Sample records for accident conditions view

  1. Graphite Oxidation Simulation in HTR Accident Conditions

    SciTech Connect (OSTI)

    Mohamed El-Genk

    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.

  2. Response of HEPA filters to simulated-accident conditions

    SciTech Connect (OSTI)

    Gregory, W.S.; Martin, R.A.; Smith, P.R.; Fenton, D.E.

    1982-01-01T23:59:59.000Z

    High-efficiency particulate air (HEPA) filters have been subjected to simulated accident conditions to determine their response to abnormal operating events. Both domestic and European standard and high-capacity filters have been evaluated to determine their response to simulated fire, explosion, and tornado conditions. The HEPA filter structural limitations for tornado and explosive loadings are discussed. In addition, filtration efficiencies during these accident conditions are reported for the first time. Our data indicate efficiencies between 80% and 90% for shock loadings below the structural limit level. We describe two types of testing for ineffective filtration - clean filters exposed to pulse-entrained aerosol and dirty filters exposed to tornado and shock pulses. Efficiency and material loss data are described. Also, the resonse of standard HEPA filters to simulated fire conditions is presented. We describe a unique method of measuring accumulated combustion products on the filter. Additionally, data relating to pressure drop vs accumulated mass during plugging are reported for simulated combustion aerosols. The effects of concentration and moisture levels on filter plugging were evaluated. We are obtaining all of the above data so that mathematical models can be developed for fire, explosion, and tornado accident analysis computer codes. These computer codes can be used to assess the response of nuclear air cleaning systems to accident conditions.

  3. Fission product release from irradiated LWR fuel under accident conditions

    SciTech Connect (OSTI)

    Strain, R.V.; Sanecki, J.E.; Osborne, M.F.

    1984-01-01T23:59:59.000Z

    Fission product release from irradiated LWR fuel is being studied by heating fuel rod segments in flowing steam and an inert carrier gas to simulate accident conditions. Fuels with a range of irradiation histories are being subjected to several steam flow rates over a wide range of temperatures. Fission product release during each test is measured by gamma spectroscopy and by detailed examination of the collection apparatus after the test has been completed. These release results are complemented by a detailed posttest examination of samples of the fuel rod segment. Results of release measurements and fuel rod characterizations for tests at 1400 through 2000/sup 0/C are presented in this paper.

  4. E-Print Network 3.0 - accident ria conditions Sample Search Results

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    ria conditions Page: << < 1 2 3 4 5 > >> 1 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: Incident:...

  5. Electrical equipment performance under severe accident conditions (BWR/Mark 1 plant analysis): Summary report

    SciTech Connect (OSTI)

    Bennett, P.R.; Kolaczkowski, A.M.; Medford, G.T.

    1986-09-01T23:59:59.000Z

    The purpose of the Performance Evaluation of Electrical Equipment during Severe Accident States Program is to determine the performance of electrical equipment, important to safety, under severe accident conditions. In FY85, a method was devised to identify important electrical equipment and the severe accident environments in which the equipment was likely to fail. This method was used to evaluate the equipment and severe accident environments for Browns Ferry Unit 1, a BWR/Mark I. Following this work, a test plan was written in FY86 to experimentally determine the performance of one selected component to two severe accident environments.

  6. 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.

  7. PRESSURE INTEGRITY OF 3013 CONTAINER UNDER POSTULATED ACCIDENT CONDITIONS

    SciTech Connect (OSTI)

    Rawls, G.

    2010-02-01T23:59:59.000Z

    A series of tests was carried out to determine the threshold for deflagration-to-detonation transition (DDT), structural loading, and structural response of the Department of Energy 3013 storage systems for the case of an accidental explosion of evolved gas within the storage containers. Three experimental fixtures were used to examine the various issues and three mixtures consisting of either stoichiometric hydrogen-oxygen, stoichiometric hydrogen-oxygen with added nitrogen, or stoichiometric hydrogen-oxygen with an added nitrogen-helium mixture were tested. Tests were carried out as a function of initial pressure from 1 to 3.5 bar and initial temperature from room temperature to 150 C. The elevated temperature tests resulted in a slight increase in the threshold pressure for DDT. The elevated temperature tests were performed to ensure the test results were bounding. Because the change was not significant the elevated temperature data are not presented in the paper. The explosions were initiated with either a small spark or a hot surface. Based on the results of these tests under the conditions investigated, it can be concluded that DDT of a stoichiometric hydrogen-oxygen mixture (and mixtures diluted with nitrogen and helium) within the 3013 containment system does not pose a threat to the structural integrity of the outer container.

  8. 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.

  9. E-Print Network 3.0 - accident conditions lessons Sample Search...

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    1 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: the lessons that are really taught by an accident or group of accidents....

  10. E-Print Network 3.0 - accident conditions vercors Sample Search...

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    de mathmatiques Collection: Mathematics 5 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: Incident:...

  11. E-Print Network 3.0 - accident containment conditions Sample...

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    Technologies and Information Sciences 9 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: Incident:...

  12. E-Print Network 3.0 - accident conditions key Sample Search Results

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

    1 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: Why System Safety Professionals Should Read Accident Reports C. M....

  13. Status report of advanced cladding modeling work to assess cladding performance under accident conditions

    SciTech Connect (OSTI)

    B.J. Merrill; Shannon M. Bragg-Sitton

    2013-09-01T23:59:59.000Z

    Scoping simulations performed using a severe accident code can be applied to investigate the influence of advanced materials on beyond design basis accident progression and to identify any existing code limitations. In 2012 an effort was initiated to develop a numerical capability for understanding the potential safety advantages that might be realized during severe accident conditions by replacing Zircaloy components in light water reactors (LWRs) with silicon carbide (SiC) components. To this end, a version of the MELCOR code, under development at the Sandia National Laboratories in New Mexico (SNL/NM), was modified by replacing Zircaloy for SiC in the MELCOR reactor core oxidation and material properties routines. The modified version of MELCOR was benchmarked against available experimental data to ensure that present SiC oxidation theory in air and steam were correctly implemented in the code. Additional modifications have been implemented in the code in 2013 to improve the specificity in defining components fabricated from non-standard materials. An overview of these modifications and the status of their implementation are summarized below.

  14. INVESTIGATION OF ACCIDENTS AND SHARING INFORMATION : AN EXPERT POINT OF VIEW

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    phenomenon, on the general design of a plant or transportation system, on the reliability of safety related of plant design and Operation including human factor, management and maintenance · at competent authorities in progress : a special group of European Process Safety Center (EPSC) dealing with accident, the networking

  15. Oxidation of SiC cladding under Loss of Coolant Accident (LOCA) conditions in LWRs

    SciTech Connect (OSTI)

    Lee, Y.; Yue, C.; Arnold, R. P.; McKrell, T. J.; Kazimi, M. S. [Dept. of Nuclear Science and Engineering, Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139-4307 (United States)

    2012-07-01T23:59:59.000Z

    An experimental assessment of Silicon Carbide (SiC) cladding oxidation rate in steam under conditions representative of Loss of Coolant Accidents (LOCA) in light water reactors (LWRs) was conducted. SiC oxidation tests were performed with monolithic alpha phase tubular samples in a vertical quartz tube at a steam temperature of 1140 deg. C and steam velocity range of 1 to 10 m/sec, at atmospheric pressure. Linear weight loss of SiC samples due to boundary layer controlled reaction of silica scale (SiO{sub 2} volatilization) was experimentally observed. The weight loss rate increased with increasing steam flow rate. Over the range of test conditions, SiC oxidation rates were shown to be about 3 orders of magnitude lower than the oxidation rates of zircaloy 4. A SiC volatilization correlation for developing laminar flow in a vertical channel is formulated. (authors)

  16. 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.

  17. Neutronics and Fuel Performance Evaluation of Accident Tolerant Fuel under Normal Operation Conditions

    SciTech Connect (OSTI)

    Xu Wu; Piyush Sabharwall; Jason Hales

    2014-07-01T23:59:59.000Z

    This report details the analysis of neutronics and fuel performance analysis for enhanced accident tolerance fuel, with Monte Carlo reactor physics code Serpent and INL’s fuel performance code BISON, respectively. The purpose is to evaluate two of the most promising candidate materials, FeCrAl and Silicon Carbide (SiC), as the fuel cladding under normal operating conditions. Substantial neutron penalty is identified when FeCrAl is used as monolithic cladding for current oxide fuel. From the reactor physics standpoint, application of the FeCrAl alloy as coating layer on surface of zircaloy cladding is possible without increasing fuel enrichment. Meanwhile, SiC brings extra reactivity and the neutron penalty is of no concern. Application of either FeCrAl or SiC could be favorable from the fuel performance standpoint. Detailed comparison between monolithic cladding and hybrid cladding (cladding + coating) is discussed. Hybrid cladding is more practical based on the economics evaluation during the transition from current UO2/zircaloy to Accident Tolerant Fuel (ATF) system. However, a few issues remain to be resolved, such as the creep behavior of FeCrAl, coating spallation, inter diffusion with zirconium, etc. For SiC, its high thermal conductivity, excellent creep resistance, low thermal neutron absorption cross section, irradiation stability (minimal swelling) make it an excellent candidate materials for future nuclear fuel/cladding system.

  18. Test plan for high-burnup fuel cladding behavior under loss-of- coolant accident conditions

    SciTech Connect (OSTI)

    Chung, H.M.; Neimark, L.A.; Kassner, T.F.

    1996-10-01T23:59:59.000Z

    Excessive oxidation, hydriding, and extensive irradiation damage occur in high-burnup fuel cladding, and as result, mechanical properties of high-burnup fuels are degraded significantly. This may influence the current fuel cladding failure limits for loss-of- coolant-accident (LOCA) situations, which are based on fuel cladding behavior for zero burnup. To avoid cladding fragmentation and fuel dispersal during a LOCA, 10 CFR 50.46 requires that peak cladding temperature shall not exceed 1204 degrees C (2200 degrees F) and that total oxidation of the fuel cladding nowhere exceeds 0.17 times total cladding thickness before oxidation. Because of the concern, a new experimental program to investigate high-burnup fuel cladding behavior under LOCA situations has been initiated under the sponsorship of the U.S. Nuclear Regulatory Commission. A hot-cell test plan to investigate single-rod behavior under simulated LOCA conditions is described in this paper. In the meantime, industry fuel design and operating conditions are expected to undergo further changes as more advanced cladding materials are developed. Under these circumstances, mechanical properties of high-burnup fuel cladding require further investigation so that results from studies on LOCA, reactivity- initiated-accident (RIA), operational transient, and power-ramping situations, can be extrapolated to modified or advanced cladding materials and altered irradiation conditions without repeating major integral experiments in test reactors. To provide the applicable data base and mechanistic understanding, tests will be conducted to determine dynamic and static fracture toughness and tensile properties. Background and rationale for selecting the specific mechanical properties tests are also described.

  19. E-Print Network 3.0 - accident conditions final Sample Search...

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    of Astronomy, University of Virginia Collection: Physics 3 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: kinetic energy and therefore can derail...

  20. GEN-IV BENCHMARKING OF TRISO FUEL PERFORMANCE MODELS UNDER ACCIDENT CONDITIONS

    SciTech Connect (OSTI)

    Blaise Collin

    2014-09-01T23:59:59.000Z

    This document presents the benchmark plan for the calculation of particle fuel performance on safety testing experiments that are representative of operational accidental transients. The benchmark is dedicated to the modeling of fission product release under accident conditions by fuel performance codes from around the world, and the subsequent comparison to post-irradiation experiment (PIE) data from the modeled heating tests. The accident condition benchmark is divided into three parts: • The modeling of a simplified benchmark problem to assess potential numerical calculation issues at low fission product release. • The modeling of the AGR-1 and HFR-EU1bis safety testing experiments. • The comparison of the AGR-1 and HFR-EU1bis modeling results with PIE data. The simplified benchmark case, thereafter named NCC (Numerical Calculation Case), is derived from “Case 5” of the International Atomic Energy Agency (IAEA) Coordinated Research Program (CRP) on coated particle fuel technology [IAEA 2012]. It is included so participants can evaluate their codes at low fission product release. “Case 5” of the IAEA CRP-6 showed large code-to-code discrepancies in the release of fission products, which were attributed to “effects of the numerical calculation method rather than the physical model” [IAEA 2012]. The NCC is therefore intended to check if these numerical effects subsist. The first two steps imply the involvement of the benchmark participants with a modeling effort following the guidelines and recommendations provided by this document. The third step involves the collection of the modeling results by Idaho National Laboratory (INL) and the comparison of these results with the available PIE data. The objective of this document is to provide all necessary input data to model the benchmark cases, and to give some methodology guidelines and recommendations in order to make all results suitable for comparison with each other. The participants should read this document thoroughly to make sure all the data needed for their calculations is provided in the document. Missing data will be added to a revision of the document if necessary.

  1. 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.

  2. Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident

    SciTech Connect (OSTI)

    Joy Rempe; Mitchell Farmer; Michael Corradini; Larry Ott; Randall Gauntt; Dana Powers

    2012-11-01T23:59:59.000Z

    The Three Mile Island Unit 2 (TMI-2) accident, which occurred on March 28, 1979, led industry and regulators to enhance strategies to protect against severe accidents in commercial nuclear power plants. Investigations in the years after the accident concluded that at least 45% of the core had melted and that nearly 19 tonnes of the core material had relocated to the lower head. Postaccident examinations indicate that about half of that material formed a solid layer near the lower head and above it was a layer of fragmented rubble. As discussed in this paper, numerous insights related to pressurized water reactor accident progression were gained from postaccident evaluations of debris, reactor pressure vessel (RPV) specimens, and nozzles taken from the RPV. In addition, information gleaned from TMI-2 specimen evaluations and available data from plant instrumentation were used to improve severe accident simulation models that form the technical basis for reactor safety evaluations. Finally, the TMI-2 accident led the nuclear community to dedicate considerable effort toward understanding severe accident phenomenology as well as the potential for containment failure. Because available data suggest that significant amounts of fuel heated to temperatures near melting, the events at Fukushima Daiichi Units 1, 2, and 3 offer an unexpected opportunity to gain similar understanding about boiling water reactor accident progression. To increase the international benefit from such an endeavor, we recommend that an international effort be initiated to (a) prioritize data needs; (b) identify techniques, samples, and sample evaluations needed to address each information need; and (c) help finance acquisition of the required data and conduct of the analyses.

  3. Improved assessment of population doses and risk factors for a nuclear power plant under accident conditions

    E-Print Network [OSTI]

    Meyer, Christopher Martin

    1985-01-01T23:59:59.000Z

    In order to assess the doses received by the members of the public due to an accident at a nuclear power plant, a number of physical processes must be modeled. These processes include the release of radioactive materials, the atmospheric dispersion... representative of the industry. Generic reactor sites must be conceptualized in order to obtain meteorologic data which is representative of the areas within the United States in which nuclear power facilities have been sited, Information such as population...

  4. VICTORIA: A mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions

    SciTech Connect (OSTI)

    Heames, T.J. (Science Applications International Corp., Albuquerque, NM (USA)); Williams, D.A.; Johns, N.A.; Chown, N.M. (UKAEA Atomic Energy Establishment, Winfrith (UK)); Bixler, N.E.; Grimley, A.J. (Sandia National Labs., Albuquerque, NM (USA)); Wheatley, C.J. (UKAEA Safety and Reliability Directorate, Culcheth (UK))

    1990-10-01T23:59:59.000Z

    This document provides a description of a model of the radionuclide behavior in the reactor coolant system (RCS) of a light water reactor during a severe accident. This document serves as the user's manual for the computer code called VICTORIA, based upon the model. The VICTORIA code predicts fission product release from the fuel, chemical reactions between fission products and structural materials, vapor and aerosol behavior, and fission product decay heating. This document provides a detailed description of each part of the implementation of the model into 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. The VICTORIA code was developed upon a CRAY-XMP at Sandia National Laboratories in the USA and a CRAY-2 and various SUN workstations at the Winfrith Technology Centre in England. 60 refs.

  5. A view of treatment process of melted nuclear fuel on a severe accident plant using a molten salt system

    SciTech Connect (OSTI)

    Fujita, R.; Takahashi, Y.; Nakamura, H.; Mizuguchi, K. [Power and Industrial Research and Development Center, Toshiba Corporation Power Systems Company, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki 210-0862 (Japan); Oomori, T. [Chemical System Design and Engineering Department, Toshiba Corporation Power Systems Company, 8 Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan)

    2013-07-01T23:59:59.000Z

    At severe accident such as Fukushima Daiichi Nuclear Power Plant Accident, the nuclear fuels in the reactor would melt and form debris which contains stable UO2-ZrO2 mixture corium and parts of vessel such as zircaloy and iron component. The requirements for solution of issues are below; -) the reasonable treatment process of the debris should be simple and in-situ in Fukushima Daiichi power plant, -) the desirable treatment process is to take out UO{sub 2} and PuO{sub 2} or metallic U and TRU metal, and dispose other fission products as high level radioactive waste; and -) the candidate of treatment process should generate the smallest secondary waste. Pyro-process has advantages to treat the debris because of the high solubility of the debris and its total process feasibility. Toshiba proposes a new pyro-process in molten salts using electrolysing Zr before debris fuel being treated.

  6. 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’

  7. Creep failure of a reactor pressure vessel lower head under severe accident conditions

    SciTech Connect (OSTI)

    Pilch, M.M.; Ludwigsen, J.S.; Chu, T.Y. [Sandia National Labs., Albuquerque, NM (United States); Rashid, Y.R. [Anatech, San Diego, CA (United States)

    1998-08-01T23:59:59.000Z

    A severe accident in a nuclear power plant could result in the relocation of large quantities of molten core material onto the lower head of he reactor pressure vessel (RPV). In the absence of inherent cooling mechanisms, failure of the RPV ultimately becomes possible under the combined effects of system pressure and the thermal heat-up of the lower head. Sandia National Laboratories has performed seven experiments at 1:5th scale simulating creep failure of a RPV lower head. This paper describes a modeling program that complements the experimental program. Analyses have been performed using the general-purpose finite-element code ABAQUS-5.6. In order to make ABAQUS solve the specific problem at hand, a material constitutive model that utilizes temperature dependent properties has been developed and attached to ABAQUS-executable through its UMAT utility. Analyses of the LHF-1 experiment predict instability-type failure. Predicted strains are delayed relative to the observed strain histories. Parametric variations on either the yield stress, creep rate, or both (within the range of material property data) can bring predictions into agreement with experiment. The analysis indicates that it is necessary to conduct material property tests on the actual material used in the experimental program. The constitutive model employed in the present analyses is the subject of a separate publication.

  8. Study of Air Ingress Across the Duct During the Accident Conditions

    SciTech Connect (OSTI)

    Hassan, Yassin

    2013-05-06T23:59:59.000Z

    The goal of this project is to study the fundamental physical phenoena associated with air ingress in very high temperature reactors (VHTRs). Air ingress may occur due to a nupture of primary piping and a subsequent breach in the primary pressure boundary in helium-cooled and graphite-moderated VHTRs. Significant air ingress is a concern because it introduces potential to expose the fuel, graphite support rods, and core to a risk of severe graphite oxidation. Two of the most probable air ingress scenarios involve rupture of a control rod or fuel access standpipe, and rupture in the main coolant pipe on the lower part of the reactor pressure vessel. Therefor, establishing a fundamental understanding of air ingress phenomena is critical in order to rationally evaluate safety of existing VHTRs and develop new designs that mimimize these risks. But despite this importance, progress toward development these predictive capabilities has been slowed by the complex nature of the underlaying phenomena. The combination of interdiffusion among multiple species, molecular diffusion, natural convection, and complex geometries, as well as the multiple chemical reactions involved, impose significant roadblocks to both modeling and experiment design. The project team will employ a coordinated experimental and computational effort that will help gain a deeper understanding of multiphased air ingress phenomena. THis project will enhance advanced modeling and simulation methods, enabling calculation of nuclear power plant transients and accident scenarios with a high degree of confidence. The following are the project tasks: Perform particle image velocimetry measurement of multiphase air ingresses Perform computational fluid dynamics analysis of air ingress phenomena

  9. 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.

  10. Molecular Dynamic Simulation of Sodium in 7-Pin LMFBR Bundle Under Hypothetical Accident Conditions

    SciTech Connect (OSTI)

    Bottoni, Maurizio [University of Ferrara, Physics Department, Via Paradiso 12, I-44100 Ferrara (Italy); Bottoni, Claudio; Scanu, John [University of Pisa, Lungarno Pacinotti, 43 - 56126 Pisa (Italy)

    2006-07-01T23:59:59.000Z

    In the frame of safety analysis of liquid metal fast breeder reactors (LMFBRs) under hypothetical Unprotected Loss of Flow (ULOF) conditions two-phase flow of sodium is simulated in a 7-pin bundle, with hexagonal lattice. Molecular dynamics, with the application of the Direct Simulation Monte Carlo (DSMC) method, and a macroscopic model describing rewetting sequences due to the flow of a sodium liquid film along the pin surfaces, are applied to simulate the coolant in the bundle. The pin surfaces and the inner surface of the hexagonal canning are treated in the Monte Carlo simulation as diffusively reflecting surfaces. Collisions of sodium molecules are computed with the 'hard-sphere' model. With respect to previous work the following improvements of the computational code were made: i) The full bundle is simulated, thus allowing for asymmetries, like a skewed power distribution, to be accounted for; ii) A pin model calculates detailed temperature distributions in the pins, so that temperature boundary conditions are computed and not imposed; iii) Post processing visualisation of computed results was developed. An out of pile sodium boiling experiment run at the Nuclear Research Center of Karlsruhe, Germany, is simulated and conclusions are drawn about the applicability of the methodology in computer codes dedicated to breeder reactors safety analysis. (authors)

  11. View

    E-Print Network [OSTI]

    2004-12-25T23:59:59.000Z

    Let fbe a meromorphic function satisfying condition (1.2), and let rj be a sequence with property (2.5). Then the set S is finite and for some subsequence of ...

  12. 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

  13. 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.

  14. 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.

  15. 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

  16. 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

  17. 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

  18. DESCRIPTION OF ACCIDENT MSU DRIVERS SIGNATURE

    E-Print Network [OSTI]

    Dyer, Bill

    DESCRIPTION OF ACCIDENT MSU DRIVERS SIGNATURE Signature 2-9-108, MCA (Statutory Coverage, in lieu-90-(4-20). CERTIFICATE OF INSURANCE X Weather Conditions: ACCIDENT INFORMATION Location: Date: - - 20 Time: : .M. Driver and Risk Management ~ 1160 Research Drive Bozeman, MT 59718 ~ (406) 994-2711 Accident Form #12;OTHER

  19. Nuclear criticality safety tools in the Chernobyl-4 accident analysis

    SciTech Connect (OSTI)

    Landeyro, P.A.

    1988-01-01T23:59:59.000Z

    The collaboration with the Italian Safety Authority (DISP), started in July 1986, has the aim of studying, from a neutronic point of view, the possible initiator event and the accident dynamics in unit four of the Chernobly nuclear power plant. This report was produced within the framework of that collaboration. A main condition of the present work was making use of standard calculational methods employed in nuclear criticality safety analysis. This means that the neutron multiplication factor calculation should be made with the modules and the cross-section libraries of the SCALE system or in any case with some KENO IV version and the burnup calculation with the ORIGEN code.

  20. Hypothetical Reactor Accident Study

    E-Print Network [OSTI]

    - W 4 DfcSkoollo Rise-R-427 CARNSORE: Hypothetical Reactor Accident Study O. Walmod-Larsen, N. O: HYPOTHETICAL REACTOR ACCIDENT STUDY O. Walmod-Larsen, N.O. Jensen, L. Kristensen, A. Heide, K.L. NedergĂĄrd, P-basis accident and a series of hypothetical core-melt accidents to a 600 MWe reactor are de- scribed

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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 ...

  6. 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...

  7. Microsoft PowerPoint - Mod 14 - HTGR Accident Analyses - final...

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

    Cooling System (SCS) Core Conditioning System (CCS) - Helium Purification System Post Accident Train y (Pebble Bed HPS PAT) - Reactor Cavity Cooling System (RCCS) A ti d *...

  8. Group Accident Insurance Certificate

    E-Print Network [OSTI]

    New Mexico, University of

    Group Accident Insurance Certificate Regents of the University of New Mexico #12;#12;Life Insurance Company GROUP ACCIDENT CERTIFICATE THIS CERTIFICATE PROVIDES LIMITED COVERAGE. PLEASE READ YOUR. THIS CERTIFICATE IS ISSUED UNDER AN ACCIDENT ONLY POLICY. IT DOES NOT PAY BENEFITS FOR LOSS CAUSED BY SICKNESS. GA

  9. Chemical factors affecting fission product transport in severe LMFBR accidents

    SciTech Connect (OSTI)

    Wichner, R.P.; Jolley, R.L.; Gat, U.; Rodgers, B.R.

    1984-10-01T23:59:59.000Z

    This study was performed as a part of a larger evaluation effort on LMFBR accident, source-term estimation. Purpose was to provide basic chemical information regarding fission product, sodium coolant, and structural material interactions required to perform estimation of fission product transport under LMFBR accident conditions. Emphasis was placed on conditions within the reactor vessel; containment vessel conditions are discussed only briefly.

  10. 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,...

  11. 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

  12. 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.

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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.

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

    SciTech Connect (OSTI)

    Wyss, G.D.; Camp, A.L.; Miller, L.A.; Dingman, S.E.; Kunsman, D.M. (Sandia National Labs., Albuquerque, NM (USA)); Medford, G.T. (Science Applications International Corp., Albuquerque, NM (USA))

    1990-06-01T23:59:59.000Z

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

  19. Analysis of Comair flight 5191 with the Functional Resonance Accident Model

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Analysis of Comair flight 5191 with the Functional Resonance Accident Model Erik Hollnagel 1 Abstract The goal of an accident investigation is to determine why a certain combination of conditions, events, and actions led to the specific outcome. Accidents in complex high risk operations

  20. Explaining the road accident risk: weather effects Ruth Bergel-Hayat1*

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Explaining the road accident risk: weather effects Ruth Bergel-Hayat1* , Mohammed Debbarh1 conditions and road accident risk at an aggregate level and on a monthly basis, in order to improve road accidents. Time series analysis models with explanatory variables that measure the weather quantitatively

  1. 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...

  2. 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,

  3. 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.

  4. 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 ...

  5. SAS4A LMFBR whole core accident analysis code

    SciTech Connect (OSTI)

    Weber, D.P.; Birgersson, G.; Bordner, G.L.; Briggs, L.L.; Cahalan, J.E.; Dunn, F.E.; Kalimullah; Miles, K.J.; Prohammer, F.G.; Tentner, A.M.

    1985-01-01T23:59:59.000Z

    To ensure that public health and safety are protected even under accident conditions in an LMFBR, many accidents are analyzed for their potential consequences. Extremely unlikely accidents that might lead to melting of reactor fuel and release of radioactive fission products are referred to as hypothetical core disruptive accidents (HCDAs). The evaluation of such accidents involves the simultaneous evaluation of thermal, mechanical, hydraulic and neutronic processes and their interactions. The complexity of this analysis requires the use of large, integrated computer codes which address the response of the reactor core and several important systems. The SAS family of codes, developed at Argonne National Laboratory, provides such an analysis capability. The SAS4A code, the latest generation of this series of codes, has recently been completed and released for use to the LMFBR safety community. This paper will summarize the important new capabilitites of this analysis tool and illustrate an application of the integrated capability, while highlighting the importance of specific phenomenological models.

  6. 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.

  7. 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.

  8. 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,...

  9. 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

  10. 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.

  11. 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)

  12. 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.

  13. 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

  14. 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

  15. 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.

  16. Accident Research Helps Save Lives of Loggers Research Brief # 33

    E-Print Network [OSTI]

    of the fatal accidents and many other accidents. Training, defined work procedures, lockout / tagout programs

  17. Study on Total Instantaneous Blockage Accident for CEFR

    SciTech Connect (OSTI)

    Zhe Wang; Xuewu Cao [Shanghai Jiaotong University, Shanghai (China)

    2006-07-01T23:59:59.000Z

    Chinese Experimental Fast Reactor (CEFR) is under construction in China. It is essential to investigate core disruptive accidents (CDAs) for the evaluation of CEFR's safety characteristic. Accident of total instantaneous blockage in single assembly scale had already been modeled and analyzed. The degradation scenario had been calculated by a fluid-dynamics analysis code for liquid-metal fast reactors (LMFRs). For further investigation of accident process and influence to the near bundles, the seven assembly scale were then simulated and calculated. Total instantaneous blockage was assumed to occur in the center assembly under normal operating conditions and consequences to neighboring assemblies were studied. The result shows that the key events such as sodium boiling, clad melting, fuel particles relocation, hexcan failure and melt discharge into neighboring six assemblies symmetrically were adequately simulated. All the key events appeared in the same sequence as the single assembly simulation, while hexcan failure occurred later than that of single assembly simulation. The reason for the different timing may be the boundary condition assumption can influence the heat removal from the blocked assembly. The seven-assembly scale model can reduce the boundary condition's uncertainties and help to give a better understanding and prediction of hypothetical accident scenario in subassembly blockage accidents for CEFR. (authors)

  18. 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

  19. 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

  20. 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

  1. Implications for accident management of adding water to a degrading reactor core

    SciTech Connect (OSTI)

    Kuan, P.; Hanson, D.J.; Pafford, D.J.; Quick, K.S.; Witt, R.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1994-02-01T23:59:59.000Z

    This report evaluates both the positive and negative consequences of adding water to a degraded reactor core during a severe accident. The evaluation discusses the earliest possible stage at which an accident can be terminated and how plant personnel can best respond to undesired results. Specifically discussed are (a) the potential for plant personnel to add water for a range of severe accidents, (b) the time available for plant personnel to act, (c) possible plant responses to water added during the various stages of core degradation, (d) plant instrumentation available to understand the core condition and (e) the expected response of the instrumentation during the various stages of severe accidents.

  2. 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...

  3. 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.

  4. 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.

  5. Post-accident gas generation from radiolysis of organic materials

    SciTech Connect (OSTI)

    Wing, J.

    1984-09-01T23:59:59.000Z

    This report presents a methodology for estimating the gas generation rates resulting from radiolysis of organic materials in paints and electrical cable insulation inside a nuclear reactor containment building under design basis accident conditions. The methodology was based on absorption of the radiation energies from the post-accident fission products and the assumed gas yields of the irradiated materials. A sample calculation was made using conservative assumptions, plant-specific data of a nuclear power plant, and a radiation source term which took into account the time-dependent release and physico-chemical behavior of the fission products.

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

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

    4, 2005, Americium Contamination Accident at the Sigma Facility, Los Alamos National Laboratory Type B Accident Investigation of the July 14, 2005, Americium Contamination Accident...

  7. 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

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

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

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

  9. 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...

  10. 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...

  11. 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

  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. 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

  17. INTERNATIONAL STUDENT & SCHOLAR Accident & Sickness Insurance Plan

    E-Print Network [OSTI]

    Bordenstein, Seth

    INTERNATIONAL STUDENT & SCHOLAR Accident & Sickness Insurance Plan 2012-2013 Plan Eligibility an accident and sickness insurance plan for international students and scholars studying in the United States are administered by NAHGA Claim Services: National Accident & Health General Agency The information provided below

  18. 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.

  19. 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...

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

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

    ignited the right leg of his 100% cotton anticontamination (anti-c) coveralls and the plastic bootie. Type B Accident Investigation, Subcontractor Employee Personal Protective...

  1. 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...

  2. 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...

  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. Mitigation of Severe Accident Consequences Using Inherent Safety Principles

    SciTech Connect (OSTI)

    R. A. Wigeland; J. E. Cahalan

    2009-12-01T23:59:59.000Z

    Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability of occurrence are typically handled without consequence through reliable engineering systems and good design practices. For accidents of lower probability, the initiating events are characterized by larger and more numerous challenges to the reactor system, such as failure of one or more major engineered systems and can also include a failure to scram the reactor in response. As the initiating conditions become more severe, they have the potential for creating serious consequences of potential safety significance, including fuel melting, fuel pin disruption and recriticality. If the progression of such accidents is not mitigated by design features of the reactor, energetic events and dispersal of radioactive materials may result. For severe accidents, there are several approaches that can be used to mitigate the consequences of such severe accident initiators, which typically include fuel pin failures and core disruption. One approach is to increase the reliability of the reactor protection system so that the probability of an ATWS event is reduced to less than 1 x 10-6 per reactor year, where larger accident consequences are allowed, meeting the U.S. NRC goal of relegating such accident consequences as core disruption to these extremely low probabilities. The main difficulty with this approach is to convincingly test and guarantee such increased reliability. Another approach is to increase the redundancy of the reactor scram system, which can also reduce the probability of an ATWS event to a frequency of less than 1 x 10-6 per reactor year or lower. The issues with this approach are more related to reactor core design, with the need for a greater number of control rod positions in the reactor core and the associated increase in complexity of the reactor protection system. A third approach is to use the inherent reactivity feedback that occurs in a fast reactor to automatically respond to the change in reactor conditions and to result in a benign response to these events. This approach has the advantage of being relatively simple to implement, and does not face the issue of reliability since only fundamental physical phenomena are used in a passive manner, not active engineered systems. However, the challenge is to present a convincing case that such passive means can be implemented and used. The purpose of this paper is to describe this third approach in detail, the technical basis and experimental validation for the approach, and the resulting reactor performance that can be achieved for ATWS events.

  5. 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).

  6. 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,...

  7. 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,...

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

    E-Print Network [OSTI]

    Fabrikant, J.I.

    2010-01-01T23:59:59.000Z

    occurred during the nuclear accident, and probably noHEALTH EFFECTS OF THE NUCLEAR ACCIDENT AT MILE ISLAND JacobENG-48 HEALTH EFFECTS OF THE NUCLEAR ACCIDENT A T THREE MILE

  9. 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,

  10. 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...

  11. Environmental Conditions Environmental Conditions

    E-Print Network [OSTI]

    Environmental Conditions Environmental Conditions Appendix II The unique geology, hydrology and instream habitat. This chapter examines how environmental conditions in the Deschutes watershed affect, the discussion characterizes the environmental conditions within three watershed areas: the Lower Deschutes

  12. 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

  13. 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.

  14. 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.

  15. 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,...

  16. 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...

  17. 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 -...

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

    Office of Environmental Management (EM)

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

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

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

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

  20. 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

  1. 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...

  2. 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,...

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

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

    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...

  4. 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...

  5. Overview of the U.S. DOE Accident Tolerant Fuel Development Program

    SciTech Connect (OSTI)

    Jon Carmack; Frank Goldner; Shannon M. Bragg-Sitton; Lance L. Snead

    2013-09-01T23:59:59.000Z

    The United States Fuel Cycle Research and Development Advanced Fuels Campaign has been given the responsibility to conduct research and development on enhanced accident tolerant fuels with the goal of performing a lead test assembly or lead test rod irradiation in a commercial reactor by 2022. The Advanced Fuels Campaign has defined fuels with enhanced accident tolerance as those that, in comparison with the standard UO2-Zircaloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations and operational transients, as well as design-basis and beyond design-basis events. This paper provides an overview of the FCRD Accident Tolerant Fuel program. The ATF attributes will be presented and discussed. Attributes identified as potentially important to enhance accident tolerance include reduced hydrogen generation (resulting from cladding oxidation), enhanced fission product retention under severe accident conditions, reduced cladding reaction with high-temperature steam, and improved fuel-cladding interaction for enhanced performance under extreme conditions. To demonstrate the enhanced accident tolerance of candidate fuel designs, metrics must be developed and evaluated using a combination of design features for a given LWR design, potential improvements to that design, and the design of an advanced fuel/cladding system. The aforementioned attributes provide qualitative guidance for parameters that will be considered for fuels with enhanced accident tolerance. It may be unnecessary to improve in all attributes and it is likely that some attributes or combination of attributes provide meaningful gains in accident tolerance, while others may provide only marginal benefits. Thus, an initial step in program implementation will be the development of quantitative metrics. A companion paper in these proceedings provides an update on the status of establishing these quantitative metrics for accident tolerant LWR fuel.1 The United States FCRD Advanced Fuels Campaign has embarked on an aggressive schedule for development of enhanced accident tolerant LWR fuels. The goal of developing such a fuel system that can be deployed in the U.S. LWR fleet in the next 10 to 20 years supports the sustainability of clean nuclear power generation in the United States.

  6. 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

  7. Markov Model of Severe Accident Progression and Management

    SciTech Connect (OSTI)

    Bari, R.A.; Cheng, L.; Cuadra,A.; Ginsberg,T.; Lehner,J.; Martinez-Guridi,G.; Mubayi,V.; Pratt,W.T.; Yue, M.

    2012-06-25T23:59:59.000Z

    The earthquake and tsunami that hit the nuclear power plants at the Fukushima Daiichi site in March 2011 led to extensive fuel damage, including possible fuel melting, slumping, and relocation at the affected reactors. A so-called feed-and-bleed mode of reactor cooling was initially established to remove decay heat. The plan was to eventually switch over to a recirculation cooling system. Failure of feed and bleed was a possibility during the interim period. Furthermore, even if recirculation was established, there was a possibility of its subsequent failure. Decay heat has to be sufficiently removed to prevent further core degradation. To understand the possible evolution of the accident conditions and to have a tool for potential future hypothetical evaluations of accidents at other nuclear facilities, a Markov model of the state of the reactors was constructed in the immediate aftermath of the accident and was executed under different assumptions of potential future challenges. This work was performed at the request of the U.S. Department of Energy to explore 'what-if' scenarios in the immediate aftermath of the accident. The work began in mid-March and continued until mid-May 2011. The analysis had the following goals: (1) To provide an overall framework for describing possible future states of the damaged reactors; (2) To permit an impact analysis of 'what-if' scenarios that could lead to more severe outcomes; (3) To determine approximate probabilities of alternative end-states under various assumptions about failure and repair times of cooling systems; (4) To infer the reliability requirements of closed loop cooling systems needed to achieve stable core end-states and (5) To establish the importance for the results of the various cooling system and physical phenomenological parameters via sensitivity calculations.

  8. TMI-2 - A Case Study for PWR Instrumentation Performance during a Severe Accident

    SciTech Connect (OSTI)

    Joy L. Rempe; Darrell L. Knudson

    2014-05-01T23:59:59.000Z

    The accident at the Three Mile Island Unit 2 (TMI-2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focussed upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations. Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this report. For each sensor, a description is provided with the measured data and conclusions related to the sensor’s survivability, and the basis for conclusions about its survivability. As noted within this document, several techniques were invoked in the TMI-2 post-accident evaluation program to assess sensor status, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this document provides recommendations related to the sensor survivability and data evaluation process that could be implemented in upcoming Fukushima Daiichi recovery efforts.

  9. TMI-2 - A Case Study for PWR Instrumentation Performance during a Severe Accident

    SciTech Connect (OSTI)

    Joy L. Rempe; Darrell L. Knudson

    2013-03-01T23:59:59.000Z

    The accident at the Three Mile Island Unit 2 (TMI-2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focussed upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations. Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this report. For each sensor, a description is provided with the measured data and conclusions related to the sensor’s survivability, and the basis for conclusions about its survivability. As noted within this document, several techniques were invoked in the TMI-2 post-accident evaluation program to assess sensor status, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this document provides recommendations related to the sensor survivability and data evaluation process that could be implemented in upcoming Fukushima Daiichi recovery efforts.

  10. Site restoration: Estimation of attributable costs from plutonium-dispersal accidents

    SciTech Connect (OSTI)

    Chanin, D.I.; Murfin, W.B. [Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States)

    1996-05-01T23:59:59.000Z

    A nuclear weapons accident is an extremely unlikely event due to the extensive care taken in operations. However, under some hypothetical accident conditions, plutonium might be dispersed to the environment. This would result in costs being incurred by the government to remediate the site and compensate for losses. This study is a multi-disciplinary evaluation of the potential scope of the post-accident response that includes technical factors, current and proposed legal requirements and constraints, as well as social/political factors that could influence decision making. The study provides parameters that can be used to assess economic costs for accidents postulated to occur in urban areas, Midwest farmland, Western rangeland, and forest. Per-area remediation costs have been estimated, using industry-standard methods, for both expedited and extended remediation. Expedited remediation costs have been evaluated for highways, airports, and urban areas. Extended remediation costs have been evaluated for all land uses except highways and airports. The inclusion of cost estimates in risk assessments, together with the conventional estimation of doses and health effects, allows a fuller understanding of the post-accident environment. The insights obtained can be used to minimize economic risks by evaluation of operational and design alternatives, and through development of improved capabilities for accident response.

  11. A highway accident involving unirradiated nuclear fuel in Springfield, Massachusetts, on December 16, 1991

    SciTech Connect (OSTI)

    Carlson, R.W.; Fischer, L.E. [Lawrence Livermore National Lab., CA (United States)

    1992-06-01T23:59:59.000Z

    In the early morning of Dec. 16, 1991, a severe accident occurred when a passenger vehicle traveling in the wrong direction collided with a tractor trailer carrying 24 unirradiated nuclear fuel assemblies in 12 containers on Interstate I-91 in Springfield, Massachusetts. The purpose of this report is to document the mechanical circumstances of the severe accident, confirm the nature and quantity of the radioactive materials involved, and assess the physical environment to which the containers were exposed and the response of the containers and their contents. The report consists of five major sections. The first section describes the circumstances and conditions of the accident and the finding of facts. The second describes the containers, the unirradiated nuclear fuel assemblies, and the tie down arrangement used for the trailer. The third describes the damage sustained during the accident to the tractor, trailer, containers, and unirradiated nuclear fuel assemblies. The fourth evaluates the accident environment and its effects on the containers and their contents. The final section gives conclusions derived from the analysis and fact finding investigation. During this severe accident, only minor injuries occurred, and at no time was the public health and safety at risk.

  12. 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

  13. 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

  14. 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

  15. 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

  16. MELCOR accident analysis for ARIES-ACT

    E-Print Network [OSTI]

    California at San Diego, University of

    MELCOR 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

  17. 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.

  18. An Investigation of the Therac-25 Accidents

    E-Print Network [OSTI]

    Yang, Junfeng

    commission investigation of the Three Mile Island incident). The Therac-25 accidents are the most serious of the Therac-25 prob- lems have been oversimplified, with misleading omissions. In an effort to remedy this, we

  19. Chernobyl accident: A comprehensive risk assessment

    SciTech Connect (OSTI)

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

    1999-11-01T23:59:59.000Z

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

  20. Chernobyl accident: A comprehensive risk assessment

    SciTech Connect (OSTI)

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

    1999-01-01T23:59:59.000Z

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

  1. 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. ...

  2. Three Mile Island accident and post-accident recovery: what did we learn

    SciTech Connect (OSTI)

    Collins, E.D.

    1982-01-01T23:59:59.000Z

    A description of the accident at Three Mile Island-2 reactor is presented. Activities related to the cleanup and decontamination of the reactor are described.

  3. 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

  4. 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

  5. LOCA with consequential or delayed LOOP accidents: Unique issues, plant vulnerability, and CDF contributions

    SciTech Connect (OSTI)

    Martinez-Guridi, G.; Samanta, P.; Chu, L.; Yang, J.

    1998-08-01T23:59:59.000Z

    A loss-of-coolant accident (LOCA) can cause a loss-of-offsite power (LOOP) wherein the LOOP is usually delayed by few seconds or longer. Such an accident is called LOCA with consequential LOOP, or LOCA with delayed LOOP (here, abbreviated as LOCA/LOOP). This paper analyzes the unique conditions that are associated with a LOCA/LOOP, presents a model, and quantifies its contribution to core damage frequency (CDF). The results show that the CDF contribution can be a dominant contributor to risk for certain plant designs, although boiling water reactors (BWRs) are less vulnerable than pressurized water reactors (PWRs).

  6. E-Print Network 3.0 - accident experience alarm Sample Search...

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

    , accident investigation, indoor air quality, bloodborne pathogens, chemical safety, lockout-tagout, hot work... Campus Fires 11 12 Accident Reporting 14 Employee Accidents 15...

  7. E-Print Network 3.0 - accident frequencies program Sample Search...

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

    of the fatal accidents and many other accidents. Training, defined work procedures, lockout tagout programs... Accident Research Helps Save Lives of Loggers Research Brief ...

  8. E-Print Network 3.0 - accident management procedures Sample Search...

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

    of the fatal accidents and many other accidents. Training, defined work procedures, lockout tagout programs... Accident Research Helps Save Lives of Loggers Research Brief ...

  9. E-Print Network 3.0 - accident management program Sample Search...

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

    of the fatal accidents and many other accidents. Training, defined work procedures, lockout tagout programs... Accident Research Helps Save Lives of Loggers Research Brief ...

  10. E-Print Network 3.0 - accident investigation sites Sample Search...

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

    Chemistry ; Biology and Medicine 6 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: accidents that occur...

  11. E-Print Network 3.0 - accident excursion occurring Sample Search...

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

    University Collection: Geosciences 4 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: accidents that occur...

  12. E-Print Network 3.0 - accident location analysis Sample Search...

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

    Conversion and Utilization ; Engineering 8 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: of the accident...

  13. E-Print Network 3.0 - accident survival time Sample Search Results

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

    Technologies and Information Sciences 3 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: of the accident...

  14. 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

  15. 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

  16. 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

  17. Superheated-steam test of ethylene propylene rubber cables using a simultaneous aging and accident environment

    SciTech Connect (OSTI)

    Bennett, P.R.; St. Clair, S.D.; Gilmore, T.W.

    1986-06-01T23:59:59.000Z

    The superheated-steam test exposed different ethylene propylene rubber (EPR) cables and insulation specimens to simultaneous aging and a 21-day simultaneous accident environment. In addition, some insulation specimens were exposed to five different aging conditions prior to the 21-day simultaneous accident simulation. The purpose of this superheated-steam test (a follow-on to the saturated-steam tests (NUREG/CR-3538)) was to: (1) examine electrical degradation of different configurations of EPR cables; (2) investigate differences between using superheated-steam or saturated-steam at the start of an accident simulation; (3) determine whether the aging technique used in the saturated-steam test induced artificial degradation; and (4) identify the constituents in EPR that affect moisture absorption.

  18. Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling

    E-Print Network [OSTI]

    Hend Mohammed El Sayed Saad; Hesham Mohammed Mohammed Mansour; Moustafa Aziz Abd El Wahab

    2013-06-05T23:59:59.000Z

    Understanding of the time-dependent behavior of the neutron population in nuclear reactor in response to either a planned or unplanned change in the reactor conditions, is a great importance to the safe and reliable operation of the reactor. In the present work, the point kinetics equations are solved numerically using stiffness confinement method (SCM). The solution is applied to the kinetics equations in the presence of different types of reactivities and is compared with different analytical solutions. This method is also used to analyze reactivity induced accidents in two reactors. The first reactor is fueled by uranium and the second is fueled by plutonium. This analysis presents the effect of negative temperature feedback with the addition positive reactivity of control rods to overcome the occurrence of control rod ejection accident and damaging of the reactor. Both power and temperature pulse following the reactivity- initiated accidents are calculated. The results are compared with previous works and satisfactory agreement is found.

  19. Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling

    E-Print Network [OSTI]

    Saad, Hend Mohammed El Sayed; Wahab, Moustafa Aziz Abd El

    2013-01-01T23:59:59.000Z

    Understanding of the time-dependent behavior of the neutron population in nuclear reactor in response to either a planned or unplanned change in the reactor conditions, is a great importance to the safe and reliable operation of the reactor. In the present work, the point kinetics equations are solved numerically using stiffness confinement method (SCM). The solution is applied to the kinetics equations in the presence of different types of reactivities and is compared with different analytical solutions. This method is also used to analyze reactivity induced accidents in two reactors. The first reactor is fueled by uranium and the second is fueled by plutonium. This analysis presents the effect of negative temperature feedback with the addition positive reactivity of control rods to overcome the occurrence of control rod ejection accident and damaging of the reactor. Both power and temperature pulse following the reactivity- initiated accidents are calculated. The results are compared with previous works and...

  20. 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.

  1. Structural aspects of the Chernobyl accident

    SciTech Connect (OSTI)

    Murray, R.C.; Cummings, G.E.

    1988-09-02T23:59:59.000Z

    On April 26, 1986 the world's worst nuclear power plant accident occurred at the Unit 4 of the Chernobyl Nuclear Power Station in the USSR. This paper presents a discussion of the design of the Chernobyl Power Plant, the sequence of events that led to the accident and the damage caused by the resulting explosion. The structural design features that contributed to the accident and resulting damage will be highlighted. Photographs and sketches obtained from various worldwide news agencies will be shown to try and gain a perspective of the extent of the damage. The aftermath, clean-up, and current situation will be discussed and the important lessons learned for the structural engineer will be presented. 15 refs., 10 figs.

  2. 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.

  3. WASTE-ACC: A computer model for analysis of waste management accidents

    SciTech Connect (OSTI)

    Nabelssi, B.K.; Folga, S.; Kohout, E.J.; Mueller, C.J.; Roglans-Ribas, J.

    1996-12-01T23:59:59.000Z

    In support of the U.S. Department of Energy`s (DOE`s) Waste Management Programmatic Environmental Impact Statement, Argonne National Laboratory has developed WASTE-ACC, a computational framework and integrated PC-based database system, to assess atmospheric releases from facility accidents. WASTE-ACC facilitates the many calculations for the accident analyses necessitated by the numerous combinations of waste types, waste management process technologies, facility locations, and site consolidation strategies in the waste management alternatives across the DOE complex. WASTE-ACC is a comprehensive tool that can effectively test future DOE waste management alternatives and assumptions. The computational framework can access several relational databases to calculate atmospheric releases. The databases contain throughput volumes, waste profiles, treatment process parameters, and accident data such as frequencies of initiators, conditional probabilities of subsequent events, and source term release parameters of the various waste forms under accident stresses. This report describes the computational framework and supporting databases used to conduct accident analyses and to develop source terms to assess potential health impacts that may affect on-site workers and off-site members of the public under various DOE waste management alternatives.

  4. Lessons learned from early criticality accidents

    SciTech Connect (OSTI)

    Malenfant, R.E.

    1996-06-01T23:59:59.000Z

    Four accidents involving the approach to criticality occurred during the period July, 1945, through May, 1996. These have been described in the format of the OPERATING EXPERIENCE WEEKLY SUMMARY which is distributed by the Office of Nuclear and Facility Safety. Although the lessons learned have been incorporated in standards, codes, and formal procedures during the last fifty years, this is their first presentation in this format. It is particularly appropriate that they be presented in the forum of the Nuclear Criticality Technology Safety Project Workshop closest to the fiftieth anniversary of the last of the four accidents, and that which was most instrumental in demonstrating the need to incorporate lessons learned.

  5. 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.

  6. Assessment of ICARE/CATHARE V1 Severe Accident Code

    SciTech Connect (OSTI)

    Chatelard, Patrick; Fleurot, Joelle; Marchand, Olivier; Drai, Patrick [IRSN, 31, avenue de la Division Leclerc, BP 17 - 92262 Fontenay-aux-Roses Cedex (France)

    2006-07-01T23:59:59.000Z

    The ICARE/CATHARE code system has been developed by the French 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) in the last decade for the detailed evaluation of Severe Accident (SA) consequences in a primary system. It is composed of the coupling of the core degradation IRSN code ICARE2 and of the thermal-hydraulics French code CATHARE2. It has been extensively used to support the level 2 Probabilistic Safety Assessment (PSA-2) of the 900 MWe PWR. This paper presents the synthesis of the ICARE/CATHARE V1 assessment which was conducted in the frame of the 'International ICARE/CATHARE Users' Club', under the management of IRSN. The ICARE/CATHARE V1 validation matrix is composed of more than 60 experiments, distributed in few thermal-hydraulics non-regression tests (to handle the front end phase of a severe accident), numerous Separate-Effect Tests, about 30 Integral Tests covering both the early and the late degradation phases, as well as a 'circuit' experiment including hydraulics loops. Finally, the simulation of the TMI-2 accident was also added to assess the code against real conditions. This validation task was aimed at assessing the ICARE/CATHARE V1 capabilities (including the stand-alone ICARE2 V3mod1 version) and also at proposing recommendations for an optimal use of this version ('Users' Guidelines'). Thus, with a correct account for the recommended guidelines, it appeared that the last ICARE/CATHARE V1 version could be reasonably used to perform best-estimate reactor studies up to a large corium slumping into the lower head. (authors)

  7. Markov Model of Accident Progression at Fukushima Daiichi

    SciTech Connect (OSTI)

    Cuadra A.; Bari R.; Cheng, L-Y; Ginsberg, T.; Lehner, J.; Martinez-Guridi, G.; Mubayi, V.; Pratt, T.; Yue, M.

    2012-11-11T23:59:59.000Z

    On March 11, 2011, a magnitude 9.0 earthquake followed by a tsunami caused loss of offsite power and disabled the emergency diesel generators, leading to a prolonged station blackout at the Fukushima Daiichi site. After successful reactor trip for all operating reactors, the inability to remove decay heat over an extended period led to boil-off of the water inventory and fuel uncovery in Units 1-3. A significant amount of metal-water reaction occurred, as evidenced by the quantities of hydrogen generated that led to hydrogen explosions in the auxiliary buildings of the Units 1 & 3, and in the de-fuelled Unit 4. Although it was assumed that extensive fuel damage, including fuel melting, slumping, and relocation was likely to have occurred in the core of the affected reactors, the status of the fuel, vessel, and drywell was uncertain. To understand the possible evolution of the accident conditions at Fukushima Daiichi, a Markov model of the likely state of one of the reactors was constructed and executed under different assumptions regarding system performance and reliability. The Markov approach was selected for several reasons: It is a probabilistic model that provides flexibility in scenario construction and incorporates time dependence of different model states. It also readily allows for sensitivity and uncertainty analyses of different failure and repair rates of cooling systems. While the analysis was motivated by a need to gain insight on the course of events for the damaged units at Fukushima Daiichi, the work reported here provides a more general analytical basis for studying and evaluating severe accident evolution over extended periods of time. This work was performed at the request of the U.S. Department of Energy to explore 'what-if' scenarios in the immediate aftermath of the accidents.

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

    E-Print Network [OSTI]

    McKemie, Martha Susan

    1979-01-01T23:59:59.000Z

    , in the final analysis, will make the greatest use of such research. Traffic Research Time Frame Requirements The largest statistical problem in using accident and violation conviction data is the fact that accidents are rare events, (O'Neall 1967). She... assumed to have resulted from the crash and are not included. TABLE 2 Distribution of Student Crashes Vs. Driving Convictions* Number of Accidents 1 2 2 O I M M g M M A 4109 (85. 4%) 1578 (79. 3X) 555 (72. 6%) 224 (71. 6%) 155 (63. 5...

  9. 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...

  10. E-Print Network 3.0 - accidents retroperspektive individuelle...

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

    de Montral Collection: Engineering 11 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  11. E-Print Network 3.0 - accident soderzhanie korotkozhivushchikh...

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

    Page: << < 1 2 3 4 5 > >> 1 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

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

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

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

  13. Technical evaluation: 300 Area steam line valve accident

    SciTech Connect (OSTI)

    Not Available

    1993-08-01T23:59:59.000Z

    On June 7, 1993, a journeyman power operator (JPO) was severely burned and later died as a result of the failure of a 6-in. valve that occurred when he attempted to open main steam supply (MSS) valve MSS-25 in the U-3 valve pit. The pit is located northwest of Building 331 in the 300 Area of the Hanford Site. Figure 1-1 shows a layout of the 300 Area steam piping system including the U-3 steam valve pit. Figure 1-2 shows a cutaway view of the approximately 10- by 13- by 16-ft-high valve pit with its various steam valves and connecting piping. Valve MSS-25, an 8-in. valve, is located at the bottom of the pit. The failed 6-in. valve was located at the top of the pit where it branched from the upper portion of the 8-in. line at the 8- by 8- by 6-in. tee and was then ``blanked off`` with a blind flange. The purpose of this technical evaluation was to determine the cause of the accident that led to the failure of the 6-in. valve. The probable cause for the 6-in. valve failure was determined by visual, nondestructive, and destructive examination of the failed valve and by metallurgical analysis of the fractured region of the valve. The cause of the accident was ultimately identified by correlating the observed failure mode to the most probable physical phenomenon. Thermal-hydraulic analyses, component stress analyses, and tests were performed to verify that the probable physical phenomenon could be reasonably expected to produce the failure in the valve that was observed.

  14. 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. Commentaires finaux. ´Ecole Polytechnique de Montr´eal, 18 mars 2011 L'accident `a la centrale nucl´eaire de

  15. Advanced sodium fast reactor accident source terms : research needs.

    SciTech Connect (OSTI)

    Powers, Dana Auburn; Clement, Bernard [IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France; Denning, Richard [Ohio State University, Columbus, OH; Ohno, Shuji [Japan Atomic Energy Agency, Ibaraki, Japan; Zeyen, Roland [Institute for Energy Petten, Saint-Paul-lez-Durance, France

    2010-09-01T23:59:59.000Z

    An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic eventEnergetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolantEntrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached claddingRates of radionuclide leaching from fuel by liquid sodiumSurface enrichment of sodium pools by dissolved and suspended radionuclidesThermal decomposition of sodium iodide in the containment atmosphereReactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model of radionuclide release progressed.

  16. Novel Accident-Tolerant Fuel Meat and Cladding

    SciTech Connect (OSTI)

    Robert D. Mariani; Pavel G Medvedev; Douglas L Porter; Steven L Hayes; James I. Cole; Xian-Ming Bai

    2013-09-01T23:59:59.000Z

    A novel accident-tolerant fuel meat and cladding are here proposed. The fuel meat design incorporates annular fuel with inserts and discs that are fabricated from a material having high thermal conductivity, for example niobium. The inserts are rods or tubes. Discs separate the fuel pellets. Using the BISON fuel performance code it was found that the peak fuel temperature can be lowered by more than 600 degrees C for one set of conditions with niobium metal as the thermal conductor. In addition to improved safety margin, several advantages are expected from the lower temperature such as decreased fission gas release and fuel cracking. Advantages and disadvantages are discussed. An enrichment of only 7.5% fully compensates the lost reactivity of the displaced UO2. Slightly higher enrichments, such as 9%, allow uprates and increased burnups to offset the initial costs for retooling. The design has applications for fast reactors and transuranic burning, which may accelerate its development. A zirconium silicide coating is also described for accident tolerant applications. A self-limiting degradation behavior for this coating is expected to produce a glassy, self-healing layer that becomes more protective at elevated temperature, with some similarities to MoSi2 and other silicides. Both the fuel and coating may benefit from the existing technology infrastructure and the associated wide expertise for a more rapid development in comparison to other, more novel fuels and cladding.

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. COMPARING THE IDENTIFICATION OF RECOMMENDATIONS BY DIFFERENT ACCIDENT

    E-Print Network [OSTI]

    Johnson, Chris

    1 COMPARING THE IDENTIFICATION OF RECOMMENDATIONS BY DIFFERENT ACCIDENT INVESTIGATORS USING Langley Research Center ,100 NASA Road / Mail Stop 130, Hampton VA 23681-2199 USA. Keywords: Accident Investigation, SOL, Root Cause Analysis. Abstract Accident reports play a key role in the safety of complex

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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 ],

  9. Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010

    SciTech Connect (OSTI)

    Hickman, D P; Wysong, A R; Heinrichs, D P; Wong, C T; Merritt, M J; Topper, J D; Gressmann, F A; Madden, D J

    2011-06-21T23:59:59.000Z

    The Lawrence Livermore National Laboratory uses neutron activation elements in a Panasonic TLD holder as a personnel nuclear accident dosimeter (PNAD). The LLNL PNAD has periodically been tested using a Cf-252 neutron source, however until 2009, it was more than 25 years since the PNAD has been tested against a source of neutrons that arise from a reactor generated neutron spectrum that simulates a criticality. In October 2009, LLNL participated in an intercomparison of nuclear accident dosimeters at the CEA Valduc Silene reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison of nuclear accident dosimeters at CEA Valduc. The reactor generated neutron irradiations for the 2010 exercise were performed at the Caliban reactor. The Caliban results are described in this report. The procedure for measuring the nuclear accident dosimeters in the event of an accident has a solid foundation based on many experimental results and comparisons. The entire process, from receiving the activated NADs to collecting and storing them after counting was executed successfully in a field based operation. Under normal conditions at LLNL, detectors are ready and available 24/7 to perform the necessary measurement of nuclear accident components. Likewise LLNL maintains processing laboratories that are separated from the areas where measurements occur, but contained within the same facility for easy movement from processing area to measurement area. In the event of a loss of LLNL permanent facilities, the Caliban and previous Silene exercises have demonstrated that LLNL can establish field operations that will very good nuclear accident dosimetry results. There are still several aspects of LLNL's nuclear accident dosimetry program that have not been tested or confirmed. For instance, LLNL's method for using of biological samples (blood and hair) has not been verified since the method was first developed in the 1980's. Because LLNL and the other DOE participants were limited in what they were allowed to do at the Caliban and Silene exercises and testing of various elements of the nuclear accident dosimetry programs cannot always be performed as guests at other sites, it has become evident that DOE needs its own capability to test nuclear accident dosimeters. Angular dependence determination and correction factors for NADs desperately need testing as well as more evaluation regarding the correct determination of gamma doses. It will be critical to properly design any testing facility so that the necessary experiments can be performed by DOE laboratories as well as guest laboratories. Alternate methods of dose assessment such as using various metals commonly found in pockets and clothing have yet to be evaluated. The DOE is planning to utilize the Godiva or Flattop reactor for testing nuclear accident dosimeters. LLNL has been assigned the primary operational authority for such testing. Proper testing of nuclear accident dosimeters will require highly specific characterization of the pulse fields. Just as important as the characterization of the pulsed fields will be the design of facilities used to process the NADs. Appropriate facilities will be needed to allow for early access to dosimeters to test and develop quick sorting techniques. These facilities will need appropriate laboratory preparation space and an area for measurements. Finally, such a facility will allow greater numbers of LLNL and DOE laboratory personnel to train on the processing and interpretation of nuclear accident dosimeters and results. Until this facility is fully operational for test purposes, DOE laboratories may need to continue periodic testing as guests of other reactor facilities such as Silene and Caliban.

  10. Retrospection of Chernobyl nuclear accident for decision analysis concerning remedial actions in Ukraine

    SciTech Connect (OSTI)

    Georgievskiy, Vladimir [Russian Research Center 'Kurchatov Insitute', Kurchatov Sq., 1, 123182 Moscow (Russian Federation)

    2007-07-01T23:59:59.000Z

    It is considered the efficacy of decisions concerning remedial actions when of-site radiological monitoring in the early and (or) in the intermediate phases was absent or was not informative. There are examples of such situations in the former Soviet Union where many people have been exposed: releases of radioactive materials from 'Krasnoyarsk-26' into Enisey River, releases of radioactive materials from 'Chelabinsk-65' (the Kishtim accident), nuclear tests at the Semipalatinsk Test Site, the Chernobyl nuclear accident etc. If monitoring in the early and (or) in the intermediate phases is absent the decisions concerning remedial actions are usually developed on the base of permanent monitoring. However decisions of this kind may be essentially erroneous. For these cases it is proposed to make retrospection of radiological data of the early and intermediate phases of nuclear accident and to project decisions concerning remedial actions on the base of both retrospective data and permanent monitoring data. In this Report the indicated problem is considered by the example of the Chernobyl accident for Ukraine. Their of-site radiological monitoring in the early and intermediate phases was unsatisfactory. In particular, the pasture-cow-milk monitoring had not been made. All official decisions concerning dose estimations had been made on the base of measurements of {sup 137}Cs in body (40 measurements in 135 days and 55 measurements in 229 days after the Chernobyl accident). For the retrospection of radiological data of the Chernobyl accident dynamic model has been developed. This model has structure similar to the structure of Pathway model and Farmland model. Parameters of the developed model have been identified for agricultural conditions of Russia and Ukraine. By means of this model dynamics of 20 radionuclides in pathways and dynamics of doses have been estimated for the early, intermediate and late phases of the Chernobyl accident. The main results are following: - During the first year after the Chernobyl accident 75-93% of Commitment Effective Dose had been formed; - During the first year after the Chernobyl accident 85-90% of damage from radiation exposure had been formed. During the next 50 years (the late phase of accident) only 10-15% of damage from radiation exposure will have been formed; - Remedial actions (agricultural remedial actions as most effective) in Ukraine are intended for reduction of the damage from consumption of production which is contaminated in the late phase of accident. I.e. agricultural remedial actions have been intended for minimization only 10 % of the total damage from radiation exposure; - Medical countermeasures can minimize radiation exposure damage by an order of magnitude greater than agricultural countermeasures. - Thus, retrospection of nuclear accident has essentially changed type of remedial actions and has given a chance to increase effectiveness of spending by an order of magnitude. This example illustrates that in order to optimize remedial actions it is required to use data of retrospection of nuclear accidents in all cases when monitoring in the early and (or) intermediate phases is unsatisfactory. (author)

  11. 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.

  12. 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

  13. 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

  14. Precursors to potential severe core damage accidents, 1986: A status report: Main report and Appendixes A,B, and C

    SciTech Connect (OSTI)

    Minarick, J W; Harris, J D; Austin, P N; Cletcher, J W; Hagen, E W

    1988-05-01T23:59:59.000Z

    The Accident Sequence Precursor Program reviews licensee event reports of operational events that have occurred at LWRs to identify and categorize precursors to potential severe core-damage accidents. Accident sequences considered in the study are those associated with inadequate core cooling. Accident sequence precursors are events that are important elements in such sequences. Such precursors could be infrequent initiating events or equipment failures that, when coupled with one or more postulated events, could result in a plant condition with inadequate core cooling. Originally proposed in the Risk Assessment Review Group Report (Lewis Committee report) in 1978, the study - subsequently named the Accident Sequence Precursor Program - was initiated at the Nuclear Operations Analysis Center in 1979. Earlier reports by the program involved assessment of events that occurred in 1969-1981 and 1984-1985. The present report involves the assessment of events that occurred during 1986. A nuclear plant has safety systems for mitigating the consequences of accidents or off-normal initiating events that may occur during the course of plant operation. These systems are built to high-quality standards and are redundant; nonetheless, they have a nonzero probability of failing or being in a failed state when required to operate. This report uses LERs and other plant data, estimated system unavailabilities, the expected average frequency of initiating events (LOFWs, LOOPs, LOCAs), and event details to evaluate the potential impact of the following two situations.

  15. Forward viewing OCT endomicroscopy

    E-Print Network [OSTI]

    Liang, Kaicheng

    2014-01-01T23:59:59.000Z

    A forward viewing fiber optic-based imaging probe device was designed and constructed for use with ultrahigh speed optical coherence tomography in the human gastrointestinal tract. The light source was a MEMS-VCSEL at 1300 ...

  16. 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.

  17. Coupled thermal analysis applied to the study of the rod ejection accident

    SciTech Connect (OSTI)

    Gonnet, M. [AREVA NP, TOUR AREVA - 1 Place Jean MILLIER, 92084 Paris La Defense Cedex (France)

    2012-07-01T23:59:59.000Z

    An advanced methodology for the assessment of fuel-rod thermal margins under RIA conditions has been developed by AREVA NP SAS. With the emergence of RIA analytical criteria, the study of the Rod Ejection Accident (REA) would normally require the analysis of each fuel rod, slice by slice, over the whole core. Up to now the strategy used to overcome this difficulty has been to perform separate analyses of sampled fuel pins with conservative hypotheses for thermal properties and boundary conditions. In the advanced methodology, the evaluation model for the Rod Ejection Accident (REA) integrates the node average fuel and coolant properties calculation for neutron feedback purpose as well as the peak fuel and coolant time-dependent properties for criteria checking. The calculation grid for peak fuel and coolant properties can be specified from the assembly pitch down to the cell pitch. The comparative analysis of methodologies shows that coupled methodology allows reducing excessive conservatism of the uncoupled approach. (authors)

  18. Viewing biology in action | EMSL

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

    Viewing biology in action Viewing biology in action DOE-funded pilot program will create mesoscale biological imaging platform James Evans EMSL received first-year funding of...

  19. Large break loss of coolant severe accident sequences at the HFIR (High Flux Isotope Reactor)

    SciTech Connect (OSTI)

    Simpson, D.B.; Greene, S.R.

    1990-01-01T23:59:59.000Z

    An assessment of many potential HFIR severe accident phenomena was conducted during the HFIR design effort, and many severe accident mitigating features were designed into the plant. These evaluation typically incorporated a bounding'' or highly conservative analysis approach and employed tools and techniques representative of the state of knowledge in the mid-1960s. Recently, programs to address severe accident issues were initiated at the Oak Ridge National Laboratory (ORNL) to support the HFIR probabilistic risk assessment (PRA) and equipment qualification and accident management studies. This paper presents the results of environment condition calculations conducted to evaluate a response of HFIR's heat exchanger cell environment to a double-ended rupture of a 0.25 m diameter coolant loop downstream of the circulating pump and check valve. The confinement calculations were performed using an atmospheric fission product source for the heat exchanger cell consistent with, but more conservative than that stipulated in Regulatory Guide 1.89. The results of the calculations indicate that the heat exchanger cell atmospheric temperature peaks at 377 K 225 seconds into the transient and then begins decreasing at approximately 1.7 K per minute. 8 refs., 5 figs.

  20. 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

    . The computer code RELAP5/MOD3 was used to model the BETHSY Integral Test Facility for a. small break loss of coolant accident. This transient simulates a 2 inch cold leg break without high pressure safety injection, following the conditions of International..., and general input to my gra, duate education. TABLE OF CONTENTS CHAPTER Page I INTRODUCTION I. 1 Need for Investigation I. 2 Computational Modeling . I. 3 Experimental Modeling I, 4 International Cooperation . 1 3 RELAP5 CODE DESCRIPTION II. 1...

  1. POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT.

    SciTech Connect (OSTI)

    DIAMOND,D.J.; BROMLEY,B.P.; ARONSON,A.L.

    2002-10-07T23:59:59.000Z

    The purpose of this study is to determine the effect of the initial power level during a rod ejection accident (REA) on the ejected rod worth and the resulting energy deposition in the fuel. The model used is for the hot zero power (HZP) conditions at the end of a typical fuel cycle for the Three Mile Island Unit 1 pressurized water reactor. PARCS, a transient, three-dimensional, two-group neutron nodal diffusion code, coupled with its own thermal-hydraulics model, is used to perform both steady-state and transient simulations. The worth of an ejected control rod is affected by both power level, and the positions of control banks. As the power level is increased, the worth of a single central control rod tends to drop due to thermal-hydraulic feedback and control bank removal, both of which flatten the radial neutron flux and power distributions. Although the peak fuel pellet enthalpy rise during an REA will be greater for a given ejected rod worth at elevated initial power levels, it is more likely the HZP condition will cause a greater net energy deposition because an ejected rod will have the highest worth at HZP. Thus, the HZP condition can be considered the most conservative in a safety evaluation.

  2. Reactivity initiated accident test series Test RIA 1-4

    SciTech Connect (OSTI)

    Martinson, Z.R.; El-Genk, M.S.; Fukuda, S.K.; LaPointe, R.E.; Osetek, D.J.

    1980-05-01T23:59:59.000Z

    The Reactivity Initiated Accident (RIA) Test RIA 1-4, the first 9-rod fuel rod bundle RIA Test to be performed at BWR hot startup conditions, was completed on April 16, 1980. The test was performed in the Power Burst Facility (PBF). Objective for Test RIA 1-4 was to provide information regarding loss-of-coolable fuel rod geometry following a RIA event for a peak fuel enthalpy equivalent to the present licensing criteria of 280 cal/g. The most severe RIA is the postulated Boiling Water Reactor (BWR) control rod drop during reactor startup. Therefore the test was conducted at BWR hot startup coolant conditions (538 K, 6.45 MPa, 0.8 1/sec). The test sequence began with steady power operation to condition the fuel, establish a short-lived fission product inventory, and calibrate the calorimetric measurements and core power chambers, neutron flux and gamma flux detectors. The test train was removed from the in-pile tube (IPT) to replace one of the fuel rods with a nominally identical irradiated rod and twelve flux wire monitors. A 2.8 ms period power burst was then performed. Coolant flow measurements were made before and after the power burst to characterize the flow blockage that occurred as a result of fuel rod failure.

  3. View dependent fluid dynamics

    E-Print Network [OSTI]

    Barran, Brian Arthur

    2006-08-16T23:59:59.000Z

    VIEW DEPENDENT FLUID DYNAMICS A Thesis by BRIAN ARTHUR BARRAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 2006 Major Subject: Visualization... Sciences VIEW DEPENDENT FLUID DYNAMICS A Thesis by BRIAN ARTHUR BARRAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved by: Chair of Committee, Donald...

  4. Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel, LP-gas and

    E-Print Network [OSTI]

    112 Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel and by keeping fuel storage facilities in top condition. Flammable Liquids and Gases Gasoline, diesel fuel, LP flammability and safety precautions. Do not keep gasoline inside the home or transport it in the trunks

  5. 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.

  6. Application of NUREG-1150 methods and results to accident management

    SciTech Connect (OSTI)

    Dingman, S.; Sype, T.; Camp, A.; Maloney, K.

    1990-01-01T23:59:59.000Z

    The use of NUREG-1150 and similar Probabilistic Risk Assessments in NRC and industry risk management programs is discussed. Risk management'' is more comprehensive than the commonly used term accident management.'' Accident management includes strategies to prevent vessel breach, mitigate radionuclide releases from the reactor coolant system, and mitigate radionuclide releases to the environment. Risk management also addresses prevention of accident initiators, prevention of core damage, and implementation of effective emergency response procedures. The methods and results produced in NUREG-1150 provide a framework within which current risk management strategies can be evaluated, and future risk management programs can be developed and assessed. Examples of the use of the NUREG-1150 framework for identifying and evaluating risk management options are presented. All phases of risk management are discussed, with particular attention given to the early phases of accidents. Plans and methods for evaluating accident management strategies that have been identified in the NRC accident management program are discussed. 2 refs., 3 figs.

  7. 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

  8. 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...

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

    Energy Savers [EERE]

    Subcontractor Radioactive Release During Transportation Activities on May 14, 2004, Bechtel Jacobs Company LLC, Oak Ridge, Tennessee (Amended) Type B Accident Investigation Board...

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

    Office of Environmental Management (EM)

    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,...

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

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

    Closure Hanford, LLC, Employee Fall Injury on July 1, 2009, At The 336 Building, Hanford Site, Washington Type B Accident Investigation Board Report on the September 4,...

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

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

    fell from a Toro Workman 3200 Utility Vehicle and fracturedhis right leg above the ankle. Type B Accident Investigation Board Report on the October 8, 2004, Grounds Worker...

  13. 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.

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

    Office of Environmental Management (EM)

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

  15. 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,...

  16. 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,...

  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 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...

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

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

    June 27, 2002, Exothermic Metal Reaction Event During Converter Disassembly in Building K-33 at the East Tennessee Technology Park Type B Accident Investigation on the June 27,...

  20. 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...

  1. 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...

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

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

    Investigation At Washington Closure Hanford, LLC, Employee Fall Injury on July 1, 2009, At The 336 Building, Hanford Site, Washington Type B Accident Investigation At Washington...

  3. 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...

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

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

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

  5. 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...

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

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

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

  7. 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...

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

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

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

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

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

    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...

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

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

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

  11. Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics

    SciTech Connect (OSTI)

    Brad Merrill; Melissa Teague; Robert Youngblood; Larry Ott; Kevin Robb; Michael Todosow; Chris Stanek; Mitchell Farmer; Michael Billone; Robert Montgomery; Nicholas Brown; Shannon Bragg-Sitton

    2014-02-01T23:59:59.000Z

    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. As a result, continual improvement of technology, including advanced materials and nuclear fuels, remains central to industry’s success. Decades of research combined with continual operation have produced steady advancements in technology and yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. In 2011, following the Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex, enhancing the accident tolerance of LWRs became a topic of serious discussion. As a result of direction from the U.S. Congress, the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) initiated an Accident Tolerant Fuel (ATF) Development program. The complex multiphysics behavior of LWR nuclear fuel makes defining specific material or design improvements difficult; as such, establishing qualitative attributes is critical to guide the design and development of fuels and cladding with enhanced accident tolerance. This report summarizes a common set of technical evaluation metrics to aid in the optimization and down selection of candidate designs. As used herein, “metrics” describe a set of technical bases by which multiple concepts can be fairly evaluated against a common baseline and against one another. Furthermore, this report describes a proposed technical evaluation methodology that can be applied to assess the ability of each concept to meet performance and safety goals relative to the current UO2 – zirconium alloy system and relative to one another. The resultant ranked evaluation can then inform concept down-selection, such that the most promising accident tolerant fuel design option(s) can continue to be developed for lead test rod or lead test assembly insertion into a commercial reactor within the desired timeframe (by 2022).

  12. Accident Response Group | National Nuclear Security Administration

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc Documentation RUCProductstwrmrAre the Effects ofAboutTest Facility VitalyGateAccessingAccident

  13. 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

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

    Broader source: Energy.gov [DOE]

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

  15. 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

  16. Stereoscopic optical viewing system

    DOE Patents [OSTI]

    Tallman, Clifford S. (Walnut Creek, CA)

    1987-01-01T23:59:59.000Z

    An improved optical system which provides the operator a stereoscopic viewing field and depth of vision, particularly suitable for use in various machines such as electron or laser beam welding and drilling machines. The system features two separate but independently controlled optical viewing assemblies from the eyepiece to a spot directly above the working surface. Each optical assembly comprises a combination of eye pieces, turning prisms, telephoto lenses for providing magnification, achromatic imaging relay lenses and final stage pentagonal turning prisms. Adjustment for variations in distance from the turning prisms to the workpiece, necessitated by varying part sizes and configurations and by the operator's visual accuity, is provided separately for each optical assembly by means of separate manual controls at the operator console or within easy reach of the operator.

  17. Stereoscopic optical viewing system

    DOE Patents [OSTI]

    Tallman, C.S.

    1986-05-02T23:59:59.000Z

    An improved optical system which provides the operator with a stereoscopic viewing field and depth of vision, particularly suitable for use in various machines such as electron or laser beam welding and drilling machines. The system features two separate but independently controlled optical viewing assemblies from the eyepiece to a spot directly above the working surface. Each optical assembly comprises a combination of eye pieces, turning prisms, telephoto lenses for providing magnification, achromatic imaging relay lenses and final stage pentagonal turning prisms. Adjustment for variations in distance from the turning prisms to the workpiece, necessitated by varying part sizes and configurations and by the operator's visual accuity, is provided separately for each optical assembly by means of separate manual controls at the operator console or within easy reach of the operator.

  18. 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.

  19. Preliminary Investigation of Candidate Materials for Use in Accident Resistant Fuel

    SciTech Connect (OSTI)

    Jason M. Harp; Paul A. Lessing; Blair H. Park; Jakeob Maupin

    2013-09-01T23:59:59.000Z

    As part of a Collaborative Research and Development Agreement (CRADA) with industry, Idaho National Laboratory (INL) is investigating several options for accident resistant uranium compounds including silicides, and nitrides for use in future light water reactor (LWR) fuels. This work is part of a larger effort to create accident tolerant fuel forms where changes to the fuel pellets, cladding, and cladding treatment are considered. The goal fuel form should have a resistance to water corrosion comparable to UO2, have an equal to or larger thermal conductivity than uranium dioxide, a melting temperature that allows the material to stay solid under power reactor conditions, and a uranium loading that maintains or improves current LWR power densities. During the course of this research, fuel fabricated at INL will be characterized, irradiated at the INL Advanced Test Reactor, and examined after irradiation at INL facilities to help inform industrial partners on candidate technologies.

  20. E-Print Network 3.0 - accident locations Sample Search Results

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

    locations Page: << < 1 2 3 4 5 > >> 1 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: of the accident...

  1. E-Print Network 3.0 - accidents Sample Search Results

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

    for: accidents Page: << < 1 2 3 4 5 > >> 1 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  2. E-Print Network 3.0 - accident site grissom Sample Search Results

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

    site grissom Page: << < 1 2 3 4 5 > >> 1 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: accidents that occur...

  3. E-Print Network 3.0 - accident reports Sample Search Results

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

    accident reports Page: << < 1 2 3 4 5 > >> 1 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  4. E-Print Network 3.0 - accident prone locations Sample Search...

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

    Energy Storage, Conversion and Utilization 9 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: of the accident...

  5. 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,...

  6. 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.

  7. 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.

  8. Road traffic accidents in Kathmandużan 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

  9. 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,

  10. 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

  11. 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

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

    E-Print Network [OSTI]

    Ferrari, Silvia

    ? 2 #12;The multiple risk situations Earthquake Tsunami Nuclear accident Energy shortage Energy priceThe 2011 Tohoku earthquake, tsunami, and Fukushima nuclear accident: the Risk Policy Aftermath of nuclear energy has blocked risk discussions and reasonable preparations. Electric companies Opponents

  13. 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.

  14. 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.

  15. 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...

  16. Risk factors for injury accidents among moped and motorcycle riders

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Risk factors for injury accidents among moped and motorcycle riders Aurélie Moskal a , Jean on the vehicle. Moped and motorcycle riders are analyzed separately, adjusting for the main characteristics of the accident. Results: for both moped and motorcycle riders, being male, not wearing a helmet, exceeding

  17. 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

  18. Berkeley Lab Accident Statistics Through January 31, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through January 31, 2009 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

  19. 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

  20. 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

  1. Berkeley Lab Accident Statistics Through February 28, 2009

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through February 28, 2009 These slides are updated on a monthly Goal DART Goal 1.17 #12;9 LBNL vs DOE Contractor Rates Berkeley Lab Site Accident Rates 5.70 4.95 3

  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. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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...

  12. 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

  13. E-Print Network 3.0 - accident fuel dispersion Sample Search...

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

    Summary: of the transportation system. We construct measures of each externality: noise, air pollution, accidents and congestion... pollution and accidents. For highway travel,...

  14. E-Print Network 3.0 - accident safety issues Sample Search Results

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

    , accident investigation, indoor air quality, bloodborne pathogens, chemical safety, lockout-tagout, hot work... Accidents 15 12;III. EH&S DEPARTMENTS AND PROGRAMS 16...

  15. Type A Accident Investigation Report of the June 25, 1997 Contract...

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

    Officer, Bonneville Power Administration, upon approval of the US Department of Energy (DOE), appointed a Type A Accident Investigation Board to investigate the accident in...

  16. E-Print Network 3.0 - accidents home Sample Search Results

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

    of Alaska Fairbanks AccidentIncident Report (personal injury) To report an automobile... accident, do not use this form, please go to: http:www.alaska.eduswrisk...

  17. E-Print Network 3.0 - accident diagrams Sample Search Results

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

    Sciences, University of Arkansas Collection: Environmental Sciences and Ecology 2 AUTOMOBILE ACCIDENT REPORT Department of Financial Services Summary: AUTOMOBILE ACCIDENT REPORT...

  18. E-Print Network 3.0 - accident issues differences Sample Search...

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

    Glasgow Collection: Computer Technologies and Information Sciences 4 September 2003 AUTOMOBILE ACCIDENTS Summary: September 2003 AUTOMOBILE ACCIDENTS UCLA STUDENT LEGAL SERVICES...

  19. E-Print Network 3.0 - accident declaration form Sample Search...

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

    of Strathclyde Collection: Mathematics 4 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: of Lethbridge Campus...

  20. E-Print Network 3.0 - accident additional information Sample...

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

    Biology and Medicine ; Environmental Sciences and Ecology 13 September 2003 AUTOMOBILE ACCIDENTS Summary: information with the other people involved in the accident. You...

  1. E-Print Network 3.0 - accidents occupational Sample Search Results

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

    Collection: Biology and Medicine 6 Exact Location : Date of Accident : AM PM Summary: SSN Cell Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date...

  2. E-Print Network 3.0 - accident causes Sample Search Results

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

    Warwick Collection: Engineering 3 Exact Location : Date of Accident : AM PM Summary: SSN Cell Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date...

  3. E-Print Network 3.0 - accident medical aspect Sample Search Results

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

    Collection: Mathematics 5 Exact Location : Date of Accident : AM PM Summary: SSN Cell Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date...

  4. E-Print Network 3.0 - accidents aviation Sample Search Results

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

    Engineering 3 A Historical Perspective on Aviation Accident Investigation C. W. Johnson Summary: A Historical Perspective on Aviation Accident Investigation C. W. Johnson C....

  5. E-Print Network 3.0 - accident sequences simulated Sample Search...

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

    Mathematics 3 A Technique for Showing Causal Arguments in Accident Reports C. W. Johnson; University of Glasgow; Glasgow, Scotland, UK Summary: for an accident report...

  6. E-Print Network 3.0 - accident analysis handbook Sample Search...

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

    Mathematics 3 A Technique for Showing Causal Arguments in Accident Reports C. W. Johnson; University of Glasgow; Glasgow, Scotland, UK Summary: relevant to the accident and...

  7. E-Print Network 3.0 - accident consequence model Sample Search...

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

    2 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: accidents in general; an increased understanding of the consequences of...

  8. E-Print Network 3.0 - accident consequences analysis Sample Search...

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

    3 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: accidents in general; an increased understanding of the consequences of...

  9. E-Print Network 3.0 - accident zone osobennosti Sample Search...

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

    Physics 2 A Technique for Showing Causal Arguments in Accident Reports C. W. Johnson; University of Glasgow; Glasgow, Scotland, UK Summary: and the work zone accident...

  10. E-Print Network 3.0 - aviation accidents findings Sample Search...

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

    Engineering 3 A Historical Perspective on Aviation Accident Investigation C. W. Johnson Summary: A Historical Perspective on Aviation Accident Investigation C. W. Johnson C....

  11. E-Print Network 3.0 - aircraft accident investigation Sample...

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

    ; Engineering 3 A Historical Perspective on Aviation Accident Investigation C. W. Johnson Summary: A Historical Perspective on Aviation Accident Investigation C. W. Johnson C....

  12. E-Print Network 3.0 - accident consequence analysis Sample Search...

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

    3 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: accidents in general; an increased understanding of the consequences of...

  13. E-Print Network 3.0 - accident research thermal Sample Search...

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

    1 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: , accident prevention, system safety Abstract System safety professionals,...

  14. E-Print Network 3.0 - accident lessons learned Sample Search...

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

    2 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: seek to learn from the results of accident investigations. We believe that...

  15. E-Print Network 3.0 - accident management center Sample Search...

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

    3 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: Why System Safety Professionals Should Read Accident Reports C. M....

  16. E-Print Network 3.0 - accident consequences elimination Sample...

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

    1 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: accidents in general; an increased understanding of the consequences of...

  17. E-Print Network 3.0 - aircraft accident victims Sample Search...

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

    The occasion... of accidents and disasters. The areas included were nuclear power plants, petrochemical plants, aircraft... accident as a case in point. Other systems that belonged...

  18. E-Print Network 3.0 - accident research priorities Sample Search...

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

    traffic accidents in Toxoplasma-infected military drivers... , for example, in a higher risk of traffic accidents in subjects with this life-long infection. Two recent......

  19. E-Print Network 3.0 - accident records Sample Search Results

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

    traffic accidents in Toxoplasma-infected military drivers... , for example, in a higher risk of traffic accidents in subjects with this life-long ... Source: Flegr, Jaroslav -...

  20. E-Print Network 3.0 - accidents industrial Sample Search Results

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

    Collection: Computer Technologies and Information Sciences 4 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: . Accidents on yard and industry tracks...

  1. E-Print Network 3.0 - accident risks methodology Sample Search...

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

    Energy Storage, Conversion and Utilization ; Engineering 6 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: ABSTRACT Train accident rates are a...

  2. E-Print Network 3.0 - accident consequence code Sample Search...

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

    and Technology Group Collection: Engineering ; Chemistry 2 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: train length and accident rate and...

  3. E-Print Network 3.0 - accidents analysis code Sample Search Results

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

    for: accidents analysis code Page: << < 1 2 3 4 5 > >> 1 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: a sensitivity analysis was conducted to...

  4. E-Print Network 3.0 - accident sequence analysis Sample Search...

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

    , Preliminary risk analysis (PRA), risk, potential accident, feared events, Automatic Train Control. I... , dangers and potential accidents respectively. At the beginning of the...

  5. E-Print Network 3.0 - accidents graves susceptibles Sample Search...

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

    BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: accidents than shorter trains. This is because longer trains are more susceptible to car... THE RELATIONSHIP BETWEEN...

  6. E-Print Network 3.0 - accident sequence evaluation Sample Search...

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

    (MIT) Collection: Engineering 48 Risk factors for injury accidents among moped and motorcycle riders Summary: are frequently available, contain information on the accident...

  7. E-Print Network 3.0 - accident severity Sample Search Results

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

    and Information Sciences 22 Risk factors for injury accidents among moped and motorcycle riders Summary: to their vulnerability, is the high risk of accident involvement,...

  8. E-Print Network 3.0 - accident consequence uncertainty Sample...

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

    Databases and Resources 56 Risk factors for injury accidents among moped and motorcycle riders Summary: Risk factors for injury accidents among moped and motorcycle riders...

  9. E-Print Network 3.0 - accident loca based Sample Search Results

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

    Collection: Fossil Fuels 34 Risk factors for injury accidents among moped and motorcycle riders Summary: -control study with accident responsibility as the event. 2....

  10. E-Print Network 3.0 - accident sequence analyses Sample Search...

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

    Collection: Mathematics 40 Risk factors for injury accidents among moped and motorcycle riders Summary: or Bulletins d'Analyse des Accidents corporels de la Circulation...

  11. E-Print Network 3.0 - accident exposure Sample Search Results

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

    Collection: Mathematics 12 Risk factors for injury accidents among moped and motorcycle riders Summary: they were responsible or not for the accident. In this way, we...

  12. 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.

  13. Multi-view kernel construction

    E-Print Network [OSTI]

    Sa, Virginia R.; Gallagher, Patrick W.; Lewis, Joshua M.; Malave, Vicente L.

    2010-01-01T23:59:59.000Z

    5157-z Multi-view kernel construction Virginia R. de Sa ·multiple different graph construction algorithms. The Ng et

  14. Protective laser beam viewing device

    DOE Patents [OSTI]

    Neil, George R.; Jordan, Kevin Carl

    2012-12-18T23:59:59.000Z

    A protective laser beam viewing system or device including a camera selectively sensitive to laser light wavelengths and a viewing screen receiving images from the laser sensitive camera. According to a preferred embodiment of the invention, the camera is worn on the head of the user or incorporated into a goggle-type viewing display so that it is always aimed at the area of viewing interest to the user and the viewing screen is incorporated into a video display worn as goggles over the eyes of the user.

  15. Accident Performance of Light Water Reactor Cladding Materials

    SciTech Connect (OSTI)

    Nelson, Andrew T. [Los Alamos National Laboratory

    2012-07-24T23:59:59.000Z

    During a loss of coolant accident as experienced at Fukushima, inadequate cooling of the reactor core forces component temperatures ever higher where they must withstand aggressive chemical environments. Conventional zirconium cladding alloys will readily oxidize in the presence of water vapor at elevated temperatures, rapidly degrading and likely failing. A cladding breach removes the critical barrier between actinides and fission products and the coolant, greatly increasing the probability of the release of radioactivity in the event of a containment failure. These factors have driven renewed international interest in both study and improvement of the materials used in commercial light water reactors. Characterization of a candidate cladding alloy or oxidation mitigation technique requires understanding of both the oxidation kinetics and hydrogen production as a function of temperature and atmosphere conditions. Researchers in the MST division supported by the DOE-NE Fuel Cycle Research and Development program are working to evaluate and quantify these parameters across a wide range of proposed cladding materials. The primary instrument employed is a simultaneous thermal analyzer (STA) equipped with a specialized water vapor furnace capable of maintaining temperatures above 1200 C in a range of atmospheres and water vapor contents. The STA utilizes thermogravimetric analysis and a coupled mass spectrometer to measure in situ oxidation and hydrogen production of candidate materials. This capability is unprecedented in study of materials under consideration for reactor cladding use, and is currently being expanded to investigate proposed coating techniques as well as the effect of coating defects on corrosion resistance.

  16. Post-accident inhalation exposure and experience with plutonium

    SciTech Connect (OSTI)

    Shinn, J

    1998-06-01T23:59:59.000Z

    This paper addresses the issue of inhalation exposure immediately afterward and for a long time following a nuclear accident. For the cases where either a nuclear weapon burns or explodes prior to nuclear fission, or at locations close to a nuclear reactor accident containing fission products, a major concern is the inhalation of aerosolized plutonium (Pu) particles producing alpha-radiation. We have conducted field studies of Pu- contaminated real and simulated accident sites at Bikini, Johnston Atoll, Tonopah (Nevada), Palomares (Spain), Chernobyl, and Maralinga (Australia).

  17. Ferritic Alloys as Accident Tolerant Fuel Cladding Material for Light Water Reactors

    SciTech Connect (OSTI)

    Rebak, Raul B. [General Electric] (ORCID:0000000280704475)

    2014-12-30T23:59:59.000Z

    The objective of the GE project is to demonstrate that advanced steels such as iron-chromium-aluminum (FeCrAl) alloys could be used as accident tolerant fuel cladding material in commercial light water reactors. The GE project does not include fuel development. Current findings support the concept that a FeCrAl alloy could be used for the cladding of commercial nuclear fuel. The use of this alloy will benefit the public since it is going to make the power generating light water reactors safer. In the Phase 1A of this cost shared project, GE (GRC + GNF) teamed with the University of Michigan, Los Alamos National Laboratory, Brookhaven National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory to study the environmental and mechanical behavior of more than eight candidate cladding material both under normal operation conditions of commercial nuclear reactors and under accident conditions in superheated steam (loss of coolant condition). The main findings are as follows: (1) Under normal operation conditions the candidate alloys (e.g. APMT, Alloy 33) showed excellent resistance to general corrosion, shadow corrosion and to environmentally assisted cracking. APMT also showed resistance to proton irradiation up to 5 dpa. (2) Under accident conditions the selected candidate materials showed several orders of magnitude improvement in the reaction with superheated steam as compared with the current zirconium based alloys. (3) Tube fabrication feasibility studies of FeCrAl alloys are underway. The aim is to obtain a wall thickness that is below 400 µm. (4) A strategy is outlined for the regulatory path approval and for the insertion of a lead fuel assembly in a commercial reactor by 2022. (5) The GE team worked closely with INL to have four rodlets tested in the ATR. GE provided the raw stock for the alloys, the fuel for the rodlets and the cost for fabrication/welding of the rodlets. INL fabricated the rodlets and the caps and welded them to provide hermetic seal. The replacement of a zirconium alloy using a ferritic material containing chromium and aluminum appears to be the most near term implementation for accident tolerant nuclear fuels.

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

    SciTech Connect (OSTI)

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

    2014-09-01T23:59:59.000Z

    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.

  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. False color viewing device

    DOE Patents [OSTI]

    Kronberg, J.W.

    1991-05-08T23:59:59.000Z

    This invention consists of a viewing device for observing objects in near-infrared false-color comprising a pair of goggles with one or more filters in the apertures, and pads that engage the face for blocking stray light from the sides so that all light reaching, the user`s eyes come through the filters. The filters attenuate most visible light and pass near-infrared (having wavelengths longer than approximately 700 nm) and a small amount of blue-green and blue-violet (having wavelengths in the 500 to 520 nm and shorter than 435 nm, respectively). The goggles are useful for looking at vegetation to identify different species and for determining the health of the vegetation, and to detect some forms of camouflage.

  1. False color viewing device

    DOE Patents [OSTI]

    Kronberg, James W. (108 Independent Blvd., Aiken, SC 29801)

    1992-01-01T23:59:59.000Z

    A viewing device for observing objects in near-infrared false-color comprising a pair of goggles with one or more filters in the apertures, and pads that engage the face for blocking stray light from the sides so that all light reaching the user's eyes come through the filters. The filters attenuate most visible light and pass near-infrared (having wavelengths longer than approximately 700 nm) and a small amount of blue-green and blue-violet (having wavelengths in the 500 to 520 nm and shorter than 435 nm, respectively). The goggles are useful for looking at vegetation to identify different species and for determining the health of the vegetation, and to detect some forms of camouflage.

  2. False color viewing device

    DOE Patents [OSTI]

    Kronberg, J.W.

    1992-10-20T23:59:59.000Z

    A viewing device for observing objects in near-infrared false-color comprising a pair of goggles with one or more filters in the apertures, and pads that engage the face for blocking stray light from the sides so that all light reaching the user's eyes come through the filters. The filters attenuate most visible light and pass near-infrared (having wavelengths longer than approximately 700 nm) and a small amount of blue-green and blue-violet (having wavelengths in the 500 to 520 nm and shorter than 435 nm, respectively). The goggles are useful for looking at vegetation to identify different species and for determining the health of the vegetation, and to detect some forms of camouflage. 7 figs.

  3. Cladding embrittlement during postulated loss-of-coolant accidents.

    SciTech Connect (OSTI)

    Billone, M.; Yan, Y.; Burtseva, T.; Daum, R.; Nuclear Engineering Division

    2008-07-31T23:59:59.000Z

    The effect of fuel burnup on the embrittlement of various cladding alloys was examined with laboratory tests conducted under conditions relevant to loss-of-coolant accidents (LOCAs). The cladding materials tested were Zircaloy-4, Zircaloy-2, ZIRLO, M5, and E110. Tests were performed with specimens sectioned from as-fabricated cladding, from prehydrided (surrogate for high-burnup) cladding, and from high-burnup fuel rods which had been irradiated in commercial reactors. The tests were designed to determine for each cladding material the ductile-to-brittle transition as a function of steam oxidation temperature, weight gain due to oxidation, hydrogen content, pre-transient cladding thickness, and pre-transient corrosion-layer thickness. For short, defueled cladding specimens oxidized at 1000-1200 C, ring compression tests were performed to determine post-quench ductility at {le} 135 C. The effect of breakaway oxidation on embrittlement was also examined for short specimens oxidized at 800-1000 C. Among other findings, embrittlement was found to be sensitive to fabrication processes--especially surface finish--but insensitive to alloy constituents for these dilute zirconium alloys used as cladding materials. It was also demonstrated that burnup effects on embrittlement are largely due to hydrogen that is absorbed in the cladding during normal operation. Some tests were also performed with longer, fueled-and-pressurized cladding segments subjected to LOCA-relevant heating and cooling rates. Recommendations are given for types of tests that would identify LOCA conditions under which embrittlement would occur.

  4. Risk communication with Fukushima residents affected by the Fukushima Daiichi accident at whole-body counting

    SciTech Connect (OSTI)

    Gunji, I.; Furuno, A.; Yonezawa, R.; Sugiyama, K. [Risk Communication Study Office, Japan Atomic Energy Agency 4-33 Muramatsu, Tokai-mura, Ibaraki, 319-1194 (Japan)

    2013-07-01T23:59:59.000Z

    After the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power plant accident, the Tokai Research and Development Center of the Japan Atomic Energy Agency (JAEA) have had direct dialogue as risk communication with Fukushima residents who underwent whole-body counting examination (WBC). The purpose of the risk communication was to exchange information and opinions about radiation in order to mitigate Fukushima residents' anxiety and stress. Two kinds of opinion surveys were performed: one survey evaluated residents' views of the nuclear accident itself and the second survey evaluated the management of WBC examination as well as the quality of JAEA's communication skills on risks. It appears that most Fukushima residents seem to have reduced their anxiety level after the direct dialogue. The results of the surveys show that Fukushima residents have the deepest anxiety and concern about their long-term health issues and that they harbor anger toward the government and TEPCO. On the other hand, many WBC patients and patients' relatives have expressed gratitude for help in reducing their feelings of anxiety.

  5. Safety First Safety Last Safety Always Roughly one out of every four accidents (25%) involves

    E-Print Network [OSTI]

    Minnesota, University of

    Safety First Safety Last Safety Always Roughly one out of every four accidents (25%) involves at an unsafe speed · Failure to check mirrors often Fleet Safety: Backing Accidents Safety Tip #2 Accidents hurt-- safety doesn't. All backing accidents are preventable. The key is to plan ahead to avoid backing

  6. 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

  7. 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

  8. 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

  9. California's Energy Future - The View to 2050

    E-Print Network [OSTI]

    2011-01-01T23:59:59.000Z

    resulted in the worst nuclear accident since the Chernobylaccidents with costs exceeding $10 billion; and 6. Reassessing the safety of nuclear

  10. Analysis of a hypothetical criticality accident in a waste supercompactor

    SciTech Connect (OSTI)

    Plaster, M.J.; Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Ruggles, A.E.; Wilkinson, A.; Yamamoto, T.; Dodds, H.L. [Univ. of Tennessee, Knoxville, TN (United States)

    1994-12-31T23:59:59.000Z

    A hypothetical nuclear criticality accident in a waste supercompactor is evaluated. The waste consists of a homogenous mixture of plutonium 49, beryllium, and air contained in a 35 gallon carbon steel drum. Possible consequences are investigated.

  11. 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.

  12. 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 ...

  13. 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 ...

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

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

    Park Building K-31 February 1, 2004 On December 17, 2003, at approximately 7:15 a.m., an accident occurred at the U.S. Department of Energy (DOE) East Tennessee Technology Park,...

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

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

    July 30, 2013, Electrical Fatality on the Bandon-Rogue No. 1 115kV Line at the Bonneville Power Administration Accident Investigation of the July 30, 2013, Electrical Fatality on...

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

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

    National Laboratory Type B Accident Investigation of the Savannah River Site Arc Flash Burn Injury on September 23, 2009, in the D Area Powerhouse Worker Health Summary, 1995-2004...

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

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

    the Savannah River Site Arc Flash Burn Injury on September 23, 2009, in the D Area Powerhouse Type B Accident Investigation of the Savannah River Site Arc Flash Burn Injury on...

  18. 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 ...

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

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

    Site October 20, 2000 On August 22, 2000, an accident occurred at the U. S. Department of Energy (DOE) Portsmouth Gaseous Diffusion Plant (PORTS) located in Piketon, Ohio. An...

  20. 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 ...

  1. 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...

  2. 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...

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

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

    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 Salt Waste...

  4. 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.

  5. 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...

  6. 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...

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

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

    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...

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

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

    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...

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

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

    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...

  10. Improved dose estimates for nuclear criticality accidents

    SciTech Connect (OSTI)

    Wilkinson, A.D.; Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Plaster, M.J.; Dodds, H.L. [Univ. of Tennessee, Knoxville, TN (United States). Nuclear Engineering Dept.; Haught, C.F. [Martin Marietta Utility Systems, Piketon, OH (United States); Yamamoto, T. [Japan Atomic Energy Research Inst., Tokai (Japan). Tokai Research Establishment; Hopper, C.M. [Oak Ridge National Lab., TN (United States)

    1995-08-01T23:59:59.000Z

    Slide rules are improved for estimating doses and dose rates resulting from nuclear criticality accidents. The original slide rules were created for highly enriched uranium solutions and metals using hand calculations along with the decades old Way-Wigner radioactive decay relationship and the inverse square law. This work uses state-of-the-art methods and better data to improve the original slide rules and also to extend the slide rule concept to three additional systems; i.e., highly enriched (93.2 wt%) uranium damp (H/{sup 235}U = 10) powder (U{sub 3}O{sub 8}) and low-enriched (5 wt%) uranium mixtures (UO{sub 2}F{sub 2}) with a H/{sup 235}U ratio of 200 and 500. Although the improved slide rules differ only slightly from the original slide rules, the improved slide rules and also the new slide rules can be used with greater confidence since they are based on more rigorous methods and better nuclear data.

  11. 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.

  12. Berkeley Lab Accident Statistics Through January 31, 2012

    E-Print Network [OSTI]

    Eisen, Michael

    1 Berkeley Lab Accident Statistics Through January 31, 2012 These slides are updated on a monthly Systems Engineer suffered the injuries from a single vehicle motorcycle accident. The employee had braked 0 0 0 0 0 0 0 1 Nuclear Science 0 0 0 0 0 0 0 0 0 0 0 0 0 Physics 0 0 0 0 0 0 0 0 0 0 0 0 0 Energy

  13. The role of NUREG-1150 in accident management

    SciTech Connect (OSTI)

    Camp, A.L.; Cramond, W.R.; Sype, T.T.

    1988-01-01T23:59:59.000Z

    NUREG-1150 is being prepared by the NRC and its contractors to estimate the risk from five commercial light water reactors: Surry, Sequoyah, Peach Bottom, Grand Gulf, and Zion. Level 3 probabilistic risk assessments (PRAs) are being prepared for each of these plants. These PRAs provide a framework for evaluating accident management alternatives from a risk standpoint. This paper describes the accident management benefits that NUREG-1150 is providing.

  14. The role of NUREG-1150 in accident management

    SciTech Connect (OSTI)

    Camp, A.L.; Cramond, W.R.; Sype, T.T.

    1988-01-01T23:59:59.000Z

    The NUREG-1150 report is being prepared by the US Nuclear Regulatory Commission and its contractors to estimate the risk from five commercial light water reactors: Surry, Sequoyah, Peach Bottom, Grand Gulf, and Zion. Level-3 probabilistic risk assessments (PRAs) are being prepared for each of these plants. These PRAs provided a framework for evaluating accident management alternatives from a risk standpoint. This paper describes the accident management benefits that NUREG-1150 is providing.

  15. Routine and post-accident sampling in nuclear reactors

    SciTech Connect (OSTI)

    Armento, W.J.; Kitts, F.G.; German, G.E.

    1980-01-01T23:59:59.000Z

    Review of the Three Mile Island accident by NRC has resulted in new post-accident-sampling-capability requirements for utilities that operate pressurized water reactors and/or boiling water reactors. Several vendors are offering equipment that they hope will suffice to met both the new NRC regulations and an operational deadline of January 1, 1981. The advantages and disadvantages of these systems and projected future-new-system needs for TVA reactors are being evaluated in light of TMI experience.

  16. 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.

  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. 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).

  3. 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...

  4. 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

  5. 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

  6. Review of experiments to evaluate the ability of electrical heater rods to simulate nuclear fuel rod behavior during postulated loss-of-coolant accidents in light water reactors

    SciTech Connect (OSTI)

    McPherson, G D; Tolman, E L

    1980-01-01T23:59:59.000Z

    Issues related to using electrical fuel rod simulators to simulate nuclear fuel rod behavior during postulated loss-of-coolant accident (LOCA) conditions in light water reactors are summarized. Experimental programs which will provide a data base for comparing electrical heater rod and nuclear fuel rod LOCA responses are reviewed.

  7. 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.

  8. 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

  9. Initial Cladding Condition

    SciTech Connect (OSTI)

    E. Siegmann

    2000-08-22T23:59:59.000Z

    The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is received at the Yucca Mountain Project (YMP) site. Most commercial nuclear fuel is encased in Zircaloy cladding. This analysis is developed to describe cladding degradation from the expected failure modes. This includes reactor operation impacts including incipient failures, potential degradation after reactor operation during spent fuel storage in pool and dry storage and impacts due to transportation. Degradation modes include cladding creep, and delayed hydride cracking during dry storage and transportation. Mechanical stresses from fuel handling and transportation vibrations are also included. This Analysis and Model Report (AMR) does not address any potential damage to assemblies that might occur at the YMP surface facilities. Ranges and uncertainties have been defined. This analysis will be the initial boundary condition for the analysis of cladding degradation inside the repository. In accordance with AP-2.13Q, ''Technical Product Development Planning'', a work plan (CRWMS M&O 2000c) was developed, issued, and utilized in the preparation of this document. There are constraints, caveats and limitations to this analysis. This cladding degradation analysis is based on commercial Pressurized Water Reactor (PWR) fuel with Zircaloy cladding but is applicable to Boiling Water Reactor (BWR) fuel. Reactor operating experience for both PWRs and BWRs is used to establish fuel reliability from reactor operation. It is limited to fuel exposed to normal operation and anticipated operational occurrences (i.e. events which are anticipated to occur within a reactor lifetime), and not to fuel that has been exposed to severe accidents. Fuel burnup projections have been limited to the current commercial reactor licensing environment with restrictions on fuel enrichment, oxide coating thickness and rod plenum pressures. The information provided in this analysis will be used in evaluating the post-closure performance of the Monitored Geologic Repository (MGR) in relation to waste form degradation.

  10. Improvement design study on steam generator of MHR-50/100 aiming higher safety level after water ingress accident

    SciTech Connect (OSTI)

    Oyama, S. [Mitsubishi Heavy Industries, Ltd., 1-1 Wadasaki-cho 1-Chome, Hyogo-ku, Kobe (Japan); Minatsuki, I.; Shimizu, K. [Mitsubishi Heavy Industries, Ltd., 16-5, Konan 2-Chome, Minato-ku, Tokyo (Japan)

    2012-07-01T23:59:59.000Z

    Mitsubishi Heavy Industries, Ltd. (MHI) has been studying on MHI original High Temperature Gas cooled Reactor (HTGR), namely MHR-50/100, for commercialization with supported by JAEA. In the heat transfer system, steam generator (SG) is one of the most important components because it should be imposed a function of heat transfer from reactor power to steam turbine system and maintaining a nuclear grade boundary. Then we especially focused an effort of a design study on the SG having robustness against water ingress accident based on our design experience of PWR, FBR and HTGR. In this study, we carried out a sensitivity analysis from the view point of economic and plant efficiency. As a result, the SG design parameter of helium inlet/outlet temperature of 750 deg. C/300 deg. C, a side-by-side layout and one unit of SG attached to a reactor were selected. In the next, a design improvement of SG was carried out from the view point of securing the level of inherent safety without reliance on active steam dump system during water ingress accident considering the situation of the Fukushima nuclear power plant disaster on March 11, 2011. Finally, according to above basic design requirement to SG, we performed a conceptual design on adapting themes of SG structure improvement. (authors)

  11. 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.

  12. 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.

  13. Security Conditions

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

    2004-07-08T23:59:59.000Z

    This Notice ensures that DOE uniformly meets the requirements of the Homeland Security Advisory System outlined in Homeland Security Presidential Directive-3, Threat Conditions and Associated Protective Measures, dated 3-11-02, and provides responses specified in Presidential Decision Directive 39, U.S. Policy on Counterterrorism (U), dated 6-21-95. It cancels DOE N 473.8, Security Conditions, dated 8-7-02. Extended until 7-7-06 by DOE N 251.64, dated 7-7-05 Cancels DOE N 473.8

  14. A Regulator's View of Cogeneration

    E-Print Network [OSTI]

    Shanaman, S. M.

    1982-01-01T23:59:59.000Z

    of the total national electric generation. In view of the energy requirements of Pennsylvania's industry and the impact of increasing energy costs on employment the Commission directed its technical staff to investigate the potential for industrial cogeneration...

  15. 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.

  16. 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

    Control of Major-Accident Hazards Involving Land Transmission Pipelines Charlotte BOUISSOU, Project Nicolas DECHY, Project Manager for Accidents Analysis and Learning from Experience Contact : charlotte, this Directive does not apply to land transmission pipelines... According to several accidents analysis

  17. E-Print Network 3.0 - accident conditions comparison Sample Search...

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

    ... Source: Ecole Polytechnique, Centre de mathmatiques Collection: Mathematics 6 Software Safety Tutorial Status Update 1 Software Safety Tutorial Summary: with severe...

  18. A Device for Search of Gamma-Radiation Intensive Sources at the Radiation Accident Condition

    SciTech Connect (OSTI)

    Batiy, Valeriy; Klyuchnykov, A; Kochnev, N; Rudko, Vladimir; shcherbin, vladimir; Yegorov, V; Schmieman, Eric A.

    2005-08-08T23:59:59.000Z

    The procedure designed for measuring angular distributions of gamma radiation and for search of gamma radiation intensive sources is described. It is based on application of the original multidetector device ShD-1, for measuring an angular distribution in a complete solid angle (4 pi). The calibration results and data on the angular distributions of intensity of gamma radiation at the roof of Chornobyl NPP ''Shelter'' are presented.

  19. 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

  20. E-Print Network 3.0 - accident risk forecasting Sample Search...

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

    Information Sciences ; Biology and Medicine 9 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  1. E-Print Network 3.0 - accident prone drivers Sample Search Results

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

    State University Collection: Geosciences 4 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  2. E-Print Network 3.0 - accident efectele medico-biologice Sample...

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

    de mathmatiques Collection: Mathematics 2 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  3. E-Print Network 3.0 - accident dinamika formirovaniya Sample...

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

    Environmental Sciences and Ecology 5 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  4. E-Print Network 3.0 - accident insurance Sample Search Results

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

    Taiwan University Collection: Geosciences 2 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  5. E-Print Network 3.0 - accidents jacob kulowski Sample Search...

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

    Technologies and Information Sciences 3 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  6. E-Print Network 3.0 - accidents involving external Sample Search...

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

    Environmental Sciences and Ecology 5 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  7. E-Print Network 3.0 - all-terrain vehicle accidents Sample Search...

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

    Chemistry ; Biology and Medicine 3 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  8. E-Print Network 3.0 - accident codes applications Sample Search...

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

    de mathmatiques Collection: Mathematics 7 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  9. E-Print Network 3.0 - accident issledovanie raspredeleniya Sample...

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

    raspredeleniya Page: << < 1 2 3 4 5 > >> 1 U of L Campus AccidentIncident Report Automobile AccidentIncident Page 1 of 2 University of Lethbridge Summary: U of L Campus...

  10. E-Print Network 3.0 - accidents dus aux Sample Search Results

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

    dus aux Search Powered by Explorit Topic List Advanced Search Sample search results for: accidents dus aux Page: << < 1 2 3 4 5 > >> 1 DCLARATION RELATIVE AUX ACCIDENTS JOINDRE AUX...

  11. E-Print Network 3.0 - accident recovery workers Sample Search...

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

    Workers' Compensation Act. Were you paid in full for the day of the accident... SSN Cell Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date...

  12. E-Print Network 3.0 - accident thermal challenge Sample Search...

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

    1 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: on the Space Shuttle Challenger Accident, Washington, D.C., June 6, 1986....

  13. E-Print Network 3.0 - accident management guidance Sample Search...

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

    2 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: of regular reading of accident reports is the prospect that doing so will...

  14. 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...

  15. 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) ...

  16. 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 ...

  17. E-Print Network 3.0 - accident data Sample Search Results

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

    and RhD phe- notype were matched with those on traffic accidents from... increased the risk of traffic accidents in military drivers. The data also indicate that RhD...

  18. 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

  19. 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...

  20. Viewing device for electron-beam equipment

    SciTech Connect (OSTI)

    Nasyrov, R.S.

    1985-06-01T23:59:59.000Z

    Viewing devices are used to observe melting, welding, and so on in vacuum systems, an it is necessary to protect the windows from droplets and vapor. A viewing device for electron-beam equipment is described in which the viewing tube and mounting flange are made as a tubular ball joint enclosed in a steel bellows, which render the viewing device flexible. Bending the viewing tube in the intervals between observations protects the viewing window from sputtering and from drops of molten metal.

  1. 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

  2. Improved dose estimates for nuclear criticality accidents: Preliminary results

    SciTech Connect (OSTI)

    Wilkinson, A.; Basoglu, B.; Bentley, C.; Dunn, M.; Plaster, M.; Yamamoto, T.; Dodds, H. [Univ. of Tennessee, Knoxville, TN (United States); Hopper, C. [Oak Ridge National Lab., TN (United States)

    1994-12-31T23:59:59.000Z

    A method for the determination of radiation doses resulting from a hypothetical crticality accident is presented. The method is an improvement over the slide-rule method cuurently used. The improved method calculates doses for low eneriched uranium as well as highly enriched solutions.

  3. Severe accident natural circulation studies at the INEL

    SciTech Connect (OSTI)

    Bayless, P.D.; Brownson, D.A.; Dobbe, C.A.; Jones, K.R.; O`Brien, J.E.; Pafford, D.J.; Schlenker, L.D.; Tung, V.X.

    1995-02-01T23:59:59.000Z

    Severe accident natural circulation flows have been investigated at the Idaho National Engineering Laboratory to better understand these flows and their potential impacts on the progression of a pressurized water reactor severe accident. Parameters affecting natural circulation in the reactor vessel and hot legs were identified and ranked based on their perceived importance. Reviews of the scaling of the 1/7-scale experiments performed by Westinghouse were undertaken. RELAP5/MOD3 calculations of two of the experiments showed generally good agreement between the calculated and observed behavior. Analyses of hydrogen behavior in the reactor vessel showed that hydrogen stratification is not likely to occur, and that an initially stratified layer of hydrogen would quickly mix with a recirculating steam flow. An analysis of the upper plenum behavior in the Three Mile Island, Unit 2 reactor concluded that vapor temperatures could have been significantly higher than the temperatures seen by the control rod drive lead screws, supporting the premise that a strong natural circulation flow was likely present during the accident. SCDAP/RELAP5 calculations of a commercial pressurized water reactor severe accident without operator actions showed that the natural circulation flows enhance the likelihood of ex-vessel piping failures long before failure of the reactor vessel lower head.

  4. 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

  5. Hanford Waste Tank Bump Accident and Consequence Analysis

    SciTech Connect (OSTI)

    BRATZEL, D.R.

    2000-06-20T23:59:59.000Z

    This report provides a new evaluation of the Hanford tank bump accident analysis and consequences for incorporation into the Authorization Basis. The analysis scope is for the safe storage of waste in its current configuration in single-shell and double-shell tanks.

  6. University Guidance for the REPORTING OF ACCIDENTS, DISEASES AND

    E-Print Network [OSTI]

    and Safety Executive (HSE), Local Authorities and Environmental Health Departments which will provide of this guidance is to advise Heads of Department, Managers and Supervisors of the system by which the University. These may be required by external agencies such as HSE and the University Insurers. 3. REPORTING AN ACCIDENT

  7. 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...

  8. 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...

  9. Environmental radionuclide distribution in Georgia after the Chernobyl accident

    SciTech Connect (OSTI)

    Mosulishvili, L.M.; Shoniya, N.I.; Katamadze, N.M. [Institute of Physics, Tbilisi, Georgia (Russian Federation)] [and others

    1994-01-01T23:59:59.000Z

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

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. accident consequence assessment: Topics by E-print Network

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

    accident consequence assessment 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 Assessing the...

  16. accident consequence assessments: Topics by E-print Network

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

    accident consequence assessments 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 Assessing the...

  17. Development of integrated core disruptive accident analysis code for FBR - ASTERIA-FBR

    SciTech Connect (OSTI)

    Ishizu, T.; Endo, H.; Tatewaki, I.; Yamamoto, T. [Japan Nuclear Energy Safety Organization JNES, Toranomon Towers Office, 4-1-28, Toranomon, Minato-ku, Tokyo (Japan); Shirakawa, N. [Inst. of Applied Energy IAE, Shimbashi SY Bldg., 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo (Japan)

    2012-07-01T23:59:59.000Z

    The evaluation of consequence at the severe accident is the most important as a safety licensing issue for the reactor core of liquid metal cooled fast breeder reactor (LMFBR), since the LMFBR core is not in an optimum condition from the viewpoint of reactivity. This characteristics might induce a super-prompt criticality due to the core geometry change during the core disruptive accident (CDA). The previous CDA analysis codes have been modeled in plural phases dependent on the mechanism driving a super-prompt criticality. Then, the following event is calculated by connecting different codes. This scheme, however, should introduce uncertainty and/or arbitrary to calculation results. To resolve the issues and obtain the consistent calculation results without arbitrary, JNES is developing the ASTERIA-FBR code for the purpose of providing the cross-check analysis code, which is another required scheme to confirm the validity of the evaluation results prepared by applicants, in the safety licensing procedure of the planned high performance core of Monju. ASTERIA-FBR consists of the three major calculation modules, CONCORD, dynamic-GMVP, and FEMAXI-FBR. CONCORD is a three-dimensional thermal-hydraulics calculation module with multi-phase, multi-component, and multi-velocity field model. Dynamic-GMVP is a space-time neutronics calculation module. FEMAXI-FBR calculates the fuel pellet deformation behavior and fuel pin failure behavior. This paper describes the needs of ASTERIA-FBR development, major module outlines, and the model validation status. (authors)

  18. A Literature Review on Ruthenium Behaviour in Nuclear Power Plant Severe Accidents

    E-Print Network [OSTI]

    Boyer, Edmond

    A Literature Review on Ruthenium Behaviour in Nuclear Power Plant Severe Accidents C. MUN , L Literature Review on Ruthenium Behaviour in Nuclear Power Plant Severe Accidents C. MUN a , L. CANTREL a , C Accidents Majeurs (DPAM), CEN Cadarache - France 1 b Commissariat ŕ l'Energie Atomique (CEA), Direction de l'Energie

  19. Cesium-137 deposition and contamination of Japanese soils due to the Fukushima nuclear accident

    E-Print Network [OSTI]

    Jacob, Daniel J.

    CONFUSION SURROUNDS THE ACCIDENT AT FUKUSHIMA DAIICHI NUCLEAR POWER Plant with regard to the amount, "Fukushima nuclear power plant accident," 21 March 2011; www.icrp.org/docs/Fukushima%20Nuclear%20Power%20-up study of the Fukushima accident can provide firm and reliable evidence for low-dose effects of radiation

  20. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    RITTMANN, P.D.

    1999-10-07T23:59:59.000Z

    Three bounding accidents postdated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing, and a hydrogen explosion. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  1. 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

  2. Hazmat Accident Education -An Integrated Shirley E. Clark, Ph.D., P.E.

    E-Print Network [OSTI]

    Pitt, Robert E.

    Hazmat Accident Education - An Integrated Approach By Shirley E. Clark, Ph.D., P.E. Formerly Accident Education - An Integrated Approach 6. Performing Organization Code 7. Authors Shirley E. Clark, accidents, emergency planning, emergency response 18. Distribution Statement 19. Security Classification (of

  3. 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

  4. Accident Analysis and Prevention, 2012 (49), pp 73-77 www.elsevier.com/locate/aap

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Accident Analysis and Prevention, 2012 (49), pp 73-77 www.elsevier.com/locate/aap doi:10.1016/j.aap.2011.07.013 Motorcyclists' speed and "looked-but-failed-to-see" accidents Nicolas Clabaux, Thierry of accidents in which a non-priority road user failed to give way to an approaching motorcyclist without seeing

  5. Modelling of Stochastic Hybrid Systems with Applications to Accident Risk Assessment

    E-Print Network [OSTI]

    Del Moral , Pierre

    Modelling of Stochastic Hybrid Systems with Applications to Accident Risk Assessment #12;The SYSTEMS WITH APPLICATIONS TO ACCIDENT RISK ASSESSMENT DISSERTATION to obtain the doctor's degree promotor Prof. dr. A. Bagchi #12;Contents 1 Introduction 3 1.1 Accident risk assessment

  6. Extending the Borders of Accident Investigation: Applying Novel Analysis Techniques to the Loss of the Brazilian

    E-Print Network [OSTI]

    Johnson, Chris

    -1- Extending the Borders of Accident Investigation: Applying Novel Analysis Techniques to the Loss. In consequence, it is becoming increasingly difficult to identify the causes of incidents and accidents back to the development of a number of novel accident investigation techniques. Most of these approaches are intended

  7. DIRECTORY OF ESReDA ACCIDENT DATABASES Jean-Philippe PINEA

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    98-62 DIRECTORY OF ESReDA ACCIDENT DATABASES Jean-Philippe PINEAĂ? INERIS - Parc Technologique Alata, Reliability and Data Association (ESReDA) "Accident Analysis" has been dealing with data collection, quality, reliability and networking of accident data. The aim of this review paper is a description and possible uses

  8. STATE OF CALIFORNIA -GENERAL SERVICES -RISK AND INSURANCE MANAGEMENT STATE DRIVER ACCIDENT REVIEW

    E-Print Network [OSTI]

    Ponce, V. Miguel

    STATE OF CALIFORNIA - GENERAL SERVICES - RISK AND INSURANCE MANAGEMENT STATE DRIVER ACCIDENT REVIEW STD. 274 (REV. 1/2003) PLEASE PRINT OR TYPE SUPERVISOR'S REVIEW - FOR DEPARTMENTAL ACCIDENT PREVENTION PURPOSE: To have supervisor investigate each driver accident, report facts and circumstances, confirm

  9. MELCOR ACCIDENT ANALYSIS FOR ARIES-ACT Paul W. Humrickhouse, Brad J. Merrill

    E-Print Network [OSTI]

    MELCOR ACCIDENT ANALYSIS FOR ARIES-ACT Paul W. Humrickhouse, Brad J. Merrill Idaho National accident (LOFA) in the ARIES-ACT1 tokamak design. ARIES-ACT1 features an advanced SiC blanket with Li consider here the implications of a loss of flow accident (LOFA) resulting from a loss of offsite power

  10. BP Texas City accident: weak signais or sheer power? Jean Christophe Le Coze,

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    BP Texas City accident: weak signais or sheer power? Jean Christophe Le Coze, Research the interprétation of the BP Texas City accident. While bringing a lot of empirical data on a wide range for sensitising the data. It however clearly indicated a référence to the Columbia Accident Investigation Board

  11. PRESENTATION OF WORK PERFORMED BY ESReDA "ACCIDENT ANALYSIS" WORKING

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    PRESENTATION OF WORK PERFORMED BY ESReDA "ACCIDENT ANALYSIS" WORKING GROUP AND GOALS FOR THE FUTURE J.P. PINEAU, INERIS, FRANCE Summary The Accident Analysis working group was initiated in January and softwares for consequences assessment of major accidents and a more statistical approach of data collected

  12. Reflection on a model of accident reporting to help to implement efficient prevention strategies

    E-Print Network [OSTI]

    Boyer, Edmond

    Reflection on a model of accident reporting to help to implement efficient prevention strategies to deliver the relevant action plan especially to control occupational accidents. The aim of the article is to present our approach to analyze the classical Heinrich's model of occupational accidents and the classical

  13. Aircraft Accident Prevention: Loss-of-Control Analysis Harry G. Kwatny

    E-Print Network [OSTI]

    Kwatny, Harry G.

    Aircraft Accident Prevention: Loss-of-Control Analysis Harry G. Kwatny , Jean-Etienne T. Dongmo NASA Langley Research Center, MS 161, Hampton, VA, 23681. The majority of fatal aircraft accidents that during the ten year period 1997-2006, 59% of fatal aircraft accidents were associated with Loss

  14. 2412 (0708) Did you know that every five minutes a person dies in an accident?

    E-Print Network [OSTI]

    2412 (0708) Did you know that every five minutes a person dies in an accident? 1 It's why your employer has provided important accident insurance protection to you while traveling -- at no cost to you Commutation- A benefit is paid if an employee is injured as a result of a covered accident that occurs while

  15. 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.

  16. Accident Reporting Policy Outline the policy regarding accident reporting on 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. Policy 1. An accident is defined as any incident that causes damage to persons or property. 2. In the glove box of every

  17. Wide field of view telescope

    DOE Patents [OSTI]

    Ackermann, Mark R. (Albuquerque, NM); McGraw, John T. (Placitas, NM); Zimmer, Peter C. (Albuquerque, NM)

    2008-01-15T23:59:59.000Z

    A wide field of view telescope having two concave and two convex reflective surfaces, each with an aspheric surface contour, has a flat focal plane array. Each of the primary, secondary, tertiary, and quaternary reflective surfaces are rotationally symmetric about the optical axis. The combination of the reflective surfaces results in a wide field of view in the range of approximately 3.8.degree. to approximately 6.5.degree.. The length of the telescope along the optical axis is approximately equal to or less than the diameter of the largest of the reflective surfaces.

  18. Type B Accident Investigation Board Report of the January 20, 1998, Electrical Accident at the Casa Grande Substation,South of Phoenix, Arizona

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type-B Accident Investigation Board appointed by Michael S.Cowan, Chief Program Officer, Western Area Power Administration.

  19. Limited View Angle Iterative CT Reconstruction

    E-Print Network [OSTI]

    ;Some Prior Literature in Limited View Tomography CT with limited-angle data and few views IRR algorithm Iterative Reconstruction-Reprojection (IRR) : An Algorithm for Limited Data Cardiac- Computed-views and limited-angle data in divergent-beam CT by E. Y. Sidky, CM Kao, and X. Pan (2006) Few-View Projection

  20. View

    E-Print Network [OSTI]

    2010-08-12T23:59:59.000Z

    all real solutions of a given system of polynomial equations. ... A crucial ingredient is a semidefinite characterization of the real radical ideal ...... The options.

  1. View

    E-Print Network [OSTI]

    2003-07-16T23:59:59.000Z

    flow equation is discretized in space using a control volume finite-element technique .... The control volume finite-element method is selected .... parallel plates.

  2. View

    E-Print Network [OSTI]

    2013-10-14T23:59:59.000Z

    based on median finding, variable fixing, and secant techniques. Keywords: ..... arithmetic operations, the overall complexity is O(n2). D. The worst case bound in ..... always work on its rated clock speed, we turned force the Linux system to use the ..... dimensionally equidistributed uniform pseudo-random number generator.

  3. View

    E-Print Network [OSTI]

    2011-01-28T23:59:59.000Z

    obtained by using different uncertainty sets estimated using simulated and ... Given a fixed mix of electric power plants (nuclear, thermal, hydroelectric, and ...

  4. View

    E-Print Network [OSTI]

    2010-03-14T23:59:59.000Z

    Aug 19, 2009 ... linear-algebraic and graph theoretic properties of this matrix class. The con- ..... The MatLab solvers linprog and quadprog were used.

  5. View

    E-Print Network [OSTI]

    1910-31-00T23:59:59.000Z

    Sep 3, 2003 ... Landau (TDGL) equation, the Maxwell equations, and an energy equation ... varying currents and magnetic fields generate thermal energy, ...

  6. View

    E-Print Network [OSTI]

    2010-07-30T23:59:59.000Z

    project of the classification of (simple) nuclear separable C*-algebras [E]. Let C? denote the category of separable C*-algebras and ?-homomorphisms.

  7. View

    E-Print Network [OSTI]

    2006-07-11T23:59:59.000Z

    the classification results of Kirchberg and Phillips using the notion of nuclear absorbing ... A simple purely infinite nuclear separable C*-algebra is called.

  8. View

    E-Print Network [OSTI]

    2008-07-07T23:59:59.000Z

    a battery of benchmark instances of up to 200 nodes are reported. These seem to be the largest instances that have been solved exactly for this problem.

  9. View

    E-Print Network [OSTI]

    2009-05-07T23:59:59.000Z

    author would also like to acknowledge the Center for High Performance Computing at VCU for providing computational infrastructure and support. 1 ...

  10. View

    E-Print Network [OSTI]

    2008-02-01T23:59:59.000Z

    the results of [8] to obtain, for each natural number n, a simple nuclear C?- algebra An whose ordered K0-group is order isomorphic to Zn. This result was further ...

  11. View

    E-Print Network [OSTI]

    2006-02-28T23:59:59.000Z

    Feb 28, 2006 ... Abstract. The major focus of this work is to compare several methods for computing the proximal point of a nonconvex function via numerical ...

  12. View

    E-Print Network [OSTI]

    andrea,,,

    In order to increase the search capability of MBH, a population framework has been proposed ... The key idea is to avoid new individuals to enter the population if someone similar (in a ..... We measure the efficiency in terms of number of (two-.

  13. View

    E-Print Network [OSTI]

    2005-05-30T23:59:59.000Z

    May 31, 2005 ... Robert M. Freund: MIT Sloan School of Management, 50 Memorial Drive, Cambridge, Massachusetts 02139-4307, ...... the transition kernel.

  14. View

    E-Print Network [OSTI]

    2005-05-12T23:59:59.000Z

    May 12, 2005 ... We propose in this paper to study the problem of estimating the cost-to- ... and have been proposed in the context of econometry in [Chen and White, 1998]. .... Rearranging terms, we see that the last relation can be written as.

  15. View

    E-Print Network [OSTI]

    2011-06-21T23:59:59.000Z

    May 14, 2010 ... Generally, even testing whether a matrix is in C? is co-NP-complete [23]. ...... One concrete example is the following: ?. ?. ?. ?. ?. ?. 1 1/3 1/3 ...

  16. Localized lesions induced by sup 137 Cs during the Goiania accident

    SciTech Connect (OSTI)

    Oliveira, A.R.; Brandao-Mello, C.E.; Valverde, N.J.; Farina, R.; Curado, M.P. (Industrias Nucleares do Brasil S.A., Rio de Janeiro (Brazil))

    1991-01-01T23:59:59.000Z

    A description is given of initial symptoms and clinical observations regarding acute localized radiation lesions in 28 persons exposed to 137Cs during the Goiania radiological accident. Specialized procedures to estimate the extent and gravity of the lesions and establish a therapeutic strategy, as well as to anticipate the prognosis in each case, are briefly discussed. Measures taken for reduction of pain and inflammation are noted, and an explanation is given for difficulties encountered due to adverse working conditions and the serious clinical manifestations presented by various patients concomitantly with their lesions. Also noted is the difficulty in obtaining credible information regarding exposure, such as source-to-object distance, duration of exposure, and source activity, which precluded dosimetry studies in most cases.

  17. Rehabilitation of soils and surface after a nuclear accident: Some techniques tried in the Chernobyl zone

    SciTech Connect (OSTI)

    Jouve, A.; Maubert, H. [IPSN/CEA, Saint Paul Lez Durance (France); Millan-Gomez, R. [CIEMAT, Madrid (Spain); Kutlakhamedov, Y. [Ukrainian Academy of Sciences, Kiev (Ukraine). Inst. of Cell Biology and Genetic Engineering

    1993-12-31T23:59:59.000Z

    Six years after the Chernobyl accident, the major part of deposited radio nuclides remains in the 3 or 4 cm of the topsoil of abandoned fields in the chernobyl zone. The Decontaminating Vegetal Network allows a layer of few centimeters of the top soil to be removed with a turf harvester. The efficiency observed at Chernobyl was 97% for cesium-137 and strontium-90. After scraping the soil with the turf harvester, the bare soil must be covered and re-grown in order to prevent wind erosion of the sandy soil. A trial spraying of polyacrylamide on the soil was carried out. This technique seems promising. Trials of bio-decontamination of the removed turf using anaerobic degradation were also carried out. This experiment provided an opportunity to measure in real conditions the transfer of radionuclides in the Chernobyl zone.

  18. Process hazards analysis (PrHA) program, bridging accident analyses and operational safety

    SciTech Connect (OSTI)

    Richardson, J. A. (Jeanne A.); McKernan, S. A. (Stuart A.); Vigil, M. J. (Michael J.)

    2003-01-01T23:59:59.000Z

    Recently the Final Safety Analysis Report (FSAR) for the Plutonium Facility at Los Alamos National Laboratory, Technical Area 55 (TA-55) was revised and submitted to the US. Department of Energy (DOE). As a part of this effort, over seventy Process Hazards Analyses (PrHAs) were written and/or revised over the six years prior to the FSAR revision. TA-55 is a research, development, and production nuclear facility that primarily supports US. defense and space programs. Nuclear fuels and material research; material recovery, refining and analyses; and the casting, machining and fabrication of plutonium components are some of the activities conducted at TA-35. These operations involve a wide variety of industrial, chemical and nuclear hazards. Operational personnel along with safety analysts work as a team to prepare the PrHA. PrHAs describe the process; identi fy the hazards; and analyze hazards including determining hazard scenarios, their likelihood, and consequences. In addition, the interaction of the process to facility systems, structures and operational specific protective features are part of the PrHA. This information is rolled-up to determine bounding accidents and mitigating systems and structures. Further detailed accident analysis is performed for the bounding accidents and included in the FSAR. The FSAR is part of the Documented Safety Analysis (DSA) that defines the safety envelope for all facility operations in order to protect the worker, the public, and the environment. The DSA is in compliance with the US. Code of Federal Regulations, 10 CFR 830, Nuclear Safety Management and is approved by DOE. The DSA sets forth the bounding conditions necessary for the safe operation for the facility and is essentially a 'license to operate.' Safely of day-to-day operations is based on Hazard Control Plans (HCPs). Hazards are initially identified in the PrI-IA for the specific operation and act as input to the HCP. Specific protective features important to worker safety are incorporated so the worker can readily identify the safety parameters of the their work. System safety tools such as Preliminary Hazard Analysis, What-If Analysis, Hazard and Operability Analysis as well as other techniques as necessary provide the groundwork for both determining bounding conditions for facility safety, operational safety, and day-to-clay worker safety.

  19. 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

  20. Analysis of a hypothetical criticality accident in a waste supercompactor

    SciTech Connect (OSTI)

    Plaster, M.J.; Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Ruggles, A.E.; Wilkinson, A.D.; Yamamoto, T.; Dodds, H.L. [Univ. of Tennessee, Knoxville, TN (United States). Nuclear Engineering Dept.

    1995-08-01T23:59:59.000Z

    A hypothetical nuclear criticality accident in a waste supercompactor is examined. The material being compressed in the compactor is a homogeneous mixture of beryllium and {sup 239}Pu. The point-kinetics equations with simple thermal-hydraulic feedback are used to model the transient behavior of the system. A computer code has been developed to solve the model equations. The computer code calculates the fission power history, fission yield, bulk temperature of the system, and several other thermal-hydraulic parameters of interest. Calculations have been performed for the waste supercompactor for various material misloading configurations. The peak power for the various accident scenarios varies from 1.04 {times} 10{sup 17} to 4.85 {times} 10{sup 20} fissions per second (fps). The total yield varies from 8.21 {times} 10{sup 17} to 7.73 {times} 10{sup 18} fissions, and the bulk temperature of the system varies from 412 to >912 K.

  1. A regulatory assessment of test data for reactivity accidents

    SciTech Connect (OSTI)

    Meyer, R.O.; Scott, H.H. [Nuclear Regulatory Commission, Washington, DC (United States); Chung, Hee M. [Argonne National Lab., IL (United States)] [and others

    1997-09-01T23:59:59.000Z

    An assessment is made of recent test data from France, Japan, and Russia, and of earlier test data from the U.S., in relation to the safety analysis performed for power reactors in the U.S. Considerations include mode of cladding failure, oxidation, hydriding, and pulse-width effects. From the data trend and from these considerations, it is concluded that the cladding failure threshold for fuel rods with moderate-to-high burnup is roughly 100 cal/g for BWRs and PWRs. Realistic plant calculations suggest that cladding failure would not occur for rod-ejection or rod-drop accidents and, therefore, that pellet fragmentation and enhanced fission product release from fuel pellets should not have to be considered in the safety analysis for these accidents. However, the data base is sparse and contains a lot of uncertainty.

  2. Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report

    SciTech Connect (OSTI)

    Lori Braase

    2013-01-01T23:59:59.000Z

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: • Give “priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools.” • Give “special technical emphasis and funding priority…to activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors.” • Report “to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020.” Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and Commercialization. The activities performed during the feasibility assessment phase include laboratory scale experiments; fuel performance code updates; and analytical assessment of economic, operational, safety, fuel cycle, and environmental impacts of the new concepts. The development and qualification stage will consist of fuel fabrication and large scale irradiation and safety basis testing, leading to qualification and ultimate NRC licensing of the new fuel. The commercialization phase initiates technology transfer to industry for implementation. Attributes for fuels with enhanced accident tolerance include improved reaction kinetics with steam and slower hydrogen generation rate, while maintaining acceptable cladding thermo-mechanical properties; fuel thermo-mechanical properties; fuel-clad interactions; and fission-product behavior. These attributes provide a qualitative guidance for parameters that must be considered in the development of fuels and cladding with enhanced accident tolerance. However, quantitative metrics must be developed for these attributes. To initiate the quantitative metrics development, a Light Water Reactor Enhanced Accident Tolerant Fuels Metrics Development Workshop was held October 10-11, 2012, in Germantown, Maryland. This document summarizes the structure and outcome of the two-day workshop. Questions regarding the content can be directed to Lori Braase, 208-526-7763, lori.braase@inl.gov.

  3. Accident at Three Mile Island: the human dimensions

    SciTech Connect (OSTI)

    Sills, D.L.; Wolf, C.P.; Shelanski, V.B. (eds.)

    1982-01-01T23:59:59.000Z

    A separate abstract was prepared for each of the 19 chapters, divided according to the following Parts: (1) Public Perceptions of Nuclear Energy; (2) Local Responses to Nuclear Plants; (3) Institutional Responsibilities for Nuclear Energy; (4) The Interaction of Social and Technical Systems; and (5) Implications for Public Policy. All of the abstracts will appear in Energy Abstracts for Policy Analysis (EAPA); three will appear in Energy Research Abstracts (ERA). At the request of the President's Commission on the Accident at Three Mile Island (the Kemeny Commission), the Social Science Research Council commissioned social scientists to write a series of papers on the human dimensions of the event. This volume includes those papers, in revised and expanded form, and a comprehensive bibliography of published and unpublished social science research on the accident and its aftermath.

  4. INDUSTRIAL/MILITARY ACTIVITY-INITIATED ACCIDENT SCREENING ANALYSIS

    SciTech Connect (OSTI)

    D.A. Kalinich

    1999-09-27T23:59:59.000Z

    Impacts due to nearby installations and operations were determined in the Preliminary MGDS Hazards Analysis (CRWMS M&O 1996) to be potentially applicable to the proposed repository at Yucca Mountain. This determination was conservatively based on limited knowledge of the potential activities ongoing on or off the Nevada Test Site (NTS). It is intended that the Industrial/Military Activity-Initiated Accident Screening Analysis provided herein will meet the requirements of the ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987) in establishing whether this external event can be screened from further consideration or must be included as a design basis event (DBE) in the development of accident scenarios for the Monitored Geologic Repository (MGR). This analysis only considers issues related to preclosure radiological safety. Issues important to waste isolation as related to impact from nearby installations will be covered in the MGR performance assessment.

  5. Berkeley Lab Accident Statistics Through November 30, 2011

    E-Print Network [OSTI]

    Eisen, Michael

    Nuclear Science 0 0 0 0 0 0 0 0 0 0 0 0 0 Physics 0 0 0 0 0 0 0 0 0 0 0 0 0 Energy & Environmental1 Berkeley Lab Accident Statistics Through November 30, 2011 These slides are updated on a monthly 0 0 0 0 0 0 Environmental Energy Tech. 0 0 0 0 0 0 0 0 0 0 0 0 0 Materials Sciences 0 0 0 0 0 0 0 0

  6. Self-mixing phenomenology in hypothetical core-disruptive accidents

    SciTech Connect (OSTI)

    Chapyak, E.J.

    1980-12-01T23:59:59.000Z

    Physical processes are investigated that lead to the thermal equilibration of a disrupted liquid metal fast breeder reactor (LMFBR) core following a hypothetical core-disruptive accident (HCDA). Their impact is assessed, particularly as relating to the SIMMER code. The turbulent structure in the core region is characterized and bounding estimates are derived of thermal equilibration (''self-mixing'') times. The implication of these results for LMFBR safety research is discussed briefly.

  7. Estimated long term health effects of the Chernobyl accident

    SciTech Connect (OSTI)

    Cardis, E. [International Agency for Research on Cancer, Lyon (France)

    1996-07-01T23:59:59.000Z

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

  8. Chernobyl accident and the problem of {sup 241}Am

    SciTech Connect (OSTI)

    Pazukhin, E.M.; Drozd, I.P.; Tokarevskii, V.V. [V.G. Khlopin Radium Institute, St. Petersburg (Russian Federation)

    1995-07-01T23:59:59.000Z

    The accumulation and decay of {sup 241}Am formed in the reactor of the fourth block of the Chernobyl atomic energy station at the time of the accident of April 26, 1986 are analyzed. Possible pathways for {sup 241}Am uptake in man are examined. The maximum equivalent dose after 70 years is estimated for a critical population living at the edge of the exclusion zone.

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

    SciTech Connect (OSTI)

    Gilles Youinou; R. Sonat Sen

    2013-09-01T23:59:59.000Z

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

  10. AQUATIC ASSESSMENT OF THE CHERNOBYL NUCLEAR ACCIDENT AND ITS REMEDIATION

    SciTech Connect (OSTI)

    Onishi, Yasuo; Kivva, Sergey L.; Zheleznyak, Mark J.; Voitsekhovitch, Oleg V.

    2007-11-01T23:59:59.000Z

    This modeling study evaluated aquatic environment affected by the Chernobyl nuclear accident and the effectiveness of remediation efforts. Study results indicate that radionuclide concentrations in the Pripyat and Dnieper rivers were well above the drinking water limits immediately after the Chernobyl accident, but have decreased significantly in subsequent years due to flashing, burying, and decay. Because high concentrations of 90Sr and 137Cs, the major radionuclides affecting human health through aquatic pathways, are associated with flooding, an earthen dike was constructed along the Pripyat River in its most contaminated floodplain. The dike was successful in reducing the 90Sr influx to the river by half. A 100-m-high movable dome called the New Safe Confinement is planned to cover the Chernobyl Shelter (formally called the sarcophagus) that was erected shortly after the accident. The NSC will reduce radionuclide contamination further in these rivers and nearby groundwater; however, even if the Chernobyl Shelter collapses before the NSC is built, the resulting peak concentrations of 90Sr and 137Cs in the Dnieper River would still be below the drinking water limits.

  11. KERENA safety concept in the context of the Fukushima accident

    SciTech Connect (OSTI)

    Zacharias, T.; Novotny, C.; Bielor, E. [AREVA NP GmbH, Paul-Gossen-Strasse 100, 91052 Erlangen (Germany)

    2012-07-01T23:59:59.000Z

    Within the last three years AREVA NP and E.On KK finalized the basic design of KERENA which is a medium sized innovative boiling water reactor, based on the operational experience of German BWR nuclear power plants (NPPs). It is a generation III reactor design with a net electrical output of about 1250 MW. It combines active safety equipment of service-proven designs with new passive safety components, both safety classified. The passive systems utilize basic laws of physics, such as gravity and natural convection, enabling them to function without electric power. Even actuation of these systems is performed thanks to basic physic laws. The degree of diversity in component and system design, achieved by combining active and passive equipment, results in a very low core damage frequency. The Fukushima accident enhanced the world wide discussion about the safety of operating nuclear power plants. World wide stress tests for operating nuclear power plants are being performed embracing both natural and man made hazards. Beside the assessment of existing power plants, also new designs are analyzed regarding the system response to beyond design base accidents. KERENA's optimal combination of diversified cooling systems (active and passive) allows passing efficiently such tests, with a high level of confidence. This paper describes the passive safety components and the KERENA reactor behavior after a Fukushima like accident. (authors)

  12. Views of the solar system

    SciTech Connect (OSTI)

    Hamilton, C.

    1995-02-01T23:59:59.000Z

    Views of the Solar System has been created as an educational tour of the solar system. It contains images and information about the Sun, planets, moons, asteroids and comets found within the solar system. The image processing for many of the images was done by the author. This tour uses hypertext to allow space travel by simply clicking on a desired planet. This causes information and images about the planet to appear on screen. While on a planet page, hyperlinks travel to pages about the moons and other relevant available resources. Unusual terms are linked to and defined in the Glossary page. Statistical information of the planets and satellites can be browsed through lists sorted by name, radius and distance. History of Space Exploration contains information about rocket history, early astronauts, space missions, spacecraft and detailed chronology tables of space exploration. The Table of Contents page has links to all of the various pages within Views Of the Solar System.

  13. Chisolm View | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectricEnergyCTBarreisVolcanic National Park |Chile:CooperationChisolm View Jump

  14. For current viewing resistor loads

    DOE Patents [OSTI]

    Lyons, Gregory R. (Tijeras, NM); Hass, Jay B. (Lee's Summit, MO)

    2011-04-19T23:59:59.000Z

    The invention comprises a terminal unit for a flat cable comprising a BNC-PCB connector having a pin for electrically contacting one or more conducting elements of a flat cable, and a current viewing resistor having an opening through which the pin extends and having a resistor face that abuts a connector face of the BNC-PCB connector, wherein the device is a terminal unit for the flat cable.

  15. SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4

    SciTech Connect (OSTI)

    Hagrman, D.T. [ed.; Allison, C.M.; Berna, G.A. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)] [and others

    1995-06-01T23:59:59.000Z

    The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light -- water-reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission products released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume, Volume IV, describes the material properties correlations and computer subroutines (MATPRO) used by SCDAP/RELAP5. formulation of the materials properties are generally semi-empirical in nature. The materials property subroutines contained in this document are for uranium, uranium dioxide, mixed uranium-plutonium dioxide fuel, zircaloy cladding, zirconium dioxide, stainless steel, stainless steel oxide, silver-indium-cadmium alloy, cadmium, boron carbide, Inconel 718, zirconium-uranium-oxygen melts, fill gas mixtures, carbon steel, and tungsten. This document also contains descriptions of the reaction and solution rate models needed to analyze a reactor accident.

  16. Transient Accident Analysis of a Supercritical Carbon Dioxide Brayton Cycle Energy Converter Coupled to an Autonomous Lead-Cooled Fast Reactor

    SciTech Connect (OSTI)

    Moisseytsev, Anton; Sienicki, James J. [Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States)

    2006-07-01T23:59:59.000Z

    The Supercritical Carbon Dioxide (S-CO{sub 2}) Brayton Cycle is a promising advanced alternative to the Rankine saturated steam cycle and recuperated gas Brayton cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO{sub 2} Brayton cycle coupled to an autonomous, natural circulation Lead-Cooled Fast Reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios. (authors)

  17. Transient accident analysis of a supercritical carbon dioxide Brayton cycle energy converter coupled to an autonomous lead-cooled fast reactor.

    SciTech Connect (OSTI)

    Moisseytsev, A.; Sienicki, J. J.; Nuclear Engineering Division

    2008-08-01T23:59:59.000Z

    The supercritical carbon dioxide (S-CO{sub 2}) Brayton cycle is a promising advanced alternative to the Rankine steam cycle and recuperated gas Brayton cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO{sub 2} Brayton cycle coupled to an autonomous, natural circulation lead-cooled fast reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios.

  18. Analysis of main steam isolation valve leakage in design basis accidents using MELCOR 1.8.6 and RADTRAD.

    SciTech Connect (OSTI)

    Salay, Michael (United States Nuclear Regulatory Commission, Washington, D.C.); Kalinich, Donald A.; Gauntt, Randall O.; Radel, Tracy E.

    2008-10-01T23:59:59.000Z

    Analyses were performed using MELCOR and RADTRAD to investigate main steam isolation valve (MSIV) leakage behavior under design basis accident (DBA) loss-of-coolant (LOCA) conditions that are presumed to have led to a significant core melt accident. Dose to the control room, site boundary and LPZ are examined using both approaches described in current regulatory guidelines as well as analyses based on best estimate source term and system response. At issue is the current practice of using containment airborne aerosol concentrations as a surrogate for the in-vessel aerosol concentration that exists in the near vicinity of the MSIVs. This study finds current practice using the AST-based containment aerosol concentrations for assessing MSIV leakage is non-conservative and conceptually in error. A methodology is proposed that scales the containment aerosol concentration to the expected vessel concentration in order to preserve the simplified use of the AST in assessing containment performance under assumed DBA conditions. This correction is required during the first two hours of the accident while the gap and early in-vessel source terms are present. It is general practice to assume that at {approx}2hrs, recovery actions to reflood the core will have been successful and that further core damage can be avoided. The analyses performed in this study determine that, after two hours, assuming vessel reflooding has taken place, the containment aerosol concentration can then conservatively be used as the effective source to the leaking MSIV's. Recommendations are provided concerning typical aerosol removal coefficients that can be used in the RADTRAD code to predict source attenuation in the steam lines, and on robust methods of predicting MSIV leakage flows based on measured MSIV leakage performance.

  19. ParaView at NERSC

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratorySpeedingOptimizingToolsto control intensePageveterans4 - ParaView

  20. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    SciTech Connect (OSTI)

    Bertini, H.W.

    1980-04-01T23:59:59.000Z

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

  1. Cyclistes Victimes d'Accident (CVA) Partie 1 : caractristiques et bilan lsionnel

    E-Print Network [OSTI]

    Cyclistes Victimes d'Accident (CVA) Partie 1 : caractéristiques et bilan lésionnel Emmanuelle des victimes d'accidents à vélo - synthèse p. 2 Unité Mixte de Recherche �pidémiologique et de ­ caractéristiques et bilan lésionnel des victimes d'accidents à vélo - synthèse p. 3 Quelles sont les

  2. E-Print Network 3.0 - accident research network Sample Search...

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

    systems to prevent past accidents from reoccurring in the future. Current Source: Kelly, Tim - Department of Computer Science, University of York (UK) Collection: Computer...

  3. A comparative analysis of accident risks in fossil, hydro, and nuclear energy chains

    SciTech Connect (OSTI)

    Burgherr, P.; Hirschberg, S. [Paul Scherrer Institute, Villigen (Switzerland)

    2008-07-01T23:59:59.000Z

    This study presents a comparative assessment of severe accident risks in the energy sector, based on the historical experience of fossil (coal, oil, natural gas, and LPG (Liquefied Petroleum Gas)) and hydro chains contained in the comprehensive Energy-related Severe Accident Database (ENSAD), as well as Probabilistic Safety Assessment (PSA) for the nuclear chain. Full energy chains were considered because accidents can take place at every stage of the chain. Comparative analyses for the years 1969-2000 included a total of 1870 severe ({>=} 5 fatalities) accidents, amounting to 81,258 fatalities. Although 79.1% of all accidents and 88.9% of associated fatalities occurred in less developed, non-OECD countries, industrialized OECD countries dominated insured losses (78.0%), reflecting their substantially higher insurance density and stricter safety regulations. Aggregated indicators and frequency-consequence (F-N) curves showed that energy-related accident risks in non-OECD countries are distinctly higher than in OECD countries. Hydropower in non-OECD countries and upstream stages within fossil energy chains are most accident-prone. Expected fatality rates are lowest for Western hydropower and nuclear power plants; however, the maximum credible consequences can be very large. Total economic damages due to severe accidents are substantial, but small when compared with natural disasters. Similarly, external costs associated with severe accidents are generally much smaller than monetized damages caused by air pollution.

  4. E-Print Network 3.0 - accidents--worker compensation laws Sample...

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

    > >> 1 LEHIGH UNIVERSITY RESEARCH AND TESTING AGREEMENT Summary: ,000,000 aggregate. Automobile Liability at 1,000,000 each accident. Workers' Compensation at statutory limits......

  5. E-Print Network 3.0 - accident temporal correlation Sample Search...

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

    coefficient is 0... .76), while air crashes have a more closely correlation to automobile accidents (0.51). Ac- cording to Epov... ). The correlation between technological...

  6. E-Print Network 3.0 - accidents problemes sanitaires Sample Search...

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

    problemes sanitaires Search Powered by Explorit Topic List Advanced Search Sample search results for: accidents problemes sanitaires Page: << < 1 2 3 4 5 > >> 1 ECOLE NATIONALE DU...

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

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

    Board Report on the May 7, 1997, Worker Injury at the Hanford Site Canister Storage Building Construction Site, Richland, Washington Level 1 Accident Investigation Report of...

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

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

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

  9. E-Print Network 3.0 - accidents utilizing relap5 Sample Search...

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

    RELAP5 heat transfer in a single HFIR channel with HEU... the relaxation source terms associated with accident based transients Shift from RELAP5 1. Active acoustic...

  10. E-Print Network 3.0 - accident experimental facility Sample Search...

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

    Summary: -Frederick and NCI- Frederick off-site facilities. C. DEFINITIONS NA D. PROCEDURES All accidents involving HHS... 1 - August 2009 REPORTINGINVESTIGATION OF VEHICLE...

  11. E-Print Network 3.0 - accident management guidelines Sample Search...

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

    results for: accident management guidelines Page: << < 1 2 3 4 5 > >> 1 Emergency Procedures Guidelines Student Group Travel Off-Campus Activity Summary: Emergency Procedures...

  12. E-Print Network 3.0 - accident types Sample Search Results

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

    Classified University Faculty Other Days per weekWork Hours Per day Information... SSN Cell Phone Home Phone Work Phone Exact Location : Date of Accident : AM PM Date...

  13. E-Print Network 3.0 - accident prevention manual Sample Search...

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

    and responsibilities in the prevention of injuries associated with manual handling activities. A key component... help and advice Any relevant manual handling accident...

  14. E-Print Network 3.0 - accident management epr Sample Search Results

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

    Civil and Environmental Engineering, San Diego State University Collection: Engineering 33 Texas Tech University System First Report of InjuryIllnessAccident Summary: Texas...

  15. E-Print Network 3.0 - accident mitigation issues Sample Search...

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

    2 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: organizational issues. These results demonstrate conclusively that as far as...

  16. E-Print Network 3.0 - accident tolerable continual Sample Search...

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

    Engineering 2 A Technique for Showing Causal Arguments in Accident Reports C. W. Johnson; University of Glasgow; Glasgow, Scotland, UK Summary: A Technique for Showing Causal...

  17. E-Print Network 3.0 - accident situation study Sample Search...

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

    2 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: conducted some initial empirical studies into the benefits of reading...

  18. E-Print Network 3.0 - accident localisation system Sample Search...

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

    drivers to find out about previous accidents... Information System The ... Source: Johnson, Chris - Department of Computing Science, University of Glasgow Collection: Computer...

  19. E-Print Network 3.0 - accident management issues Sample Search...

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

    3 Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson Summary: organizational issues. These results demonstrate conclusively that as far as...

  20. E-Print Network 3.0 - alternative accident sequences Sample Search...

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

    Sciences 3 A Technique for Showing Causal Arguments in Accident Reports C. W. Johnson; University of Glasgow; Glasgow, Scotland, UK Summary: alternate positions on the...