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Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Report on a workshop on transportation-accident scenarios involving spent fuel  

SciTech Connect (OSTI)

Much confusion and skepticism resulted from the scenarios for transportation accidents involving spent fuel that have been presented in environmental impact statements because the supporting assumptions and conclusions from the scenarios did not always appear to be consistent. As a result, the Transportation Technology Center gathered a group whose participants were experts in disciplines related to the transport of spent fuel to consider the scenarios. The group made a number of recommendations about scenario development and about areas in need of further study. This report documents the discussions held and the recommendations and conclusions of the group.

Wilmot, E.L.; McClure, J.D.; Luna, R.E.

1981-02-01T23:59:59.000Z

2

Accident resistant transport container  

DOE Patents [OSTI]

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.

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

1980-01-01T23:59:59.000Z

3

Probability of spent fuel transportation accidents  

SciTech Connect (OSTI)

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.

McClure, J. D.

1981-07-01T23:59:59.000Z

4

Improving Transportation Safety Through Accident  

E-Print Network [OSTI]

;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

Minnesota, University of

5

DEVELOPMENT AND USE OF A DIRECTORY OF ACCIDENT DATABASES INVOLVING  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

6

Decontamination Dressdown at a Transportation Accident Involving  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergy CooperationRequirements Matrix DOE-STD-3009-2014ofOutline1:Department of

7

Chemical factors affecting fission product transport in severe LMFBR accidents  

SciTech Connect (OSTI)

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.

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

1984-10-01T23:59:59.000Z

8

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

E-Print Network [OSTI]

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

Minnesota, University of

9

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

10

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

E-Print Network [OSTI]

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

Kirschner, Denise

11

E-Print Network 3.0 - accidents involving fuel Sample Search...  

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

Education for the newspaper NRC- Summary: , since it tells you how many kilomters an automobile has to travel before it is involved in an accident... one kilometer by automobile...

12

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

E-Print Network [OSTI]

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

Aldrich, David C.

1979-01-01T23:59:59.000Z

13

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

SciTech Connect (OSTI)

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.

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

1992-06-01T23:59:59.000Z

14

Emergency Response to a Transportation Accident Involving Radioactive  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergy CooperationRequirementsDraft EnvironmentalRoadDepartment5-CE-14020)BUILDINGMaterial |

15

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

SciTech Connect (OSTI)

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

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

1990-01-01T23:59:59.000Z

16

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

SciTech Connect (OSTI)

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

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

1990-12-31T23:59:59.000Z

17

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...

18

Radioactive material (RAM) transportation accident and incident experience in the U.S.A. (1971--1997)  

SciTech Connect (OSTI)

The Radioactive Materials Incident Report (RMIR) database was developed in 1981 at the Transportation Technology Center of Sandia National Laboratories to support its research and development activities for the US Department of Energy (DOE). This database contains information about radioactive materials transportation incidents that have occurred in the US since 1971. These data were drawn from the US Department of Transportation`s (DOT) Hazardous Materials Incident Report system, from Nuclear Regulatory Commission (NRC) files, and from various agencies including state radiological control offices. Support for the RMIR data base is funded by the National Transportation Program (EM-70) of the US Department of Energy. Transportation events in RMIR are classified in one of the following ways: as a transportation accident, as a handling accident, or as a reported incident. This presentation will provide definitions for these classifications and give examples of each. The primary objective of this presentation is to provide information on nuclear materials transportation accident incident events in the US for the period 1971--1997. Among the areas to be examined are: transportation accidents by mode, package response during accidents and an examination of accidents where release of contents has occurred.

McClure, J.D.; Yoshimura, H.R.; Fagan, H.F. [Sandia National Labs., Albuquerque, NM (United States). Transportation Systems Analysis Dept.; Thomas, T. [Dept. of Energy National Transportation Program (United States)

1997-11-01T23:59:59.000Z

19

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

SciTech Connect (OSTI)

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.

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

2014-09-01T23:59:59.000Z

20

Release and transport of fission product cesium in the TMI-2 accident  

SciTech Connect (OSTI)

Approximately 50% of the fission product cesium was released from the overheated UO/sub 2/ fuel in the TMI-2 accident. Steam that boiled away from a water pool in the bottom of the reactor vessel transported the released fission products throughout the reactor coolant system (RCS). Some fission products passed directly through a leaking valve with steam and water into the containment structure, but most deposited on dry surfaces inside of the RCS before being dissolved or resuspended when the RCS was refilled with water. A cesium transport model was developed that extended measured cesium in the RCS back to the first day of the accident. The model revealed that approx.62% of the released /sup 137/Cs deposited on dry surfaces inside of the RCS before being slowly leached and transported out of the RCS in leaked or letdown water. The leach rates from the model agreed reasonably well with those measured in the laboratory. The chemical behavior of cesium in the TMI-2 accident agreed with that observed in fission product release tests at Oak Ridge National Laboratory (ORNL).

Lorenz, R.A.; Collins, J.L.

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Co-relation of Variables Involved in the Occurrence of Crane Accidents in U.S. through Logit Modeling.  

E-Print Network [OSTI]

technical challenges, which has lead to escalation of danger on a construction site. Data from OSHA show that crane accidents have increased rapidly from 2000 to 2004. By analyzing the characteristics of all the crane accident inspections, we can better...

Bains, Amrit Anoop Singh

2010-10-12T23:59:59.000Z

22

Shutdown mechanisms for a hypothetical criticality accident involving HEU powder: Preliminary results  

SciTech Connect (OSTI)

This work examines the physical processes that would cause an accidental criticality involving higly enriched uranium(HEU) powder to shut down naturally. The study analyses an excursion resulting from the continous poring of slightly damp HEU powder (either UO{sub 3} or UF{sub 4} containing 1.5% water) onto a concrete floor.

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

1994-12-31T23:59:59.000Z

23

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

SciTech Connect (OSTI)

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

Marsha Keister

2001-02-01T23:59:59.000Z

24

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

25

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

E-Print Network [OSTI]

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

Maalel, Ahmed

2012-01-01T23:59:59.000Z

26

TRANSPORT INVOLVING CONDUCTING FIBERS IN A NON-CONDUCTING MATRIX  

E-Print Network [OSTI]

result is a material with high electrical conductivity and low thermal conductivity. Transport Models,2 , J. Rozen3 Introduction Thermal and electrical transport through a low-conductivity matrix containing conversion devices high electrical conductivity and low thermal conductivity are preferred for superior

Walker, D. Greg

27

Dose estimates in a loss of lead shielding truck accident.  

SciTech Connect (OSTI)

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.

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

2009-08-01T23:59:59.000Z

28

Potential health risks from postulated accidents involving the Pu-238 RTG (radioisotope thermoelectric generator) on the Ulysses solar exploration mission  

SciTech Connect (OSTI)

Potential radiation impacts from launch of the Ulysses solar exploration experiment were evaluated using eight postulated accident scenarios. Lifetime individual dose estimates rarely exceeded 1 mrem. Most of the potential health effects would come from inhalation exposures immediately after an accident, rather than from ingestion of contaminated food or water, or from inhalation of resuspended plutonium from contaminated ground. For local Florida accidents (that is, during the first minute after launch), an average source term accident was estimated to cause a total added cancer risk of up to 0.2 deaths. For accidents at later times after launch, a worldwide cancer risk of up to three cases was calculated (with a four in a million probability). Upper bound estimates were calculated to be about 10 times higher. 83 refs.

Goldman, M. (California Univ., Davis, CA (USA)); Nelson, R.C. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Bollinger, L. (Air Force Inspection and Safety Center, Kirtland AFB, NM (USA)); Hoover, M.D. (Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (USA). Inhalation Toxicology Research Inst.); Templeton, W. (Pacific Northwest Lab., Richland, WA (USA)); Anspaugh, L. (Lawren

1990-11-02T23:59:59.000Z

29

ATP-binding cassette-like transporters are involved in the transport of lignin precursors across plasma and vacuolar membranes  

SciTech Connect (OSTI)

Lignin is a complex biopolymer derived primarily from the condensation of three monomeric precursors, the monolignols. The synthesis of monolignols occurs in the cytoplasm. To reach the cell wall where they are oxidized and polymerized, they must be transported across the cell membrane. However, the molecular mechanisms underlying the transport process are unclear. There are conflicting views about whether the transport of these precursors occurs by passive diffusion or is an energized active process; further, we know little about what chemical forms are required. Using isolated plasma and vacuolar membrane vesicles prepared from Arabidopsis, together with applying different transporter inhibitors in the assays, we examined the uptake of monolignols and their derivatives by these native membrane vesicles. We demonstrate that the transport of lignin precursors across plasmalemma and their sequestration into vacuoles are ATP-dependent primary-transport processes, involving ATP-binding cassette-like transporters. Moreover, we show that both plasma and vacuolar membrane vesicles selectively transport different forms of lignin precursors. In the presence of ATP, the inverted plasma membrane vesicles preferentially take up monolignol aglycones, whereas the vacuolar vesicles are more specific for glucoconjugates, suggesting that the different ATP-binding cassette-like transporters recognize different chemical forms in conveying them to distinct sites, and that glucosylation of monolignols is necessary for their vacuolar storage but not required for direct transport into the cell wall in Arabidopsis.

Miao, Y.C.; Liu, C.

2010-12-28T23:59:59.000Z

30

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

E-Print Network [OSTI]

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

Johnson, C.W.

31

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

E-Print Network [OSTI]

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

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

2012-01-01T23:59:59.000Z

32

Unavoidable Accident  

E-Print Network [OSTI]

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’

Grady, Mark F.

2009-01-01T23:59:59.000Z

33

NORTHWESTERN UNIVERSITY ACCIDENT REPORT FORM  

E-Print Network [OSTI]

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

Shahriar, Selim

34

Accident Response Group  

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

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.

1991-09-20T23:59:59.000Z

35

Abstract--Petroleum transportation accidents often cause losses of millions of dollars and take human lives. SIGA  

E-Print Network [OSTI]

Pessoal de NĂ­vel Superior (CAPES)/Fund for the Improvement of Secondary Education (FIPSE) Grant for the US of an Accident/Incident Reporting System--safety information systems utilized by large companies to monitor, but did not. ) [1]. The system has been in existence since 2002, and since its creation has registered

Virginia, University of

36

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

Broader source: Energy.gov [DOE]

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

37

Accident Investigations  

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

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

2011-03-04T23:59:59.000Z

38

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

SciTech Connect (OSTI)

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

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

1992-02-01T23:59:59.000Z

39

COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS  

SciTech Connect (OSTI)

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.

S.O. Bader

1999-10-18T23:59:59.000Z

40

Accident Investigations  

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

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

1996-04-26T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Accident Investigations  

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

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

1995-10-26T23:59:59.000Z

42

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,...

43

An analysis of factors contributing to train-involved crashes  

E-Print Network [OSTI]

. Crashes involving trains and vehicles are a significant safety problem in Texas each year. This research attempts to identify and analyze contributing factors to train-involved accidents in Texas. Three years of accident data (1328 total accidents) were...

Cooner, Scott Allen

1995-01-01T23:59:59.000Z

44

Transport involving conducting fibers in a non-conducting matrix R. A. Hansela  

E-Print Network [OSTI]

result is a material with high electrical conduc- tivity and low thermal conductivity. If we consider, conducting fibers, thin-film devices 1. Introduction Thermal and electrical transport through a low to predict conductance of the combined system. However, if the two materials are similar in conductivity

Walker, D. Greg

45

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

46

STATE OF CALIFORNIA -DGS ORIM VEHICLE ACCIDENT REPORT  

E-Print Network [OSTI]

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

Ponce, V. Miguel

47

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

E-Print Network [OSTI]

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

Farritor, Shane

48

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...

49

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,...

50

Commercial SNF Accident Release Fractions  

SciTech Connect (OSTI)

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.

J. Schulz

2004-11-05T23:59:59.000Z

51

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

E-Print Network [OSTI]

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

Azevedo, Ricardo

52

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...

53

Simulation of transportation of low enriched uranium solutions  

SciTech Connect (OSTI)

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

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

1996-08-01T23:59:59.000Z

54

Assessment of the risk of transporting propane by truck and train  

SciTech Connect (OSTI)

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

Geffen, C.A.

1980-03-01T23:59:59.000Z

55

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

56

Employee Accident / Incident Investigation Report Employee Name _________________________________________________________________  

E-Print Network [OSTI]

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

Long, Nicholas

57

REAC/TS Radiation Accident Registry: An Overview  

SciTech Connect (OSTI)

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.

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

58

Investigation of transport process involved in FGD. Final technical report for the third year, September 1992--August 1993  

SciTech Connect (OSTI)

This report describes the work done in the third year of the project {open_quotes}Investigation of Transport Processes Involved in FGD{close_quotes}. The objectives of this five year plan of study is to experimentally obtain a basic understanding of (1) turbulent flow structure of the mixing zone and its influence on particle dispersion, (2) the effect of particle loading on turbulent properties and mixing, (3) the effect of jet entrainment, (4) water spray-sorbent interaction, sorbent wetting and mixing, (5) investigate the flow field where certain ratios of jet velocity to flue gas velocity result in regions of negative flow and define onset of negative flow (6) sorbent reactivity in mixing zone and (7) effect of particle agglomeration. In the first two years of the project a sorbent injection facility which can simulate the conditions encountered in COOLSIDE set up was designed and built. Non-intrusive laser based diagnostic tools PDA/LDA was used for flow characterization of particle laden jet in cocurrent flows. All tasks for third year were addressed. The accomplishments for the third year include the following. For the investigation of Lime Laden Jet Flow, since no existing technique was capable of providing the simultaneous measurement of irregular shaped particle size and velocity, a new technique, TTLDV which utilizes the transit time in LDV measurement volume and the LDV velocity measurements to obtain simultaneous particle size and velocity measurements was developed. Better Sorbent Injection Methods and Optimized Injection Schemse were investigated. Progress was made in the development of Technique to Study Particulate Droplet Interactions, the task was not completed because of difficulties encountered due to differences in the refractive index of glass beads and water droplets. The investigations of flow reversal resulting from spray jet cocurrent flow interactions was completed.

Kadambi, J.R.; Kadaba, V.; Yurteri, C.

1993-09-01T23:59:59.000Z

59

Radionuclide release calculations for selected severe accident scenarios  

SciTech Connect (OSTI)

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.

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

60

Placental findings in cord accidents  

E-Print Network [OSTI]

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

Parast, Mana M

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

The Accident Externality from Driving  

E-Print Network [OSTI]

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

Edlin, Aaron S.; Karaca-Mandic, Pinar

2007-01-01T23:59:59.000Z

62

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

E-Print Network [OSTI]

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...

Hayes, Carolyn A

1997-01-01T23:59:59.000Z

63

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

E-Print Network [OSTI]

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

Suzuki, Masatsugu

64

Interpreting Accident Statistics  

E-Print Network [OSTI]

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 ...

Ferreira, Joseph Jr.

65

A Road Accident  

E-Print Network [OSTI]

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...

G.yu lha

66

Transportation  

E-Print Network [OSTI]

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

Vinson, Steve

2013-01-01T23:59:59.000Z

67

Group Accident Insurance Certificate  

E-Print Network [OSTI]

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

New Mexico, University of

68

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

E-Print Network [OSTI]

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

Arnold, Jonathan

69

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

E-Print Network [OSTI]

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

Kelly, Scott David

70

E-Print Network 3.0 - accident analysis documentation Sample...  

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

and Data Analysis, 2000). This has... Research Record 1487, 68-74. Grder, P., 1994. Bicycle accidents in Maine: an analysis. Transportation... at signalized intersections,...

71

Accidents, engineering and history at NASA: 1967-2003  

E-Print Network [OSTI]

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 ...

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

2009-01-01T23:59:59.000Z

72

Chernobyl accident: A comprehensive risk assessment  

SciTech Connect (OSTI)

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.

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

1999-11-01T23:59:59.000Z

73

Chernobyl accident: A comprehensive risk assessment  

SciTech Connect (OSTI)

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.

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

1999-01-01T23:59:59.000Z

74

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,...

75

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

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

76

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

E-Print Network [OSTI]

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

Thaxton, Christopher S.

77

The Accident Externality from Driving  

E-Print Network [OSTI]

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

Edlin, Aaron S.; Karaca-Mandic, Pinar

2005-01-01T23:59:59.000Z

78

The Accident Externality from Driving  

E-Print Network [OSTI]

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

Edlin, Aaron S.; Karaca-Mandic, Pinar

2003-01-01T23:59:59.000Z

79

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

E-Print Network [OSTI]

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

Stoddard, Angela May

1994-01-01T23:59:59.000Z

80

A framework for the assessment of severe accident management strategies  

SciTech Connect (OSTI)

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.

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

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

TIPS ON ACCIDENT/INCIDENT REPORTING Accident Reporting Why?  

E-Print Network [OSTI]

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

Lennard, William N.

82

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

E-Print Network [OSTI]

http://travel.state.gov/travel/about/who/who_1245.html AT THE SCENE OF AN ACCIDENT FORM AT THE SCENE, FILL OUT THE BELOW INFORMATION ORS 811.700 REQUIRES DRIVERS INVOLVED IN AN ACCIDENT TO EXCHANGE-737-7252 or risk@oregonstate.edu IMMEDIATELY if this was a serious accident (i.e. ambulance involved, vehicle towed

Tullos, Desiree

83

Lessons learned from early criticality accidents  

SciTech Connect (OSTI)

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.

Malenfant, R.E.

1996-06-01T23:59:59.000Z

84

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...

85

E-Print Network 3.0 - accident heat transfer Sample Search Results  

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

accident situations involving hundreds of kilograms... of the expansion, heat transfer is small and therefore fuel-coolant mixing and hydro- dynamics must be considered... from the...

86

Transportation  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatusButler TinaContact-Information-Transmission SignTransport

87

ACCIDENT TOLERANT FUEL ANALYSIS  

SciTech Connect (OSTI)

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.

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

88

Accident Tolerant Fuel Analysis  

SciTech Connect (OSTI)

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.

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

2014-09-01T23:59:59.000Z

89

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...

90

Estimating Pedestrian Accident Exposure: Protocol Report  

E-Print Network [OSTI]

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,

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

2007-01-01T23:59:59.000Z

91

Bicycle Accident 12/21/11 and Consequences S. J. Peale In riding my bicycle to work, I have a choice between two routes: 1. Over Fairview overpass  

E-Print Network [OSTI]

Bicycle Accident 12/21/11 and Consequences S. J. Peale In riding my bicycle to work, I have put into an ambulance for transport to Cottage Hospital Trauma Center. From the accident report

Fygenson, Deborah Kuchnir

92

SAS4A LMFBR whole core accident analysis code  

SciTech Connect (OSTI)

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.

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

93

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

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

94

Accident at Creswell Colliery, Derbyshire   

E-Print Network [OSTI]

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 ...

Bryan, Andrew

95

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

96

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

E-Print Network [OSTI]

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

97

Electrical shock accident investigation  

SciTech Connect (OSTI)

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.

Not Available

1994-09-30T23:59:59.000Z

98

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

SciTech Connect (OSTI)

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

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

1995-10-01T23:59:59.000Z

99

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

SciTech Connect (OSTI)

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

Blanchard, A.

1999-04-15T23:59:59.000Z

100

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,...

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

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

E-Print Network [OSTI]

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

Sielecki, Leonard E.

2001-01-01T23:59:59.000Z

102

BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE  

E-Print Network [OSTI]

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

Suzuki, Masatsugu

103

BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE  

E-Print Network [OSTI]

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

Suzuki, Masatsugu

104

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

105

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

E-Print Network [OSTI]

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

Thaxton, Christopher S.

106

University of Pittsburgh Vehicle Accident Report Form  

E-Print Network [OSTI]

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

Sibille, Etienne

107

Exact Location : Date of Accident : AM PM  

E-Print Network [OSTI]

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

Swaddle, John

108

Bordereau de transmission accident du travail  

E-Print Network [OSTI]

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

Pouyanne, Nicolas

109

An Interview About an Accident  

E-Print Network [OSTI]

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...

G.yu lha

2009-12-17T23:59:59.000Z

110

Parent Involvement  

E-Print Network [OSTI]

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

Howard, Jeff W.

2005-05-10T23:59:59.000Z

111

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

E-Print Network [OSTI]

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

Karczmarek, Joanna

112

Graphite Oxidation Simulation in HTR Accident Conditions  

SciTech Connect (OSTI)

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.

Mohamed El-Genk

2012-10-19T23:59:59.000Z

113

Dualmode transportation - impact on the electric grid  

E-Print Network [OSTI]

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

Azcarate Lara, Francisco Javier

2009-05-15T23:59:59.000Z

114

Dualmode transportation - impact on the electric grid  

E-Print Network [OSTI]

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

Azcarate Lara, Francisco Javier

2008-10-10T23:59:59.000Z

115

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...

116

The Wildlife Accident Reporting System (WARS) in British Columbia  

E-Print Network [OSTI]

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

Sielecki, Leonard E.

2003-01-01T23:59:59.000Z

117

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...

118

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...

119

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...

120

Estimating Pedestrian Accident Exposure: Automated Pedestrian Counting Devices Report  

E-Print Network [OSTI]

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

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

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Accident Conditions versus Regulatory Test for NRC-Approved UF6 Packages  

SciTech Connect (OSTI)

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.

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

2003-01-01T23:59:59.000Z

122

BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE  

E-Print Network [OSTI]

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

Suzuki, Masatsugu

123

RICE UNIVERSITY ACCIDENT/INJURY REPORT  

E-Print Network [OSTI]

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

Natelson, Douglas

124

Analysis of accidents during flashing operations  

E-Print Network [OSTI]

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...

Obermeyer, Michael Edward

1993-01-01T23:59:59.000Z

125

UWO Vehicle ACCIDENT REPORTING FORM  

E-Print Network [OSTI]

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

Sinnamon, Gordon J.

126

ASSESSING CAUSAL FACTORS IN INDIVIDUAL ROAD ACCIDENTS  

E-Print Network [OSTI]

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

Minnesota, University of

127

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

128

DESCRIPTION OF ACCIDENT MSU DRIVERS SIGNATURE  

E-Print Network [OSTI]

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

Dyer, Bill

129

INTERNATIONAL STUDENT & SCHOLAR Accident & Sickness Insurance Plan  

E-Print Network [OSTI]

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

Bordenstein, Seth

130

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

SciTech Connect (OSTI)

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

NONE

1999-04-01T23:59:59.000Z

131

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

SciTech Connect (OSTI)

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

Youngen, G.

1988-10-01T23:59:59.000Z

132

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

SciTech Connect (OSTI)

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).

NONE

1991-09-01T23:59:59.000Z

133

RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel  

SciTech Connect (OSTI)

This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows{trademark} environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident.

Yuan, Y.C. [Square Y Consultants, Orchard Park, NY (US); Chen, S.Y.; Biwer, B.M.; LePoire, D.J. [Argonne National Lab., IL (US)

1995-11-01T23:59:59.000Z

134

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

135

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...

136

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...

137

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...

138

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...

139

Transporting radioactive materials: Q & A to your questions  

SciTech Connect (OSTI)

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

Not Available

1993-04-01T23:59:59.000Z

140

Accident Report Form Victim's Name  

E-Print Network [OSTI]

: Transported By: First Aid By: Witness Phone: Method of Transportation: ID# Male Female Time of Injury: am/pm Phone: [pink form] Age: Time Notified: am/pm Student Faculty Staff Public: Open Rec Aquatics COA Fitness an alcohol/water solution. - Dispose of the contaminated supplies (gauze, gloves, paper towel, etc.) using

Amin, S. Massoud

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

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

SciTech Connect (OSTI)

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

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

2012-09-30T23:59:59.000Z

142

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,...

143

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,...

144

HEALTH EFFECTS OF THE NUCLEAR ACCIDENT AT THREE MILE ISLAND  

E-Print Network [OSTI]

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

Fabrikant, J.I.

2010-01-01T23:59:59.000Z

145

HEALTH EFFECTS OF THE NUCLEAR ACCIDENT AT THREE MILE ISLAND  

E-Print Network [OSTI]

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,

Fabrikant, J.I.

2010-01-01T23:59:59.000Z

146

Does Daylight Savings Time Affect Traffic Accidents?  

E-Print Network [OSTI]

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...

Deen, Sophia 1988-

2012-04-20T23:59:59.000Z

147

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

E-Print Network [OSTI]

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

Johnson, Peter D.

148

The Fukushima Daiichi Accident Study Information Portal  

SciTech Connect (OSTI)

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.

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

2012-11-01T23:59:59.000Z

149

EVALUATION DES CONSEQUENCES D'ACCIDENTS DE TRANSPORT  

E-Print Network [OSTI]

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

Boyer, Edmond

150

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,...

151

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...

152

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 -...

153

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...

154

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...

155

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

156

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...

157

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,...

158

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...

159

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...

160

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

SciTech Connect (OSTI)

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

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

1997-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

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

SciTech Connect (OSTI)

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

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

1991-09-01T23:59:59.000Z

162

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

E-Print Network [OSTI]

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

Wang, Yinhai

163

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

E-Print Network [OSTI]

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

Jiang, Wen

164

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

E-Print Network [OSTI]

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

US Army Corps of Engineers

165

UoS Motor Accident Report Form COMPANY DETAILS  

E-Print Network [OSTI]

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

Sussex, University of

166

MELCOR accident analysis for ARIES-ACT  

E-Print Network [OSTI]

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

California at San Diego, University of

167

Review of models applicable to accident aerosols  

SciTech Connect (OSTI)

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.

Glissmeyer, J.A.

1983-07-01T23:59:59.000Z

168

An Investigation of the Therac-25 Accidents  

E-Print Network [OSTI]

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

Yang, Junfeng

169

A systems approach to food accident analysis  

E-Print Network [OSTI]

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. ...

Helferich, John D

2011-01-01T23:59:59.000Z

170

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

SciTech Connect (OSTI)

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.

Collins, E.D.

1982-01-01T23:59:59.000Z

171

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

E-Print Network [OSTI]

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

Su, Xiao

172

Enriching Sustainable Transport Decisions: Inputs from Operations Research and the Management Sciences  

E-Print Network [OSTI]

to decision processes involving sustainable transportused to enrich sustainable transport decision processes andthe process of making decisions about sustainable transport

Wellar, Barry; Garrison, William

2009-01-01T23:59:59.000Z

173

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

174

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

SciTech Connect (OSTI)

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.

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

1988-05-01T23:59:59.000Z

175

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

SciTech Connect (OSTI)

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.

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

1993-11-01T23:59:59.000Z

176

Accident simulation and consequence analysis in support of MHTGR safety evaluations  

SciTech Connect (OSTI)

This paper summarizes research performed at Oak Ridge National Laboratory (ORNL) to assist the Nuclear Regulatory Commission (NRC) in preliminary determinations of licensability of the US Department of Energy (DOE) reference design of a standard modular high-temperature gas-cooled reactor (MHTGR). The work described includes independent analyses of core heatup and steam ingress accidents, and the reviews and analyses of fuel performance and fission product transport technology.

Ball, S.J.; Wichner, R.P.; Smith, O.L.; Conklin, J.C. (Oak Ridge National Lab., TN (United States)); Barthold, W.P. (Barthold Associates, Inc., Knoxville, TN (United States))

1991-01-01T23:59:59.000Z

177

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...

178

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 ...

179

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 ...

180

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 ...

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

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...

182

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...

183

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...

184

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...

185

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

E-Print Network [OSTI]

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

Premo, Dean B.; Rogers, Elizabeth I.

2001-01-01T23:59:59.000Z

186

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

E-Print Network [OSTI]

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

Hornstein, Emily Putnam

2010-01-01T23:59:59.000Z

187

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

E-Print Network [OSTI]

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

Gibson, JH; Schröder, I; Wayne, NL

2014-01-01T23:59:59.000Z

188

ORNL experiments to characterize fuel release from the reactor primary containment in severe LMFBR accidents  

SciTech Connect (OSTI)

This paper presents results from aerosol source term experiments performed in the ORNL Aerosol Release and Transport (ART) Program sponsored by the US NRC. The tests described were performed to provide information on fuel release from an LMFBR primary containment as a result of a hypothetical core-disruptive accident (HCDA). The release path investigated in these tests assumes that a fuel/sodium bubble is formed after disassembly that transports fuel and fission products through the sodium coolant and cover gas to be relased into the reactor secondary containment. Due to the excellent heat transfer characteristics of the sodium, there is potential for large attenuation of the maximum release.

Wright, A.L.; Kress, T.S.; Smith, A.M.

1980-01-01T23:59:59.000Z

189

Commitment to Public Involvement  

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

Create a Sustainable Future Commitment to Public Involvement Commitment to Public Involvement LANL is commited to our neighbors August 1, 2013 Lab Director McMillan talks with...

190

Assessment of CRBR core disruptive accident energetics  

SciTech Connect (OSTI)

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.

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

1984-03-01T23:59:59.000Z

191

Enhanced Accident Tolerant LWR Fuels: Metrics Development  

SciTech Connect (OSTI)

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.

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

2013-09-01T23:59:59.000Z

192

Structural aspects of the Chernobyl accident  

SciTech Connect (OSTI)

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.

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

1988-09-02T23:59:59.000Z

193

A Review of Criticality Accidents 2000 Revision  

SciTech Connect (OSTI)

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.

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

2000-05-01T23:59:59.000Z

194

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

SciTech Connect (OSTI)

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.

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

195

Combining information processing, personality, and demographic variables to predict motor vehicle crash involvement  

E-Print Network [OSTI]

and reflects attitudes, beliefs, and motivations of drivers (Elander et al. , 1993). McGwire (1976) has suggested that, in general, people who are involved in accidents are emotionally immature, irresponsible, unhappy, and more likely to have a disturbed... crashes, although this approach is often successfully used in other areas. For instance, Hansen (1989) proposed a viable model of the cause of industrial accidents that included biodata, personality, and cognitive factors. As suggested by Lawton...

Hanson, Amber Ann

2000-01-01T23:59:59.000Z

196

LESSONS LEARNED FROM A RECENT LASER ACCIDENT  

SciTech Connect (OSTI)

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.

Woods, Michael; /SLAC

2011-01-26T23:59:59.000Z

197

The temporal effect of traffic violations and accidents on accident occurrence  

E-Print Network [OSTI]

, 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...

McKemie, Martha Susan

1979-01-01T23:59:59.000Z

198

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

SciTech Connect (OSTI)

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

ALDERMAN, C.A.

2000-09-19T23:59:59.000Z

199

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...

200

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...

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

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...

202

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...

203

L'accident la centrale nuclaire de Quelques explications scientifiques  

E-Print Network [OSTI]

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

Skorobogatiy, Maksim

204

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

205

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

E-Print Network [OSTI]

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

Jawitz, James W.

206

For the mathematically accident prone student W Stephen Wilson  

E-Print Network [OSTI]

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

Wilson, W. Stephen

207

A New Accident Model for Engineering Safer Systems Nancy Leveson  

E-Print Network [OSTI]

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

Leveson, Nancy

208

Structure Evolution of Dynamic Bayesian Network for Traffic Accident Detection  

E-Print Network [OSTI]

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

Cho, Sung-Bae

209

COMPARING THE IDENTIFICATION OF RECOMMENDATIONS BY DIFFERENT ACCIDENT  

E-Print Network [OSTI]

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

Johnson, Chris

210

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

211

A STAMP ANALYSIS OF THE LEX COMAIR 5191 ACCIDENT  

E-Print Network [OSTI]

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

Leveson, Nancy

212

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

E-Print Network [OSTI]

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

Long, Nicholas

213

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

E-Print Network [OSTI]

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

Jia, Songtao

214

CLAIMANT AUTO ACCIDENT REPORT For Completion by Driver  

E-Print Network [OSTI]

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

Tullos, Desiree

215

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

E-Print Network [OSTI]

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

Jr, Hiram Larangeira de Almeida; Fiss, Roberto Coswig

2008-01-01T23:59:59.000Z

216

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]

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

Leveson, Nancy

217

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]

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

Borenstein, Elhanan

218

Broken Arrows: Radiological hazards from nuclear warhead accidents (the Minot USAF base nuclear weapons incident)  

E-Print Network [OSTI]

According to numerous press reports, in 2007 at Minot US Air Force Base six AGM-129 Advanced Cruise Missiles mistakenly armed with W80-1 thermonuclear warheads were loaded on a B-52H heavy bomber in place of six unarmed AGM-129 missiles that were awaiting transport to Barksdale US Air Force Base for disposal. The live nuclear missiles were not reported missing, and stood unsecured and unguarded while mounted to the aircraft for a period of 36 hours. The present work investigates the radiological hazards associated with a worst-case postulated accident that would disperse the nuclear material of the six warheads in large metropolitan cities. Using computer simulations approximate estimates are derived for the ensuing cancer mortality and land contamination after the accident. Health, decontamination and evacuation costs are also estimated in the framework of the linear risk model.

Liolios, Theodore

2009-01-01T23:59:59.000Z

219

Evaluation Metrics Applied to Accident Tolerant Fuels  

SciTech Connect (OSTI)

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.

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

2014-10-01T23:59:59.000Z

220

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

SciTech Connect (OSTI)

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.

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

2010-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

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

SciTech Connect (OSTI)

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

Morris, Robert Noel [ORNL

2008-03-01T23:59:59.000Z

222

EPR Severe Accident Threats and Mitigation  

SciTech Connect (OSTI)

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)

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

223

US Department of Energy Chernobyl accident bibliography  

SciTech Connect (OSTI)

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.

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

1992-04-01T23:59:59.000Z

224

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

SciTech Connect (OSTI)

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

Layne Pincock; Wendell Hintze; Dr. Koji Shirai

2012-07-01T23:59:59.000Z

225

Transportation Services  

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

Transportation Services Transporting nuclear materials within the United States and throughout the world is a complicated and sometimes highly controversial effort requiring...

226

Local Transportation  

E-Print Network [OSTI]

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

227

Greening Transportation  

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

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

228

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

SciTech Connect (OSTI)

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

Conard, R.A.

1992-09-01T23:59:59.000Z

229

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

SciTech Connect (OSTI)

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.

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

1984-04-01T23:59:59.000Z

230

E-Print Network 3.0 - accidents involving radioactive Sample...  

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

of Mechanical Engineering, University of Nebraska-Lincoln Collection: Engineering 4 Spatial Data Analysis and Modeling of Radioactively-Contaminated Territories: Lessons...

231

Chamber transport  

SciTech Connect (OSTI)

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

OLSON,CRAIG L.

2000-05-17T23:59:59.000Z

232

Involvement and Communication Committee.  

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

Public Involvement and Communication Committee Chair 1 : Liz Mattson 4 , Alternate Vice Chair 1 : Ken Niles 4 , Member Committee Members 2 : Shelley Cimon Peggy Maze Johnson Rob...

233

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

SciTech Connect (OSTI)

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

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

1996-12-30T23:59:59.000Z

234

Transportation of medical isotopes  

SciTech Connect (OSTI)

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

Nielsen, D.L.

1997-11-19T23:59:59.000Z

235

Spent Fuel Transportation Cask Response to the Caldecott Tunnel Fire Scenario  

SciTech Connect (OSTI)

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

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

2007-01-01T23:59:59.000Z

236

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)

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.

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

1992-09-01T23:59:59.000Z

237

Application of NUREG-1150 methods and results to accident management  

SciTech Connect (OSTI)

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.

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

1990-01-01T23:59:59.000Z

238

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

Broader source: Energy.gov [DOE]

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

239

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

SciTech Connect (OSTI)

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.

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

2007-11-01T23:59:59.000Z

240

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

SciTech Connect (OSTI)

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

Kelsey, Charles T. IV [Los Alamos National Laboratory

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

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

SciTech Connect (OSTI)

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

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

1994-12-01T23:59:59.000Z

242

Interdisciplinary Institute for Innovation Le risque d'accident nuclaire  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

243

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...

244

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,...

245

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,...

246

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...

247

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 *...

248

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...

249

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,...

250

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,...

251

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...

252

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...

253

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,...

254

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...

255

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...

256

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...

257

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...

258

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...

259

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...

260

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...

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

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...

262

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...

263

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...

264

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...

265

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

266

Georgia Hosts Multi-Agency Waste Isolation Pilot Plant Transportation Exercise  

Broader source: Energy.gov [DOE]

COVINGTON, Ga. – Emergency personnel throughout the U.S. who respond in the event of a potential accident involving radioactive waste shipments take part in mock training scenarios to help them prepare for an actual incident.

267

Transportation risk assessment for ethanol transport  

E-Print Network [OSTI]

the quantitative risks involved with an ethanol pipeline. Pipelines that run from the Midwest, where the vast majority of ethanol is produced, to the target areas where reformulated gasoline is required (California, Texas Gulf Coast, New England Atlantic Coast... Atlantic Coast because of the large volume. It is beneficial to look at these areas as opposed to the iv smaller areas because pipeline transportation requires very large volumes. In order to find a meaningful comparison between all three...

Shelton Davis, Anecia Delaine

2008-10-10T23:59:59.000Z

268

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

E-Print Network [OSTI]

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

Isabirye, Stephen B.

1989-01-01T23:59:59.000Z

269

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

SciTech Connect (OSTI)

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.

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

270

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).

271

Material Selection for Accident Tolerant Fuel Cladding  

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

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

none,

2014-07-01T23:59:59.000Z

272

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...

273

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...

274

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...

275

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...

276

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...

277

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,...

278

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.

279

E-Print Network 3.0 - accident conditions lessons 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: the lessons that are really taught by an accident or group of accidents....

280

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

E-Print Network [OSTI]

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.

Rogers, Elizabeth I.

2003-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Road traffic accidents in Kathmandużan hour of education yields a glimmer of hope  

E-Print Network [OSTI]

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

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

2013-01-01T23:59:59.000Z

282

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

E-Print Network [OSTI]

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,

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

2007-01-01T23:59:59.000Z

283

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

E-Print Network [OSTI]

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

Kronzucker, Herbert J.

284

The 2011 Tohoku earthquake, tsunami, and Fukushima nuclear accident  

E-Print Network [OSTI]

? 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

Ferrari, Silvia

285

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

SciTech Connect (OSTI)

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.

POWERS, T.B.

2000-03-20T23:59:59.000Z

286

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation  

SciTech Connect (OSTI)

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.

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

2000-03-23T23:59:59.000Z

287

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...

288

Risk factors for injury accidents among moped and motorcycle riders  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

289

Berkeley Lab Accident Statistics Through December 31, 2008  

E-Print Network [OSTI]

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

Eisen, Michael

290

Berkeley Lab Accident Statistics Through January 31, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

291

Berkeley Lab Accident Statistics Through November 30, 2008  

E-Print Network [OSTI]

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

Eisen, Michael

292

Berkeley Lab Accident Statistics Through November 30, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

293

Berkeley Lab Accident Statistics Through February 28, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

294

Berkeley Lab Accident Statistics Through August 31, 2008  

E-Print Network [OSTI]

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

Eisen, Michael

295

Berkeley Lab Accident Statistics Through April 30, 2010  

E-Print Network [OSTI]

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

Eisen, Michael

296

Berkeley Lab Accident Statistics Through May 31, 2010  

E-Print Network [OSTI]

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

Eisen, Michael

297

Berkeley Lab Accident Statistics Through June 30, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

298

Berkeley Lab Accident Statistics Through January 31, 2010  

E-Print Network [OSTI]

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

Eisen, Michael

299

Berkeley Lab Accident Statistics Through October 31, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

300

Berkeley Lab Accident Statistics Through September 30, 2008  

E-Print Network [OSTI]

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

Eisen, Michael

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Berkeley Lab Accident Statistics Through April 30, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

302

Berkeley Lab Accident Statistics Through December 31, 2010  

E-Print Network [OSTI]

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

Eisen, Michael

303

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...

304

CASE STUDY FOR ENHANCED ACCIDENT TOLERANCE DESIGN CHANGES  

SciTech Connect (OSTI)

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

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

2014-09-01T23:59:59.000Z

305

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

SciTech Connect (OSTI)

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.

Audin, L.

1990-12-01T23:59:59.000Z

306

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

SciTech Connect (OSTI)

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

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

1995-02-01T23:59:59.000Z

307

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

E-Print Network [OSTI]

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

Johnson, Chris

308

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...

309

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...

310

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

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

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

311

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...

312

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...

313

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...

314

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...

315

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

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

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

316

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...

317

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...

318

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...

319

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....

320

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...

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While these samples are representative of the content of NLEBeta,
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321

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...

322

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...

323

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....

324

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...

325

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...

326

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....

327

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....

328

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...

329

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,...

330

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...

331

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....

332

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...

333

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...

334

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......

335

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 -...

336

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...

337

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...

338

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...

339

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...

340

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...

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

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...

342

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...

343

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...

344

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....

345

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...

346

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...

347

MELCOR accident analysis for ARIES-ACT  

SciTech Connect (OSTI)

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.

Paul W. Humrickhouse; Brad J. Merrill

2012-08-01T23:59:59.000Z

348

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

SciTech Connect (OSTI)

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

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

1986-01-01T23:59:59.000Z

349

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

Broader source: Energy.gov [DOE]

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

350

Accident Response Group | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

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

351

TRANSPORT INVOLVING CONDUCTING FIBERS IN A NON-CONDUCTING MATRIX  

E-Print Network [OSTI]

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

Walker, D. Greg

352

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

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

353

ASI Student Involvement Outcomes ASI Student Involvement Outcomes  

E-Print Network [OSTI]

ASI Student Involvement Outcomes ASI Student Involvement Outcomes A student involved in the activities, programs, and services of the Associated Students, CSUF, Inc. develops and demonstrates achievement in the following (adopted from the University of Minnesota Student Success Outcomes

de Lijser, Peter

354

Post-accident inhalation exposure and experience with plutonium  

SciTech Connect (OSTI)

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).

Shinn, J

1998-06-01T23:59:59.000Z

355

Transportation Security  

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

Preliminary Draft - For Review Only 1 Transportation Security Draft Annotated Bibliography Review July 2007 Preliminary Draft - For Review Only 2 Work Plan Task * TEC STG Work...

356

Computational Transportation  

E-Print Network [OSTI]

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

Illinois at Chicago, University of

357

Transportation Institutional Plan  

SciTech Connect (OSTI)

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

Not Available

1986-08-01T23:59:59.000Z

358

The Accident at Fukushima: What Happened?  

SciTech Connect (OSTI)

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.

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

2012-07-01T23:59:59.000Z

359

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

360

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

E-Print Network [OSTI]

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

Calgary, University of

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Analysis of a hypothetical criticality accident in a waste supercompactor  

SciTech Connect (OSTI)

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.

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

362

Response of Soviet VVER-440 accident localization systems to overpressurization  

SciTech Connect (OSTI)

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.

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

1989-01-01T23:59:59.000Z

363

Modeling control room crews for accident sequence analysis  

E-Print Network [OSTI]

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 ...

Huang, Y. (Yuhao)

1991-01-01T23:59:59.000Z

364

Failsafe : living with man-made disaster and accident  

E-Print Network [OSTI]

"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 ...

Higgins, Saoirse, 1966-

2004-01-01T23:59:59.000Z

365

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,...

366

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...

367

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...

368

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...

369

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...

370

A STAMP model of the Überlingen aircraft collision accident  

E-Print Network [OSTI]

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 ...

Wong, Brian, 1982 Nov 11-

2004-01-01T23:59:59.000Z

371

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...

372

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...

373

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...

374

Some methods of estimating uncertainty in accident reconstruction  

E-Print Network [OSTI]

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.

Milan Batista

2011-07-20T23:59:59.000Z

375

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...

376

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...

377

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...

378

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...

379

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...

380

Accident Investigation Report | Department of Energy  

Office of Environmental Management (EM)

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

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Improved dose estimates for nuclear criticality accidents  

SciTech Connect (OSTI)

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.

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

382

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

SciTech Connect (OSTI)

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

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

1994-12-01T23:59:59.000Z

383

Trees as Filters of Radioactive Fallout from the Chernobyl Accident  

E-Print Network [OSTI]

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.

Brownridge, James D

2011-01-01T23:59:59.000Z

384

Berkeley Lab Accident Statistics Through January 31, 2012  

E-Print Network [OSTI]

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

Eisen, Michael

385

The role of NUREG-1150 in accident management  

SciTech Connect (OSTI)

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.

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

1988-01-01T23:59:59.000Z

386

The role of NUREG-1150 in accident management  

SciTech Connect (OSTI)

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.

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

1988-01-01T23:59:59.000Z

387

Routine and post-accident sampling in nuclear reactors  

SciTech Connect (OSTI)

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.

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

1980-01-01T23:59:59.000Z

388

Evaluation of accident frequencies at the canister storage building  

SciTech Connect (OSTI)

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.

LIU, Y.J.

1999-05-13T23:59:59.000Z

389

Berkeley Lab Accident Statistics Through July 31, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

390

Berkeley Lab Accident Statistics Through September 30, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

391

Berkeley Lab Accident Statistics Through May 31, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

392

Berkeley Lab Accident Statistics Through October 31, 2008  

E-Print Network [OSTI]

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

Eisen, Michael

393

Berkeley Lab Accident Statistics Through August 31, 2009  

E-Print Network [OSTI]

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

Eisen, Michael

394

Transportation Market Distortions  

E-Print Network [OSTI]

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

Litman, Todd

2006-01-01T23:59:59.000Z

395

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).

396

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]

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...

Anonymous

1969-01-01T23:59:59.000Z

397

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]

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

Wu, Mingshen

398

NORMES D'ACTUACI EN CAS D'ACCIDENT 1. Els accidents hauran de justificar-se mitjanant la corresponent comunicaci  

E-Print Network [OSTI]

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

Geffner, Hector

399

Human factors review for Severe Accident Sequence Analysis (SASA)  

SciTech Connect (OSTI)

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.

Krois, P.A.; Haas, P.M.; Manning, J.J.; Bovell, C.R.

1984-01-01T23:59:59.000Z

400

VICTORIA: A mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions. Revision 1  

SciTech Connect (OSTI)

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.

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

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Accounting for Co-benefits in Asia's Transportation Sector: Methods...  

Open Energy Info (EERE)

has two objectives. The first is to examine methodological issues involved in using guidelines to measure co-benefits from transport projects (developing baselines,...

402

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]

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

California at San Diego, University of

403

Multiscale thermal transport.  

SciTech Connect (OSTI)

A concurrent computational and experimental investigation of thermal transport is performed with the goal of improving understanding of, and predictive capability for, thermal transport in microdevices. The computational component involves Monte Carlo simulation of phonon transport. In these simulations, all acoustic modes are included and their properties are drawn from a realistic dispersion relation. Phonon-phonon and phonon-boundary scattering events are treated independently. A new set of phonon-phonon scattering coefficients are proposed that reflect the elimination of assumptions present in earlier analytical work from the simulation. The experimental component involves steady-state measurement of thermal conductivity on silicon films as thin as 340nm at a range of temperatures. Agreement between the experiment and simulation on single-crystal silicon thin films is excellent, Agreement for polycrystalline films is promising, but significant work remains to be done before predictions can be made confidently. Knowledge gained from these efforts was used to construct improved semiclassical models with the goal of representing microscale effects in existing macroscale codes in a computationally efficient manner.

Graham, Samuel Jr. (; .); Wong, C. C.; Piekos, Edward Stanley

2004-02-01T23:59:59.000Z

404

Supplementary documentation for an Environmental Impact Statement regarding the Pantex Plant: long-term radiological risk assessment for postulated accidents  

SciTech Connect (OSTI)

This report documents work performed in support of preparation of an Environmental Impact Statement regarding the Department of Energy's (DOE) Pantex Plant near Amarillo, Texas. The long-term health effects to people farming the areas studied by Wenzel in 1982 are calculated in this report by predicting plutonium transport in the Texas Panhandle, southeastern Iowa, and south central Washington using the BIOTRAN model. Inhalation and ingestion radiation doses are calculated for each hypothetical accident with releases of 120-, 30-, and 0.625-kg plutonium at the Pantex Plant and the Iowa Army Ammunition Plant (IAAP). The greatest radiation dose for the Pantex Plant and IAAP accidents is the inhalation dose, which accounts for greater than 90% of the long-term effect. Only a 0.625-kg plutonium release is addressed for the Hanford site. Deposited PuO/sub 2/ at levels greater than 0.4 ..mu..Ci/m/sup 2/ dose not extend offsite. Therefore, health effects were not calculated for Hanford. The estimated number of health effects (cancer deaths) based on 1990 populations was higher for these accidents at the Pantex Plant than the IAAP; but the cancer mortality risk (chance/100,000) was found to be greater at the IAAP because of the larger population density closer to the IAAP.

Wenzel, W.J.; Gallegos, A.F.

1982-12-01T23:59:59.000Z

405

Methods for air cleaning system design and accident analysis  

SciTech Connect (OSTI)

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.

Gregory, W.S.; Nichols, B.D.

1986-01-01T23:59:59.000Z

406

PNNL Results from 2010 CALIBAN Criticality Accident Dosimeter Intercomparison Exercise  

SciTech Connect (OSTI)

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.

Hill, Robin L.; Conrady, Matthew M.

2011-10-28T23:59:59.000Z

407

Study on Total Instantaneous Blockage Accident for CEFR  

SciTech Connect (OSTI)

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)

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

2006-07-01T23:59:59.000Z

408

56113.Transport and integration 13.1 Transport  

E-Print Network [OSTI]

be classified according to the hazard involved: · Mirror segments. The size of each segment allows transport by laser beams. This grid defines the X-Y-Z location of each node of the structure. Each node can several light cranes with a maximum payload of 3 tons. thereby allowing for redundancy. · The structural

Liske, Jochen

409

Molecular Mechanism of Biological Proton Transport  

SciTech Connect (OSTI)

Proton transport across lipid membranes is a fundamental aspect of biological energy transduction (metabolism). This function is mediated by a Grotthuss mechanism involving proton hopping along hydrogen-bonded networks embedded in membrane-spanning proteins. Using molecular simulations, the authors have explored the structural, dynamic, and thermodynamic properties giving rise to long-range proton translocation in hydrogen-bonded networks involving water molecules, or water wires, which are emerging as ubiquitous H{sup +}-transport devices in biological systems.

Pomes, R.

1998-09-01T23:59:59.000Z

410

Cognitive Radio will revolutionize American transportation  

ScienceCinema (OSTI)

Cognitive Radio will revolutionize American transportation. Through smart technology, it will anticipate user needs; detect available bandwidths and frequencies then seamlessly connect vehicles, infrastructures, and consumer devices; and it will support the Department of Transportation IntelliDrive Program, helping researchers, auto manufacturers, and Federal and State officials advance the connectivity of US transportation systems for improved safety, mobility, and environmental conditions. Using cognitive radio, a commercial vehicle will know its driver, onboard freight and destination route. Drivers will save time and resources communicating with automatic toll booths and know ahead of time whether to stop at a weigh station or keep rolling. At accident scenes, cognitive radio sensors on freight and transportation modes can alert emergency personnel and measure on-site, real-time conditions such as a chemical leak. The sensors will connect freight to industry, relaying shipment conditions and new delivery schedules. For industry or military purposes, cognitive radio will enable real-time freight tracking around the globe and its sensory technology can help prevent cargo theft or tampering by alerting shipper and receiver if freight is tampered with while en route. For the average consumer, a vehicle will tailor the transportation experience to the passenger such as delivering age-appropriate movies via satellite. Cognitive radio will enhance transportation safety by continually sensing what is important to the user adapting to its environment and incoming information, and proposing solutions that improve mobility and quality of life.

None

2013-12-06T23:59:59.000Z

411

Cognitive Radio will revolutionize American transportation  

SciTech Connect (OSTI)

Cognitive Radio will revolutionize American transportation. Through smart technology, it will anticipate user needs; detect available bandwidths and frequencies then seamlessly connect vehicles, infrastructures, and consumer devices; and it will support the Department of Transportation IntelliDrive Program, helping researchers, auto manufacturers, and Federal and State officials advance the connectivity of US transportation systems for improved safety, mobility, and environmental conditions. Using cognitive radio, a commercial vehicle will know its driver, onboard freight and destination route. Drivers will save time and resources communicating with automatic toll booths and know ahead of time whether to stop at a weigh station or keep rolling. At accident scenes, cognitive radio sensors on freight and transportation modes can alert emergency personnel and measure on-site, real-time conditions such as a chemical leak. The sensors will connect freight to industry, relaying shipment conditions and new delivery schedules. For industry or military purposes, cognitive radio will enable real-time freight tracking around the globe and its sensory technology can help prevent cargo theft or tampering by alerting shipper and receiver if freight is tampered with while en route. For the average consumer, a vehicle will tailor the transportation experience to the passenger such as delivering age-appropriate movies via satellite. Cognitive radio will enhance transportation safety by continually sensing what is important to the user adapting to its environment and incoming information, and proposing solutions that improve mobility and quality of life.

None

2013-07-22T23:59:59.000Z

412

Transportation needs assessment: Emergency response section  

SciTech Connect (OSTI)

The transportation impacts of moving high level nuclear waste (HLNW) to a repository at Yucca Mountain in Nevada are of concern to the residents of the State as well as to the residents of other states through which the nuclear wastes might be transported. The projected volume of the waste suggests that shipments will occur on a daily basis for some period of time. This will increase the risk of accidents, including a catastrophic incident. Furthermore, as the likelihood of repository construction and operation and waste shipments increase, so will the attention given by the national media. This document is not to be construed as a willingness to accept the HLNW repository on the part of the State. Rather it is an initial step in ensuring that the safety and well-being of Nevada residents and visitors and the State`s economy will be adequately addressed in federal decision-making pertaining to the transportation of HLNW into and across Nevada for disposal in the proposed repository. The Preferred Transportation System Needs Assessment identifies critical system design elements and technical and social issues that must be considered in conducting a comprehensive transportation impact analysis. Development of the needs assessment and the impact analysis is especially complex because of the absence of information and experience with shipping HLNW and because of the ``low probability, high consequence`` aspect of the transportation risk.

NONE

1989-05-01T23:59:59.000Z

413

HYDROGEN FROM BIOMASS FOR URBAN TRANSPORTATION  

E-Print Network [OSTI]

biomass, such as peanut shells, for urban transportation. The process involves pyrolysis of the biomassHYDROGEN FROM BIOMASS FOR URBAN TRANSPORTATION Collaborating Project Team Y. Yeboah (PI) and K and liquid fuels) · Potential sources of hydrogen include biomass, natural gas and other fossil fuels. #12

414

A Transportation Risk Assessment Tool for Analyzing the Transport of Spent Nuclear Fuel and High-Level Radioactive Waste to the Proposed Yucca Mountain Repository  

SciTech Connect (OSTI)

The Yucca Mountain Transportation Database was developed as a data management tool for assembling and integrating data from multiple sources to compile the potential transportation impacts presented in the Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada (DEIS). The database uses the results from existing models and codes such as RADTRAN, RISKIND, INTERLINE, and HIGHWAY to estimate transportation-related impacts of transporting spent nuclear fuel and high-level radioactive waste from commercial reactors and U. S. Department of Energy (DOE) facilities to Yucca Mountain. The source tables in the database are compendiums of information from many diverse sources including: radionuclide quantities for each waste type; route and route characteristics for rail, legal-weight truck, heavy haul. truck, and barge transport options; state-specific accident and fatality rates for routes selected for analysis; packaging and shipment data by waste type; unit risk factors; the complex behavior of the packaged waste forms in severe transport accidents; and the effects of exposure to radiation or the isotopic specific effects of radionclides should they be released in severe transportation accidents. The database works together with the codes RADTRAN (Neuhauser, et al, 1994) and RISKlND (Yuan, et al, 1995) to calculate incident-free dose and accident risk. For the incident-free transportation scenario, the database uses RADTRAN and RISKIND-generated data to calculate doses to offlink populations, onlink populations, people at stops, crews, inspectors, workers at intermodal transfer stations, guards at overnight stops, and escorts, as well as non-radioactive pollution health effects. For accident scenarios, the database uses RADTRAN-generated data to calculate dose risks based on ingestion, inhalation, resuspension, immersion (cloudshine), and groundshine as well as non-radioactive traffic fatalities. The Yucca Mountain EIS Transportation Database was developed using Microsoft Access 97{trademark} software and the Microsoft Windows NT{trademark} operating system. The database consists of tables for storing data, forms for selecting data for querying, and queries for retrieving the data in a predefined format. Database queries retrieve records based on input parameters and are used to calculate incident-free and accident doses using unit risk factors obtained from RADTRAN results. The next section briefly provides some background that led to the development of the database approach used in preparing the Yucca Mountain DEIS. Subsequent sections provide additional details on the database structure and types of impacts calculated using the database.

Ralph Best; T. Winnard; S. Ross; R. Best

2001-08-17T23:59:59.000Z

415

Compendium of the Environmental Measurements Laboratory's research projects related to the Chernobyl nuclear accident  

SciTech Connect (OSTI)

Following the accident at the Chernobyl nuclear reactor power station in the USSR on April 26, 1986, the Environmental Measurements Laboratory (EML) initiated a number of research projects as follows: (1) selected sites in both the Deposition and Surface Air networks were alerted and their sampling protocols adjusted to accommodate the anticipated arrival times and activity concentrations of the Chernobyl debris; (2) a number of cooperative programs involving field work, sampling, analysis and data interpretation were set up with institutions and scientists in other countries; (3) EML's Regional Baseline Station at Chester, NJ, as well as the roof of the Laboratory in New York City, provided bases for sampling and measurements to study the radionuclide concentrations, radiation levels, physical characteristics and potential biological implications of the Chernobyl fallout on the northeastern United States; and (4) the resulting fallout from the Chernobyl accident provided an 'experiment of opportunity' in that it enabled us to study fresh fission product deposition using collection systems resurrected from the 1950's and 1960's for comparison with current state-of-the-art methodology. The 13 reports of this volume have been entered separately into the data base.

Volchok, H L; Chieco, N [comps.

1986-10-01T23:59:59.000Z

416

FSAR fire accident analysis for a plutonium facility  

SciTech Connect (OSTI)

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.

Lam, K.

1997-06-01T23:59:59.000Z

417

Post-accident gas generation from radiolysis of organic materials  

SciTech Connect (OSTI)

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.

Wing, J.

1984-09-01T23:59:59.000Z

418

Neurotransmitter Transporters  

E-Print Network [OSTI]

at specialized synaptic junctions where electrical excitability in the form of an action potential is translated membrane of neurons and glial cells. Transporters harness electrochemical gradients to force the movement.els.net #12;The response produced when a transmitter interacts with its receptors, the synaptic potential

Bergles, Dwight

419

STAMP-Based Analysis of a Refinery Overflow Accident Nancy Leveson, Margaret Stringfellow, and John Thomas  

E-Print Network [OSTI]

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

Leveson, Nancy

420

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...

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

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...

422

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...

423

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...

424

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...

425

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...

426

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...

427

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...

428

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...

429

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

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

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:...

430

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...

431

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...

432

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....

433

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...

434

Three dimensional effects in analysis of PWR steam line break accident  

E-Print Network [OSTI]

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) ...

Tsai, Chon-Kwo

435

The Effect of the 18-Year Old Drinking Age on Auto Accidents  

E-Print Network [OSTI]

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 ...

Cucchiaro, Stephen

436

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...

437

Accident Analysis and Prevention 42 (2010) 213224 Contents lists available at ScienceDirect  

E-Print Network [OSTI]

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

Wisconsin at Madison, University of

438

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...

439

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]

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

Acton, Scott

440

Improved dose estimates for nuclear criticality accidents: Preliminary results  

SciTech Connect (OSTI)

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.

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

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Response of HEPA filters to simulated-accident conditions  

SciTech Connect (OSTI)

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.

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

1982-01-01T23:59:59.000Z

442

Severe accident natural circulation studies at the INEL  

SciTech Connect (OSTI)

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.

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

443

Source: http://www.ftc.gov/debtcollection ost accidents  

E-Print Network [OSTI]

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

Oliver, Douglas L.

444

Hanford Waste Tank Bump Accident and Consequence Analysis  

SciTech Connect (OSTI)

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.

BRATZEL, D.R.

2000-06-20T23:59:59.000Z

445

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

446

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...

447

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...

448

Environmental radionuclide distribution in Georgia after the Chernobyl accident  

SciTech Connect (OSTI)

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.

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

1994-01-01T23:59:59.000Z

449

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...

450

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...

451

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...

452

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...

453

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...

454

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...

455

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...

456

Nuclear fuel cycle facility accident analysis handbook  

SciTech Connect (OSTI)

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

NONE

1998-03-01T23:59:59.000Z

457

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

E-Print Network [OSTI]

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

Boyer, Edmond

458

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

E-Print Network [OSTI]

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

Jacob, Daniel J.

459

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

SciTech Connect (OSTI)

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.

RITTMANN, P.D.

1999-10-07T23:59:59.000Z

460

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

E-Print Network [OSTI]

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

Pitt, Robert E.

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

462

Modelling of Stochastic Hybrid Systems with Applications to Accident Risk Assessment  

E-Print Network [OSTI]

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

Del Moral , Pierre

463

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

E-Print Network [OSTI]

-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

Johnson, Chris

464

DIRECTORY OF ESReDA ACCIDENT DATABASES Jean-Philippe PINEA  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

465

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

E-Print Network [OSTI]

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

Ponce, V. Miguel

466

Analysis of Comair flight 5191 with the Functional Resonance Accident Model  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

467

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

468

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

469

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

470

PRESENTATION OF WORK PERFORMED BY ESReDA "ACCIDENT ANALYSIS" WORKING  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

471

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

E-Print Network [OSTI]

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

Boyer, Edmond

472

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

E-Print Network [OSTI]

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

Kwatny, Harry G.

473

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

474

Testing of a Transport Cask for Research Reactor Spent Fuel - 13003  

SciTech Connect (OSTI)

Since the beginning of the last decade three Latin American countries that operate research reactors - Argentina, Brazil and Chile - have been joining efforts to improve the regional capability in the management of spent fuel elements from the TRIGA and MTR reactors operated in the region. A main drive in this initiative, sponsored by the International Atomic Energy Agency, is the fact that no definite solution regarding the back end of the research reactor fuel cycle has been taken by any of the participating country. However, any long-term solution - either disposition in a repository or storage away from reactor - will involve at some stage the transportation of the spent fuel through public roads. Therefore, a licensed cask that provides adequate shielding, assurance of subcriticality, and conformance to internationally accepted safety, security and safeguards regimes is considered a strategic part of any future solution to be adopted at a regional level. As a step in this direction, a packaging for the transport of irradiated fuel for MTR and TRIGA research reactors was designed by the tri-national team and a half-scale model equipped with the MTR version of the internal basket was constructed in Argentina and Brazil and tested in Brazil. Three test campaigns have been carried out so far, covering both normal conditions of transportation and hypothetical accident conditions. After failing the tests in the first two test series, the specimen successfully underwent the last test sequence. A second specimen, incorporating the structural improvements in view of the previous tests results, will be tested in the near future. Numerical simulations of the free drop and thermal tests are being carried out in parallel, in order to validate the computational modeling that is going to be used as a support for the package certification. (authors)

Mourao, Rogerio P.; Leite da Silva, Luiz [Centro de Desenvolvimento da Tecnologia Nuclear, Belo Horizonte (Brazil)] [Centro de Desenvolvimento da Tecnologia Nuclear, Belo Horizonte (Brazil); Miranda, Carlos A.; Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil)] [Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil); Quintana, Jose F.A.; Saliba, Roberto O. [Comision Nacional de Energia Atomica, Bariloche (Argentina)] [Comision Nacional de Energia Atomica, Bariloche (Argentina); Novara, Oscar E. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)] [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

2013-07-01T23:59:59.000Z

475

NREL: Transportation Research - Transportation and Hydrogen Newsletter...  

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

The Future of Sustainable Transportation This is the January 2015 issue of the Transportation and Hydrogen Newsletter. Illustration of an electric vehicle Illustration of an...

476

Accident Reporting Policy Outline the policy regarding accident reporting on University of Michigan (U-M) vehicles.  

E-Print Network [OSTI]

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

Kirschner, Denise

477

On the Prevalence of Organizational Factors in Recent U.S. Transportation Accidents  

E-Print Network [OSTI]

Holloway,C.M. Johnson,C.W. Proceedings of the 23rd International System Safety Conference, 22-26 August 2005, San Diego, California, International Systems Safety Society

Holloway, C.M.; Johnson, C.W.

478

Audit of the Department of Energy's Transportation Accident Resistant Container Program, IG-0380  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement3--Logistical5/08 Attendance List1-02Evaluation Report TheU.S.Audit of the OFFICE1,

479

Effects of improved modeling on best estimate BWR severe accident analysis  

SciTech Connect (OSTI)

Since 1981, ORNL has completed best estimate studies analyzing several dominant BWR accident scenarios. These scenarios were identified by early Probabilistic Risk Assessment (PRA) studies and detailed ORNL analysis complements such studies. In performing these studies, ORNL has used the MARCH code extensively. ORNL investigators have identified several deficiencies in early versions of MARCH with regard to BWR modeling. Some of these deficiencies appear to have been remedied by the most recent release of the code. It is the purpose of this paper to identify several of these deficiencies. All the information presented concerns the degraded core thermal/hydraulic analysis associated with each of the ORNL studies. This includes calculations of the containment response. The period of interest is from the time of permanent core uncovery to the end of the transient. Specific objectives include the determination of the extent of core damage and timing of major events (i.e., onset of Zr/H/sub 2/O reaction, initial clad/fuel melting, loss of control blade structure, etc.). As mentioned previously the major analysis tool used thus far was derived from an early version of MARCH. BWRs have unique features which must be modeled for best estimate severe accident analysis. ORNL has developed and incorporated into its version of MARCH several improved models. These include (1) channel boxes and control blades, (2) SRV actuations, (3) vessel water level, (4) multi-node analysis of in-vessel water inventory, (5) comprehensive hydrogen and water properties package, (6) first order correction to the ideal gas law, and (7) separation of fuel and cladding. Ongoing and future modeling efforts are required. These include (1) detailed modeling for the pressure suppression pool, (2) incorporation of B/sub 4/C/steam reaction models, (3) phenomenological model of corium mass transport, and (4) advanced corium/concrete interaction modeling. 10 references, 17 figures, 1 table.

Hyman, C.R.; Ott, L.J.

1984-01-01T23:59:59.000Z

480

Uncertainty and sensitivity analysis of a fire-induced accident scenario involving binary variables and mechanistic codes  

E-Print Network [OSTI]

In response to the transition by the United States Nuclear Regulatory Commission (NRC) to a risk-informed, performance-based fire protection rulemaking standard, Fire Probabilistic Risk Assessment (PRA) methods have been ...

Minton, Mark A. (Mark Aaron)

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


481

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

E-Print Network [OSTI]

standards and guidance. The Management of Health and Safety at Work Regulations 1999 (HSE, 1999) require 951 4064, Mark.Bowell@hse.gsi.gov.uk Abstract. This paper presents the results of a project electronic systems (E/E/PES) in satisfying particular requirements of the Management of Health and Safety

Johnson, Chris

482

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.

483

Results from simulated upper-plenum aerosol transport tests  

SciTech Connect (OSTI)

A series of eight aerosol transport experiments, designated as Aerosol Transport Tests (ATT) A101 through A108, has recently been completed at the Oak Ridge National Laboratory (ORNL). These tests provide a data base for validation of aerosol transport modeling used in the TRAP-MELT2 computer code (Jordan and Kuhlman, 1985), which was developed at Battelle Columbus Laboratories to calculate aerosol/fission-product transport in the reactor coolant system in postulated light-water reactor (LWR) core-melt accidents. Results from tests A103 and A104 have been summarized in a previous paper (Wright and Pattison, 1985a); the present paper discusses results from tests A105 through A108.

Wright, A.L.; Pattison, W.L.

1986-01-01T23:59:59.000Z

484

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

SciTech Connect (OSTI)

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.

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

1986-09-01T23:59:59.000Z

485

Public involvement in radioactive waste management decisions  

SciTech Connect (OSTI)

Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

NONE

1994-04-01T23:59:59.000Z

486

Mitigation of Severe Accident Consequences Using Inherent Safety Principles  

SciTech Connect (OSTI)

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.

R. A. Wigeland; J. E. Cahalan

2009-12-01T23:59:59.000Z

487

Greening Transportation  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Big Sky LearningGetGraphene's 3D CounterpartDepartmentTransportation

488

Transportation Infrastructure  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomen Owned SmallOf The 2012 Greenbuy3 Archive Transportation Fact of the Week

489

Analysis of a hypothetical criticality accident in a waste supercompactor  

SciTech Connect (OSTI)

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.

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

490

A regulatory assessment of test data for reactivity accidents  

SciTech Connect (OSTI)

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.

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

491

Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report  

SciTech Connect (OSTI)

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.

Lori Braase

2013-01-01T23:59:59.000Z

492

Accident at Three Mile Island: the human dimensions  

SciTech Connect (OSTI)

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.

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

1982-01-01T23:59:59.000Z

493

INDUSTRIAL/MILITARY ACTIVITY-INITIATED ACCIDENT SCREENING ANALYSIS  

SciTech Connect (OSTI)

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.

D.A. Kalinich

1999-09-27T23:59:59.000Z

494

Berkeley Lab Accident Statistics Through November 30, 2011  

E-Print Network [OSTI]

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

Eisen, Michael

495

Markov Model of Severe Accident Progression and Management  

SciTech Connect (OSTI)

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.

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

496

Self-mixing phenomenology in hypothetical core-disruptive accidents  

SciTech Connect (OSTI)

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.

Chapyak, E.J.

1980-12-01T23:59:59.000Z

497

Estimated long term health effects of the Chernobyl accident  

SciTech Connect (OSTI)

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.

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

1996-07-01T23:59:59.000Z

498

Chernobyl accident and the problem of {sup 241}Am  

SciTech Connect (OSTI)

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.

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

1995-07-01T23:59:59.000Z

499

Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis  

SciTech Connect (OSTI)

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.

Gilles Youinou; R. Sonat Sen

2013-09-01T23:59:59.000Z

500

AQUATIC ASSESSMENT OF THE CHERNOBYL NUCLEAR ACCIDENT AND ITS REMEDIATION  

SciTech Connect (OSTI)

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.

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

2007-11-01T23:59:59.000Z