Heather [Idaho National Laboratory; Johns, Jesse [Texas A& M University; Teague, Melissa [Idaho National Laboratory; Tonks, Michael Idaho National Laboratory; Youngblood, Robert [Idaho National Laboratory

    2014-09-01T23:59:59.000Z

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

  2. Accident Tolerant Fuel Analysis

    SciTech Connect (OSTI)

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

    2014-09-01T23:59:59.000Z

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

  3. Evaluation of severe accident risks: Quantification of major input parameters: MAACS (MELCOR Accident Consequence Code System) input

    SciTech Connect (OSTI)

    Sprung, J.L.; Jow, H-N (Sandia National Labs., Albuquerque, NM (USA)) [Sandia National Labs., Albuquerque, NM (USA); Rollstin, J.A. (GRAM, Inc., Albuquerque, NM (USA)) [GRAM, Inc., Albuquerque, NM (USA); Helton, J.C. (Arizona State Univ., Tempe, AZ (USA)) [Arizona State Univ., Tempe, AZ (USA)

    1990-12-01T23:59:59.000Z

    Estimation of offsite accident consequences is the customary final step in a probabilistic assessment of the risks of severe nuclear reactor accidents. Recently, the Nuclear Regulatory Commission reassessed the risks of severe accidents at five US power reactors (NUREG-1150). Offsite accident consequences for NUREG-1150 source terms were estimated using the MELCOR Accident Consequence Code System (MACCS). Before these calculations were performed, most MACCS input parameters were reviewed, and for each parameter reviewed, a best-estimate value was recommended. This report presents the results of these reviews. Specifically, recommended values and the basis for their selection are presented for MACCS atmospheric and biospheric transport, emergency response, food pathway, and economic input parameters. Dose conversion factors and health effect parameters are not reviewed in this report. 134 refs., 15 figs., 110 tabs.

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

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

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

  5. Estimating Pedestrian Accident Exposure: Protocol Report

    E-Print Network [OSTI]

    Greene-Roesel, Ryan; Diogenes, Mara Chagas; Ragland, David R

    2007-01-01T23:59:59.000Z

    A Method of Measuring Exposure to Pedestrian Accident Risk.Accident Analysis and Prevention, Vol. 14, 1982, pp 397-405.Estimating Pedestrian Accident Exposure: Protocol Report,

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

    SciTech Connect (OSTI)

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

    1993-12-31T23:59:59.000Z

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

  7. Statistical evaluation of design-error related accidents

    SciTech Connect (OSTI)

    Ott, K.O.; Marchaterre, J.F.

    1980-01-01T23:59:59.000Z

    In a recently published paper (Campbell and Ott, 1979), a general methodology was proposed for the statistical evaluation of design-error related accidents. The evaluation aims at an estimate of the combined residual frequency of yet unknown types of accidents lurking in a certain technological system. Here, the original methodology is extended, as to apply to a variety of systems that evolves during the development of large-scale technologies. A special categorization of incidents and accidents is introduced to define the events that should be jointly analyzed. The resulting formalism is applied to the development of the nuclear power reactor technology, considering serious accidents that involve in the accident-progression a particular design inadequacy.

  8. Accident at Creswell Colliery, Derbyshire 

    E-Print Network [OSTI]

    Bryan, Andrew

    MINISTRY OF FUEL AND POWER ACCIDENT AT CRESWELL COLLIERY, DERBYSHIRE REPORT On the causes of, and the circumstances attending, the accident which occurred at Creswell Colliery, Derbyshire, on the 26th September, 1950 BY ...

  9. Accident Report Form Victim's Name

    E-Print Network [OSTI]

    Amin, S. Massoud

    Accident Report Form Date: Victim's Name: Address: Classification: Program Area: Activity: Brief Description of Accident: Body Fluid Spill: Action Taken by DRS Employee: Witness Name: Witness Address:____________________________________ DOB: Intramurals Front Back Revision - 2011 **Location of Accident** URC North Gymnasium URC South

  10. UNIVERSITY OF TRENTO ACCIDENT INSURANCE

    E-Print Network [OSTI]

    1 UNIVERSITY OF TRENTO ACCIDENT INSURANCE POLICY This document reflects the contractual conditions in force, though it should not be considered as a binding analysis of the coverage and, in case of accident for the purposes stated. TYPE OF COVERAGE = GROUP ACCIDENT INSURANCE POLICY No. = 088 00429120 COMPANY NAME

  11. http://travel.state.gov/travel/about/who/who_1245.html AT THE SCENE OF AN ACCIDENT FORM

    E-Print Network [OSTI]

    Tullos, Desiree

    -737-7252 or risk@oregonstate.edu IMMEDIATELY if this was a serious accident (i.e. ambulance involved, vehicle towed). If this is an OSU Motor Pool vehicle, also call 541-737-4141. If OSU Risk not available, LEAVE MESSAGE. You may also Accident and Insurance Report" (required for accidents with ANY injury, when a vehicle is towed, and

  12. 34.02.99.M2.01 Post-Accident Testing Instructions Page 1 of 3 STANDARD ADMINISTRATIVE PROCEDURE

    E-Print Network [OSTI]

    34.02.99.M2.01 Post-Accident Testing Instructions Page 1 of 3 STANDARD ADMINISTRATIVE PROCEDURE 34.02.99.M2.01 Post-Accident Testing Instructions Approved June 15, 1999 Revised March 26, 2010 Next is to set forth responsibilities for those involved in post-accident testing. Procedures

  13. Modeling and analyses of postulated UF{sub 6} release accidents in gaseous diffusion plant

    SciTech Connect (OSTI)

    Kim, S.H.; Taleyarkhan, R.P.; Keith, K.D.; Schmidt, R.W. [Oak Ridge National Lab., TN (United States); Carter, J.C. [J.C. Carter Associates, Inc., Oak Ridge, TN (United States); Dyer, R.H. [Dyer Enterprises, Oak Ridge, TN (United States)

    1995-10-01T23:59:59.000Z

    Computer models have been developed to simulate the transient behavior of aerosols and vapors as a result of a postulated accident involving the release of uranium hexafluoride (UF{sub 6}) into the process building of a gaseous diffusion plant. UF{sub 6} undergoes an exothermic chemical reaction with moisture (H{sub 2}O) in the air to form hydrogen fluoride (HF) and radioactive uranyl fluoride (UO{sub 2}F{sub 2}). As part of a facility-wide safety evaluation, this study evaluated source terms consisting of UO{sub 2}F{sub 2} as well as HF during a postulated UF{sub 6} release accident in a process building. In the postulated accident scenario, {approximately}7900 kg (17,500 lb) of hot UF{sub 6} vapor is released over a 5 min period from the process piping into the atmosphere of a large process building. UO{sub 2}F{sub 2} mainly remains as airborne-solid particles (aerosols), and HF is in a vapor form. Some UO{sub 2}F{sub 2} aerosols are removed from the air flow due to gravitational settling. The HF and the remaining UO{sub 2}F{sub 2} are mixed with air and exhausted through the building ventilation system. The MELCOR computer code was selected for simulating aerosols and vapor transport in the process building. MELCOR model was first used to develop a single volume representation of a process building and its results were compared with those from past lumped parameter models specifically developed for studying UF{sub 6} release accidents. Preliminary results indicate that MELCOR predicted results (using a lumped formulation) are comparable with those from previously developed models.

  14. Electrical shock accident investigation

    SciTech Connect (OSTI)

    Not Available

    1994-09-30T23:59:59.000Z

    This report documents results of the accident investigation of an electrical shock received by two subcontractor employees on May 13, 1994, at the Pinellas Plant. The direct cause of the electrical shock was worker contact with a cut ``hot`` wire and a grounded panelboard (PPA) enclosure. Workers presumed that all wires in the enclosure were dead at the time of the accident and did not perform thorough Lockout/Tagout (LO/TO). Three contributing causes were identified. First, lack of guidance in the drawing for the modification performed in 1987 allowed the PPA panel to be used as a junction box. The second contributing cause is that Environmental, Safety and Health (ES&H) procedures do not address multiple electrical sources in an enclosure. Finally, the workers did not consider the possibility of multiple electrical sources. The root cause of the electrical shock was the inadequacy of administrative controls, including construction requirement and LO/TO requirements, and subcontractor awareness regarding multiple electrical sources. Recommendations to prevent further reoccurrence of this type of accident include revision of ES&H Standard 2.00, Electrical Safety Program Manual, to document requirements for multiple electrical sources in a single enclosure to specify a thorough visual inspection as part of the voltage check process. In addition, the formality of LO/TO awareness training for subcontractor electricians should be increased.

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

    SciTech Connect (OSTI)

    Blanchard, A.

    1999-04-15T23:59:59.000Z

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

  16. accident causes: Topics by E-print Network

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

    accident causes First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Abstract--Petroleum transportation...

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

    Energy Savers [EERE]

    June 17, 2012, Construction Accident - Structural Steel Collapse at The Over pack Storage Expansion 2 at the Naval Reactors Facility at the Idaho National Laboratory, Idaho Falls,...

  18. Evaluating the effectiveness of wildlife accident mitigation installations with the wildlife accident reporting system (WARS) in British Columbia

    E-Print Network [OSTI]

    Sielecki, Leonard E.

    2001-01-01T23:59:59.000Z

    EFFECTIVENESS OF WILDLIFE ACCIDENT MITIGATION INSTALLATIONSWITH THE WILDLIFE ACCIDENT REPORTING SYSTEM (WARS) INadministers the Wildlife Accident Reporting System (WARS), a

  19. accidents involving fuel: Topics by E-print Network

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

    ray upon decay. We find that pressurized light-water-reactors fueled with LEU-thorium fuel at high burnup (70 MWdkg) produce U-233 with U-232 contamination levels of about 0.4...

  20. Accident motivates scholarship recipient

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWP TWP Related LinksATHENA couldAboutClean WaterAccessingAccident

  1. Emergency response to a highway accident in Springfield, Massachusetts, on December 16, 1991

    SciTech Connect (OSTI)

    Not Available

    1992-06-01T23:59:59.000Z

    On December 16, 1991, a truck carrying unirradiated (fresh) nuclear fuel was involved in an accident on US Interstate 91, in Springfield, Massachusetts. This report describes the emergency response measures undertaken by local, State, Federal, and private parties. The report also discusses ``lessons learned`` from the response to the accident and suggests areas where improvements might be made.

  2. Emergency response to a highway accident in Springfield, Massachusetts, on December 16, 1991

    SciTech Connect (OSTI)

    Not Available

    1992-06-01T23:59:59.000Z

    On December 16, 1991, a truck carrying unirradiated (fresh) nuclear fuel was involved in an accident on US Interstate 91, in Springfield, Massachusetts. This report describes the emergency response measures undertaken by local, State, Federal, and private parties. The report also discusses lessons learned'' from the response to the accident and suggests areas where improvements might be made.

  3. Iodine behavior in containment under LWR accident conditions

    SciTech Connect (OSTI)

    Wisbey, S.J.; Beahm, E.C.; Shockley, W.E.; Wang, Y.M.

    1986-01-01T23:59:59.000Z

    The description of containment iodine behavior in reactor accident sequences requires an understanding of iodine volatility effects, deposition and revaporization/resuspension (from surfaces and aerosols), chemical changes between species, and mass transport. The experimental work in this program has largely centered on the interactions of iodine in or with water pools. The formation of volatile iodine, as I/sub 2/ or organic iodides, is primarily dependent on radiation and solution pH. Lower pH results in increased formation of volatile iodine species; thus, for example, a pH of 3.05 resulted in a conversion of I/sup -/ to I/sub 2/ that was more than two orders of magnitude greater than tests run at pH 6.1 or 6.8. The formation or organic iodides involving water pools has been linked to the presence of iodine as I/sub 2/, the solution/gas contact, and to the type of organic material.

  4. BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE Especially Designed for Students of insurance. Your coverage is governed by a policy of student accident and sickness insurance underwritten

  5. BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE Especially Designed for International Students is governed by a policy of student accident and sickness insurance underwritten by BCS Insurance Company BCS

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

    Broader source: Energy.gov [DOE]

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

  7. ASU SUPERVISOR'S ACCIDENT/ILLNESS INVESTIGATION FORM Return to: ASU HRS Workers' Comp Office, PO Box 32010, Founders Hall, Boone, NC 28608

    E-Print Network [OSTI]

    Thaxton, Christopher S.

    ASU SUPERVISOR'S ACCIDENT/ILLNESS INVESTIGATION FORM Return to: ASU HRS Workers' Comp Office, PO Services Workers' Comp Office within 24 hours or as soon as possible after the accident/illness. IMMEDIATELY report all accidents involving serious bodily injury or death to the Workers' Comp Office (X 6488

  8. A review of criticality accidents

    SciTech Connect (OSTI)

    Stratton, W R; Smith, D R

    1989-03-01T23:59:59.000Z

    Criticality accidents and the characteristics of prompt power excursions are discussed. Forty-one accidental power transients are reviewed. In each case where available, enough detail is given to help visualize the physical situation, the cause or causes of the accident, the history and characteristics of the transient, the energy release, and the consequences, if any, to personnel and property. Excursions associated with large power reactors are not included in this study, except that some information on the major accident at the Chernobyl reactor in April 1986 is provided in the Appendix. 67 refs., 21 figs., 2 tabs.

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

    SciTech Connect (OSTI)

    Ammerman, D.J.

    1996-10-01T23:59:59.000Z

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

  10. Parent Involvement

    E-Print Network [OSTI]

    Howard, Jeff W.

    2005-05-10T23:59:59.000Z

    To be successful, a 4-H program must have parent involvement. Although 4-H leaders and Extension agents may interest young people in becoming members, they need the parents' goodwill and support to keep them interested, enthusiastic and active. Here...

  11. University of Pittsburgh Vehicle Accident Report Form

    E-Print Network [OSTI]

    Sibille, Etienne

    University of Pittsburgh Vehicle Accident Report Form To be completed by the driver immediately following the accident (if medically able) and return this completed form to Fleet Services, Dept of Parking-624-1817 A. Report Date: ______/______/_______ B: Accident Data Date of accident

  12. Exact Location : Date of Accident : AM PM

    E-Print Network [OSTI]

    Swaddle, John

    SSN Cell Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date accident treatment provided? Yes No Where Was time lost from work? Yes No If yes, how long? Could this accident have the following information as soon as it relates to your work related accident/injury/illness within 72 hours

  13. Bordereau de transmission accident du travail

    E-Print Network [OSTI]

    Pouyanne, Nicolas

    Bordereau de transmission accident du travail Service des pensions et accidents du travail accidents du travail du CNRS Accompagné des pièces requises Nom .................................................... Prénom ........................ Matricule ...... Composition du dossier Observations Déclaration d'accident

  14. An Interview About an Accident

    E-Print Network [OSTI]

    G.yu lha

    2009-12-17T23:59:59.000Z

    Length of track 0:02:32 Related tracks (include description/relationship if appropriate) Title of track An Interview About an Accident Translation of title Description (to be used in archive entry) The respondent recalls how he and his... wife survived a motorcycle accident. Genre or type (i.e. epic, song, ritual) Interview Name of recorder (if different from collector) G.yu lha Date of recording December 17th 2009 Place of recording Siyuewu Village, Puxi Township, Rangtang...

  15. Source terms for plutonium aerosolization from nuclear weapon accidents

    SciTech Connect (OSTI)

    Stephens, D.R.

    1995-07-01T23:59:59.000Z

    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.

  16. 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.

    1992-11-01T23:59:59.000Z

    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.

  17. Dualmode transportation - impact on the electric grid

    E-Print Network [OSTI]

    Azcarate Lara, Francisco Javier

    2009-05-15T23:59:59.000Z

    Continual increase in transport demand and uneven road capacity results in chaotic traffic congestion, brings with it high levels of air pollution, an elevated number of accidents, and an insatiable demand for oil to satisfy the motorized vehicles...

  18. Dualmode transportation - impact on the electric grid 

    E-Print Network [OSTI]

    Azcarate Lara, Francisco Javier

    2009-05-15T23:59:59.000Z

    Continual increase in transport demand and uneven road capacity results in chaotic traffic congestion, brings with it high levels of air pollution, an elevated number of accidents, and an insatiable demand for oil to satisfy the motorized vehicles...

  19. Dualmode transportation - impact on the electric grid 

    E-Print Network [OSTI]

    Azcarate Lara, Francisco Javier

    2008-10-10T23:59:59.000Z

    Continual increase in transport demand and uneven road capacity results in chaotic traffic congestion, brings with it high levels of air pollution, an elevated number of accidents, and an insatiable demand for oil to satisfy the motorized vehicles...

  20. Dualmode transportation - impact on the electric grid

    E-Print Network [OSTI]

    Azcarate Lara, Francisco Javier

    2008-10-10T23:59:59.000Z

    Continual increase in transport demand and uneven road capacity results in chaotic traffic congestion, brings with it high levels of air pollution, an elevated number of accidents, and an insatiable demand for oil to satisfy the motorized vehicles...

  1. UBC Student & Visitor Incident/Accident Report This report is to be completed by, or on behalf of, Visitors to UBC Campus and UBC Students who have been injured on

    E-Print Network [OSTI]

    Karczmarek, Joanna

    UBC Student & Visitor Incident/Accident Report This report is to be completed by, or on behalf of of Transportation to Medical Facility: Department Visited Date and Time of Incident/Accident (m/d/y) ____/____/____ ____:____ am / pm Describe the exact location of accident. (Include building name and room number

  2. Use of inelastic analysis to determine the response of packages to puncture accidents

    SciTech Connect (OSTI)

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

    1996-08-01T23:59:59.000Z

    The accurate analytical determination of the response of radioactive material transportation packages to the hypothetical puncture accident requires inelastic analysis techniques. Use of this improved analysis method recudes the reliance on empirical and approximate methods to determine the safety for puncture accidents. This paper will discuss how inelastic analysis techniques can be used to determine the stresses, strains and deformations resulting from puncture accidents for thin skin materials with different backing materials. A method will be discussed to assure safety for all of these types of packages.

  3. Graphite Oxidation Simulation in HTR Accident Conditions

    SciTech Connect (OSTI)

    El-Genk, Mohamed

    2012-10-19T23:59:59.000Z

    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.

  4. The Wildlife Accident Reporting System (WARS) in British Columbia

    E-Print Network [OSTI]

    Sielecki, Leonard E.

    2003-01-01T23:59:59.000Z

    2001, WARS 2000 Wildlife Accident Reporting System (2000related motor vehicle accident claim data and funding toTHE WILDLIFE ACCIDENT REPORTING SYSTEM (WARS) IN BRITISH

  5. Type B Accident Investigation Board Report on the September 7...

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

    Accident Investigation Board Report on the September 7, 2001, Burn Accident at Oak Ridge National Laboratory, Building 9210 Type B Accident Investigation Board Report on the...

  6. Type B Accident Investigation of the Subcontractor Employee Injuries...

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

    Type B Accident Investigation of the Subcontractor Employee Injuries from a November 15, 2000, Fall Accident at the Oak Ridge National Laboratory Type B Accident Investigation of...

  7. Estimating Pedestrian Accident Exposure: Automated Pedestrian Counting Devices Report

    E-Print Network [OSTI]

    Bu, Fanping; Greene-Roesel, Ryan; Diogenes, Mara Chagas; Ragland, David R

    2007-01-01T23:59:59.000Z

    291. Estimating Pedestrian Accident Exposure: Draft ProtocolEstimating Pedestrian Accident Exposure: Draft Protocol39. Estimating Pedestrian Accident Exposure: Draft Protocol

  8. Use of principal components analysis and three-dimensional atmospheric-transport models for reactor-consequence evaluation

    SciTech Connect (OSTI)

    Gudiksen, P.H.; Walton, J.J.; Alpert, D.J.; Johnson, J.D.

    1982-01-01T23:59:59.000Z

    This work explores the use of principal components analysis coupled to three-dimensional atmospheric transport and dispersion models for evaluating the environmental consequences of reactor accidents. This permits the inclusion of meteorological data from multiple sites and the effects of topography in the consequence evaluation; features not normally included in such analyses. The technique identifies prevailing regional wind patterns and their frequencies for use in the transport and dispersion calculations. Analysis of a hypothetical accident scenario involving a release of radioactivity from a reactor situated in a river valley indicated the technique is quite useful whenever recurring wind patterns exist, as is often the case in complex terrain situations. Considerable differences were revealed in a comparison with results obtained from a more conventional Gaussian plume model using only the reactor site meteorology and no topographic effects.

  9. OSSA - An optimized approach to severe accident management: EPR application

    SciTech Connect (OSTI)

    Sauvage, E. C.; Prior, R.; Coffey, K. [AREVA, FRAMATOME-ANP SAS, Paris, 92084 La Defense (France); Mazurkiewicz, S. M. [AREVA, FRAMATOME-ANP Inc, Lynchburg, VA 24506-0935 (United States)

    2006-07-01T23:59:59.000Z

    There is a recognized need to provide nuclear power plant technical staff with structured guidance for response to a potential severe accident condition involving core damage and potential release of fission products to the environment. Over the past ten years, many plants worldwide have implemented such guidance for their emergency technical support center teams either by following one of the generic approaches, or by developing fully independent approaches. There are many lessons to be learned from the experience of the past decade, in developing, implementing, and validating severe accident management guidance. Also, though numerous basic approaches exist which share common principles, there are differences in the methodology and application of the guidelines. AREVA/Framatome-ANP is developing an optimized approach to severe accident management guidance in a project called OSSA ('Operating Strategies for Severe Accidents'). There are still numerous operating power plants which have yet to implement severe accident management programs. For these, the option to use an updated approach which makes full use of lessons learned and experience, is seen as a major advantage. Very few of the current approaches covers all operating plant states, including shutdown states with the primary system closed and open. Although it is not necessary to develop an entirely new approach in order to add this capability, the opportunity has been taken to develop revised full scope guidance covering all plant states in addition to the fuel in the fuel building. The EPR includes at the design phase systems and measures to minimize the risk of severe accident and to mitigate such potential scenarios. This presents a difference in comparison with existing plant, for which severe accidents where not considered in the design. Thought developed for all type of plants, OSSA will also be applied on the EPR, with adaptations designed to take into account its favourable situation in that field. This revised approach will incorporate a number of new features which will simplify and streamline the guidance material while ensuring comprehensive guidance for response to any severe accident. Examples of such features include : - Identification of severe accident challenges based on plant specific studies. - Revision of the split of responsibilities between operations and technical support center staff. - Fixed setpoint entry conditions, ensuring that the transition from emergency procedures takes place at a consistent core/fuel condition (regardless of scenario), and which fixes the time window available to attempt ultimate preventive measures. - A safety function concept for monitoring plant conditions (in the control room). - An integrated graphic-based diagnostic tool including entry condition, challenge prioritization, and exit condition monitoring to be used by the technical support team. This paper describes the basic features of OSSA, and project status. (authors)

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

    SciTech Connect (OSTI)

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

    2003-01-01T23:59:59.000Z

    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.

  11. accidents: Topics by E-print Network

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

    Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date accident treatment provided? Yes No Where Was time lost from work? Yes No If yes, how long? Could this...

  12. BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE Especially Designed for the Dependents. It is not a contract of insurance. Your coverage is governed by a policy of student accident and sickness insurance

  13. RICE UNIVERSITY ACCIDENT/INJURY REPORT

    E-Print Network [OSTI]

    Natelson, Douglas

    RICE UNIVERSITY ACCIDENT/INJURY REPORT Please Print Section A: Details of incident Injury Work Exposure to radiation Mental stress factors Noise Insect/animal bite Vehicle accident Slip

  14. Analysis of accidents during flashing operations

    E-Print Network [OSTI]

    Obermeyer, Michael Edward

    1993-01-01T23:59:59.000Z

    University, 1976 Federal Highway Administration Study, 1980 San Francisco Study National Study Portland, Oregon Study Summary of Literature Review Studies 13 14 16 17 20 CHAPTER Page III. ACCIDENT ANALYSIS METHODOLOGY . 22 Study Site Location... V. SUMMARY AND FINDINGS 44 REFERENCES 48 VITA 50 LIST OF TABLES TABLE 1. Groupings for Marson's Accident Analysis 2. Groupings for San Francisco Accident Analysis 3. Groupings for Portland Accident Analysis 4. Sample Sizes by Volume Ratio 5...

  15. UWO Vehicle ACCIDENT REPORTING FORM

    E-Print Network [OSTI]

    Sinnamon, Gordon J.

    UWO Vehicle ­ ACCIDENT REPORTING FORM To be completed at the scene. (Important: Do not admit liability or discuss any settlement.) If there are personal injuries or severe damage to the vehicle, call 911. If vehicle is drivable and if it's safe to do so, pull to the side of road away from traffic. Put

  16. TREE FAILURES AND ACCIDENTS IN

    E-Print Network [OSTI]

    Standiford, Richard B.

    .DEPARTMENT O F AGRICULTURE GENERAL TECHNICAL REPORT PSW- 24 #12;TREE FAILURES AND ACCIDENTS IN RECREATION are major concerns. Injuries, fatalities, and high property losses occur each year as a result of tree losses associated with public occupancy. Hazard reduction can limit such losses to predefined levels

  17. RADTRAN3. Radioactive Material Transport Risk

    SciTech Connect (OSTI)

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

    1986-02-01T23:59:59.000Z

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

  18. ASSESSING CAUSAL FACTORS IN INDIVIDUAL ROAD ACCIDENTS

    E-Print Network [OSTI]

    Minnesota, University of

    ASSESSING CAUSAL FACTORS IN INDIVIDUAL ROAD ACCIDENTS: COLLECTIVE RESPONSIBILITY IN FREEWAY REAR accident report: Happened on I-94 in downtown Minneapolis Happened during the afternoon peak period Vehicle" is a "condition or event" such that "had the condition or event been prevented...the accident would not occur

  19. The Hartford Life and Accident Insurance

    E-Print Network [OSTI]

    The Hartford Life and Accident Insurance Company Group Numbers Basic Term Life - 677984 Basic by The Hartford Life and Accident Insurance Company. (Referred to as The Hartford or Hartford.) General from an accident, the benefit will be equal to $140,000 ($70,000 basic group term life PLUS $70

  20. Office of Inspector General report on inspection of selected issues regarding the Department of Energy accident investigation program

    SciTech Connect (OSTI)

    NONE

    1999-04-01T23:59:59.000Z

    One method used by the Department of Energy (DOE) to promote worker safety is through the Department`s accident investigation program. The objectives of the program are, among other things, to enhance safety and health of employees, to prevent the recurrence of accidents, and to reduce accident fatality rates and promote a downward trend in the number and severity of accidents. The Assistant Secretary, Office of Environment, Safety and Health (EH), through the EH Office of the Deputy Assistant Secretary for Oversight, is responsible for implementation of the Department`s accident investigation program. As part of the inspection, the authors reviewed an April 1997 EH accident investigation report regarding an accident involving a Lockheed Martin Energy Systems (LMES) welder, who suffered fatal burns when his clothing caught fire while he was using a cutting torch at the Oak Ridge K-25 Site. They also reviewed reports of other accident investigations conducted by EH and DOE field organizations. Based on the review of these reports, the authors identified issues concerning the adequacy of the examination and reporting by accident investigation boards of specific management systems and organizations as a possible accident root cause. The inspection also identified issues concerning worker safety that they determined required immediate management attention, such as whether occurrences were being reported in the appropriate management systems and whether prompt consideration was being given to implementing revisions of national standards when the revisions increased worker safety.

  1. Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

    SciTech Connect (OSTI)

    Youngen, G.

    1988-10-01T23:59:59.000Z

    The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

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

    SciTech Connect (OSTI)

    NONE

    1991-09-01T23:59:59.000Z

    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).

  3. TOWARDS SHARING OF DATA FROM ACCIDENTS WITH CHEMICALS J.P. Pineau, J.F. Lechaudel

    E-Print Network [OSTI]

    Boyer, Edmond

    in Flixborough (explosion with 29 fatalities) in 1974, Sandoz Bäle (fire with release of chemicals in water substance such äs a major emission, fire or explosion leading to serious damage to human health, transportation and use of chemicals were at the origin of very severe accidents. The manufacture of explosives

  4. Synthesis of VERCORS and Phebus data in severe accident codes and applications.

    SciTech Connect (OSTI)

    Gauntt, Randall O.

    2010-04-01T23:59:59.000Z

    The Phebus and VERCORS data have played an important role in contemporary understanding and modeling of fission product release and transport from damaged LWR fuel. The data from these test programs have allowed improvement of MELCOR modeling of release and transport processes for both low enrichment uranium fuel as well as high burnup and MOX fuels. The following paper describes the derivation, testing and incorporation of improved radionuclide release models into the MELCOR severe accident code.

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

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

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

  6. MELCOR Accident Consequence Code System (MACCS)

    SciTech Connect (OSTI)

    Chanin, D.I. (Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA)); Sprung, J.L.; Ritchie, L.T.; Jow, Hong-Nian (Sandia National Labs., Albuquerque, NM (USA))

    1990-02-01T23:59:59.000Z

    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.

  7. MELCOR Accident Consequence Code System (MACCS)

    SciTech Connect (OSTI)

    Jow, H.N.; Sprung, J.L.; Ritchie, L.T. (Sandia National Labs., Albuquerque, NM (USA)); Rollstin, J.A. (GRAM, Inc., Albuquerque, NM (USA)); Chanin, D.I. (Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA))

    1990-02-01T23:59:59.000Z

    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 previously used 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. Volume I, the User's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems. Volume II, the Model Description, describes the underlying models that are implemented in the code, and Volume III, the Programmer's Reference Manual, describes the code's structure and database management. 59 refs., 14 figs., 15 tabs.

  8. Computerized Accident Incident Reporting System | Department...

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

    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...

  9. ORISE: REAC/TS Radiation Accident Registries

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

    Accident Registries The Radiation Emergency Assistance CenterTraining Site (REACTS) at the Oak Ridge Institute for Science and Education (ORISE) maintains a number of radiation...

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

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

    tools utilized in the investigation of "accidents" can be valuable in looking at leading indicators associated with our safety program, to determine the embedded precursors to...

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

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

    February 18, 2003, at the East Tennessee Technology Park, Oak Ridge, Tennessee Type B Accident Investigation, Subcontractor Employee Personal Protective Equipment Ignition Incident...

  12. Severe accident research in Canada

    SciTech Connect (OSTI)

    Simpson, L.A. [AECL Research, Pinawa, Manitoba (Canada)

    1994-12-31T23:59:59.000Z

    The reactor safety research program in Canada not only recognizes the unique features of the CANDU reactor, but is supplemented by a strong interaction with the LWR research community. This is especially so in the area of severe accidents. We participate in international programs such as Phebus FP and CSARP to take advantage of cooperative efforts on phenomena that are generic to all reactors, but also have our distinct programs in Canada on severe fuel damage, fission product chemistry, aerosol behaviour and hydrogen combustion and mitigation. These programs address the characteristics of Canadian nuclear fuel and containment design, and our own series of severe accident scenarios. The scope of the R&D encompasses separate effects experiments, model development and code development, leading to validation testing in several large integral test facilities including the Radioiodine Test Facility and the Blowdown Test Facility in the NRU reactor. We also have extensive hydrogen combustion test facilities including the Large Scale Vented Combustion Test Facility now under construction. The essence of the program is described with examples from recent experiments and analysis.

  13. Accident Analysis for the NIST Research Reactor Before and After Fuel Conversion

    SciTech Connect (OSTI)

    Baek J.; Diamond D.; Cuadra, A.; Hanson, A.L.; Cheng, L-Y.; Brown, N.R.

    2012-09-30T23:59:59.000Z

    Postulated accidents have been analyzed for the 20 MW D2O-moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The analysis has been carried out for the present core, which contains high enriched uranium (HEU) fuel and for a proposed equilibrium core with low enriched uranium (LEU) fuel. The analyses employ state-of-the-art calculational methods. Three-dimensional Monte Carlo neutron transport calculations were performed with the MCNPX code to determine homogenized fuel compositions in the lower and upper halves of each fuel element and to determine the resulting neutronic properties of the core. The accident analysis employed a model of the primary loop with the RELAP5 code. The model includes the primary pumps, shutdown pumps outlet valves, heat exchanger, fuel elements, and flow channels for both the six inner and twenty-four outer fuel elements. Evaluations were performed for the following accidents: (1) control rod withdrawal startup accident, (2) maximum reactivity insertion accident, (3) loss-of-flow accident resulting from loss of electrical power with an assumption of failure of shutdown cooling pumps, (4) loss-of-flow accident resulting from a primary pump seizure, and (5) loss-of-flow accident resulting from inadvertent throttling of a flow control valve. In addition, natural circulation cooling at low power operation was analyzed. The analysis shows that the conversion will not lead to significant changes in the safety analysis and the calculated minimum critical heat flux ratio and maximum clad temperature assure that there is adequate margin to fuel failure.

  14. HEALTH EFFECTS OF THE NUCLEAR ACCIDENT AT THREE MILE ISLAND

    E-Print Network [OSTI]

    Fabrikant, J.I.

    2010-01-01T23:59:59.000Z

    Commission on the Accident at Three Mile Island (Fabrikant,Commission on the Accident at Three Mile Island. (Fahrikant,Commission on the Accident at Three Mile Island. (Fabrikant,

  15. accident victims: Topics by E-print Network

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

    Every year, traffic congestion and traffic accidents have been Cho, Sung-Bae 118 The Analysis of a Friendly Fire Accident using a Systems Model of Accidents* N.G. Leveson,...

  16. accident zone osobennosti: Topics by E-print Network

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

    Every year, traffic congestion and traffic accidents have been Cho, Sung-Bae 62 The Analysis of a Friendly Fire Accident using a Systems Model of Accidents* N.G. Leveson,...

  17. accident victim conduite: Topics by E-print Network

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

    Every year, traffic congestion and traffic accidents have been Cho, Sung-Bae 152 The Analysis of a Friendly Fire Accident using a Systems Model of Accidents* N.G. Leveson,...

  18. Derivation of Accident-Specific Material-at-Risk Equivalency Factors

    SciTech Connect (OSTI)

    Jason P. Andrus; Dr. Chad L. Pope

    2012-05-01T23:59:59.000Z

    A novel method for calculating material at risk (MAR) dose equivalency developed at the Idaho National Laboratory (INL) now allows for increased utilization of dose equivalency for facility MAR control. This method involves near-real time accounting for the use of accident and material specific release and transport. It utilizes all information from the committed effective dose equation and the five factor source term equation to derive dose equivalency factors which can be used to establish an overall facility or process MAR limit. The equivalency factors allow different nuclide spectrums to be compared for their respective dose consequences by relating them to a specific quantity of an identified reference nuclide. The ability to compare spectrums to a reference limit ensures that MAR limits are in fact bounding instead of attempting to establish a representative or bounding spectrum which may lead to unintended or unanalyzed configurations. This methodology is then coupled with a near real time material tracking system which allows for accurate and timely material composition information and corresponding MAR equivalency values. The development of this approach was driven by the complex nature of processing operations in some INL facilities. This type of approach is ideally suited for facilities and processes where the composition of the MAR and possible release mechanisms change frequently but in well defined fashions and in a batch-type nature.

  19. MELCOR accident analysis for ARIES-ACT

    E-Print Network [OSTI]

    California at San Diego, University of

    Flow Flow #12;Fusion Safety Program · MELCOR is a code originally designed to model severe accidentMELCOR accident analysis for ARIES-ACT Paul Humrickhouse Brad Merrill INL Fusion Safety Program progression in water-cooled fission reactors · INL has modified it for fusion; MELCOR 1.8.5 for fusion has

  20. Does Daylight Savings Time Affect Traffic Accidents?

    E-Print Network [OSTI]

    Deen, Sophia 1988-

    2012-04-20T23:59:59.000Z

    This paper studies the effect of changes in accident pattern due to Daylight Savings Time (DST). The extension of the DST in 2007 provides a natural experiment to determine whether the number of traffic accidents is affected by shifts in hours...

  1. TRAVEL ACCIDENT INSURANCE PLAN 01-01-2012 The Travel Accident Insurance Plan provides 24-hour Accident coverage while on Authorized

    E-Print Network [OSTI]

    Johnson, Peter D.

    1 TRAVEL ACCIDENT INSURANCE PLAN 01-01-2012 The Travel Accident Insurance Plan provides 24-hour Accident coverage while on Authorized Business Travel. Coverage begins at the actual starting point. Please note that the Employer reserves the right to amend or terminate this Travel Accident Insurance

  2. EVALUATION DES CONSEQUENCES D'ACCIDENTS DE TRANSPORT

    E-Print Network [OSTI]

    Boyer, Edmond

    radioactives matières corrosives matières et objets dangereux divers CLASSE LIMITATIVE oui non non en partie inflammables (polymères, point éclair lithium. * Le degré de toxicité est établi en

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

    SciTech Connect (OSTI)

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

    1997-05-01T23:59:59.000Z

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

  4. The Fukushima Daiichi Accident Study Information Portal

    SciTech Connect (OSTI)

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

    2012-11-01T23:59:59.000Z

    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.

  5. A methodology for estimating the residual contamination contribution to the source term in a spent-fuel transport cask

    SciTech Connect (OSTI)

    Sanders, T.L. (Sandia National Labs., Albuquerque, NM (United States)); Jordan, H. (EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant); Pasupathi, V. (Battelle, Columbus, OH (United States)); Mings, W.J. (USDOE Idaho Field Office, Idaho Falls, ID (United States)); Reardon, P.C. (GRAM, Inc., Albuquerque, NM (United States))

    1991-09-01T23:59:59.000Z

    This report describes the ranges of the residual contamination that may build up in spent-fuel transport casks. These contamination ranges are calculated based on data taken from published reports and from previously unpublished data supplied by cask transporters. The data involve dose rate measurements, interior smear surveys, and analyses of water flushed out of cask cavities during decontamination operations. A methodology has been developed to estimate the effect of residual contamination on spent-fuel cask containment requirements. Factors in estimating the maximum permissible leak rates include the form of the residual contamination; possible release modes; internal gas-borne depletion; and the temperature, pressure, and vibration characteristics of the cask during transport under normal and accident conditions. 12 refs., 9 figs., 4 tabs.

  6. Type B Accident Investigation Board Report on the November 1...

    Office of Environmental Management (EM)

    B Accident Investigation Board Report on the November 1, 1999, Construction Injury at the Monticello Mill Tailings Remedial Action Site, Monticello, Utah Type B Accident...

  7. 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...

  8. 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...

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

    Office of Environmental Management (EM)

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

  10. accident analysis structural: Topics by E-print Network

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

    provides a theoretical foundation for the introduction of unique new types of accident analysis, hazard analysis, accident prevention strategies including new approaches to...

  11. accident prone drivers: Topics by E-print Network

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

    provides a theoretical foundation for the introduction of unique new types of accident analysis, hazard analysis, accident prevention strategies including new approaches to...

  12. accident related release: Topics by E-print Network

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

    age on auto accidents is examined by employing an interrupted time series analysis of monthly accident data covering the period January, 1969, through September 1973. The data ......

  13. Radiological Release Accident Investigation Report- Phase 1 Radiation Report

    Broader source: Energy.gov [DOE]

    Phase 1 of this accident investigation report is an independent product of the Accident Investigation Board appointed by Matthew Moury, Deputy Assistant Secretary, Safety, Security, and Quality...

  14. Type B Accident Investigation of the July 12, 2007, Forklift...

    Energy Savers [EERE]

    2, 2007, Forklift and Pedestrian Accident at the Paducah Gaseous Diffusion Plant, PortsmouthPaducah Project Office Type B Accident Investigation of the July 12, 2007, Forklift and...

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

    Energy Savers [EERE]

    Investigation of the July 12, 2007, Forklift and Pedestrian Accident at the Paducah Gaseous Diffusion Plant, PortsmouthPaducah Project Office Type B Accident Investigation...

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

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

    Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video September 20, 2013 -...

  17. Partnership Logging Accidents Cornelis de Hoop, LA Forest Products Lab

    E-Print Network [OSTI]

    Partnership Logging Accidents · by · Cornelis de Hoop, LA Forest Products Lab · Albert Lefort Agreement · 1998 & 1999 Accident Reports · 25 injuries reported · 185 loggers signed up · 8 deaths 1999

  18. accident management aids: Topics by E-print Network

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

    Accident, Illness and Liability Coverage Risk Management in the 4-H Youth Development Program Environmental Sciences and Ecology Websites Summary: 1 Accident, Illness and...

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

    Energy Savers [EERE]

    Accident Investigation of the June 1, 2013, Stairway Fall Resulting in a Federal Employee Fatality at DOE Headquarters Germantown, Maryland Accident Investigation of the June 1,...

  20. accident sequence precursor: Topics by E-print Network

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

    Susskind; Nicolaos Toumbas 2000-03-17 7 Pedestrian Accidents - In-depth Analysis and Accident Figures. Open Access Theses and Dissertations Summary: ?? Pedestrian fatalities and...

  1. accident phenomenology cours: Topics by E-print Network

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

    Demande Commentaires Parrott, Lael 211 Pedestrian Accidents - In-depth Analysis and Accident Figures. Open Access Theses and Dissertations Summary: ?? Pedestrian fatalities and...

  2. accident management summary: Topics by E-print Network

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

    Management of the Acute Radiation Syndrome 2001 flow Feed back Radiation Accident MedicalManagement COMPENDIUMCOMPENDIUM MEDICAL MANAGEMENT OF RADIATION ACCIDENTS...

  3. Relating aviation service difficulty reports to accident data for safety trend prediction

    SciTech Connect (OSTI)

    Fullwood, R.; Hall, R.; Martinez, G.; Uryasev, S.

    1996-03-13T23:59:59.000Z

    This work explores the hypothesis that Service Difficulty Reports (SDR - primarily inspection reports) are related to Accident Incident Data System (AIDS - reports primarily compiled from National Transportation Safety Board (NTSB) accident investigations). This work sought and found relations between equipment operability reported in the SDR and aviation safety reported in AIDS. Equipment is not the only factor in aviation accidents, but it is the factor reported in the SDR. Two approaches to risk analysis were used: (1) The conventional method, in which reporting frequencies are taken from a data base (SDR), and used with an aircraft reliability block diagram model of the critical systems to predict aircraft failure, and (2) Shape analysis that uses the magnitude and shape of the SDR distribution compared with the AIDS distribution to predict aircraft failure.

  4. Estimating Rear-End Accident Probabilities at Signalized Intersections: An Occurrence-Mechanism Approach

    E-Print Network [OSTI]

    Wang, Yinhai

    Estimating Rear-End Accident Probabilities at Signalized Intersections: An Occurrence intersections, rear-end accidents are frequently the predominant accident type. These accidents result from to this deceleration. This paper mathematically represents this process, by expressing accident probability

  5. Accident sequence precursor events with age-related contributors

    SciTech Connect (OSTI)

    Murphy, G.A.; Kohn, W.E.

    1995-12-31T23:59:59.000Z

    The Accident Sequence Precursor (ASP) Program at ORNL analyzed about 14.000 Licensee Event Reports (LERs) filed by US nuclear power plants 1987--1993. There were 193 events identified as precursors to potential severe core accident sequences. These are reported in G/CR-4674. Volumes 7 through 20. Under the NRC Nuclear Plant Aging Research program, the authors evaluated these events to determine the extent to which component aging played a role. Events were selected that involved age-related equipment degradation that initiated an event or contributed to an event sequence. For the 7-year period, ORNL identified 36 events that involved aging degradation as a contributor to an ASP event. Except for 1992, the percentage of age-related events within the total number of ASP events over the 7-year period ({approximately}19%) appears fairly consistent up to 1991. No correlation between plant ape and number of precursor events was found. A summary list of the age-related events is presented in the report.

  6. COMPARING THE IDENTIFICATION OF RECOMMENDATIONS BY DIFFERENT ACCIDENT

    E-Print Network [OSTI]

    Johnson, Chris

    will be identified for similar incidents. Accident analysis methods can also help to reduce individual bias

  7. SUPERVISOR'S ACCIDENT INVESTIGATION FORM Employee's Name: Job Title

    E-Print Network [OSTI]

    Jiang, Wen

    SUPERVISOR'S ACCIDENT INVESTIGATION FORM Employee's Name: Job Title: Time employee has been in current position? How long had employee been at work prior to injury? Accident Date: Time of Accident: AM PM Overtime: Yes No Location of Accident (Be Specific): Specific Task Being Performed at Time

  8. ACCIDENT PREVENTION SIGNS, TAGS, LABELS, SIGNALS, PIPING SYSTEM IDENTIFICATION AND

    E-Print Network [OSTI]

    US Army Corps of Engineers

    EM 385-1-1 XX Sep 13 i Section 8 ACCIDENT PREVENTION SIGNS, TAGS, LABELS, SIGNALS, PIPING SYSTEM............................................................8-13 Tables: 8-1 Accident Prevention Sign Requirements..........................8-17 8-2 Accident.......................................8-24 8-9 Accident Prevention Tags.............................................8-25 #12;EM 385-1-1 XX

  9. UoS Motor Accident Report Form COMPANY DETAILS

    E-Print Network [OSTI]

    Sussex, University of

    UNIV01FL02 UoS Motor Accident Report Form COMPANY DETAILS INSURED: University of Sussex ADDRESS: LOCATION: DESCRIPTION OF HOW ACCIDENT HAPPENED: PLEASE DRAW A SKETCH OF THE ACCIDENT: #12;DRIVER DETAILS: PREVIOUS ACCIDENTS: ADDRESS: VEHICLE DETAILS DATE VEHICLE PURCHASED: MAKE/MODEL: REGISTRATION: MILEAGE

  10. Review of models applicable to accident aerosols

    SciTech Connect (OSTI)

    Glissmeyer, J.A.

    1983-07-01T23:59:59.000Z

    Estimations of potential airborne-particle releases are essential in safety assessments of nuclear-fuel facilities. This report is a review of aerosol behavior models that have potential applications for predicting aerosol characteristics in compartments containing accident-generated aerosol sources. Such characterization of the accident-generated aerosols is a necessary step toward estimating their eventual release in any accident scenario. Existing aerosol models can predict the size distribution, concentration, and composition of aerosols as they are acted on by ventilation, diffusion, gravity, coagulation, and other phenomena. Models developed in the fields of fluid mechanics, indoor air pollution, and nuclear-reactor accidents are reviewed with this nuclear fuel facility application in mind. The various capabilities of modeling aerosol behavior are tabulated and discussed, and recommendations are made for applying the models to problems of differing complexity.

  11. Dose calculations for severe LWR accident scenarios

    SciTech Connect (OSTI)

    Margulies, T.S.; Martin, J.A. Jr.

    1984-05-01T23:59:59.000Z

    This report presents a set of precalculated doses based on a set of postulated accident releases and intended for use in emergency planning and emergency response. Doses were calculated for the PWR (Pressurized Water Reactor) accident categories of the Reactor Safety Study (WASH-1400) using the CRAC (Calculations of Reactor Accident Consequences) code. Whole body and thyroid doses are presented for a selected set of weather cases. For each weather case these calculations were performed for various times and distances including three different dose pathways - cloud (plume) shine, ground shine and inhalation. During an emergency this information can be useful since it is immediately available for projecting offsite radiological doses based on reactor accident sequence information in the absence of plant measurements of emission rates (source terms). It can be used for emergency drill scenario development as well.

  12. Use of root in vehicular accident reconstruction

    E-Print Network [OSTI]

    Scurlock, Bob

    2011-01-01T23:59:59.000Z

    The purpose of this article is to introduce the reader to the ROOT data analysis software package, and demonstrate how it may be used to complement one's accident reconstruction analyses.

  13. A systems approach to food accident analysis

    E-Print Network [OSTI]

    Helferich, John D

    2011-01-01T23:59:59.000Z

    Food borne illnesses lead to 3000 deaths per year in the United States. Some industries, such as aviation, have made great strides increasing safety through careful accident analysis leading to changes in industry practices. ...

  14. Assessing economic consequences of radiation accidents

    SciTech Connect (OSTI)

    Rowe, M.D.; Lee, J.C.; Grimshaw, C.A.; Kalb, P.D.

    1987-01-01T23:59:59.000Z

    This project reviewed the literature on the economic consequences of accidents to determine the availability of assessment methods and data and their applicability to the high-level radioactive waste (HLW) disposal system before closure; determined needs for expansion, revision, or adaptation of methods and data for modeling economic consequences of accidents of the scale projected for the disposal system; and gathered data that might be useful for the needed revisions. 8 refs., 1 tab.

  15. Georgia Hosts Multi-Agency Waste Isolation Pilot Plant Transportation...

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

    Ga. - Emergency personnel throughout the U.S. who respond in the event of a potential accident involving radioactive waste shipments take part in mock training scenarios to help...

  16. risk_policies_accident_std_vist.doc/ac 1 Revised 07.26.13 STUDENT AND VISITOR ACCIDENT

    E-Print Network [OSTI]

    Su, Xiao

    risk_policies_accident_std_vist.doc/ac 1 Revised 07.26.13 STUDENT AND VISITOR ACCIDENT REPORTING: 408-924-1892 Student and Visitor Accident Reporting Guidelines These guidelines provide instructions for reporting and handling accidents or incidents that happen to students and visitors while on the San José

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

    SciTech Connect (OSTI)

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

    2003-02-25T23:59:59.000Z

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

  18. Estimate of radionuclide release characteristics into containment under severe accident conditions. Final report

    SciTech Connect (OSTI)

    Nourbakhsh, H.P. [Brookhaven National Lab., Upton, NY (United States)

    1993-11-01T23:59:59.000Z

    A detailed review of the available light water reactor source term information is presented as a technical basis for development of updated source terms into the containment under severe accident conditions. Simplified estimates of radionuclide release and transport characteristics are specified for each unique combination of the reactor coolant and containment system combinations. A quantitative uncertainty analysis in the release to the containment using NUREG-1150 methodology is also presented.

  19. Fuel Accident Condition Simulator (FACS) Furnace for Post-Irradiation Heating Tests of VHTR Fuel Compacts

    SciTech Connect (OSTI)

    Paul A Demkowicz; Paul Demkowicz; David V Laug

    2010-10-01T23:59:59.000Z

    Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as part of the Next Generation Nuclear Plant Fuels Development and Qualification Program. The PIE campaign will include extensive accident testing of irradiated very high temperature reactor fuel compacts to verify fission product retention characteristics at high temperatures. This work will be carried out at both the Idaho National Laboratory (INL) and the Oak Ridge National Laboratory, beginning with accident tests on irradiated fuel from the AGR-1 experiment in 2010. A new furnace system has been designed, built, and tested at INL to perform high temperature accident tests. The Fuel Accident Condition Simulator furnace system is designed to heat fuel specimens at temperatures up to 2000°C in helium while monitoring the release of volatile fission metals (e.g. Cs, Ag, Sr, Eu, and I) and fission gases (Kr, Xe). Fission gases released from the fuel to the sweep gas are monitored in real time using dual cryogenic traps fitted with high purity germanium detectors. Condensable fission products are collected on a plate attached to a water-cooled cold finger that can be exchanged periodically without interrupting the test. Analysis of fission products on the condensation plates involves dry gamma counting followed by chemical analysis of selected isotopes. This paper will describe design and operational details of the Fuel Accident Condition Simulator (FACS) furnace system, as well as preliminary system calibration results.

  20. Essays on Urban Transportation and Transportation Energy Policy

    E-Print Network [OSTI]

    Kim, Chun Kon

    2008-01-01T23:59:59.000Z

    fundamental explanation. Accident Analysis & Prevention, 29(the national economy? Accident Analysis & Prevention, 32(6),rate and car size. Accident Analysis & Prevention, 16(5-6),

  1. Probabilistic risk assessment course documentation. Volume 7. Environmental transport and consequence analysis

    SciTech Connect (OSTI)

    Ritchie, L.T.; Alpert, D.J.; Burke, R.P.; Ostmeyer, R.M.; Kaiser, G.D.; Runkle, G.E.; Woodard, K.

    1985-08-01T23:59:59.000Z

    Consequence models have been designed to assess health and economic risks from potential accidents at nuclear power plants. These models have been applied to an ever increasing variety of problems with ever increasing demands to improve modeling capabilities and provide greater realism. This course discusses the environmental transport of postulated radiological releases and the elements and purpose of accident consequence evaluation.

  2. Creating an urban deer-vehicle accident management plan using information from a town's GIS project

    E-Print Network [OSTI]

    Premo, Dean B.; Rogers, Elizabeth I.

    2001-01-01T23:59:59.000Z

    AN URBAN DEER-VEHICLE ACCIDENT MANAGEMENT PLAN USINGincrease in deer vehicle accidents. Given the Town'sof increased deer vehicle accidents which, in the past 10

  3. Do "Accidents" Happen? An Examination of Injury Mortality Among Maltreated Children

    E-Print Network [OSTI]

    Hornstein, Emily Putnam

    2010-01-01T23:59:59.000Z

    2002;26. Garling T. Children's environments, accidents,and accident prevention: An introduction. In: Garling T,Toward a Psychology of Accident Prevention. New York: Plenum

  4. A research university's rapid response to a fatal chemistry accident: Safety changes and outcomes

    E-Print Network [OSTI]

    Gibson, JH; Schröder, I; Wayne, NL

    2014-01-01T23:59:59.000Z

    to a fatal chemistry accident: Safety changes and outcomesprogram following a chemistry accident in December 2008 thatcommunity. Since the 2008 accident at UCLA, the na- tional

  5. Exploratory Analysis of Motor Carrier Accident Risk And Daily Driving Patterns

    E-Print Network [OSTI]

    Jovanis, Paul P.; Kaneko, Tetsuya; Lin, Tzuoo-Din

    1991-01-01T23:59:59.000Z

    in a Sleeper Berth," Accident Analysis and Prevention. 1988,Survival Theory," Accident Analysis and Prevention, Vol. 21,most of the analyses with accident data compared actual

  6. Estimating Pedestrian Accident Exposure: Approaches to a Statewide Pedestrian Exposure Database

    E-Print Network [OSTI]

    Greene-Roesel, Ryan; Diogenes, Mara Chagas; Ragland, David R

    2007-01-01T23:59:59.000Z

    in New Zealand. Accident Analysis and Prevention, Vol. 27,System Network-Traffic Accident Analysis and SurveillanceAutomated Traffic Accident Surveillance and Analysis System,

  7. Multiday Driving Patterns and Motor Carrier Accident Risk: A Disagregate Analysis

    E-Print Network [OSTI]

    Kaneko, Tetsuya; Jovanis, Paul P.

    1991-01-01T23:59:59.000Z

    as a survival process, Accident Analysis and Prevention, 22:a sleeper berth, rest Accident Analysis and Prevention, 20:using survival theory, Accident Analysis and Prevention, 21:

  8. Assessment of CRBR core disruptive accident energetics

    SciTech Connect (OSTI)

    Theofanous, T.G.; Bell, C.R.

    1984-03-01T23:59:59.000Z

    The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document. This assessment was performed for the Nuclear Regulatory Commission under the direction of the CRBR Program Office within the Office of Nuclear Reactor Regulation. It considered in detail the accident behavior for three accident initiators that are representative of three different classes of events; unprotected loss of flow, unprotected reactivity insertion, and protected loss of heat sink. The primary system's energetics accommodation capability was realistically, yet conservatively, determined in terms of core events. This accommodation capability was found to be equivalent to an isentropic work potential for expansion to one atmosphere of 2550 MJ or a ramp rate of about 200 $/s applied to a classical two-phase disassembly.

  9. 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

    2013-09-01T23:59:59.000Z

    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.

  10. 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

    2000-05-01T23:59:59.000Z

    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.

  11. LESSONS LEARNED FROM A RECENT LASER ACCIDENT

    SciTech Connect (OSTI)

    Woods, Michael; /SLAC

    2011-01-26T23:59:59.000Z

    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.

  12. MELCOR accident consequence code system (MACCS)

    SciTech Connect (OSTI)

    Alpert, D.J.; Chanin, D.I.; Helton, J.C.; Ostmeyer, R.M.; Ritchie, L.T.

    1985-01-01T23:59:59.000Z

    Currently, the usefulness of reactor accident consequence assessments for providing guidance for planning and decision making is limited by the poor definition of uncertainties in predicted results. The MELCOR Accident Consequence Code System has been structured to facilitate performing uncertainty and sensitivity analyses. MACCS incorporates improved modeling capabilities in the treatment of variable or long duration releases, deposition modeling, dosimetry, emergency response, radiological health effects, and economic effects. At this writing (March 1985), the new code system has been completed and is undergoing testing, de-bugging, etc. Release of the first version of the full MELCOR code system, with associated documentation, is anticipated for the Autumn of 1985.

  13. Accident and Off Normal Response and Recovery from Multi Canister Overpack (MCO) Processing Events

    SciTech Connect (OSTI)

    ALDERMAN, C.A.

    2000-09-19T23:59:59.000Z

    In the process of removing spent nuclear fuel (SNF) from the K Basins through its subsequent packaging, drymg, transportation and storage steps, the SNF Project must be able to respond to all anticipated or foreseeable off-normal and accident events that may occur. Response procedures and recovery plans need to be in place, personnel training established and implemented to ensure the project will be capable of appropriate actions. To establish suitable project planning, these events must first be identified and analyzed for their expected impact to the project. This document assesses all off-normal and accident events for their potential cross-facility or Multi-Canister Overpack (MCO) process reversal impact. Table 1 provides the methodology for establishing the event planning level and these events are provided in Table 2 along with the general response and recovery planning. Accidents and off-normal events of the SNF Project have been evaluated and are identified in the appropriate facility Safety Analysis Report (SAR) or in the transportation Safety Analysis Report for Packaging (SARP). Hazards and accidents are summarized from these safety analyses and listed in separate tables for each facility and the transportation system in Appendix A, along with identified off-normal events. The tables identify the general response time required to ensure a stable state after the event, governing response documents, and the events with potential cross-facility or SNF process reversal impacts. The event closure is predicated on stable state response time, impact to operations and the mitigated annual occurrence frequency of the event as developed in the hazard analysis process.

  14. The temporal effect of traffic violations and accidents on accident occurrence

    E-Print Network [OSTI]

    McKemie, Martha Susan

    1979-01-01T23:59:59.000Z

    THE TEMPORAL EFFECT OF TRAFFIC VIOLATIONS AND ACCIDENTS ON ACCIDENT OCCURRENCE A Thesis by . 1artha Susan McKemie Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER... OF SCIENCE December 1979 Major Subject: Industrial Engineering THE TEMPORAL El'FECT OF TRAI'FIC VIOIATIONS AND ACCIDENTS ON XCCIDENT OCCURPEENCE A Thesis by Martha Susan McKemie Approved as to style and content by: / ~J' (Chairman of Commi tee...

  15. Decontamination analysis of the NUWAX-83 accident site using DECON

    SciTech Connect (OSTI)

    Tawil, J.J.

    1983-11-01T23:59:59.000Z

    This report presents an analysis of the site restoration options for the NUWAX-83 site, at which an exercise was conducted involving a simulated nuclear weapons accident. This analysis was performed using a computer program deveoped by Pacific Northwest Laboratory. The computer program, called DECON, was designed to assist personnel engaged in the planning of decontamination activities. The many features of DECON that are used in this report demonstrate its potential usefulness as a site restoration planning tool. Strategies that are analyzed with DECON include: (1) employing a Quick-Vac option, under which selected surfaces are vacuumed before they can be rained on; (2) protecting surfaces against precipitation; (3) prohibiting specific operations on selected surfaces; (4) requiring specific methods to be used on selected surfaces; (5) evaluating the trade-off between cleanup standards and decontamination costs; and (6) varying of the cleanup standards according to expected exposure to surface.

  16. accident localisation system: Topics by E-print Network

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

    to designing performance monitoring and safety metrics. 1 Nancy Leveson 2004-01-01 14 The Analysis of a Friendly Fire Accident using a Systems Model of Accidents* N.G. Leveson,...

  17. accident issledovanie raspredeleniya: Topics by E-print Network

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

    Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date accident treatment provided? Yes No Where Was time lost from work? Yes No If yes, how long? Could this...

  18. accident soderzhanie korotkozhivushchikh: Topics by E-print Network

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

    Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date accident treatment provided? Yes No Where Was time lost from work? Yes No If yes, how long? Could this...

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

    SciTech Connect (OSTI)

    Hill, Robin L.; Conrady, Matthew M.

    2010-06-30T23:59:59.000Z

    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.

  20. Type B Accident Investigation, Response to the 24 Command Wildland...

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

    Type B Accident Investigation, Response to the 24 Command Wildland Fire on the Hanford Site, June 27-July 1, 2000 Type B Accident Investigation, Response to the 24 Command Wildland...

  1. accidents epidemiology trends: Topics by E-print Network

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

    8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Accident epidemiology and the US chemical industry: accident history and worst-case data from...

  2. accident du travail: Topics by E-print Network

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

    18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Bordereau de transmission accident du travail Mathematics Websites Summary: Bordereau de transmission accident du...

  3. ACCIDENT ANALYSIS AND HAZARD ANALYSIS FOR HUMAN AND ORGANIZATIONAL FACTORS

    E-Print Network [OSTI]

    Leveson, Nancy

    culpable. An accident analysis method is needed that will guide the work, aid in the analysis of the role

  4. Characterization of a nuclear accident dosimeter

    E-Print Network [OSTI]

    Burrows, Ronald Allen

    1995-01-01T23:59:59.000Z

    The 23rd nuclear accident dosimetry intercomparison was held during the week of June 12-16, 1995 at Los Alamos National Laboratory. This report presents the results of this event, referred to as NAD 23, as related to the performance of Sandia...

  5. INTERNATIONAL STUDENT & SCHOLAR Accident & Sickness Insurance Plan

    E-Print Network [OSTI]

    Bordenstein, Seth

    and scholars participating in international educational programs outside of the United States. It is strongly an accident and sickness insurance plan for international students and scholars studying in the United States. The International Student & Scholar plan has a low monthly rate of $70 per person. WE'VE GOT YOU COVERED

  6. ANS severe accident program overview & planning document

    SciTech Connect (OSTI)

    Taleyarkhan, R.P.

    1995-09-01T23:59:59.000Z

    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.

  7. L'accident la centrale nuclaire de Quelques explications scientifiques

    E-Print Network [OSTI]

    Skorobogatiy, Maksim

    L'accident à la centrale nucléaire de Fukushima Quelques explications scientifiques G. Marleau, J´eal, 18 mars 2011 L'accident `a la centrale nucl´eaire de Fukushima ­ 1/29 Accident de Fukushima 1 Contenu de Fukushima. 3. La puissance résiduelle. 4. Perte de refroidissement et conséquences. 5

  8. Policy 3240 Accident Review Committee 1 OLD DOMINION UNIVERSITY

    E-Print Network [OSTI]

    Policy 3240 ­ Accident Review Committee 1 OLD DOMINION UNIVERSITY University Policy Policy #3240 ACCIDENT REVIEW COMMITTEE Responsible Oversight Executive: Vice President for Administration and Finance vehicles for which ODU is responsible and the University's Accident Review Committee in the review

  9. HEALTH AND ACCIDENT INSURANCE VERIFICATION ******************** TO BE COMPLETED BY STUDENT ********************

    E-Print Network [OSTI]

    Jawitz, James W.

    HEALTH AND ACCIDENT INSURANCE VERIFICATION ******************** TO BE COMPLETED BY STUDENT Services Office of the university of Florida requires that s/he has health and accident insurance with your participating in study abroad activate hold health and accident insurance with a minimum coverage of $200

  10. For the mathematically accident prone student W Stephen Wilson

    E-Print Network [OSTI]

    Wilson, W. Stephen

    For the mathematically accident prone student by W Stephen Wilson Many students make the claim answers, whatever the reason for the incorrect answer. Students who are accident prone in mathematics. This is generally good advice for anyone, not just the accident prone. As problems get more and more complicated

  11. A New Accident Model for Engineering Safer Systems Nancy Leveson

    E-Print Network [OSTI]

    Leveson, Nancy

    A New Accident Model for Engineering Safer Systems Nancy Leveson Aeronautics and Astronautics Dept changes in the etiology of accidents and is creating a need for changes in the explanatory mechanisms used. We need better and less subjective understanding of why accidents occur and how to prevent future

  12. Structure Evolution of Dynamic Bayesian Network for Traffic Accident Detection

    E-Print Network [OSTI]

    Cho, Sung-Bae

    Structure Evolution of Dynamic Bayesian Network for Traffic Accident Detection Ju-Won Hwang, Young and the accuracy in a domain of the traffic accident detection. Keywords-structure of dynamic Bayesian network; Bayesian network, evolution I. INTRODUCTION Every year, traffic congestion and traffic accidents have been

  13. Annexes 195 13.11 Fecal Accident Plan

    E-Print Network [OSTI]

    Annexes 195 13.11 Fecal Accident Plan Residual and Contact Time Table Loose Stool Chlorine Residual and Contact Time Table Formed Stool Chlorine Residual mg/l or PPM Time Minutes 2 25 Sample Fecal Accident/spa at three locations to ensure proper mixing. Record fecal accidents in maintenance logs. Follow normal pool

  14. A STAMP ANALYSIS OF THE LEX COMAIR 5191 ACCIDENT

    E-Print Network [OSTI]

    Leveson, Nancy

    A STAMP ANALYSIS OF THE LEX COMAIR 5191 ACCIDENT Thesis submitted in partial fulfilment;A STAMP ANALYSIS OF THE LEX COMAIR 5191 ACCIDENT Paul S. Nelson 2 #12;Acknowledgements I want pressure" (Dekker, 2007, p. 131) A new, holistic systems perspective, accident model is used for analysis

  15. Accident/Injury Reporting, Investigation, & Basic First Aid Plan

    E-Print Network [OSTI]

    Long, Nicholas

    Accident/Injury Reporting, Investigation, & Basic First Aid Plan Environmental Health, Safety of accidents/injuries at Stephen F. Austin State University (SFASU) and provides basic first aid practices. It is designed to help reduce injuries by reducing unsafe or hazardous conditions and discouraging accident

  16. COLUMBIA UNIVERSITY Departmental Accident Report Form for Worker's Compensation Benefits

    E-Print Network [OSTI]

    Jia, Songtao

    COLUMBIA UNIVERSITY Departmental Accident Report Form for Worker's Compensation Benefits EMPLOYEE___________ ACCIDENT DATA (to be completed by employee) Date of Injury_____/_____/____ Time of Injury the employee How did the injury or illness occur? (Describe fully the events that caused the accident) Describe

  17. CLAIMANT AUTO ACCIDENT REPORT For Completion by Driver

    E-Print Network [OSTI]

    Tullos, Desiree

    CLAIMANT AUTO ACCIDENT REPORT For Completion by Driver D E P A R T M E N T O F A D M I N I S T R Address City State Zip For what purpose was car being used at time of accident? Has damage been repaired signals did you give? Other Driver? Who investigated? Who Cited and Why? Describe Accident CONTINUE

  18. Scar sarcoidosis with a 50-year interval between an accident and onset of lesions

    E-Print Network [OSTI]

    Jr, Hiram Larangeira de Almeida; Fiss, Roberto Coswig

    2008-01-01T23:59:59.000Z

    year interval between an accident and onset of lesions Hiramreported in scars of accidents [ 2 ], herpes zoster [ 1 ],

  19. Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery

    SciTech Connect (OSTI)

    Layne Pincock; Wendell Hintze; Dr. Koji Shirai

    2012-07-01T23:59:59.000Z

    Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics: packaging, transportation, and disposition. This research work was performed as a collaboration between Japan’s Central Research Institute of Electric Power Industry (CRIEPI) and the Idaho National Laboratory (INL). Hundreds of TMI-2 related documents were searched and pertinent information was gleaned from these documents. Other important information was also obtained by interviewing employees who were involved first hand in various aspects of the TMI-2 cleanup effort. This paper is organized into three main sections: (1) Transport from Three Mile Island to Central Facilities Area at INL, (2) Transport from INL Central Receiving Facility to INL Test Area North (TAN) and wet storage at TAN, and (3) Transport from TAN to INL Idaho Nuclear Technology and Engineering Center (INTEC) and Dry Storage at INTEC. Within each of these sections, lessons learned from performing recovery activities are presented and their applicability to the Fukushima Daiichi nuclear power plant cleanup are outlined.

  20. Effects of non-latching blast valves on the source term and consequences of the design-basis accidents in the Device Assembly Facility (DAF)

    SciTech Connect (OSTI)

    Nguyen, D.H.

    1993-08-01T23:59:59.000Z

    The analysis of the Design-Basis Accidents (DBA) involving high explosives (HE) and Plutonium (Pu) in the assembly cell of the Device Assembly Facility (DAF), which was completed earlier, assumed latching blast valves in the ventilation system of the assembly cell. Latching valves effectively sealed a release path through the ventilation duct system. However, the blast valves in the assembly cell, as constructed are actually non-latching valves, and would reopen when the gas pressure drops to 0.5 psi above one atmosphere. Because the reopening of the blast valves provides an additional release path to the environment, and affects the material transport from the assembly cell to other DAF buildings, the DOE/NV DAF management has decided to support an additional analysis of the DAF`s DBA to account for the effects of non-latching valves. Three cases were considered in the DAF`s DBA, depending on the amount of HE and Pu involved, as follows: Case 1 -- 423 {number_sign}HE, 16 kg Pu; Case 2 -- 150 {number_sign}HE 10 kg Pu; Case 3 -- 55 {number_sign}HE 5 kg Pu. The results of the analysis with non-latching valves are summarized.

  1. Local Transportation

    E-Print Network [OSTI]

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

  2. Greening Transportation

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

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

  3. Rflexions sur le transfert mthodologique de l'analyse qualitative d'accidents de la circulation routire issue de l'tude dtaille des accidents (EDA) franaise aux

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    transfer for qualitative road accident analysis obtained from French Detailed Accident Studies (DAS the comprehensive accident analysis methodologies used in developed countries provide an understanding of the origin accident studies (DASs) and their adaptation to the analysis of accident reports. Colombia has

  4. The Analysis of a Friendly Fire Accident using a Systems Model of Accidents* N.G. Leveson, Ph.D.; Massachusetts Institute of Technology; Cambridge, Massachusetts

    E-Print Network [OSTI]

    Leveson, Nancy

    The Analysis of a Friendly Fire Accident using a Systems Model of Accidents* N.G. Leveson, Ph.D.; University of Victoria; Victoria, Canada Keywords: accident analysis, accident models Abstract In another paper presented at this conference, Leveson describes a new accident model based on systems theory [2

  5. HOW TO REPORT AN ACCIDENT, INCIDENT OR NEAR MISS 1. Notify your supervisor or lab manager as soon as possible of your accident, incident, or

    E-Print Network [OSTI]

    Borenstein, Elhanan

    HOW TO REPORT AN ACCIDENT, INCIDENT OR NEAR MISS 1. Notify your supervisor or lab manager as soon as possible of your accident, incident, or near miss. 2. Fill out the online accident report (OARS) form://www.ehs.washington.edu/ohsoars/index.shtm. The supervisor, lab manager, or person who had the accident can fill out the form. 3. For any serious accidents

  6. Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 3: Fission-Product Transport and Dose PIRTs

    SciTech Connect (OSTI)

    Morris, Robert Noel [ORNL

    2008-03-01T23:59:59.000Z

    This Fission Product Transport (FPT) Phenomena Identification and Ranking Technique (PIRT) report briefly reviews the high-temperature gas-cooled reactor (HTGR) FPT mechanisms and then documents the step-by-step PIRT process for FPT. The panel examined three FPT modes of operation: (1) Normal operation which, for the purposes of the FPT PIRT, established the fission product circuit loading and distribution for the accident phase. (2) Anticipated transients which were of less importance to the panel because a break in the pressure circuit boundary is generally necessary for the release of fission products. The transients can change the fission product distribution within the circuit, however, because temperature changes, flow perturbations, and mechanical vibrations or shocks can result in fission product movement. (3) Postulated accidents drew the majority of the panel's time because a breach in the pressure boundary is necessary to release fission products to the confinement. The accidents of interest involved a vessel or pipe break, a safety valve opening with or without sticking, or leak of some kind. Two generic scenarios were selected as postulated accidents: (1) the pressurized loss-of-forced circulation (P-LOFC) accident, and (2) the depressurized loss-of-forced circulation (D-LOFC) accidents. FPT is not an accident driver; it is the result of an accident, and the PIRT was broken down into a two-part task. First, normal operation was seen as the initial starting point for the analysis. Fission products will be released by the fuel and distributed throughout the reactor circuit in some fashion. Second, a primary circuit breach can then lead to their release. It is the magnitude of the release into and out of the confinement that is of interest. Depending on the design of a confinement or containment, the impact of a pressure boundary breach can be minimized if a modest, but not excessively large, fission product attenuation factor can be introduced into the release path. This exercise has identified a host of material properties, thermofluid states, and physics models that must be collected, defined, and understood to evaluate this attenuation factor. The assembled PIRT table underwent two iterations with extensive reorganization between meetings. Generally, convergence was obtained on most issues, but different approaches to the specific physics and transport paths shade the answers accordingly. The reader should be cautioned that merely selecting phenomena based on high importance and low knowledge may not capture the true uncertainty of the situation. This is because a transport path is composed of several serial linkages, each with its own uncertainty. The propagation of a chain of modest uncertainties can lead to a very large uncertainty at the end of a long path, resulting in a situation that is of little regulatory guidance.

  7. West Valley Demonstration Project Transportation Emergency Management...

    Office of Environmental Management (EM)

    WVDP emergency management programs in dealing with transportation events involving hazardous materials (not related to nuclear weapons components), since the site is...

  8. Evaluation Metrics Applied to Accident Tolerant Fuels

    SciTech Connect (OSTI)

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

    2014-10-01T23:59:59.000Z

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

  9. Sandia National Laboratories: Severe Accident Modeling

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

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

  10. Chamber transport

    SciTech Connect (OSTI)

    OLSON,CRAIG L.

    2000-05-17T23:59:59.000Z

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

  11. 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

    2010-03-01T23:59:59.000Z

    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.

  12. Fallout: The experiences of a medical team in the care of a Marshallese population accidently exposed to fallout radiation

    SciTech Connect (OSTI)

    Conard, R.A.

    1992-09-01T23:59:59.000Z

    This report presents an historical account of the experiences of the Brookhaven Medical Team in the examination and treatment of the Marshallese people following their accidental exposure to radioactive fallout in 1954. This is the first time that a population has been heavily exposed to radioactive fallout, and even though this was a tragic mishap, the medical findings have provided valuable information for other accidents involving fallout such as the recent reactor accident at Chernobyl. Noteworthy has been the unexpected importance of radioactive iodine in the fallout in producing thyroid abnormalities.

  13. EPR Severe Accident Threats and Mitigation

    SciTech Connect (OSTI)

    Azarian, G. [Framatome ANP SAS, Tour Areva, Place de la Coupole 92084 Paris la Defense (France); Kursawe, H.M.; Nie, M.; Fischer, M.; Eyink, J. [Framatome ANP GmbH, Freyeslebenstrasse, 1, D-91058 Erlangen (Germany); Stoudt, R.H. [Framatome ANP Inc. - 3315 Old Forest Rd, Lynchburgh, VA 24501 (United States)

    2004-07-01T23:59:59.000Z

    Despite the extremely low EPR core melt frequency, an improved defence-in-depth approach is applied in order to comply with the EPR safety target: no stringent countermeasures should be necessary outside the immediate plant vicinity like evacuation, relocation or food control other than the first harvest in case of a severe accident. Design provisions eliminate energetic events and maintain the containment integrity and leak-tightness during the entire course of the accident. Based on scenarios that cover a broad range of physical phenomena and which provide a sound envelope of boundary conditions associated with each containment challenge, a selection of representative loads has been done, for which mitigation measures have to cope with. This paper presents the main critical threats and the approach used to mitigate those threats. (authors)

  14. US Department of Energy Chernobyl accident bibliography

    SciTech Connect (OSTI)

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

    1992-04-01T23:59:59.000Z

    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.

  15. Understanding the Columbia Space Shuttle Accident

    SciTech Connect (OSTI)

    Osheroff, Doug (Stanford University) [Stanford University

    2004-06-16T23:59:59.000Z

    On February 1, 2003, the NASA space shuttle Columbia broke apart during re-entry over East Texas at an altitude of 200,000 feet and a velocity of approximately 12,000 mph. All aboard perished. Prof. Osheroff was a member of the board that investigated the origins of this accident, both physical and organizational. In his talk he will describe how the board was able to determine with almost absolute certainty the physical cause of the accident. In addition, Prof. Osherhoff will discuss its organizational and cultural causes, which are rooted deep in the culture of the human spaceflight program. Why did NASA continue to fly the shuttle system despite the persistent failure of a vital sub-system that it should have known did indeed pose a safety risk on every flight? Finally, Prof. Osherhoff will touch on the future role humans are likely to play in the exploration of space.

  16. Mitigative techniques and analysis of generic site conditions for ground-water contamination associated with severe accidents

    SciTech Connect (OSTI)

    Shafer, J.M.; Oberlander, P.L.; Skaggs, R.L.

    1984-04-01T23:59:59.000Z

    The purpose of this study is to evaluate the feasibility of using ground-water contaminant mitigation techniques to control radionuclide migration following a severe commercial nuclear power reactor accident. The two types of severe commercial reactor accidents investigated are: (1) containment basemat penetration of core melt debris which slowly cools and leaches radionuclides to the subsurface environment, and (2) containment basemat penetration of sump water without full penetration of the core mass. Six generic hydrogeologic site classifications are developed from an evaluation of reported data pertaining to the hydrogeologic properties of all existing and proposed commercial reactor sites. One-dimensional radionuclide transport analyses are conducted on each of the individual reactor sites to determine the generic characteristics of a radionuclide discharge to an accessible environment. Ground-water contaminant mitigation techniques that may be suitable, depending on specific site and accident conditions, for severe power plant accidents are identified and evaluated. Feasible mitigative techniques and associated constraints on feasibility are determined for each of the six hydrogeologic site classifications. The first of three case studies is conducted on a site located on the Texas Gulf Coastal Plain. Mitigative strategies are evaluated for their impact on contaminant transport and results show that the techniques evaluated significantly increased ground-water travel times. 31 references, 118 figures, 62 tables.

  17. Transportation of medical isotopes

    SciTech Connect (OSTI)

    Nielsen, D.L.

    1997-11-19T23:59:59.000Z

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

  18. Spent Fuel Transportation Cask Response to the Caldecott Tunnel Fire Scenario

    SciTech Connect (OSTI)

    Adkins, Harold E.; Koeppel, Brian J.; Cuta, Judith M.

    2007-01-01T23:59:59.000Z

    On April 7, 1982, a tank truck and trailer carrying 8,800 gallons of gasoline was involved in an accident in the Caldecott tunnel on State Route 24 near Oakland, California. The tank trailer overturned and subsequently caught fire. The United States Nuclear Regulatory Commission (USNRC), one of the agencies responsible for ensuring the safe transportation of radioactive materials in the United States, undertook analyses to determine the possible regulatory implications of this particular event for the transportation of spent nuclear fuel by truck. The Fire Dynamics Simulator (FDS) code developed by National Institute of Standards and Technology (NIST) was used to determine the thermal environment in the Caldecott tunnel during the fire. The FDS results were used to define boundary conditions for a thermal transient model of a truck transport cask containing spent nuclear fuel. The Nuclear Assurance Corporation (NAC) Legal Weight Truck (LWT) transportation cask was selected for this evaluation, as it represents a typical truck (over-the-road) cask, and can be used to transport a wide variety of spent nuclear fuels. Detailed analysis of the cask response to the fire was performed using the ANSYS® computer code to evaluate the thermal performance of the cask design in this fire scenario. This report describes the methods and approach used to assess the thermal response of the selected cask design to the conditions predicted in the Caldecott tunnel fire. The results of the analysis are presented in detail, with an evaluation of the cask response to the fire. The staff concluded that some components of smaller transportation casks resembling the NAC LWT, despite placement within an ISO container, could degrade significantly. Small transportation casks similar to the NAC LWT would probably experience failure of seals in this severe accident scenario. USNRC staff evaluated the radiological consequences of the cask response to the Caldecott tunnel fire. Although some components heated up beyond their service temperatures, the staff determined that there would be no significant release as a result of the fire for the NAC LWT and similar casks.

  19. Source term evaluation for postulated UF{sub 6} release accidents in gaseous diffusion plants -- Summer ventilation mode (non-seismic cases)

    SciTech Connect (OSTI)

    Kim, S.H.; Chen, N.C.J.; Taleyarkhan, R.P.; Wendel, M.W.; Keith, K.D.; Schmidt, R.W. [Oak Ridge National Lab., TN (United States); Carter, J.C. [J.C. Carter Associates, Inc., Knoxville, TN (United States); Dyer, R.H. [Dyer Enterprises, Harriman, TN (United States)

    1996-12-30T23:59:59.000Z

    Computer models have been developed to simulate the transient behavior of aerosols and vapors as a result of a postulated accident involving the release of uranium hexafluoride (UF{sub 6}) into the process building of a gaseous diffusion plant. For the current study, gaseous UF{sub 6} is assumed to get released in the cell housing atmosphere through B-line break at 58.97 kg/s for 10 min and 30 min duration at the Paducah and Portsmouth Gaseous Diffusion Plants. The released UF{sub 6} undergoes an exothermic chemical reaction with moisture (H{sub 2}O) in the air to form hydrogen fluoride (HF) and radioactive uranyl fluoride (UO{sub 2}F{sub 2}) while it disperses throughout the process building. As part of a facility-wide safety evaluation, this study evaluated source terms consisting of UO{sub 2}F{sub 2} as well as HF during a postulated UF{sub 6} release accident in a process building. UO{sub 2}F{sub 2} mainly remains as airborne-solid particles (aerosols), and HF is in a vapor form. Some UO{sub 2}F{sub 2} aerosols are removed from the air flow due to gravitational settling. The HF and the remaining UO{sub 2}F{sub 2} are mixed with air and exhausted through the building ventilation system. The MELCOR computer code was selected for simulating aerosols and vapor transport in the process building. To characterize leakage flow through the cell housing wall, 3-D CFD tool (CFDS-FLOW3D) was used. About 57% of UO{sub 2}F{sub 2} was predicted to be released into the environment. Since HF was treated as vapor, close to 100% was estimated to get released into the environment.

  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. [Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstrasse 400, D-01328 Dresden (Germany)

    2012-07-01T23:59:59.000Z

    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. Microbial Transport in the Subsurface

    SciTech Connect (OSTI)

    Ginn, Timothy R.; Camesano, Terri; Scheibe, Timothy D.; Nelson, Kirk B.; Clement, T. P.; Wood, Brian D.

    2005-12-01T23:59:59.000Z

    In this article we focus on the physical, chemical, and biological processes involved in the transport of bacteria in the saturated subsurface. We will first review conceptual models of bacterial phases in the subsurface, and then the processes controlling fate and transport on short (e.g., bioremediation) time scales. Finally we briefly review field bacterial transport experiments and discuss a number of issues that impact the application of current process descriptions and models at the field scale.

  2. Hazardous-material accidents near nuclear power plants: an evaluation of analyses and approaches

    SciTech Connect (OSTI)

    Kot, C.A.; Lin, H.C.; van Erp, J.B.; Eichler, T.V.; Wiedermann, A.H.

    1983-10-01T23:59:59.000Z

    The state of knowledge concerning postulated accidents involving offsite hazardous materials in the vicinity of nuclear power plants is critically evaluated. This effort is part of a study to analyze the potential effects of offsite hazards upon the safety of nuclear power plants and to develop a technical basis for the assessment of siting approaches. The evaluation includes consideration of data bases and statistics of hazardous materials and accidents involving them, deterministic aspects of possible material dispersion and threat environments, the susceptibility and vulnerability of vital plant systems, and a critical review of past licensing experience and regulatory practice with respect to these hazards. While many of the data bases and analysis methods exist for an adequate estimate of threat and plant response, this knowledge is not fully used and no comprehensive guidance has been developed. Siting of nuclear power plants relative to offsite hazardous materials is a risk based procedure that considers both probabilities and consequences of events that make up accident scenarios. In this context it appears feasible to improve the procedures vis-a-vis the perception of safety, economy of effort, and efficiency of implementation. A scenario dependent conditional risk approach is outlined as a possible means of improving the siting procedures.

  3. Chernobyl Studies Project: Working group 7.0, Environmental transport and health effects. Progress report, March--September 1994

    SciTech Connect (OSTI)

    Anspaugh, L.R.; Hendrickson, S.M. [eds.

    1994-12-01T23:59:59.000Z

    In April 1988, the US and the former-USSR signed a Memorandum of Cooperation (MOC) for Civilian Nuclear Reactor Safety; this MOC was a direct result of the accident at the Chernobyl Nuclear Power Plant Unit 4 and the following efforts by the two countries to implement a joint program to improve the safety of nuclear power plants and to understand the implications of environmental releases. A Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS) was formed to implement the MOC. The JCCCNRS established many working groups; most of these were the responsibility of the Nuclear Regulatory Commission, as far as the US participation was concerned. The lone exception was Working Group 7 on Environmental Transport and Health Effects, for which the US participation was the responsibility of the US Department of Energy (DOE). The purpose of Working Group 7 was succintly stated to be, ``To develop jointly methods to project rapidly the health effects of any future nuclear reactor accident.`` To implement the work DOE then formed two subworking groups: 7.1 to address Environmental Transport and 7.2 to address Health Effects. Thus, the DOE-funded Chernobyl Studies Project began. The majority of the initial tasks for this project are completed or near completion. The focus is now turned to the issue of health effects from the Chernobyl accident. Currently, we are involved in and making progress on the case-control and co-hort studies of thyroid diseases among Belarussian children. Dosimetric aspects are a fundamental part of these studies. We are currently working to implement similar studies in Ukraine. A major part of the effort of these projects is supporting these studies, both by providing methods and applications of dose reconstruction and by providing support and equipment for the medical teams.

  4. FASTGRASS: A mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

    SciTech Connect (OSTI)

    Rest, J.; Zawadzki, S.A. (Argonne National Lab., IL (United States))

    1992-09-01T23:59:59.000Z

    The primary physical/chemical models that form the basis of the FASTGRASS mechanistic computer model for calculating fission-product release from nuclear fuel are described. Calculated results are compared with test data and the major mechanisms affecting the transport of fission products during steady-state and accident conditions are identified.

  5. Bounding Radionuclide Inventory and Accident Consequence Calculation for the 1L Target

    SciTech Connect (OSTI)

    Kelsey, Charles T. IV [Los Alamos National Laboratory

    2011-01-01T23:59:59.000Z

    A bounding radionuclide inventory for the tungsten of the Los Alamos Neutron Science Center (LANSCE) IL Target is calculated. Based on the bounding inventory, the dose resulting from the maximum credible incident (MCI) is calculated for the maximally exposed offsite individual (MEOl). The design basis accident involves tungsten target oxidation following a loss of cooling accident. Also calculated for the bounding radionuclide inventory is the ratio to the LANSCE inventory threshold for purposes of inventory control as described in the target inventory control policy. A bounding radionuclide inventory calculation for the lL Target was completed using the MCNPX and CINDER'90 codes. Continuous beam delivery at 200 {micro}A to 2500 mA{center_dot}h was assumed. The total calculated activity following this irradiation period is 205,000 Ci. The dose to the MEOI from the MCI is 213 mrem for the bounding inventory. The LANSCE inventory control threshold ratio is 132.

  6. Accident Investigation at the Idaho National Laboratory Engineering Demonstration Facility, February 2013

    Broader source: Energy.gov [DOE]

    On Monday, February 12, 2013, a principal investigator at the Idaho National Laboratory (INL) Engineering Demonstration Facility (IEDF) was testing the system configuration of experimental process involving liquid sodium carbonate. An unanticipated event occurred that resulted in the ejection of the 900° C liquid sodium carbonate from the system. The ejected liquid came into contact with the principal investigator and caused multiple second and third degree burn injuries to approximately 10 percent of his body. The Office of Health, Safety and Security (HSS) Site Lead for the Idaho Site shadowed the accident investigation team assembled by the contractor in an effort to independently verify that a rigorous, thorough, and unbiased investigation was taking place, and to maintain awareness of the events surrounding the accident

  7. Accident source terms for boiling water reactors with high burnup cores.

    SciTech Connect (OSTI)

    Gauntt, Randall O.; Powers, Dana Auburn; Leonard, Mark Thomas

    2007-11-01T23:59:59.000Z

    The primary objective of this report is to provide the technical basis for development of recommendations for updates to the NUREG-1465 Source Term for BWRs that will extend its applicability to accidents involving high burnup (HBU) cores. However, a secondary objective is to re-examine the fundamental characteristics of the prescription for fission product release to containment described by NUREG-1465. This secondary objective is motivated by an interest to understand the extent to which research into the release and behaviors of radionuclides under accident conditions has altered best-estimate calculations of the integral response of BWRs to severe core damage sequences and the resulting radiological source terms to containment. This report, therefore, documents specific results of fission product source term analyses that will form the basis for the HBU supplement to NUREG-1465. However, commentary is also provided on observed differences between the composite results of the source term calculations performed here and those reflected NUREG-1465 itself.

  8. Simulations of argon accident scenarios in the ATLAS experimental cavern a safety analysis

    E-Print Network [OSTI]

    Balda, F

    2002-01-01T23:59:59.000Z

    Some characteristic accidents in the ATLAS experimental cavern (UX15) are simulated by means of STAR-CD, a code using the "Finite-Volume" method. These accidents involve different liquid argon leaks from the barrel cryostat of the detector, thus causing the dispersion of the argon into the Muon Chamber region and the evaporation of the liquid. The subsequent temperature gradients and distribution of argon concentrations, as well as their evolution in time are simulated and discussed, with the purpose of analysing the dangers related to asphyxiation and to contact with cryogenic fluids for the working personnel. A summary of the theory that stands behind the code is also given. In order to validate the models, an experimental test on a liquid argon spill performed earlier is simulated, showing that the program is able to output reliable results. At the end, some safety-related recommendations are listed.

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment ofLetter Report:40PMDepartment ofs oLetter fromAccident on the

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment ofLetter Report:40PMDepartment ofs oLetter fromAccident on

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  14. Natural Circulation in the Blanket Heat Removal System During a Loss-of-Pumping Accident (LOFA) Based on Initial Conceptual Design

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    A transient natural convection model of the APT blanket primary heat removal (HR) system was developed to demonstrate that the blanket could be cooled for a sufficient period of time for long term cooling to be established following a loss-of-flow accident (LOFA). The particular case of interest in this report is a complete loss-of-pumping accident. For the accident scenario in which pumps are lost in both the target and blanket HR systems, natural convection provides effective cooling of the blanket for approximately 68 hours, and, if only the blanket HR systems are involved, natural convection is effective for approximately 210 hours. The heat sink for both of these accident scenarios is the assumed stagnant fluid and metal on the secondary sides of the heat exchangers.

  15. Interdisciplinary Institute for Innovation Le risque d'accident nuclaire

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Interdisciplinary Institute for Innovation Le risque d'accident nucléaire majeur : calcul et-27Feb2013 #12;Le risque d'accident nucléaire majeur : calcul et perception des probabilités1 François Lévêque L'accident de Fukushima Daiichi s'est produit le 11 mars 2011. Cette catastrophe nucléaire

  16. assigned accident investigation: Topics by E-print Network

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

    33 Long-term investigations of radiocaesium activity concentrations in carps in north Croatia after the Chernobyl accident CERN Preprints Summary: Long-term investigations of...

  17. accident source term: Topics by E-print Network

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

    42 Long-term investigations of radiocaesium activity concentrations in carps in north Croatia after the Chernobyl accident CERN Preprints Summary: Long-term investigations of...

  18. accident investigation: Topics by E-print Network

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

    26 Long-term investigations of radiocaesium activity concentrations in carps in north Croatia after the Chernobyl accident CERN Preprints Summary: Long-term investigations of...

  19. accident source terms: Topics by E-print Network

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

    42 Long-term investigations of radiocaesium activity concentrations in carps in north Croatia after the Chernobyl accident CERN Preprints Summary: Long-term investigations of...

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

    Office of Environmental Management (EM)

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

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

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

    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...

  2. affecting reactor accident: Topics by E-print Network

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

    METEOROLOGY; NUCLEAR POWER PLANTS; P CODES; PWR TYPE REACTORS; RADIATION 2 Does Daylight Savings Time Affect Traffic Accidents? Texas A&M University - TxSpace Summary: This...

  3. Type A Accident Investigation Board Report on the February 20...

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

    February 20, 1996, Fall Fatality at the Radioactive Waste Management Complex Transuranic Storage Area - Retrieval Enclosure, Idaho National Engineering Laboratory Type A Accident...

  4. Microsoft Word - Case Study for Enhanced Accident Tolerance Design...

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

    2355 Case Study for Enhanced Accident Tolerance Design Changes Steven Prescott Curtis Smith Tony Koonce June 2014 DISCLAIMER This information was prepared as an account of work...

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

    Energy Savers [EERE]

    on the October 15, 2001, Grout Injection Operator Injury at the Cold Test Pit South, Idaho National Engineering and Environmental Laboratory Type B Accident Investigation Board...

  6. accident loca testing: Topics by E-print Network

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

    for the degree ol' MASTER OF SCIENCE May 1992 Major Subject: Nuclear Engineering SIMULATION OF A SMALL BREAK LOSS OF COOLANT ACCIDENT CONDUCTED AT THE BETHSY INTEGRAL TEST...

  7. Sec. Herrington Leads Delegation in Response to Chernobyl Accident...

    National Nuclear Security Administration (NNSA)

    Sec. Herrington Leads Delegation in Response to Chernobyl Accident | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the...

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

    Energy Savers [EERE]

    at the Separations Process Research Unit (SPRU), Building H2 Demolition, in Niskayuna, New, York Type B Accident Investigation Board Report of the September 29, 2010,...

  9. accident prevention manual: Topics by E-print Network

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

    Wu, Mingshen 9 Chest--Manual Defrost Models Biology and Medicine Websites Summary: old refrigerator or freezer, please follow the instructions below to help prevent accidents....

  10. accident management programme: Topics by E-print Network

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

    ACCIDENT FIRE POLLUTION "NEAR MISS immediately after the occurrence. 3 Material damage or pollution Total volume of mercury spillage was approximately 200 ml. Of that volume,...

  11. accident management programmes: Topics by E-print Network

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

    ACCIDENT FIRE POLLUTION "NEAR MISS immediately after the occurrence. 3 Material damage or pollution Total volume of mercury spillage was approximately 200 ml. Of that volume,...

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

    Energy Savers [EERE]

    Report, May 8, 2004, Exothermic Metal Reactor Event During Sodium Transfer Activities, East Tennessee Technology Park, Oak Ridge, Tennessee Type B Accident Investigation Board...

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

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

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

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

    Energy Savers [EERE]

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

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

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

    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,...

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

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

    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...

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

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

    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...

  18. accident resistant container: Topics by E-print Network

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

    failure of thermal barrier coatings (TBCs) driven by thickening Wadley, Haydn 2 OTHER ACCIDENT?24. ANY PERSON WHO KNOWINGLY AND WITH INTENT TO DEFRAUD ANY INSURANCE COMPANY OR...

  19. accident diagrams: Topics by E-print Network

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

    study of groups (see 22 or 26) Victor Guba; Mark Sapir 1996-01-01 2 AUTOMOBILE ACCIDENT REPORT Department of Financial Services Geosciences Websites Summary: . 0103 (USE...

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

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

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

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

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

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

  2. accident response calculations: Topics by E-print Network

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

    25 Next Page Last Page Topic Index 1 Primary Responsibilities 1. Identify potential accident hazards. Materials Science Websites Summary: Primary Responsibilities 1. Identify...

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

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

    at the K-25 Building, East Tennessee Technology Park, Oak Ridge, Tennessee Type B Accident Investigation Board Report of the Bechtel Jacobs Company, LLC Employee Fall Injury on...

  4. accident conditions final: Topics by E-print Network

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

    to evaluate human weather discomfort due to hot conditions and then tested for work accident differences using non-parametric procedures. Present findings showed that hot weather...

  5. Severe Accident Studies | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transfer toSensor Technologies for a SmartSevere Accident Studies

  6. Ramkrishna Mukherjee. Uganda: An Historical Accident?: Class, Natona, State Formation. Trenton, New Jersey: Africa World Press, 1985 281pp.

    E-Print Network [OSTI]

    Isabirye, Stephen B.

    1989-01-01T23:59:59.000Z

    Trenton, Historical Accident? : Class, Natona, New Jersey:in Mukherjee Historical Accident. analyzes the "poUticalare not an "historical accident." War, Violence and Children

  7. Comparative analyses of spent nuclear fuel transport modal options: Transport options under existing site constraints

    SciTech Connect (OSTI)

    Brentlinger, L.A.; Hofmann, P.L.; Peterson, R.W.

    1989-08-01T23:59:59.000Z

    The movement of nuclear waste can be accomplished by various transport modal options involving different types of vehicles, transport casks, transport routes, and intermediate intermodal transfer facilities. A series of systems studies are required to evaluate modal/intermodal spent fuel transportation options in a consistent fashion. This report provides total life-cycle cost and life-cycle dose estimates for a series of transport modal options under existing site constraints. 14 refs., 7 figs., 28 tabs.

  8. Analysis of the risk of transporting spent nuclear fuel by train

    SciTech Connect (OSTI)

    Elder, H.K.

    1981-09-01T23:59:59.000Z

    This report uses risk analyses to analyze the safety of transporting spent nuclear fuel for commercial rail shipping systems. The rail systems analyzed are those expected to be used in the United States when the total electricity-generating capacity by nuclear reactors is 100 GW in the late 1980s. Risk as used in this report is the product of the probability of a release of material to the environment and the consequences resulting from the release. The analysis includes risks in terms of expected fatalities from release of radioactive materials due to transportation accidents involving PWR spent fuel shipped in rail casks. The expected total risk from such shipments is 1.3 x 10/sup -4/ fatalities per year. Risk spectrums are developed for shipments of spent fuel that are 180 days and 4 years out-of-reactor. The risk from transporting spent fuel by train is much less (by 2 to 4 orders of magnitude) than the risk to society from other man-caused events such as dam failure.

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

    SciTech Connect (OSTI)

    Su'ud, Zaki; Anshari, Rio [Nuclear and Biophysics Research Group, Dept. of Physics, Bandung Institute of Technology, Jl.Ganesha 10, Bandung, 40132 (Indonesia)

    2012-06-06T23:59:59.000Z

    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.

  10. Enforcement Guidance Supplement 98-02: DOE Enforcement Activities where Off-site Transportation Issues are also Present.

    Broader source: Energy.gov [DOE]

    Recently several questions have arisen regarding the scope of Price-Anderson enforcement when transportation issues are directly or indirectly involved in an incident. These questions can be separated into two areas, (1) transportation issues that involve on-site transportation typically not regulated by the Department of Transportation (DOT), and (2) transportation issues that involve off-site transportation. This guidance addresses off-site transportation that is regulated by DOT and other state and federal agencies.

  11. Material Selection for Accident Tolerant Fuel Cladding

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

    none,

    2014-07-01T23:59:59.000Z

    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. However, 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 ?’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated. Keywords: Accident tolerant LWR Fuel cladding, FeCrAl, Mo, Ti2AlC, Al2O3, high temperature steam oxidation resistance« less

  12. Material Selection for Accident Tolerant Fuel Cladding

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

    none,

    2014-07-01T23:59:59.000Z

    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. However, 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 ?’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated. Keywords: Accident tolerant LWR Fuel cladding, FeCrAl, Mo, Ti2AlC, Al2O3, high temperature steam oxidation resistance

  13. Essays on Transportation Safety, Economics, and Policy

    E-Print Network [OSTI]

    Scholl, Patricia Lynn

    2011-01-01T23:59:59.000Z

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

  14. Modeling & analysis of criticality-induced severe accidents during refueling for the Advanced Neutron Source Reactor

    SciTech Connect (OSTI)

    Georgevich, V.; Kim, S.H.; Taleyarkhan, R.P.; Jackson, S.

    1992-10-01T23:59:59.000Z

    This paper describes work done at the Oak Ridge National Laboratory (ORNL) for evaluating the potential and resulting consequences of a hypothetical criticality accident during refueling of the 330-MW Advanced Neutron Source (ANS) research reactor. The development of an analytical capability is described. Modeling and problem formulation were conducted using concepts of reactor neutronic theory for determining power level escalation, coupled with ORIGEN and MELCOR code simulations for radionuclide buildup and containment transport Gaussian plume transport modeling was done for determining off-site radiological consequences. Nuances associated with modeling this blast-type scenario are described. Analysis results for ANS containment response under a variety of postulated scenarios and containment failure modes are presented. It is demonstrated that individuals at the reactor site boundary will not receive doses beyond regulatory limits for any of the containment configurations studied.

  15. Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video

    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.

  16. Using a town’s GIS project to create a deer-vehicle accident management plan

    E-Print Network [OSTI]

    Rogers, Elizabeth I.

    2003-01-01T23:59:59.000Z

    TO CREATE A DEER-VEHICLE ACCIDENT MANAGEMENT PLAN Elizabethhigh numbers of deer-vehicle accidents (DVAs) on a landscapeto provide an assessment of accident risk in time and space.

  17. Road traffic accidents in Kathmandu¿an hour of education yields a glimmer of hope

    E-Print Network [OSTI]

    Basnet, Bibhusan; Vohra, Rais; Bhandari, Amit; Pandey, Subash

    2013-01-01T23:59:59.000Z

    et al. : Road traffic accidents in Kathmandu— an hour ofOpen Access Road traffic accidents in Kathmandu—an hour ofnumber of road traffic accidents in the year 2012 decreased

  18. accident victims bio-indicateurs: Topics by E-print Network

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

    Every year, traffic congestion and traffic accidents have been Cho, Sung-Bae 119 The Analysis of a Friendly Fire Accident using a Systems Model of Accidents* N.G. Leveson,...

  19. Estimating Pedestrian Accident Exposure: Approaches to a Statewide Pedestrian Exposure Database

    E-Print Network [OSTI]

    Greene-Roesel, Ryan; Diogenes, Mara Chagas; Ragland, David R

    2007-01-01T23:59:59.000Z

    Pedestrian Exposure to Risk of Road Accident in New Zealand.Accident Analysis and Prevention, Vol. 27, No. 3, 1995, pp.Automated Traffic Accident Surveillance and Analysis System,

  20. UNIVERSITY OF TORONTO ACCIDENT/INCIDENT/OCCUPATIONAL DISEASE REPORT FOR EMPLOYEES

    E-Print Network [OSTI]

    Kronzucker, Herbert J.

    UNIVERSITY OF TORONTO ACCIDENT/INCIDENT/OCCUPATIONAL DISEASE REPORT FOR EMPLOYEES RELEVANT SECTIONS: _______________________________________ NAME OF SUPERVISOR TO WHOM ACCIDENT WAS REPORTED: _________________________________ TELEPHONE: _____________________ IF THERE WAS A DELAY IN REPORTING THIS ACCIDENT, LIST REASON

  1. CASE STUDY FOR ENHANCED ACCIDENT TOLERANCE DESIGN CHANGES

    SciTech Connect (OSTI)

    Prescott, Steven [Idaho National Laboratory; Smith, Curtis [Idaho National Laboratory; Tony Koonce

    2014-09-01T23:59:59.000Z

    The ability to better characterize and quantify safety margin is important to improved decision making about Light Water Reactor (LWR) design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the Risk Informed Safety Margin Characterization (RISMC) Pathway provides methods and tools that enable mitigation options known as risk informed margins management (RIMM) strategies. The methods and tools provided by RISMC are essential to a comprehensive and integrated RIMM approach that supports effective preservation of margin for both active and passive SSCs. In this report, we discuss the methods and technologies behind RIMM for an application focused on enhanced accident tolerance design changes for a representative nuclear power plant. We look at a variety of potential plant modifications and evaluate, using the RISMC approach, the implications to safety margin for the various strategies.

  2. TRANSPORT INVOLVING CONDUCTING FIBERS IN A NON-CONDUCTING MATRIX

    E-Print Network [OSTI]

    Walker, D. Greg

    to sev- eral applications including flexible thin-film transistors, PEM fuel cells, and direct energy, particularly Peltier devices, high electrical conductivity and low thermal conductivity are preferred

  3. accident analysis codes: Topics by E-print Network

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

    accident analysis codes First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Analysis of accidents during...

  4. Evaluation of Accident Frequencies at the Canister Storage Bldg (CSB)

    SciTech Connect (OSTI)

    POWERS, T.B.

    2000-03-20T23:59:59.000Z

    By using simple frequency calculations and fault tree logic, an evaluation of the design basis accident frequencies at the Canister Storage Building has been performed. The following are the design basis accidents: Mechanical damage of MCO; Gaseous release from the MCO; MCO internal hydrogen deflagration; MCO external hydrogen deflagration; Thermal runaway reactions inside the MCO; and Violation of design temperature criteria.

  5. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    1999-09-09T23:59:59.000Z

    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.

  6. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    1999-10-20T23:59:59.000Z

    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.

  7. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.; PIEPHO, M.G.

    2000-03-23T23:59:59.000Z

    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.

  8. accident analysis documentation: Topics by E-print Network

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

    accident analysis documentation First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Analysis of accidents...

  9. Berkeley Lab Accident Statistics Through December 31, 2008

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through December 31, 2008 These slides are updated on a monthly Goal DART Goal 1.17 #12;8 LBNL vs DOE Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3

  10. accident proneness: Topics by E-print Network

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

    accident proneness First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Accident proneness as an expression...

  11. accident analysis: Topics by E-print Network

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

    accident analysis First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Analysis of accidents during flashing...

  12. accident atuacao da: Topics by E-print Network

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

    accident atuacao da First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 DIRECTORY OF ESReDA ACCIDENT...

  13. accident lofa analysis: Topics by E-print Network

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

    accident lofa analysis First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 MELCOR ACCIDENT ANALYSIS FOR...

  14. Berkeley Lab Accident Statistics Through November 30, 2008

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through November 30, 2008 These slides are updated on a monthly Rates Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1

  15. accident precursor analysis: Topics by E-print Network

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

    accident precursor analysis First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Analysis of accidents...

  16. aircraft accident victims: Topics by E-print Network

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

    aircraft accident victims First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Cyclistes Victimes d'Accident...

  17. accident prone locations: Topics by E-print Network

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

    accident prone locations First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Accident proneness as an...

  18. Berkeley Lab Accident Statistics Through November 30, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through November 30, 2009 These slides are updated on a monthly Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1

  19. accident severity: Topics by E-print Network

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

    accident severity First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Accidents on the campus Severe...

  20. accident proneness prospect: Topics by E-print Network

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

    accident proneness prospect First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Accident proneness as an...

  1. accident consequences health: Topics by E-print Network

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

    accident consequences health First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 HEALTH AND ACCIDENT...

  2. Berkeley Lab Accident Statistics Through August 31, 2008

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through August 31, 2008 These slides are updated on a monthly 1.17 #12;7 LBNL vs DOE Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3

  3. Berkeley Lab Accident Statistics Through April 30, 2010

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through April 30, 2010 These slides are updated on a monthly Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1

  4. accident characteristics: Topics by E-print Network

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

    accident characteristics First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 guia accidents BSICA ...

  5. alternative accident sequences: Topics by E-print Network

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

    alternative accident sequences First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Beyond Normal Accidents...

  6. Berkeley Lab Accident Statistics Through May 31, 2010

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through May 31, 2010 These slides are updated on a monthly basis DOE Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2

  7. Berkeley Lab Accident Statistics Through June 30, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through June 30, 2009 These slides are updated on a monthly Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1

  8. Berkeley Lab Accident Statistics Through January 31, 2010

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through January 31, 2010 These slides are updated on a monthly Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28

  9. accident types: Topics by E-print Network

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

    accident types First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Risk Advisor for Car Accidents Javier...

  10. Berkeley Lab Accident Statistics Through October 31, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through October 31, 2009 These slides are updated on a monthly;8 LBNL vs DOE Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2

  11. accident compensation insurance: Topics by E-print Network

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

    accident compensation insurance First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Group Accident...

  12. Berkeley Lab Accident Statistics Through September 30, 2008

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through September 30, 2008 These slides are updated on a monthly.17 #12;7 LBNL vs DOE Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3

  13. accident situation study: Topics by E-print Network

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

    accident situation study First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Hypothetical Reactor Accident...

  14. accident exposure: Topics by E-print Network

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

    accident exposure First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Estimating Pedestrian Accident...

  15. Berkeley Lab Accident Statistics Through April 30, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through April 30, 2009 These slides are updated on a monthly Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2. 93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1

  16. accident sequence analyses: Topics by E-print Network

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

    accident sequence analyses First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Analysing Aviation Accidents...

  17. accident insurance: Topics by E-print Network

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

    accident insurance First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Group Accident Insurance Certificate...

  18. Berkeley Lab Accident Statistics Through December 31, 2010

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through December 31, 2010 These slides are updated on a monthly.17 #12;9 LBNL vs DOE Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3

  19. aircraft accident cases: Topics by E-print Network

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

    accident cases First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 HOW PAST LOSS OF CONTROL ACCIDENTS MAY...

  20. accident dosimetry systems: Topics by E-print Network

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

    accident dosimetry systems First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 A New Accident Model for...

  1. accident loca based: Topics by E-print Network

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

    accident loca based First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 A GIS based traffic accident data...

  2. Nuclear waste shipping container response to severe accident conditions, A brief critique of the modal study

    SciTech Connect (OSTI)

    Audin, L.

    1990-12-01T23:59:59.000Z

    The Modal Study (NUREG/CR-4829) attempts to upgrade the analysis of spent nuclear fuel transportation accidents, and to verify the validity of the present regulatory scheme of cask performance standards as a means to minimize risk. While an improvement over many prior efforts in this area (such as NUREG-0170), it unfortunately fails to create a realistic simulation either of a shipping cask, the severe conditions to which it could be subjected, or the potential damage to the spent fuel cargo during an accident. There are too many deficiencies in its analysis to allow acceptance of its results for the presumed cask design, and many pending changes in new containers, cargoes and shipping patterns will limit applicability of the Modal Study to future shipments. In essence, the Modal Study is a good start, but is too simplistic, incomplete, outdated and open to serious question to be used as the basis for any present-day environmental or risk assessment of spent fuel transportation. It needs to be redone, with peer review during its production and experimental verification of its assumptions, before it has any relevance to the shipments planned to Yucca Mountain. Finally, it must be expanded into a full risk assessment by inputing its radiological release fractions and probabilities into a valid dispersal simulation to properly determine the impact of its results. 51 refs.

  3. The Fuel Accident Condition Simulator (FACS) furnace system for high temperature performance testing of VHTR fuel

    SciTech Connect (OSTI)

    Paul A. Demkowicz; David V. Laug; Dawn M. Scates; Edward L. Reber; Lyle G. Roybal; John B. Walter; Jason M. Harp; Robert N. Morris

    2012-10-01T23:59:59.000Z

    The AGR-1 irradiation of TRISO-coated particle fuel specimens was recently completed and represents the most successful such irradiation in US history, reaching peak burnups of greater than 19% FIMA with zero failures out of 300,000 particles. An extensive post-irradiation examination (PIE) campaign will be conducted on the AGR-1 fuel in order to characterize the irradiated fuel properties, assess the in-pile fuel performance in terms of coating integrity and fission metals release, and determine the fission product retention behavior during high temperature safety testing. A new furnace system has been designed, built, and tested to perform high temperature accident tests. The Fuel Accident Condition Simulator furnace system is designed to heat fuel specimens at temperatures up to 2000 degrees C in helium while monitoring the release of volatile fission metals (e.g. Cs, Ag, Sr, and Eu), iodine, and fission gases (Kr, Xe). Fission gases released from the fuel to the sweep gas are monitored in real time using dual cryogenic traps fitted with high purity germanium detectors. Condensable fission products are collected on a plate attached to a water-cooled cold finger that can be exchanged periodically without interrupting the test. Analysis of fission products on the condensation plates involves dry gamma counting followed by chemical analysis of selected isotopes. This paper will describe design and operational details of the Fuel Accident Condition Simulator furnace system and the associated fission gas monitoring system, as well as preliminary system calibration results.

  4. Accident source terms for Light-Water Nuclear Power Plants. Final report

    SciTech Connect (OSTI)

    Soffer, L.; Burson, S.B.; Ferrell, C.M.; Lee, R.Y.; Ridgely, J.N.

    1995-02-01T23:59:59.000Z

    In 1962 tile US Atomic Energy Commission published TID-14844, ``Calculation of Distance Factors for Power and Test Reactors`` which specified a release of fission products from the core to the reactor containment for a postulated accident involving ``substantial meltdown of the core``. This ``source term``, tile basis for tile NRC`s Regulatory Guides 1.3 and 1.4, has been used to determine compliance with tile NRC`s reactor site criteria, 10 CFR Part 100, and to evaluate other important plant performance requirements. During the past 30 years substantial additional information on fission product releases has been developed based on significant severe accident research. This document utilizes this research by providing more realistic estimates of the ``source term`` release into containment, in terms of timing, nuclide types, quantities and chemical form, given a severe core-melt accident. This revised ``source term`` is to be applied to the design of future light water reactors (LWRs). Current LWR licensees may voluntarily propose applications based upon it.

  5. A Technique for Showing Causal Arguments in Accident Reports C. W. Johnson; University of Glasgow; Glasgow, Scotland, UK

    E-Print Network [OSTI]

    Johnson, Chris

    A Technique for Showing Causal Arguments in Accident Reports C. W. Johnson; University of Glasgow: causes, accidents, logic, argument, visualization, road traffic accidents Abstract In the prototypical accident report, specific findings, particularly those related to causes and contributing factors

  6. Simulation of a small break loss of coolant accident conducted at the BETHSY Integral Test Facility 

    E-Print Network [OSTI]

    Bott, Charles Patrick

    1992-01-01T23:59:59.000Z

    CHAPTER I INTRODUCTION I. l Need for Investigation The transfer of thermal energy from a, nuclear reactor core to electrical output from s, turbine involves the use of a, working fluid which will reliably remove the energy from the core. The cooling..., and extensive valving. An off normal event, such as a piping rupture or valve malfunction could cause a system trans&ent snd possibly lead to a reactor accident. To ensure the hot nuclear fuel is contained inside its cladding, the cladding must be prevented...

  7. Status of ANL out-of-pile investigations of severe accident phenomena for liquid metal reactors

    SciTech Connect (OSTI)

    Spencer, B.W.; Marchaterre, J.F.; Anderson, R.P.; Armstrong, D.R.; Baker, L.; Cho, D.H.; Gabor, J.D.; Pedersen, D.R.; Sienicki, J.J.; Stein, R.P.

    1986-01-01T23:59:59.000Z

    Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on quantifying reactivity feedbacks, and in particular enhancing negative feedback, so that advanced LMR designs will provide inherently safe operation. The status of recent HCDA-related laboratory research performed at ANL, up to the time that such activities were no longer needed to support CRBR licensing, is described. Included are descriptions of programs addressing sodium channel voiding, fuel sweepout, fuel dispersal and plugging, boiled-up pool, UO/sub 2//sodium FCI, and debris coolability. Descriptions of recent investigations involving the metal fuel/sodium system are also included.

  8. Involvement and Communication Committee.

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

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

  9. Overview of experimental support for fission-product transport analyses at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Wichner, R.P.

    1983-01-01T23:59:59.000Z

    The program was designed to determine fission product and aerosol release rates from irradiated fuel under accident conditions, to identify the chemical forms of the released material, and to correlate the results with experimental and specimen conditions with the data from related experiments. These tests of PWR fuel were conducted and fuel specimen and test operating data are presented. The nature and rate of fission product vapor interaction with aerosols were studied. Aerosol deposition rates and transport in the reactor vessel during LWR core-melt accidents were studied. The Nuclear Safety Pilot Plant is dedicated to developing an expanded data base on the behavior of aerosols generated during a severe accident.

  10. MELCOR accident analysis for ARIES-ACT

    SciTech Connect (OSTI)

    Paul W. Humrickhouse; Brad J. Merrill

    2012-08-01T23:59:59.000Z

    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.

  11. Accident Response Group | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    involving nuclear weapons. The ARG staff includes scientists, engineers, technicians, health physics and safety specialist from NNSA's and the Department of Energy's national...

  12. Angular dependence of a simple accident dosimeter

    SciTech Connect (OSTI)

    Devine, R. T. (Robert T.); Romero, L. L. (Leonard L.); Olsher, R. H. (Richard H.)

    2004-01-01T23:59:59.000Z

    A simple dosimeter made of a sulfur tablet, bare and cadmium covered indium foils and a cadmium covered copper foil has been modeled using MCNP5. Studies of the model without phantom or other confounding factors have shown that the cross sections and fluence-to-dose factors generated by the Monte Carlo method agree with those generated by analytic expressions for the high energy component. The threshold cross sections for the detectors on a phantom were calculated. The resulting doses assigned agree well with exposures made to three critical assemblies. In this study the angular dependence on a phantom is studied and compared with measurements taken on the GODIVA reactor. The dosimeter positions on the phantom are facing the source, on the back and the side. In previous papers the modeling of a simple dosimeter made of a sulfur tablet, bare and cadmium covered indium foils and a cadmium covered copper foil has been modeled using MCNP5. The conclusion made was that most of the neutron dose from criticality assemblies results from the high energy neutron fluences determined by the sulfur and indium detectors. The results using doses measured from the GODIVA, SHEBA, and bare and lead shielded SILENE reactors confirmed this. The angular dependence of an accident dosemeter is of interest in evaluating the exposure of personnel. To investigate this effect accident dosemeters were placed on a phantom and exposed to the GODIVA reactor at phantom orientations of 0{sup o}, 45{sup o}, 90{sup o}, 135{sup o}, and 180{sup o} to the assembly center line.

  13. Transportation Institutional Plan

    SciTech Connect (OSTI)

    Not Available

    1986-08-01T23:59:59.000Z

    This Institutional Plan is divided into three chapters. Chapter 1 provides background information, discusses the purposes of the Plan and the policy guidance for establishing the transportation system, and describes the projected system and the plans for its integrated development. Chapter 2 discusses the major participants who must interact to build the system. Chapter 3 suggests mechanisms for interaction that will foster wide participation in program planning and implementation and provides a framework for managing and resolving the issues related to development and operation of the transportation system. A list of acronyms and a glossary are included for the reader's convenience. Also included in this Plan are four appendices. Of particular importance is Appendix A, which includes detailed discussion of specific transportation issues. Appendices B, C, and D provide supporting material to assist the reader in understanding the roles of the involved institutions.

  14. Computational Transportation

    E-Print Network [OSTI]

    Illinois at Chicago, University of

    ), in-vehicle computers, and computers in the transportation infrastructure are integrated ride- sharing, real-time multi-modal routing and navigation, to autonomous/assisted driving

  15. Safety concept while managing radioactive waste formed as a result of decontamination measures at territories of Ukraine after Chernobyl power plant accident

    SciTech Connect (OSTI)

    Karamushka, V.P.; Chukhin, S.G.; Ostroborodov, V.V. [VNIPIPROMTECHNOLOGII, Moscow (Russian Federation)

    1993-12-31T23:59:59.000Z

    This article addresses the decision-making processes that are involved in the management of radioactive wastes that were created as a result of the Chernobyl reactor accident. The authors propose a systematic approach to reach this goal. Radiation safety must be provided in order to provide protection for man and the environment at the present time and in the future.

  16. Thermal testing of packages for transport of radioactive wastes

    SciTech Connect (OSTI)

    Koski, J.A.

    1994-12-31T23:59:59.000Z

    Shipping containers for radioactive materials must be shown capable of surviving tests specified by regulations such as Title 10, Code of Federal Regulations, Part 71 (called 10CFR71 in this paper) within the United States. Equivalent regulations hold for other countries such as Safety Series 6 issued by the International Atomic Energy Agency. The containers must be shown to be capable of surviving, in order, drop tests, puncture tests, and thermal tests. Immersion testing in water is also required, but must be demonstrated for undamaged packages. The thermal test is intended to simulate a 30 minute exposure to a fully engulfing pool fire that could occur if a transport accident involved the spill of large quantities of hydrocarbon fuels. Various qualification methods ranging from pure analysis to actual pool fire tests have been used to prove regulatory compliance. The purpose of this paper is to consider the alternatives for thermal testing, point out the strengths and weaknesses of each approach, and to provide the designer with the information necessary to make informed decisions on the proper test program for the particular shipping container under consideration. While thermal analysis is an alternative to physical testing, actual testing is often emphasized by regulators, and this report concentrates on these testing alternatives.

  17. Transfers and path choice in urban public transport systems

    E-Print Network [OSTI]

    Guo, Zhan, 1973-

    2008-01-01T23:59:59.000Z

    Transfers are endemic in public transport systems. Empirical evidence shows that a large portion of public transport journeys involve at least one change of vehicles, and that the transfer experience significantly affects ...

  18. Transportation Market Distortions

    E-Print Network [OSTI]

    Litman, Todd

    2006-01-01T23:59:59.000Z

    of Highways, Volpe National Transportation Systems Center (Evaluating Criticism of Transportation Costing, VictoriaFrom Here: Evaluating Transportation Diversity, Victoria

  19. The Accident at Fukushima: What Happened?

    SciTech Connect (OSTI)

    Fujie, Takao [Japan Nuclear Technology Institute - JANTI (Japan)

    2012-07-01T23:59:59.000Z

    At 2:46 PM, on the coast of the Pacific Ocean in eastern Japan, people were spending an ordinary afternoon. The earthquake had a magnitude of 9.0, the fourth largest ever recorded in the world. Avery large number of aftershocks were felt after the initial earthquake. More than 100 of them had a magnitude of over 6.0. There were very few injured or dead at this point. The large earthquake caused by this enormous crustal deformation spawned a rare and enormous tsunami that crashed down 30-40 minutes later. It easily cleared the high levees, washing away cars and houses and swallowing buildings of up to three stories in height. The largest tsunami reading taken from all regions was 40 meters in height. This tsunami reached the West Coast of the United States and the Pacific coast of South America, with wave heights of over two meters. It was due to this tsunami that the disaster became one of a not imaginable scale, which saw the number of dead or missing reach about 20,000 persons. The enormous tsunami headed for 15 nuclear power plants on the Pacific coast, but 11 power plants withstood the tsunami and attained cold shutdown. The flood height of the tsunami that struck each power station ranged to a maximum of 15 meters. The Fukushima Daiichi Nuclear Power Plant Units experienced the largest and the cores of three reactors suffered meltdown. As a result, more than 160,000 residents were forced to evacuate, and are still living in temporary accommodation. The main focus of this presentation is on what happened at the Fukushima Daiichi, and how station personnel responded to the accident, with considerable international support. A year after the Fukushima Daiichi accident, Japan is in the process of leveraging the lessons learned from the accident to further improve the safety of nuclear power facilities and regain the trust of society. In this connection, not only international organizations, including IAEA, and WANO, but also governmental organizations and nuclear industry representatives from various countries, have been evaluating what happened at Fukushima Daiichi. Support from many countries has contributed to successfully stabilizing the Fukushima Daiichi Nuclear Power Station. International cooperation is required as Japan started along the long road to decommissioning the reactors. Such cooperation with the international community would achieve the decommissioning of the damaged reactors. Finally, recovery plans by the Japanese government to decontaminate surrounding regions have been started in order to get residents back to their homes as early as possible. Looking at the world's nuclear power industry, there are currently approximately 440 reactors in operation and 60 under construction. Despite the dramatic consequences of the Fukushima Daiichi catastrophe it is expected that the importance of nuclear power generation will not change in the years to come. Newly accumulated knowledge and capabilities must be passed on to the next generation. This is the duty put upon us and which is one that we must embrace.

  20. Analysis of containment performance and radiological consequences under severe accident conditions for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Kim, S.H.; Taleyarkhan, R.P.

    1994-01-01T23:59:59.000Z

    A severe accident study was conducted to evaluate conservatively scoped source terms and radiological consequences to support the Advanced Neutron Source (ANS) Conceptual Safety Analysis Report (CSAR). Three different types of severe accident scenarios were postulated with a view of evaluating conservatively scoped source terms. The first scenario evaluates maximum possible steaming loads and associated radionuclide transport, whereas the next scenario is geared towards evaluating conservative containment loads from releases of radionuclide vapors and aerosols with associated generation of combustible gases. The third scenario follows the prescriptions given by the 10 CFR 100 guidelines. It was included in the CSAR for demonstrating site-suitability characteristics of the ANS. Various containment configurations are considered for the study of thermal-hydraulic and radiological behaviors of the ANS containment. Severe accident mitigative design features such as the use of rupture disks were accounted for. This report describes the postulated severe accident scenarios, methodology for analysis, modeling assumptions, modeling of several severe accident phenomena, and evaluation of the resulting source term and radiological consequences.

  1. MATADOR: a computer code for the analysis of radionuclide behavior during degraded core accidents in light water reactors

    SciTech Connect (OSTI)

    Baybutt, P.; Raghuram, S.; Avci, H.I.

    1985-04-01T23:59:59.000Z

    A new computer code called MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) has been developed to replace the CORRAL computer code which was written for the Reactor Safety Study (WASH-1400). This report contains a detailed description of the models used in MATADOR. MATADOR is intended for use in system risk studies to analyze radionuclide transport and deposition in reactor containments. The principal output of the code is information on the timing and magnitude of radionuclide releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containment and their removal by natural deposition and the operation of engineered safety systems such as sprays. The code requires input data on the source term from the primary system, the geometry of the containment, and the thermal-hydraulic conditions in the containment.

  2. Accident Investigation Report | Department of Energy

    Office of Environmental Management (EM)

    mine fire involving a salt haul truck occurred at DOE's WIPP near Carlsbad, New Mexico. The Board began the investigation on February 10, 2014, and the report is now final...

  3. Assessment of possible consequences of a hypothetical reactivity accident associated with a {open_quotes}Topaz-2{close_quotes} spacecraft reactor entering water

    SciTech Connect (OSTI)

    Glushkov, E.S.; Ermoshin, M.Yu.; Ponomarev-Stepnoi; Skorlygin, V.V.

    1994-12-01T23:59:59.000Z

    An accident analysis for a Russian Topaz-2 nuclear reactor is summarized. The accident scenario involves emergency return from orbit, severe damage to reactor structural elements, and subsequent falling of the reactor core into the ocean. The thermionic converter reactor, used in spacecraft, has a large neutron leakage which decreases when water enters the inner core cavity. Preliminary results of numerical modeling, summarized in the article, show that the possible consequences of the hypothetical accidental submersion are limited. 8 refs., 2 figs., 2 tabs.

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

    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...

  5. Analysing Aviation Accidents using WB-Analysis An Application for Multimodal Reasoning

    E-Print Network [OSTI]

    Moeller, Ralf

    Analysing Aviation Accidents using WB-Analysis An Application://www.rvs.uni-bielefeld.de We describe our ongoing work in accident analysis. Accident reports should tell* * us at least what the accident was and what the critical events were. A third requirement th* *ey should fulfil is to explain

  6. INTRODUCTION OF FREQUENCY IN FRANCE FOLLOWING THE AZF ACCIDENT Clment LENOBLE*

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    INTRODUCTION OF FREQUENCY IN FRANCE FOLLOWING THE AZF ACCIDENT Clément LENOBLE* , Clarisse DURAND** * INERIS, Accident risks division, Parc Technologique Alata BP2, F-60550 Verneuil-en-Halatte ** French been consecutive to industrial accidents. Two years after the industrial accident of AZF (French

  7. Monthly Theme OARS January 2009 Report an Accident / Incident / Near Miss

    E-Print Network [OSTI]

    Calgary, University of

    Monthly Theme ­ OARS ­ January 2009 Report an Accident / Incident / Near Miss Online Accident Reporting System (OARS) debuts January 2009 EH&S has a NEW online system to report any accident or incident that happens at the University. The web- based reporting system is called OARS -- Online Accident Reporting

  8. accident hydrologic analysis: Topics by E-print Network

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

    (SFHS) is a non information, contact: - Neil JohnsonMWH - Jayantha ObeysekeraSFWMD - Mike SukopFIU - Chris PetersCH2M HILL Sukop, Mike 291 HOW TO REPORT AN ACCIDENT,...

  9. Type B Accident Investigation Board Report on the Head Injury...

    Office of Environmental Management (EM)

    on the Head Injury to a Miner at the Waste Isolation Pilot Plant, Carlsbad, New Mexico - August 25, 2004 Type B Accident Investigation Board Report on the Head Injury to a Miner at...

  10. Type B Accident Investigation Of The February 25, 2009 Injury...

    Energy Savers [EERE]

    To A Passenger In An Electric Cart At The Waste Isolation Pilot Plant, Carlsbad, New Mexico Type B Accident Investigation Of The February 25, 2009 Injury To A Passenger In An...

  11. accident consequence code: Topics by E-print Network

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

    MACPISA-CANDU (more) Pohl, Daniel J. 2009-01-01 5 Validation of severe accident codes against Phebus FP for plant applications: status of the PHEBEN2 project CiteSeer...

  12. A STAMP model of the Überlingen aircraft collision accident

    E-Print Network [OSTI]

    Wong, Brian, 1982 Nov 11-

    2004-01-01T23:59:59.000Z

    STAMP is a method for evaluating accidents that is based on systems theory. It departs from traditional event chain models that tend to focus on human errors instead of the goals and motives that triggered the errors. The ...

  13. Modeling control room crews for accident sequence analysis

    E-Print Network [OSTI]

    Huang, Y. (Yuhao)

    1991-01-01T23:59:59.000Z

    This report describes a systems-based operating crew model designed to simulate the behavior of an nuclear power plant control room crew during an accident scenario. This model can lead to an improved treatment of potential ...

  14. accidents traffic: Topics by E-print Network

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

    specifically, three distinct studies (more) OShields, Lara Lynn 2007-01-01 2 Does Daylight Savings Time Affect Traffic Accidents? Texas A&M University - TxSpace Summary: This...

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

    Office of Environmental Management (EM)

    January 10, 2006, Flash Fire and Injury at the Savannah River National Laboratory Type B Accident Investigation of the January 10, 2006, Flash Fire and Injury at the Savannah River...

  16. Response of Soviet VVER-440 accident localization systems to overpressurization

    SciTech Connect (OSTI)

    Kulak, R.F.; Fiala, C.; Sienicki, J.J.

    1989-01-01T23:59:59.000Z

    The Soviet designed VVER-440 model V230 and VVER-440 model V213 reactors do not use full containments to mitigate the effects of accidents. Instead, these VVER-440 units employ a sealed set of interconnected compartments, collectively called the accident localization system (ALS), to reduce the release of radionuclides to the atmosphere during accidents. Descriptions of the VVER accident localization structures may be found in the report DOE NE-0084. The objective of this paper is to evaluate the structural integrity of the VVER-440 ALS at the Soviet design pressure, and to determine their response to pressure loadings beyond the design value. Complex, three-dimensional, nonlinear, finite element models were developed to represent the major structural components of the localization systems of the VVER-440 models V230 and V213. The interior boundary of the localization system was incrementally pressurized in the calculations until the prediction of gross failure. 6 refs., 9 figs.

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

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

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

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

    Office of Environmental Management (EM)

    Savannah River Site Hand Injury at the Salt Waste Processing Facility on October 6, 2009 Type B Accident Investigation Board Report of the Savannah River Site Hand Injury at the...

  19. Type B Accident Investigation of the Savannah River Site Arc...

    Energy Savers [EERE]

    H2 Demolition, in Niskayuna, New, York Type B Accident Investigation Board Report of the Savannah River Site Hand Injury at the Salt Waste Processing Facility on October 6, 2009...

  20. Failsafe : living with man-made disaster and accident

    E-Print Network [OSTI]

    Higgins, Saoirse, 1966-

    2004-01-01T23:59:59.000Z

    "There is no progress with out progress of the catastrophe." Virilio. This thesis project proposes that technological solutions in the design of our systems are not enough to prevent 'man-made' accident. Social, organisational ...

  1. accidents radiologiques sur: Topics by E-print Network

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

    SUR L'ORIGINE DES BRUITS DU COEUR ET DES ACCIDENTS DE DCOMPRESSION EN PLONGE : LA CAVITATION. Engineering Websites Summary: CAVITATION. HYPOTH?SE SUR L'ORIGINE DE LA FERMETURE...

  2. The 2011 Tohoku earthquake, tsunami, and Fukushima nuclear accident

    E-Print Network [OSTI]

    Ferrari, Silvia

    The 2011 Tohoku earthquake, tsunami, and Fukushima nuclear accident: the Risk Policy Aftermath 3 #12;Personal experience in March 2011 Tsukuba 170km Tokyo 230km Fukushima Daiichi nuclear power

  3. Type B Accident Investigation of the Acid Vapor Inhalation on...

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

    2005, in TA-48, Building RC-1 Room 402 at the Los Alamos National Laboratory Type B Accident Investigation of the Acid Vapor Inhalation on June 7, 2005, in TA-48, Building RC-1...

  4. accident locations: Topics by E-print Network

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

    17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Exact Location : Date of Accident : AM PM Environmental Sciences and Ecology Websites Summary: SSN Cell Phone Home...

  5. accidents dus aux: Topics by E-print Network

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

    qui taient en lgre hausse lanne dernire. De plus, il ny a eu aucun accident de trajet avec arrt en 2002. Pour le personnel LHC gnie civil, les rsultats...

  6. accident risks methodology: Topics by E-print Network

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

    13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Design Basis Accident Radiological Assessment Calculational Methodology CiteSeer Summary: submitted revised...

  7. Type B Accident Investigation Board Report on the September 1...

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

    September 1, 1999, Plutonium Intakes at the Savannah River Site FB-Line Type B Accident Investigation Board Report on the September 1, 1999, Plutonium Intakes at the Savannah River...

  8. accident phebus program: Topics by E-print Network

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

    Test FPT1 CiteSeer Summary: The contribution of radioiodine to risk from a severe accident is recognized to be one of the highest among all the fission products. In a long term...

  9. Some methods of estimating uncertainty in accident reconstruction

    E-Print Network [OSTI]

    Milan Batista

    2011-07-20T23:59:59.000Z

    In the paper four methods for estimating uncertainty in accident reconstruction are discussed: total differential method, extreme values method, Gauss statistical method, and Monte Carlo simulation method. The methods are described and the program solutions are given.

  10. accident dosimetry system: Topics by E-print Network

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

    11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 A New Accident Model for Engineering Safer Systems Nancy Leveson Engineering Websites Summary: A New...

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

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

    F-TRU Waste Remediation Facility at the Savannah River Site on June 14, 2010 Type B Accident Investigation Board Report Employee Puncture Wound at the F-TRU Waste Remediation...

  12. Iodine chemical forms in LWR severe accidents

    SciTech Connect (OSTI)

    Beahm, E.C.; Weber, C.F.; Kress, T.S.; Parker, G.W.

    1991-01-01T23:59:59.000Z

    Calculated data from seven severe accident sequences in light-water reactor plants were used to assess the chemical forms of iodine in containment. In most of the calculations for the seven sequences, iodine entering containment from the reactor coolant system was almost entirely in the form of CsI with very small contributions of I or HI. The largest fraction of iodine in forms other than CsI was a total of 3.2% as I plus HI. Within the containment, the CsI will deposit onto walls and other surfaces, as well as in water pools, largely in the form of iodide (I{sup {minus}}). The radiation induced conversion of I{sup {minus}} in water pools into I{sub 2} is strongly dependent on pH. In systems where the pH was controlled above 7, little additional elemental iodine would be produced in the containment atmosphere. When the pH falls below 7, it may be assumed that it is not being controlled, and large fractions of iodine as I{sub 2} within the containment atmosphere may be produced. 16 refs.

  13. Accounting for Co-benefits in Asia's Transportation Sector: Methods...

    Open Energy Info (EERE)

    has two objectives. The first is to examine methodological issues involved in using guidelines to measure co-benefits from transport projects (developing baselines,...

  14. Innovative approach to modeling accident response of Gravel Gerties

    SciTech Connect (OSTI)

    Kramer, M.; McClure, P.; Sullivan, H.

    1997-08-01T23:59:59.000Z

    Recent safety analyses at nuclear explosive facilities have renewed interest in the accident phenomenology associated with explosions in nuclear explosive cells, which are commonly referred to as {open_quotes}Gravel Gerties.{close_quotes} The cells are used for the assembly and disassembly of nuclear explosives and are located in the Device Assembly Facility (DAF) at the Nevada Test Site (NTS) and at the Pantex facility. The cells are designed to mitigate the release of special nuclear material to the environment in the event of a detonation of high explosive within the Gravel Gertie. Although there are some subtle differences between the cells of DAF and Pantex, their general design, geometry, and configuration are similar. The cells consist of a round room approximately 10.4 m in diameter and 5.2 m high enclosed by 0.3-m-thick concrete. Each cell has a wire-rope cantenary roof overlain with gravel. The gravel is approximately 6.9 m deep at the center of the roof and decreases toward the outer edge of the cell. The cell is connected to a corridor and subsequent rooms through an interlocking blast door. In the event of a accidental explosion involving significant amounts of high explosive, the roof structure is lifted by the force of the explosion, the supporting cables break, the gravel is lifted by the blast (resulting in rapid venting of the cell), and the gravel roof collapses, filling the cell. The lifting and subsequent collapse of the gravel, which acts much like a piston, is very challenging to model.

  15. Evaluation of accident frequencies at the canister storage building

    SciTech Connect (OSTI)

    LIU, Y.J.

    1999-05-13T23:59:59.000Z

    By using the fault tree logic, an evaluation of the design basis accident frequencies at the Canister Storage Building has been performed. The evaluation demonstrates that due to low frequency of occurrences, the following design basis accidents are considered not credible (annual frequency of less than 10{sup -6}): Rearrangement of multi-canister overpack (MCO) internals; Gaseous release from the MCO; MCO internal hydrogen explosion; MCO external hydrogen explosion; Thermal runaway reactions inside the MCO; and Violation of design temperature criteria.

  16. Trees as Filters of Radioactive Fallout from the Chernobyl Accident

    E-Print Network [OSTI]

    Brownridge, James D

    2011-01-01T23:59:59.000Z

    This paper is a copy of an unpublished study of the filtering effect of red maple trees (acer rubrum) on fission product fallout near Binghamton, NY, USA following the 1986 Chernobyl accident. The conclusions of this work may offer some insight into what is happening in the forests exposed to fallout from the Fukushima Daiichi Nuclear Plant accident. This posting is in memory of Noel K. Yeh.

  17. Berkeley Lab Accident Statistics Through July 31, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through July 31, 2009 These slides are updated on a monthly Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1.92 3.90 3.41 2.65 2

  18. Berkeley Lab Accident Statistics Through September 30, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through September 30, 2009 These slides are updated on a monthly Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1.92 3.90 3.41 2.65 2

  19. Berkeley Lab Accident Statistics Through May 31, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through May 31, 2009 These slides are updated on a monthly basis Berkeley Lab Site Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1

  20. Berkeley Lab Accident Statistics Through October 31, 2008

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through October 31, 2008 These slides are updated on a monthly Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1.72 0.40 3.90 3.41 2

  1. Berkeley Lab Accident Statistics Through August 31, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through August 31, 2009 These slides are updated on a monthly Accident Rates 5.70 4.95 3.79 2.92 2.93 3.27 3.63 2.44 2.17 2.51 1.17 1.81 1.28 1.65 1.92 3.90 3.41 2.65 2

  2. electrifyingthefuture transportation

    E-Print Network [OSTI]

    Birmingham, University of

    electrifyingthefuture transportation The UK Government's carbon reduction strategy vehicles and the new Birmingham Science City Energy Systems Integration Laboratory (ESIL) will further enhance this work. The laboratory - unique within the UK and world leading - brings together cutting edge

  3. 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).

  4. Civil aircraft accident Report on the Accident to Boeing 707-465 G-Arwe at Heathrow Airport, London on 8th April 1968 

    E-Print Network [OSTI]

    Anonymous

    1969-01-01T23:59:59.000Z

    A3.C.A.P. 324 Civil aircraft accident Report on the Accident to Boeing 707-465 G-Arwe at Heathrow Airport, London on 8th April 1968...

  5. Alcohol, Drugs, and Accident Prevention (RC-371/-571) Course Description The role of alcohol and drugs and their relationship to accident causation will be examined. The problem

    E-Print Network [OSTI]

    Wu, Mingshen

    Alcohol, Drugs, and Accident Prevention (RC-371/-571) Course Description The role of alcohol and drugs and their relationship to accident causation will be examined. The problem of alcoholism and drug

  6. Multiscale thermal transport.

    SciTech Connect (OSTI)

    Graham, Samuel Jr. (; .); Wong, C. C.; Piekos, Edward Stanley

    2004-02-01T23:59:59.000Z

    A concurrent computational and experimental investigation of thermal transport is performed with the goal of improving understanding of, and predictive capability for, thermal transport in microdevices. The computational component involves Monte Carlo simulation of phonon transport. In these simulations, all acoustic modes are included and their properties are drawn from a realistic dispersion relation. Phonon-phonon and phonon-boundary scattering events are treated independently. A new set of phonon-phonon scattering coefficients are proposed that reflect the elimination of assumptions present in earlier analytical work from the simulation. The experimental component involves steady-state measurement of thermal conductivity on silicon films as thin as 340nm at a range of temperatures. Agreement between the experiment and simulation on single-crystal silicon thin films is excellent, Agreement for polycrystalline films is promising, but significant work remains to be done before predictions can be made confidently. Knowledge gained from these efforts was used to construct improved semiclassical models with the goal of representing microscale effects in existing macroscale codes in a computationally efficient manner.

  7. NORMES D'ACTUACI EN CAS D'ACCIDENT 1. Els accidents hauran de justificar-se mitjanant la corresponent comunicaci

    E-Print Network [OSTI]

    Geffner, Hector

    NORMES D'ACTUACI� EN CAS D'ACCIDENT 1. Els accidents hauran de justificar-se mitjançant la corresponent comunicació d'accident que haurà d'emplenar el club, entitat esportiva o empresa prenedora a la als serveis mèdics concertats és necessari aportar la comunicació d'accident certificada i identificar

  8. Molecular Mechanism of Biological Proton Transport

    SciTech Connect (OSTI)

    Pomes, R.

    1998-09-01T23:59:59.000Z

    Proton transport across lipid membranes is a fundamental aspect of biological energy transduction (metabolism). This function is mediated by a Grotthuss mechanism involving proton hopping along hydrogen-bonded networks embedded in membrane-spanning proteins. Using molecular simulations, the authors have explored the structural, dynamic, and thermodynamic properties giving rise to long-range proton translocation in hydrogen-bonded networks involving water molecules, or water wires, which are emerging as ubiquitous H{sup +}-transport devices in biological systems.

  9. VICTORIA: A mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions. Revision 1

    SciTech Connect (OSTI)

    Heams, T J [Science Applications International Corp., Albuquerque, NM (United States); Williams, D A; Johns, N A; Mason, A [UKAEA, Winfrith, (England); Bixler, N E; Grimley, A J [Sandia National Labs., Albuquerque, NM (United States); Wheatley, C J [UKAEA, Culcheth (England); Dickson, L W [Atomic Energy of Canada Ltd., Chalk River, ON (Canada); Osborn-Lee, I [Oak Ridge National Lab., TN (United States); Domagala, P; Zawadzki, S; Rest, J [Argonne National Lab., IL (United States); Alexander, C A [Battelle, Columbus, OH (United States); Lee, R Y [Nuclear Regulatory Commission, Washington, DC (United States)

    1992-12-01T23:59:59.000Z

    The VICTORIA model of radionuclide behavior in the reactor coolant system (RCS) of a light water reactor during a severe accident is described. It has been developed by the USNRC to define the radionuclide phenomena and processes that must be considered in systems-level models used for integrated analyses of severe accident source terms. The VICTORIA code, based upon this model, predicts fission product release from the fuel, chemical reactions involving fission products, vapor and aerosol behavior, and fission product decay heating. Also included is a detailed description of how the model is implemented in VICTORIA, the numerical algorithms used, and the correlations and thermochemical data necessary for determining a solution. A description of the code structure, input and output, and a sample problem are provided.

  10. Human factors review for Severe Accident Sequence Analysis (SASA)

    SciTech Connect (OSTI)

    Krois, P.A.; Haas, P.M.; Manning, J.J.; Bovell, C.R.

    1984-01-01T23:59:59.000Z

    The paper will discuss work being conducted during this human factors review including: (1) support of the Severe Accident Sequence Analysis (SASA) Program based on an assessment of operator actions, and (2) development of a descriptive model of operator severe accident management. Research by SASA analysts on the Browns Ferry Unit One (BF1) anticipated transient without scram (ATWS) was supported through a concurrent assessment of operator performance to demonstrate contributions to SASA analyses from human factors data and methods. A descriptive model was developed called the Function Oriented Accident Management (FOAM) model, which serves as a structure for bridging human factors, operations, and engineering expertise and which is useful for identifying needs/deficiencies in the area of accident management. The assessment of human factors issues related to ATWS required extensive coordination with SASA analysts. The analysis was consolidated primarily to six operator actions identified in the Emergency Procedure Guidelines (EPGs) as being the most critical to the accident sequence. These actions were assessed through simulator exercises, qualitative reviews, and quantitative human reliability analyses. The FOAM descriptive model assumes as a starting point that multiple operator/system failures exceed the scope of procedures and necessitates a knowledge-based emergency response by the operators. The FOAM model provides a functionally-oriented structure for assembling human factors, operations, and engineering data and expertise into operator guidance for unconventional emergency responses to mitigate severe accident progression and avoid/minimize core degradation. Operators must also respond to potential radiological release beyond plant protective barriers. Research needs in accident management and potential uses of the FOAM model are described. 11 references, 1 figure.

  11. LOSS OF COOLANT ACCIDENT AND LOSS OF FLOW ACCIDENT ANALYSIS OF THE ARIES-AT DESIGN E. A. Mogahed, L. El-Guebaly, A. Abdou, P. Wilson, D. Henderson and the ARIES Team

    E-Print Network [OSTI]

    California at San Diego, University of

    LOSS OF COOLANT ACCIDENT AND LOSS OF FLOW ACCIDENT ANALYSIS OF THE ARIES-AT DESIGN E. A. Mogahed, L accident (LOCA) and loss of flow accident (LOFA) analysis is performed for ARIES-AT, an advanced fusion of steel in the reactor is about (600 °C - 700°C) after about 4 days from the onset of the accident

  12. Preliminary Design Report for Modeling of Hydrogen Uptake in Fuel Rod Cladding During Severe Accidents

    SciTech Connect (OSTI)

    Siefken, Larry James

    1999-02-01T23:59:59.000Z

    Preliminary designs are described for models of hydrogen and oxygen uptake in fuel rod cladding during severe accidents. Calculation of the uptake involves the modeling of seven processes: (1) diffusion of oxygen from the bulk gas into the boundary layer at the external cladding surface, (2) diffusion from the boundary layer into the oxide layer, (3) diffusion from the inner surface of the oxide layer into the metallic part of the cladding, (4) uptake of hydrogen in the event that the clad-ding oxide layer is dissolved in a steam-starved region, (5) embrittlement of cladding due to hydrogen uptake, (6) cracking of cladding during quenching due to its embrittlement and (7) release of hydrogen from the cladding after cracking of the cladding. An integral diffusion method is described for calculating the diffusion processes in the cladding. Experimental results are presented that show a rapid uptake of hydrogen in the event of dissolution of the oxide layer and a rapid release of hydrogen in the event of cracking of the oxide layer. These experimental results are used as a basis for calculating the rate of hydrogen uptake and the rate of hydrogen release. The uptake of hydrogen is limited to the equilibrium solubility calculated by applying Sievert's law. The uptake of hydrogen is an exothermic reaction that accelerates the heatup of a fuel rod. An embrittlement criteria is described that accounts for hydrogen and oxygen concentration and the extent of oxidation. A design is described for implementing the models for hydrogen and oxygen uptake and cladding embrittlement into the programming framework of the SCDAP/RELAP5 code. A test matrix is described for assessing the impact of the proposed models on the calculated behavior of fuel rods in severe accident conditions. This report is a revision and reissue of the report entitled; "Preliminary Design Report for Modeling of Hydrogen Uptake in Fuel Rod Cladding During Severe Accidents."

  13. Cognitive Radio will revolutionize American transportation

    ScienceCinema (OSTI)

    None

    2013-12-06T23:59:59.000Z

    Cognitive Radio will revolutionize American transportation. Through smart technology, it will anticipate user needs; detect available bandwidths and frequencies then seamlessly connect vehicles, infrastructures, and consumer devices; and it will support the Department of Transportation IntelliDrive Program, helping researchers, auto manufacturers, and Federal and State officials advance the connectivity of US transportation systems for improved safety, mobility, and environmental conditions. Using cognitive radio, a commercial vehicle will know its driver, onboard freight and destination route. Drivers will save time and resources communicating with automatic toll booths and know ahead of time whether to stop at a weigh station or keep rolling. At accident scenes, cognitive radio sensors on freight and transportation modes can alert emergency personnel and measure on-site, real-time conditions such as a chemical leak. The sensors will connect freight to industry, relaying shipment conditions and new delivery schedules. For industry or military purposes, cognitive radio will enable real-time freight tracking around the globe and its sensory technology can help prevent cargo theft or tampering by alerting shipper and receiver if freight is tampered with while en route. For the average consumer, a vehicle will tailor the transportation experience to the passenger such as delivering age-appropriate movies via satellite. Cognitive radio will enhance transportation safety by continually sensing what is important to the user adapting to its environment and incoming information, and proposing solutions that improve mobility and quality of life.

  14. Cognitive Radio will revolutionize American transportation

    SciTech Connect (OSTI)

    None

    2013-07-22T23:59:59.000Z

    Cognitive Radio will revolutionize American transportation. Through smart technology, it will anticipate user needs; detect available bandwidths and frequencies then seamlessly connect vehicles, infrastructures, and consumer devices; and it will support the Department of Transportation IntelliDrive Program, helping researchers, auto manufacturers, and Federal and State officials advance the connectivity of US transportation systems for improved safety, mobility, and environmental conditions. Using cognitive radio, a commercial vehicle will know its driver, onboard freight and destination route. Drivers will save time and resources communicating with automatic toll booths and know ahead of time whether to stop at a weigh station or keep rolling. At accident scenes, cognitive radio sensors on freight and transportation modes can alert emergency personnel and measure on-site, real-time conditions such as a chemical leak. The sensors will connect freight to industry, relaying shipment conditions and new delivery schedules. For industry or military purposes, cognitive radio will enable real-time freight tracking around the globe and its sensory technology can help prevent cargo theft or tampering by alerting shipper and receiver if freight is tampered with while en route. For the average consumer, a vehicle will tailor the transportation experience to the passenger such as delivering age-appropriate movies via satellite. Cognitive radio will enhance transportation safety by continually sensing what is important to the user adapting to its environment and incoming information, and proposing solutions that improve mobility and quality of life.

  15. Transportation needs assessment: Emergency response section

    SciTech Connect (OSTI)

    NONE

    1989-05-01T23:59:59.000Z

    The transportation impacts of moving high level nuclear waste (HLNW) to a repository at Yucca Mountain in Nevada are of concern to the residents of the State as well as to the residents of other states through which the nuclear wastes might be transported. The projected volume of the waste suggests that shipments will occur on a daily basis for some period of time. This will increase the risk of accidents, including a catastrophic incident. Furthermore, as the likelihood of repository construction and operation and waste shipments increase, so will the attention given by the national media. This document is not to be construed as a willingness to accept the HLNW repository on the part of the State. Rather it is an initial step in ensuring that the safety and well-being of Nevada residents and visitors and the State`s economy will be adequately addressed in federal decision-making pertaining to the transportation of HLNW into and across Nevada for disposal in the proposed repository. The Preferred Transportation System Needs Assessment identifies critical system design elements and technical and social issues that must be considered in conducting a comprehensive transportation impact analysis. Development of the needs assessment and the impact analysis is especially complex because of the absence of information and experience with shipping HLNW and because of the ``low probability, high consequence`` aspect of the transportation risk.

  16. Methods for air cleaning system design and accident analysis

    SciTech Connect (OSTI)

    Gregory, W.S.; Nichols, B.D.

    1986-01-01T23:59:59.000Z

    This paper describes methods, in the form of a handbook and five computer codes, that can be used for air cleaning system design and accident analysis. Four of the codes were developed primarily at the Los Alamos National Laboratory, and one was developed in France. Tools such as these are used to design ventilation systems in the mining industry but do not seem to be commonly used in the nuclear industry. For example, the Nuclear Air Cleaning Handbook is an excellent design reference, but it fails to include information on computer codes that can be used to aid in the design process. These computer codes allow the analyst to use the handbook information to form all the elements of a complete system design. Because these analysis methods are in the form of computer codes, they allow the analyst to investigate many alternative designs. In addition, the effects of many accident scenarios on the operation of the air cleaning system can be evaluated. These tools originally were intended for accident analysis, but they have been used mostly as design tools by several architect-engineering firms. The Cray, VAX, and personal computer versions of the codes, an accident analysis handbook, and the codes' availability will be discussed. The application of these codes to several design operations of nuclear facilities will be illustrated, and their use to analyze the effect of several accident scenarios also will be described.

  17. PNNL Results from 2010 CALIBAN Criticality Accident Dosimeter Intercomparison Exercise

    SciTech Connect (OSTI)

    Hill, Robin L.; Conrady, Matthew M.

    2011-10-28T23:59:59.000Z

    This document reports the results of the Hanford personnel nuclear accident dosimeter (PNAD) and fixed nuclear accident dosimeter (FNAD) during a criticality accident dosimeter intercomparison exercise at the CEA Valduc Center on September 20-23, 2010. Pacific Northwest National Laboratory (PNNL) participated in a criticality accident dosimeter intercomparison exercise at the Commissariat a Energie Atomique (CEA) Valduc Center near Dijon, France on September 20-23, 2010. The intercomparison exercise was funded by the U.S. Department of Energy, Nuclear Criticality Safety Program, with Lawrence Livermore National Laboratory as the lead Laboratory. PNNL was one of six invited DOE Laboratory participants. The other participating Laboratories were: Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Savannah River Site (SRS), the Y-12 National Security Complex at Oak Ridge, and Sandia National Laboratory (SNL). The goals of PNNL's participation in the intercomparison exercise were to test and validate the procedures and algorithm currently used for the Hanford personnel nuclear accident dosimeters (PNADs) on the metallic reactor, CALIBAN, to test exposures to PNADs from the side and from behind a phantom, and to test PNADs that were taken from a historical batch of Hanford PNADs that had varying degrees of degradation of the bare indium foil. Similar testing of the PNADs was done on the Valduc SILENE test reactor in 2009 (Hill and Conrady, 2010). The CALIBAN results are reported here.

  18. Accident Sequence Evaluation Program: Human reliability analysis procedure

    SciTech Connect (OSTI)

    Swain, A.D.

    1987-02-01T23:59:59.000Z

    This document presents a shortened version of the procedure, models, and data for human reliability analysis (HRA) which are presented in the Handbook of Human Reliability Analysis With emphasis on Nuclear Power Plant Applications (NUREG/CR-1278, August 1983). This shortened version was prepared and tried out as part of the Accident Sequence Evaluation Program (ASEP) funded by the US Nuclear Regulatory Commission and managed by Sandia National Laboratories. The intent of this new HRA procedure, called the ''ASEP HRA Procedure,'' is to enable systems analysts, with minimal support from experts in human reliability analysis, to make estimates of human error probabilities and other human performance characteristics which are sufficiently accurate for many probabilistic risk assessments. The ASEP HRA Procedure consists of a Pre-Accident Screening HRA, a Pre-Accident Nominal HRA, a Post-Accident Screening HRA, and a Post-Accident Nominal HRA. The procedure in this document includes changes made after tryout and evaluation of the procedure in four nuclear power plants by four different systems analysts and related personnel, including human reliability specialists. The changes consist of some additional explanatory material (including examples), and more detailed definitions of some of the terms. 42 refs.

  19. Radiological Impact Assessment (RIA) following a postulated accident in PHWRS

    SciTech Connect (OSTI)

    Soni, N.; Kansal, M.; Rammohan, H. P.; Malhotra, P. K. [Reactor Safety and Analysis, Nuclear Power Corporation of India Ltd., Nabhkiya Urja Bhavan, Anushakti Nagar, Mumbai Maharashtra 400094 (India)

    2012-07-01T23:59:59.000Z

    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)

  20. A Transportation Risk Assessment Tool for Analyzing the Transport of Spent Nuclear Fuel and High-Level Radioactive Waste to the Proposed Yucca Mountain Repository

    SciTech Connect (OSTI)

    Ralph Best; T. Winnard; S. Ross; R. Best

    2001-08-17T23:59:59.000Z

    The Yucca Mountain Transportation Database was developed as a data management tool for assembling and integrating data from multiple sources to compile the potential transportation impacts presented in the Draft 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 (DEIS). The database uses the results from existing models and codes such as RADTRAN, RISKIND, INTERLINE, and HIGHWAY to estimate transportation-related impacts of transporting spent nuclear fuel and high-level radioactive waste from commercial reactors and U. S. Department of Energy (DOE) facilities to Yucca Mountain. The source tables in the database are compendiums of information from many diverse sources including: radionuclide quantities for each waste type; route and route characteristics for rail, legal-weight truck, heavy haul. truck, and barge transport options; state-specific accident and fatality rates for routes selected for analysis; packaging and shipment data by waste type; unit risk factors; the complex behavior of the packaged waste forms in severe transport accidents; and the effects of exposure to radiation or the isotopic specific effects of radionclides should they be released in severe transportation accidents. The database works together with the codes RADTRAN (Neuhauser, et al, 1994) and RISKlND (Yuan, et al, 1995) to calculate incident-free dose and accident risk. For the incident-free transportation scenario, the database uses RADTRAN and RISKIND-generated data to calculate doses to offlink populations, onlink populations, people at stops, crews, inspectors, workers at intermodal transfer stations, guards at overnight stops, and escorts, as well as non-radioactive pollution health effects. For accident scenarios, the database uses RADTRAN-generated data to calculate dose risks based on ingestion, inhalation, resuspension, immersion (cloudshine), and groundshine as well as non-radioactive traffic fatalities. The Yucca Mountain EIS Transportation Database was developed using Microsoft Access 97{trademark} software and the Microsoft Windows NT{trademark} operating system. The database consists of tables for storing data, forms for selecting data for querying, and queries for retrieving the data in a predefined format. Database queries retrieve records based on input parameters and are used to calculate incident-free and accident doses using unit risk factors obtained from RADTRAN results. The next section briefly provides some background that led to the development of the database approach used in preparing the Yucca Mountain DEIS. Subsequent sections provide additional details on the database structure and types of impacts calculated using the database.

  1. Compendium of the Environmental Measurements Laboratory's research projects related to the Chernobyl nuclear accident

    SciTech Connect (OSTI)

    Volchok, H L; Chieco, N [comps.

    1986-10-01T23:59:59.000Z

    Following the accident at the Chernobyl nuclear reactor power station in the USSR on April 26, 1986, the Environmental Measurements Laboratory (EML) initiated a number of research projects as follows: (1) selected sites in both the Deposition and Surface Air networks were alerted and their sampling protocols adjusted to accommodate the anticipated arrival times and activity concentrations of the Chernobyl debris; (2) a number of cooperative programs involving field work, sampling, analysis and data interpretation were set up with institutions and scientists in other countries; (3) EML's Regional Baseline Station at Chester, NJ, as well as the roof of the Laboratory in New York City, provided bases for sampling and measurements to study the radionuclide concentrations, radiation levels, physical characteristics and potential biological implications of the Chernobyl fallout on the northeastern United States; and (4) the resulting fallout from the Chernobyl accident provided an 'experiment of opportunity' in that it enabled us to study fresh fission product deposition using collection systems resurrected from the 1950's and 1960's for comparison with current state-of-the-art methodology. The 13 reports of this volume have been entered separately into the data base.

  2. FSAR fire accident analysis for a plutonium facility

    SciTech Connect (OSTI)

    Lam, K.

    1997-06-01T23:59:59.000Z

    The Final Safety Analysis Report (FSAR) for a plutonium facility as required by DOE Orders 5480.23 and 5480.22 has recently been completed and approved. The facility processes and stores radionuclides such as Pu-238, Pu-239, enriched uranium, and to a lesser degree other actinides. This facility produces heat sources. DOE Order 5480.23 and DOE-STD-3009-94 require analysis of different types of accidents (operational accidents such as fires, explosions, spills, criticality events, and natural phenomena such as earthquakes). The accidents that were analyzed quantitatively, or the Evaluation Basis Accidents (EBAs), were selected based on a multi-step screening process that utilizes extensively the Hazards Analysis (HA) performed for the facility. In the HA, specific accident scenarios, with estimated frequency and consequences, were developed for each identified hazard associated with facility operations and activities. Analysis of the EBAs and comparison of their consequences to the evaluation guidelines established the safety envelope for the facility and identified the safety-class structures, systems, and components. This paper discusses the analysis of the fire EBA. This fire accident was analyzed in relatively great detail in the FSAR because of its potential off-site consequences are more severe compared to other events. In the following, a description of the scenario is first given, followed by a brief summary of the methodology for calculating the source term. Finally, the author discuss how a key parameter affecting the source term, the leakpath factor, was determined, which is the focus of this paper.

  3. Transportation and its Infrastructure

    E-Print Network [OSTI]

    2007-01-01T23:59:59.000Z

    40 pp. IEA, 2004c: Biofuels for Transport: An Internationalthe ACT Map scenario, transport biofuels production reachesestimates that biofuels’ share of transport fuel could

  4. Effect of shape reactivity on the rod-ejection accident

    SciTech Connect (OSTI)

    Neogy, P.; Carew, J.F.

    1982-09-01T23:59:59.000Z

    The shape reactivity has a significant influence on the rod ejection accident. After the control rod is fully ejected from the core, the neutron flux undergoes a large reduction at the ejected rod location. The corresponding effect on the control reactivity is comparable in magnitude to the Doppler reactivity, and makes a significant contribution to limiting the power excursion during the transient. The neglect of this effect in point kinetics and space time synthesis analyses of the rod ejection accident may account in part for the large degree of conservatism usually associated with these analyses.

  5. Radionuclide-inventory impacts on reactor-accident consequences

    SciTech Connect (OSTI)

    Ostmeyer, R.M.

    1981-01-01T23:59:59.000Z

    To examine the potential impacts of the different radionuclide inventories on predicted accident consequences, and the appropriateness of inventory scaling, a series of calculations was performed using CRAC2, a modified version of the WASH-1400 consequence model. Consequences were calculated assuming (1) an SST-1 accident (large scale core melt with uncontrolled release directly to the atmosphere), (2) Indian Point population and wind-rose data, (3) New York City weather data, and (4) a distribution of evacuations within 16 km of the reactor.

  6. Reactor accident consequence analysis code (MACCS)

    SciTech Connect (OSTI)

    Jow, Hong-Nian; Sprung, J.L.; Chanin, D.I.; Helton, J.C.; Rollstin, J.A. (Sandia National Labs., Albuquerque, NM (USA); Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA); Arizona State Univ., Tempe, AZ (USA); GRAM, Inc., Albuquerque, NM (USA))

    1990-01-01T23:59:59.000Z

    Sandia National Laboratories has been involved in the performance of risk assessments for the US Nuclear Regulatory Commission for more than a decade. As part of this effort, Sandia developed the reactor consequence analysis codes, CRAC2, and more recently, MACCS. CRAC2 is an improved version of CRAC, which was used in the Reactor Safety Study (also known as WASH-1400). MACCS was used in recent risk assessments for five nuclear power plants (NUREG-1150). MACCS incorporates many model improvements over CRAC2. Some of these improvements are discussed. A comparison of results obtained with CRAC2 and MACCS is also presented. 19 refs., 3 tabs.

  7. Testing of a Transport Cask for Research Reactor Spent Fuel - 13003

    SciTech Connect (OSTI)

    Mourao, Rogerio P.; Leite da Silva, Luiz [Centro de Desenvolvimento da Tecnologia Nuclear, Belo Horizonte (Brazil)] [Centro de Desenvolvimento da Tecnologia Nuclear, Belo Horizonte (Brazil); Miranda, Carlos A.; Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil)] [Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil); Quintana, Jose F.A.; Saliba, Roberto O. [Comision Nacional de Energia Atomica, Bariloche (Argentina)] [Comision Nacional de Energia Atomica, Bariloche (Argentina); Novara, Oscar E. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)] [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    2013-07-01T23:59:59.000Z

    Since the beginning of the last decade three Latin American countries that operate research reactors - Argentina, Brazil and Chile - have been joining efforts to improve the regional capability in the management of spent fuel elements from the TRIGA and MTR reactors operated in the region. A main drive in this initiative, sponsored by the International Atomic Energy Agency, is the fact that no definite solution regarding the back end of the research reactor fuel cycle has been taken by any of the participating country. However, any long-term solution - either disposition in a repository or storage away from reactor - will involve at some stage the transportation of the spent fuel through public roads. Therefore, a licensed cask that provides adequate shielding, assurance of subcriticality, and conformance to internationally accepted safety, security and safeguards regimes is considered a strategic part of any future solution to be adopted at a regional level. As a step in this direction, a packaging for the transport of irradiated fuel for MTR and TRIGA research reactors was designed by the tri-national team and a half-scale model equipped with the MTR version of the internal basket was constructed in Argentina and Brazil and tested in Brazil. Three test campaigns have been carried out so far, covering both normal conditions of transportation and hypothetical accident conditions. After failing the tests in the first two test series, the specimen successfully underwent the last test sequence. A second specimen, incorporating the structural improvements in view of the previous tests results, will be tested in the near future. Numerical simulations of the free drop and thermal tests are being carried out in parallel, in order to validate the computational modeling that is going to be used as a support for the package certification. (authors)

  8. Severity of injuries in different modes of transport, expressed with disability-adjusted life years (DALYs)

    E-Print Network [OSTI]

    Tainio, Marko; Olkowicz, Dorota; Teresi?ski, Grzegorz; de Nazelle, Audrey; Nieuwenhuijsen, Mark J.

    2014-07-11T23:59:59.000Z

    ; STRADA: Swedish traffic accident data acquisition; YLD: Years lost due to disability; YLL: Years of life lost. Warsaw. TAPAS is a four year project (partly) funded by the Coca-Cola greenhouse-gas emissions: urban land transport. Lancet 2009, Mendez M...

  9. Public involvement in radioactive waste management decisions

    SciTech Connect (OSTI)

    NONE

    1994-04-01T23:59:59.000Z

    Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

  10. Dynamic modeling of physical phenomena for probabilistic assessment of spent fuel accidents

    SciTech Connect (OSTI)

    Benjamin, A.S.

    1997-11-01T23:59:59.000Z

    If there should be an accident involving drainage of all the water from a spent fuel pool, the fuel elements will heat up until the heat produced by radioactive decay is balanced by that removed by natural convection to air, thermal radiation, and other means. If the temperatures become high enough for the cladding or other materials to ignite due to rapid oxidation, then some of the fuel might melt, leading to an undesirable release of radioactive materials. The amount of melting is dependent upon the fuel loading configuration and its age, the oxidation and melting characteristics of the materials, and the potential effectiveness of recovery actions. The authors have developed methods for modeling the pertinent physical phenomena and integrating the results with a probabilistic treatment of the uncertainty distributions. The net result is a set of complementary cumulative distribution functions for the amount of fuel melted.

  11. Analysis of risk reduction methods for interfacing system LOCAs (loss-of-coolant accidents) at PWRs

    SciTech Connect (OSTI)

    Bozoki, G.; Kohut, P.; Fitzpatrick, R.

    1988-01-01T23:59:59.000Z

    The Reactor Safety Study (WASH-1400) predicted that Interfacing System Loss-of-Coolant Accidents (ISL) events were significant contributors to risk even though they were calculated to be relatively low frequency events. However, there are substantial uncertainties involved in determining the probability and consequences of the ISL sequences. For example, the assumed valve failure modes, common cause contributions and the location of the break/leak are all uncertain and can significantly influence the predicted risk from ISL events. In order to provide more realistic estimates for the core damage frequencies (CDFs) and a reduction in the magnitude of the uncertainties, a reexamination of ISL scenarios at PWRs has been performed by Brookhaven National Laboratory. The objective of this study was to investigate the vulnerability of pressurized water reactor designs to ISLs and identify any improvements that could significantly reduce the frequency/risk of these events.

  12. Analysis of station blackout accidents for the Bellefonte pressurized water reactor

    SciTech Connect (OSTI)

    Gasser, R D; Bieniarz, P P; Tills, J L

    1986-09-01T23:59:59.000Z

    An analysis has been performed for the Bellefonte PWR Unit 1 to determine the containment loading and the radiological releases into the environment from a station blackout accident. A number of issues have been addressed in this analysis which include the effects of direct heating on containment loading, and the effects of fission product heating and natural convection on releases from the primary system. The results indicate that direct heating which involves more than about 50% of the core can fail the Bellefonte containment, but natural convection in the RCS may lead to overheating and failure of the primary system piping before core slump, thus, eliminating or mitigating direct heating. Releases from the primary system are significantly increased before vessel breach due to natural circulation and after vessel breach due to reevolution of retained fission products by fission product heating of RCS structures.

  13. NREL: Transportation Research - Transportation and Hydrogen Newsletter...

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

    The Future of Sustainable Transportation This is the January 2015 issue of the Transportation and Hydrogen Newsletter. Illustration of an electric vehicle Illustration of an...

  14. The Effect of the 18-Year Old Drinking Age on Auto Accidents

    E-Print Network [OSTI]

    Cucchiaro, Stephen

    The effect of Massachusetts' reduced drinking age on auto accidents is examined by employing an interrupted time series analysis of monthly accident data covering the period January, 1969, through September 1973. The data ...

  15. STAMP-Based Analysis of a Refinery Overflow Accident Nancy Leveson, Margaret Stringfellow, and John Thomas

    E-Print Network [OSTI]

    Leveson, Nancy

    1 STAMP-Based Analysis of a Refinery Overflow Accident Nancy Leveson, Margaret Stringfellow, and John Thomas As an example of STAMP, we have taken an accident report produced for a real refinery

  16. accident efectele medico-biologice: Topics by E-print Network

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

    Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date accident treatment provided? Yes No Where Was time lost from work? Yes No If yes, how long? Could this...

  17. Three dimensional effects in analysis of PWR steam line break accident

    E-Print Network [OSTI]

    Tsai, Chon-Kwo

    A steam line break accident is one of the possible severe abnormal transients in a pressurized water reactor. It is required to present an analysis of a steam line break accident in the Final Safety Analysis Report (FSAR) ...

  18. Calculation Notes for Subsurface Leak Resulting in Pool, TWRS FSAR Accident Analysis

    SciTech Connect (OSTI)

    Hall, B.W.

    1996-09-25T23:59:59.000Z

    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.

  19. Calculation notes for surface leak resulting in pool, TWRS FSAR accident analysis

    SciTech Connect (OSTI)

    Hall, B.W.

    1996-09-25T23:59:59.000Z

    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.

  20. Natural Language Processing (NLP) tools for the analysis of incident and accident reports

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Natural Language Processing (NLP) tools for the analysis of incident and accident reports, Analysis of accidents/incidents, Categorization, Textual similarity INTRODUCTION Learning valuable lessons, (ii) the analysis of reports regardless of the categorization in order to expand the analysis

  1. Accident Analysis and Prevention 42 (2010) 213224 Contents lists available at ScienceDirect

    E-Print Network [OSTI]

    Wisconsin at Madison, University of

    Accident Analysis and Prevention 42 (2010) 213­224 Contents lists available at ScienceDirect Accident Analysis and Prevention journal homepage: www.elsevier.com/locate/aap Rainfall effect on single

  2. Type A Accident Investigation Board Report on the July 1, 2008...

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

    July 1, 2008, of the Vehicle Fatality Accident-Western Area Power Marketing Administration Type A Accident Investigation Board Report on the July 1, 2008, of the Vehicle Fatality...

  3. MSIV leakage airborne iodine transport

    SciTech Connect (OSTI)

    Cline, J.E. (Cline Associates Inc., Rockville, MD (United States))

    1993-01-01T23:59:59.000Z

    Gaseous iodine deposits on surfaces exposed to vapors. Basic chemical and physical principles predict this behavior, and several laboratory and in-plant measurements demonstrate the characteristic. An empirical model was developed that describes the deposition, resuspension, and transformation of airborne radioiodine molecular species as a stream containing these forms moves along its pathway. The model uses a data base of measured values of deposition and resuspension rates in its application and describes the conversion of the more reactive inorganic iodine species I[sub 2] to the less reactive organic species CH[sub 3]I as the iodine deposits and resuspends along the path. It also considers radioactive decay and chemical surface bonding during residence on surfaces. For the 8-day [sup 131]I, decay during the airborne portion of the transport is negligible. Verification of the model included measurement tests of long gaseous-activity sampling lines of different diameters, operated at different flow rates and stream temperatures. The model was applied to the streams at a boiling water reactor nuclear power plant to describe the transport through leaking main steam isolation valves (MSIVs), following a loss-of-coolant accident.

  4. University of Virginia Agency 207 Accident Report for Workers' Compensation Claim Please complete this form and turn it in to your department's Human Resource Coordinator or

    E-Print Network [OSTI]

    Acton, Scott

    University of Virginia Agency 207 Accident Report for Workers' Compensation Claim Please complete Accident Reported: __________Reported Accident to:___________________________________ Was Supervisor(es)___________________________________________________________________ Information About the Nature and Cause of Accident Machine, tool, or object causing injury

  5. Nuclear fuel cycle facility accident analysis handbook

    SciTech Connect (OSTI)

    NONE

    1998-03-01T23:59:59.000Z

    The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

  6. accident codes applications: Topics by E-print Network

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

    accident codes applications First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Validation of severe...

  7. Accident Research Helps Save Lives of Loggers Research Brief # 33

    E-Print Network [OSTI]

    of the Strategic Partnership Agreement between logging companies and the federal Occupational Safety & Health Administration (OSHA), 257 logging companies agreed to submit their accident reports annually to the Louisiana and continues to present the results of new logging safety research to nearly every logging company

  8. alamos nuclear accidents: Topics by E-print Network

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

    alamos nuclear accidents First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Fukushima Nuclear Power Plant...

  9. accident nuclear materials: Topics by E-print Network

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

    accident nuclear materials First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 NUREGCR-7034 Analysis of...

  10. Application of Evidential Networks in quantitative analysis of railway accidents

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Application of Evidential Networks in quantitative analysis of railway accidents Felipe Aguirre1 during the qualitative or quantitative evaluation of risk. Several new techniques for HRA were invented. As a consequence, safety engineers try to take into account this factor in risk assessment. However, human

  11. Berkeley Lab Accident Statistics Through December 31, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    Engineering Environmental Energy Tech. Genomics Life Sciences Materials Sciences NERSC Center Nuclear Science Energy Tech. Genomics Life Sciences Materials Sciences NERSC Center Nuclear Science Physical Biosciences1 Berkeley Lab Accident Statistics Through December 31, 2009 These slides are updated on a monthly

  12. Interdisciplinary Institute for Innovation Le risque d'accident nuclaire

    E-Print Network [OSTI]

    Boyer, Edmond

    . Cochran. (2011), Fukushima nuclear disaster and its implication for US nuclear power reactors. Ce chiffre Lévêque L'accident de Fukushima Daiichi s'est produit le 11 mars 2011. Cette catastrophe nucléaire irrémédiablement associée à une centrale nucléaire dont l'homme a perdu le contrôle. Fukushima Daiichi a ainsi fait

  13. Source: http://www.ftc.gov/debtcollection ost accidents

    E-Print Network [OSTI]

    Oliver, Douglas L.

    Source: http://www.ftc.gov/debtcollection M ost accidents on the job are caused by un- safe actions-852-4392 #12;Source: Office of Dietary Supplements, National Institutes of Health F requently the missing piece to finding work-life balance is "mindset." This is a psycho- logical leap to rock-solid commit- ment

  14. Accident Analysis and Prevention 40 (2008) 12441248 Short communication

    E-Print Network [OSTI]

    McLeod, Ian

    2008-01-01T23:59:59.000Z

    Accident Analysis and Prevention 40 (2008) 1244­1248 Short communication Power computations in time the intervention analysis of the policy, it is important to ensure that the statistical tests have enough power in a wide variety of traffic safety intervention analysis applications. Our method is illustrated

  15. accident sequence evaluation: Topics by E-print Network

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

    accident sequence evaluation First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Resugaring: Lifting...

  16. accident research network: Topics by E-print Network

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

    accident research network First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Structure Evolution of...

  17. accident reports: Topics by E-print Network

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

    accident reports First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 TIPS ON ACCIDENTINCIDENT REPORTING...

  18. accident core heatup: Topics by E-print Network

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

    accident core heatup First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Appendix 10 Spent Fuel Heatup Time...

  19. accident management: Topics by E-print Network

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

    accident management First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Medical Management of Radiation...

  20. accident ria conditions: Topics by E-print Network

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

    accident ria conditions First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Ria-kehitys Ruby Rsence...

  1. accident alarm systems: Topics by E-print Network

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

    accident alarm systems First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 FIRE ALARM SYSTEMS AND...

  2. accident research priorities: Topics by E-print Network

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

    accident research priorities First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Chapter 6: Research...

  3. accident rates: Topics by E-print Network

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

    accident rates First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Tangent length and sight distance...

  4. accident analysis software: Topics by E-print Network

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

    accident analysis software First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 The Role of Software in...

  5. accident and emergency medicine: Topics by E-print Network

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

    accident and emergency medicine First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Nanotechnology:...

  6. accident management measures: Topics by E-print Network

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

    accident management measures First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Medical Management of...

  7. accident retrospective estimation: Topics by E-print Network

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

    accident retrospective estimation First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Some methods of...

  8. accident frequencies program: Topics by E-print Network

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

    accident frequencies program First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 INTRODUCTION OF FREQUENCY...

  9. advanced accident sequence: Topics by E-print Network

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

    advanced accident sequence First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Math 55a: Honors Advanced...

  10. accident consequence model: Topics by E-print Network

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

    accident consequence model First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Conservation consequences of...

  11. accident conditions vercors: Topics by E-print Network

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

    accident conditions vercors First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 RUNNING HEAD: Subaerial...

  12. accident dinamika formirovaniya: Topics by E-print Network

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

    accident dinamika formirovaniya First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Adaptv dinamika: mirt l...

  13. accident conditions key: Topics by E-print Network

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

    accident conditions key First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Range Condition: Key to...

  14. accident recovery workers: Topics by E-print Network

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

    accident recovery workers First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 COLUMBIA UNIVERSITY...

  15. accident sequence analysis: Topics by E-print Network

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

    accident sequence analysis First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Biological Sequence Analysis...

  16. accident sequences simulated: Topics by E-print Network

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

    accident sequences simulated First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Combining Simulation with...

  17. accident reconstruction: Topics by E-print Network

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

    accident reconstruction First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Photogrammetry in Traffic...

  18. accident management epr: Topics by E-print Network

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

    accident management epr First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Medical Management of Radiation...

  19. accident alarm system: Topics by E-print Network

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

    accident alarm system First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 FIRE ALARM SYSTEMS AND PROCEDURES...

  20. accident progression event: Topics by E-print Network

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

    accident progression event First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 EVENT CALCULUS,...