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Note: This page contains sample records for the topic "transportation accident involving" from the National Library of EnergyBeta (NLEBeta).
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1

Decontamination Dressdown at a Transportation Accident Involving  

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

Decontamination Dressdown at a Transportation Accident Involving Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Decontamination Dressdown at a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on how the decontamination dressdown process is implemented. During this discussion, the instructor can present various scenarios, each of which would discuss decontamination at the accident scene. The purpose of this discussion would be to cover how responders

2

EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Emer Emer Emer Emer Emer Emergency Response to a T gency Response to a T gency Response to a T gency Response to a T gency Response to a Transportation ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional

3

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Video User' s Guide Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond

4

Emergency Response to a Transportation Accident Involving Radioactive  

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

Response to a Transportation Accident Involving Response to a Transportation Accident Involving Radioactive Material Emergency Response to a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on each response disciplines' activities or duties at the scene. During this discussion, the instructor can present response scenarios, each of which would have a different discipline arriving first at the accident scene. The purpose of this discussion

5

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

6

Accidents  

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

Health Risks » Accidents Health Risks » Accidents DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Accidents A discussion of accidents involving depleted UF6 storage cylinders, including possible health effects, accident risk, and accident history. Potential Health Effects from Cylinder Accidents Accidents involving depleted UF6 storage cylinders are a concern because they could result in an uncontrolled release of UF6 to the environment, which could potentially affect the health of workers and members of the public living downwind of the accident site. Accidental release of UF6 from storage cylinders or during processing activities could result in injuries or fatalities. The most immediate hazard after a release would be from inhalation of hydrogen fluoride (HF), a highly corrosive gas formed when

7

Piercing tool, Transportation Accident Resistant Container (TARC)  

SciTech Connect (OSTI)

Transportation Accident Resistant Containers (TARC)s are used for enhanced safety during movement of nuclear weapons. Its design features a tough stainless steel outer skin, redwood for impact mitigation and fire protection and a rugged aluminum inner container. Redwood absorbs impact energy by crushing, similar to the way foam crushes in other containers. Redwood also functions to insulate the weapon from heat and fire. When a TARC is involved in a fire, the redwood will slowly burn forming a good insulating char. The redwood can continue to smolder once the fire is out. To ensure the smolder is extinguished, water can be directed into any accident caused hole in the skin. If no hole exists, it may be necessary to create one. This document discusses tool selection, testing, and a simple but effective method of creating an access hole in the outer skin large enough to apply fire fighting techniques.

Lari, P.

1994-08-01T23:59:59.000Z

8

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

9

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

10

Tort Law in road accidents. The involvement of police vehicles  

Science Journals Connector (OSTI)

Some members of Law Enforcement must use motor vehicles to fulfill its constitutional mission. To face up to traffic accidents, the Spanish Criminal Policy has been implemented criminal, procedural, administra...

Flix Francisco Serrano Gallardo

2009-10-01T23:59:59.000Z

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

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

SciTech Connect (OSTI)

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

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

1985-01-01T23:59:59.000Z

14

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

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)

1990-12-31T23:59:59.000Z

16

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

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

1, 1995 1, 1995 IG-1 INFORMATION: Report on "Audit of the Department of Energy's Transportation Accident Resistant Container Program" The Secretary BACKGROUND: The U.S. Department of Energy (Department) has ultimate responsibility for the safety of all nuclear explosives and weapons operations conducted by the Department and its contractors. The Department also has joint responsibility for the safety of nuclear weapons in the custody of the Armed Services. Since the 1970s, the Department has designed, developed, and produced accident resistant containers to promote safety when transporting certain types of nuclear weapons by air. DISCUSSION: After successfully developing and modifying accident resistant containers for

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

Severe Accident Studies  

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

Severe Accident Studies Severe Accident Studies Christopher S. Bajwa Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards USNRC 2012 U.S. DOE National Transportation Stakeholders Forum (NTSF) May 15 - 17, 2012 Knoxville, TN * Going The Distance? - The Safe Transport of Spent Nuclear Fuel and High-Level Radioactive Waste in the United States * Released February 9, 2006 * Conclusions: * NRC safety regulations are adequate to ensure package containment effectiveness over a wide range of transport conditions, including most credible accident conditions. * The radiological risks are well understood and are generally low, with the possible exception of risks from releases in extreme accidents involving long duration, fully engulfing fires.

19

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

20

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 Americas 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

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

Accident analysis of railway transportation of low-level radioactive and hazardous chemical wastes: Application of the /open quotes/Maximum Credible Accident/close quotes/ concept  

SciTech Connect (OSTI)

The maximum credible accident (MCA) approach to accident analysis places an upper bound on the potential adverse effects of a proposed action by using conservative but simplifying assumptions. It is often used when data are lacking to support a more realistic scenario or when MCA calculations result in acceptable consequences. The MCA approach can also be combined with realistic scenarios to assess potential adverse effects. This report presents a guide for the preparation of transportation accident analyses based on the use of the MCA concept. Rail transportation of contaminated wastes is used as an example. The example is the analysis of the environmental impact of the potential derailment of a train transporting a large shipment of wastes. The shipment is assumed to be contaminated with polychlorinated biphenyls and low-level radioactivities of uranium and technetium. The train is assumed to plunge into a river used as a source of drinking water. The conclusions from the example accident analysis are based on the calculation of the number of foreseeable premature cancer deaths the might result as a consequence of this accident. These calculations are presented, and the reference material forming the basis for all assumptions and calculations is also provided.

Ricci, E.; McLean, R.B.

1988-09-01T23:59:59.000Z

22

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

23

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

Broader source: Energy.gov [DOE]

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

24

Multibody Models for Vehicle Accident Reconstruction  

Science Journals Connector (OSTI)

Simplified multibody models can be used to reconstruct accidents involving complex dynamics, particularly, in the first stages of accident investigation, accidents involving motorcycles and pedestrians [1], [2].

Ricardo J. F. Portal; Joo M. P. Dias

2006-01-01T23:59:59.000Z

25

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

E-Print Network [OSTI]

were divided into categories with respect to accident types, construction operations, degree of accident, fault, contributing factors, crane types, victims occupation, organs affected and load. Descriptive analysis was performed to compliment...

Bains, Amrit Anoop Singh

2010-10-12T23:59:59.000Z

26

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

27

On transport mechanisms in solar cells involving organic semiconductors.  

E-Print Network [OSTI]

??El conocimiento del mecanismo de transporte o de conduccin en las clulas solares es til para identificar las prdidas elctricas. En esta tesis, se han (more)

Nolasco Montao, Jairo Csar

2011-01-01T23:59:59.000Z

28

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

29

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

30

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

31

Experiences in methods to involve key players in planning protective actions in the case of a nuclear accident  

Science Journals Connector (OSTI)

......parliamentarians and experts see nuclear power. Energy Policy 19 (5), 464-472...IN THE CASE OF A NUCLEAR ACCIDENT 131 9...for environmental policy alternatives. J...parliamentarians and experts see nuclear power. Energy Policy 19 (5), 464......

K. Sinkko; R. P. Hmlinen; R. Hnninen

2004-06-01T23:59:59.000Z

32

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

33

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

E-Print Network [OSTI]

investigating the immediate and underlying causes of incidents and accidents to ensure that remedial action techniques that might be used to investigate the underlying causes of E/E/PES related incidents. The following sections, therefore, introduce two techniques to support the investigation of this class

Johnson, Chris

34

Transportation  

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

Health Risks » Transportation Health Risks » Transportation DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Transportation A discussion of health risks associated with transport of depleted UF6. Transport Regulations and Requirements In the future, it is likely that depleted uranium hexafluoride cylinders will be transported to a conversion facility. For example, it is currently anticipated that the cylinders at the ETTP Site in Oak Ridge, TN, will be transported to the Portsmouth Site, OH, for conversion. Uranium hexafluoride has been shipped safely in the United States for over 40 years by both truck and rail. Shipments of depleted UF6 would be made in accordance with all applicable transportation regulations. Shipment of depleted UF6 is regulated by the

35

Intelligent Transportation Systems - Center for Transportation Analysis  

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

Intelligent Transportation Systems Intelligent Transportation Systems The Center for Transportation Analysis does specialty research and development in intelligent transportation systems. Intelligent Transportation Systems (ITS) are part of the national strategy for improving the operational safety, efficiency, and security of our nation's highways. Since the early 1990s, ITS has been the umbrella under which significant efforts have been conducted in research, development, testing, deployment and integration of advanced technologies to improve the measures of effectiveness of our national highway network. These measures include level of congestion, the number of accidents and fatalities, delay, throughput, access to transportation, and fuel efficiency. A transportation future that includes ITS will involve a significant improvement in these

36

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

37

Two-dimensional chemotherapy simulations demonstrate fundamental transport and tumor response limitations involving nanoparticles  

Science Journals Connector (OSTI)

...chemotherapy simulations demonstrate fundamental transport and tumor response...estimation that demonstrate fundamental convective and diffusive transport...which is drug-sensitive and does not develop resistance; targeted...our analysis shows that fundamental transport limitations are...

Vittorio Cristini; John Sinek; and Hermann Frieboes

2005-05-01T23:59:59.000Z

38

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

E-Print Network [OSTI]

Pessoal de Nível 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

39

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.

40

Microsoft Word - Unrelated Accident  

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

For Immediate Release For Immediate Release Truck Accident Did Not Involve WIPP Shipment CARLSBAD, N.M., October 1, 2009 - A Wednesday night truck accident north of Albuquerque on Highway 165 that involved an 18-wheeler is not related to Waste Isolation Pilot Plant (WIPP) transuranic waste shipments. Involved in the accident was a load of new, unused 55-gallon drums manufactured in Carlsbad that was en route to Richland, Washington. The Waste Isolation Pilot Plant is a U.S. Department of Energy facility designed to safely isolate defense-related transuranic waste from people and the environment. Waste temporarily stored at sites around the country is shipped to WIPP and permanently disposed in rooms mined out of an ancient salt formation 2,150 feet below the surface. WIPP, which began waste

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

Alcohol and Motor Accidents  

Science Journals Connector (OSTI)

... averaged 18 a day and the injuries more than 600. Half the deaths were among pedestrians and a fifth among pedal cyclists, while drivers of motor vehicles and their passengers ... vehicles and their passengers had only a third to a fourth as many accidents as pedestrians. Although the data of the Ministry of Transport indicate that only 1 in 80 ...

1937-01-30T23:59:59.000Z

42

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

43

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

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

Comparative expression of candidate genes involved in sodium transport and compartmentation in citrus  

Science Journals Connector (OSTI)

Abstract Plants possess a number of mechanisms to cope with sodium (Na+) under salt stress conditions that include minimizing Na+ influx, maximizing efflux back to the growth medium or to apoplastic spaces via Na+/H+ antiporters in the plasma membrane, intracellular compartmentation of Na+ into the vacuole, as well as recirculation of Na+ out of the shoot via the phloem. Na+ transport in plants constitutes a complex system, in which different Na+ transporters are closely related and their functions are matched tightly. The fact that in citrus under salt stress does chloride appear to be the more toxic ion has led to little attention being paid to Na+ uptake and transport mechanisms in citrus. The aim of this study was to provide insight into the links between the expression levels of candidate Na+ transporter genes (SOS1, NHX1, HKT1), as well as tonoplast proton pumps (V-ATPase, V-PPiase), and Na+ tolerance in two citrus rootstocks, Cleopatra mandarin and trifoliate orange, differing in their Na+ exclusion capacity under salt stress. According to the results of this preliminary study, we hypothesize that higher root Na+ concentration in trifoliate orange genotype, and thus lower allocation of this ion in the shoots, is the result of an enhanced retrieval of Na+ from xylem stream, and an impaired translocation to the shoot tissues, probably as a consequence of the overexpression of putative SOS1 (in roots) and HKT1 (both in roots and shoots). Moreover, the higher transcriptional levels of putative NHX1 found in roots and shoots of trifoliate orange plantlets compared to those of Cleopatra mandarin, together with the enhanced activity of the tonoplast proton pumps in the former, might reveal the preferential sequestration into vacuole of retrieved Na+ from xylem mainly in roots.

B. Martnez-Alcntara; M.R. Martnez-Cuenca; A. Quiones; D.J. Iglesias; E. Primo-Millo; M.A. Forner-Giner

2015-01-01T23:59:59.000Z

46

FAQ 37-What are the potential health risks from transportation of depleted  

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

depleted uranium metal or oxide? depleted uranium metal or oxide? What are the potential health risks from transportation of depleted uranium metal or oxide? In the PEIS, risks associated with transportation of depleted uranium oxide and metal were estimated for transport by either rail or truck. Normal transport of oxide or metal would result in low-level external exposure to radiation for persons in the vicinity of a shipment. Based on estimates in the PEIS, the levels of exposure would result in negligible increased cancer risks. Risks from material released in an accident were also estimated. For a hypothetical railcar accident involving powder U3O8 that was assumed to occur in a highly-populated urban area under stable (nighttime) weather conditions, it was estimated that up to 20 people might experience irreversible adverse effects from chemical toxicity, with no fatalities expected. Approximately 2 potential latent cancer fatalities from radiological hazards are estimated for an accident under the same conditions. The probability of such an accident occurring is very low. The consequences from a truck accident would be lower, because trucks have a smaller shipment capacity. The consequences of transportation accidents involving depleted uranium metal would be much smaller than those involving uranium oxide because uranium metal would be in the form of solid blocks and would not be easily dispersed in an accident.

47

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...

48

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

49

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

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

chemical attack Slide 10 10 Modular HTGR Accident Safety Evaluations * Challenges to core heat removal - Loss of heat transport (HTS) & shutdown forced cooling systems (SCSCCS)...

50

Nuclear accident and incident public affairs (pa) guidance  

SciTech Connect (OSTI)

This Directive reissues reference (a) DoD Directive 5230.16 to update DoD policy, responsibilities, and procedures for the prompt release of information to the public in the interest of public safety, and to prevent public alarm in the event of accidents or significant incidents involving nuclear weapons or nuclear components, radioactive material, nuclear weapon launch or transport vehicles (when a nuclear weapon is aboard), or nuclear reactors under DoD control. It updates DoD policy, responsibilities, and procedures during an improvised nuclear device (IND) incident.

Not Available

1993-12-20T23:59:59.000Z

51

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

52

Transportation Emergency Preparedness Program (TEPP) | Department of Energy  

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

Transportation Emergency Preparedness Program (TEPP) Transportation Emergency Preparedness Program (TEPP) Transportation Emergency Preparedness Program (TEPP) In an effort to address responder concerns, the Department retooled its approach to emergency responder preparedness and implemented the more simplified and responder-friendly Transportation Emergency Preparedness Program (TEPP). TEPP is a component of the overall comprehensive emergency management system established by DOE Order (DOE O) 151.1, Comprehensive Emergency Management System. TEPP integrates a basic approach to transportation emergency planning and preparedness activities under a single program with the goal to ensure DOE, its operating contractors, and state, tribal, and local emergency responders are prepared to respond promptly, efficiently, and effectively to accidents involving DOE

53

Transportation  

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

Transportation Transportation Transportation of Depleted Uranium Materials in Support of the Depleted Uranium Hexafluoride Conversion Program Issues associated with transport of depleted UF6 cylinders and conversion products. Conversion Plan Transportation Requirements The DOE has prepared two Environmental Impact Statements (EISs) for the proposal to build and operate depleted uranium hexafluoride (UF6) conversion facilities at its Portsmouth and Paducah gaseous diffusion plant sites, pursuant to the National Environmental Policy Act (NEPA). The proposed action calls for transporting the cylinder at ETTP to Portsmouth for conversion. The transportation of depleted UF6 cylinders and of the depleted uranium conversion products following conversion was addressed in the EISs.

54

Crisis Events as a Catalyst for Change in the US Air Transportation  

E-Print Network [OSTI]

Historically, aircraft accidents have preceded the implementation of many changes in the US Air Transportation

Mozdzanowska, Aleksandra

55

Calculation of the far range atmospheric transport of radionuclides after the Fukushima accident with the atmospheric dispersion model MATCH of the JRODOS system  

Science Journals Connector (OSTI)

The paper presents estimates of the far-range atmospheric dispersion of radionuclides after the accident at Fukushima Daiichi Nuclear Power Plant (NPP), obtained using the long-range atmospheric dispersion model MATCH. Software tools were developed to run MATCH in the EU nuclear emergency response system JRODOS using freely available numerical weather prediction (NWP) data of the Global Forecasting System (GFS) operated by the United States National Center of Environmental Prediction (NCEP). Comparisons are made of results with JRODOS/MATCH and a standalone MATCH operated by Swedish Meteorological and Hydrological Institute (SMHI) driven by the European Center for Medium-Range Weather Forecasts (ECMWF) NWP data.

Ivan V. Kovalets; Lennart Robertson; Christer Persson; Svitlana N. Didkivska; Ievgen A. Ievdin; Dmytro Trybushnyi

2014-01-01T23:59:59.000Z

56

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

Broader source: Energy.gov [DOE]

On Friday, May 14, 2004, at approximately 11:30 a.m., a dump truck transporting mixing tank T-12 (Tank T-12) from the New Hydrofracture Facility (NHF) Decontamination and Decommissioning (D&D) Project arrived at the Environmental Management Waste Management Facility (EMWMF). Upon arrival, an incoming radiological survey was performed.

57

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,...

58

Transportation  

Science Journals Connector (OSTI)

The romantic rides in Sandburgs eagle-car changed society. On the one hand, motor vehicle transportation is an integral thread of societys fabric. On the other hand, excess mobility fractures old neighborh...

David Hafemeister

2014-01-01T23:59:59.000Z

59

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

60

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

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

Release fractions for Rocky Flats specific accidents  

SciTech Connect (OSTI)

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

Weiss, R.C.

1992-09-01T23:59:59.000Z

62

Release fractions for Rocky Flats specific accidents  

SciTech Connect (OSTI)

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

Weiss, R.C.

1992-01-01T23:59:59.000Z

63

Lessons from Major Accidents  

Science Journals Connector (OSTI)

The following lessons emerged from the accident, and have applications for the design of semi-submersible floating units: Cracks introduced during construction must be d...

Jan-Erik Vinnem

2014-01-01T23:59:59.000Z

64

Accident Investigation Report  

Broader source: Energy.gov [DOE]

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

65

Radiological Release Accident Investigation Report  

Broader source: Energy.gov [DOE]

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

66

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

2012-06-07T23:59:59.000Z

67

Quantification of the number of injured people due to hazardous material accidents  

Science Journals Connector (OSTI)

Accidents with hazardous materials may threaten the lives of people living in the direct environment of the transportation infrastructure. In many countries, fire brigades play a major role in advising the authorities when they are dealing with issues where hazardous materials are involved. Since emergency responders have to deal with injured persons, information concerning the number of injured people and the types of injuries is relevant to them. In response to this need, we developed a method for calculating the number of injured people. This method was applied to the (re)development plans for the largest railway station in the Netherlands, Utrecht Central station. Through this intermodal transfer terminal, both passengers and substantial amounts of hazardous materials are transported. The fire brigades used the injury information to assess the spatial development plans and transportation plans for hazardous materials. Furthermore, the fire brigades used the injury information to determine their suppression tactics and equipment requirements.

Nils Rosmuller; Inge Trijssenaar; Johan Reinders; Peter Blokker

2012-01-01T23:59:59.000Z

68

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

69

Transportation  

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

Due to limited parking, all visitors are strongly encouraged to: Due to limited parking, all visitors are strongly encouraged to: 1) car-pool, 2) take the Lab's special conference shuttle service, or 3) take the regular off-site shuttle. If you choose to use the regular off-site shuttle bus, you will need an authorized bus pass, which can be obtained by contacting Eric Essman in advance. Transportation & Visitor Information Location and Directions to the Lab: Lawrence Berkeley National Laboratory is located in Berkeley, on the hillside directly above the campus of University of California at Berkeley. The address is One Cyclotron Road, Berkeley, California 94720. For comprehensive directions to the lab, please refer to: http://www.lbl.gov/Workplace/Transportation.html Maps and Parking Information: On Thursday and Friday, a limited number (15) of barricaded reserved parking spaces will be available for NON-LBNL Staff SNAP Collaboration Meeting participants in parking lot K1, in front of building 54 (cafeteria). On Saturday, plenty of parking spaces will be available everywhere, as it is a non-work day.

70

Visibility and Road Accidents  

Science Journals Connector (OSTI)

... road accidents from a very unusual point of view. These writers investigated the beliefs of pedestrians regarding their own visibility, to see how far these beliefs compared with their actual ... drive.

1940-11-23T23:59:59.000Z

71

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

72

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

73

Federally Led Accident Investigation Reports | Department of...  

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

Federally Led Accident Investigation Reports Federally Led Accident Investigation Reports Includes Pre-March 2011 Type A Reports September 1, 1998 Type A Accident Investigation...

74

Accident Investigation Handbook  

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

SENSI NOT MEAS UREMENT TIVE D DOE-HDBK-1 1208-2012 July 2012 DOE E HA ANDBOOK K Ac ccide ent and d Op pera ational Sa afety y An naly ysis Volume e I: Ac ccide ent A Analy ysis Tec chniq ques U.S. Depar rtmen nt of En nergy Was shingto on, D.C C. 205 85 DOE-HDBK-1208-2012 INTRODUCTION - HANDBOOK APPLICATION AND SCOPE Accident Investigations (AI) and Operational Safety Reviews (OSR) are valuable for evaluating technical issues, safety management systems and human performance and environmental conditions to prevent accidents, through a process of continuous organizational learning. This Handbook brings together the strengths of the experiences gained in conducting Department of Energy (DOE) accident investigations over the past many years. That experience encourages us

75

Naval Spent Fuel Rail Shipment Accident Exercise Objectives  

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

NAVAL SPENT FUEL RAIL SHIPMENT NAVAL SPENT FUEL RAIL SHIPMENT ACCIDENT EXERCISE OBJECTIVES * Familiarize stakeholders with the Naval spent fuel ACCIDENT EXERCISE OBJECTIVES Familiarize stakeholders with the Naval spent fuel shipping container characteristics and shipping practices * Gain understanding of how the NNPP escorts who accompany the spent fuel shipments will interact with civilian emergency services representatives g y p * Allow civilian emergency services agencies the opportunity to evaluate their response to a pp y p simulated accident * Gain understanding of how the communications links that would be activated in an accident involving a Naval spent fuel shipment would work 1 NTSF May 11 ACCIDENT EXERCISE TYPICAL TIMELINE * Conceptual/Organizational Meeting - April 6 E R T i d it t t d TYPICAL TIMELINE

76

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

77

Computerized Accident Incident Reporting System  

Broader source: Energy.gov [DOE]

The Computerized Accident/Incident Reporting System is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE...

78

Road Accidents and Research  

Science Journals Connector (OSTI)

... of speed); later still to lack of care in all road users without exception (pedestrians, cyclists and drivers), that is, the whole community. Before blaming the 'human ... to probe into such other accident causes as the varying number of traffic units including pedestrians brought on to the roads by more hours of sunshine. Two drought years increased ...

MERVYN O'GORMAN

1944-05-20T23:59:59.000Z

79

Chemical Stockpile Disposal Program rapid accident assessment  

SciTech Connect (OSTI)

This report develops a scheme for the rapid assessment of a release of toxic chemicals resulting from an accident in one of the most chemical weapon demilitarization plants or storage areas. The system uses such inputs as chemical and pressure sensors monitoring the plant and reports of accidents radioed to the Emergency Operations Center by work parties or monitoring personnel. A size of release can be estimated from previous calculations done in the risk analysis, from back calculation from an open-air chemical sensor measurement, or from an estimated percentage of the inventory of agent at the location of the release. Potential consequences of the estimated release are calculated from real-time meteorological data, surrounding population data, and properties of the agent. In addition to the estimated casualties, area coverage and no-death contours vs time would be calculated. Accidents are assigned to one of four categories: community emergencies, which are involve a threat to off-site personnel; on-post emergencies, which involve a threat only to on-site personnel; advisory, which involves a potential for threat to on-site personnel; and chemical occurrence, which can produce an abnormal operating condition for the plant but no immediate threat to on-site personnel. 9 refs., 20 tabs.

Chester, C.V.

1990-08-01T23:59:59.000Z

80

The lived experience of post-traumatic stress disorder as described by motor vehicle accident victims in Jordan.  

E-Print Network [OSTI]

??Aim: To explore the lived experience of post-traumatic stress disorder (PTSD) as described by individuals who have been involved in a motor vehicle accident (MVA) (more)

Al-Kofahy, Lilibeth

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.


81

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

82

Clean Slate transportation and human health risk assessment  

SciTech Connect (OSTI)

Public concern regarding activities involving radioactive material generally focuses on the human health risk associated with exposure to ionizing radiation. This report describes the results of a risk analysis conducted to evaluate risk for excavation, handling, and transport of soil contaminated with transuranics at the Clean Slate sites. Transportation risks were estimated for public transport routes from the Tonopah Test Range (TTR) to the Envirocore disposal facility or to the Area 3 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) for both radiological risk and risk due to traffic accidents. Human health risks were evaluated for occupational and radiation-related health effects to workers. This report was generated to respond to this public concern, to provide an evaluation of the risk, and to assess feasibility of transport of the contaminated soil for disposal.

NONE

1997-02-01T23:59:59.000Z

83

The Chernobyl Nuclear Accident  

Science Journals Connector (OSTI)

...often repeated belief of the opponents of nuclear power that the risks, whatever they are, outweigh the need for and the known value of nuclear energy in developing electric power in the world. We are some 44 years away from the first development of nuclear energy, and yet the authors of this editorial... To the Editor: Cassel and Leaning began their editorial (July 27 issue)1 with a review of the report on the Chernobyl nuclear accident by Baranov et al.2 in the same issue, but they very quickly shifted to a barrage of warning shots across the bow of the ...

1990-02-08T23:59:59.000Z

84

Secure Transportation_final_print-ready  

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

A A History of Secure Transportation * The transportation of the CEUSP material in casks will be made by Hittman Transport, a commercial carrier * Hittman Transport is a specialty company whose primary mission is transporting hazardous materials * Transport method meets all of the requirements of the Department of Energy, Nuclear Regulatory Commission, and Department of Transportation for shipment of hazardous radioactive material * Hittman Transport maintains drivers with DOE security clearances and all shipments will be escorted by armed Federal officers Hittman Transport drivers' average number of years experience 26 Completed Hittman Transport shipments without significant accident or loss of material 196K Hittman Transport began supporting the nuclear industry

85

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

SciTech Connect (OSTI)

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

Not Available

1992-06-01T23:59:59.000Z

86

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

SciTech Connect (OSTI)

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

Not Available

1992-06-01T23:59:59.000Z

87

Nuclear Reactor Severe Accident Experiments  

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

Nuclear Reactor Severe Accident Experiments Nuclear Reactor Severe Accident Experiments Capabilities Engineering Experimentation Reactor Safety Testing and Analysis Overview Nuclear Reactor Severe Accident Experiments MAX NSTF SNAKE Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Nuclear Reactor Severe Accident Experiments 1 2 3 4 5 6 7 We perform experiments simulating reactor core melt phenomena in which molten core debris ("corium") erodes the concrete floor of a containment building. This occurred during the Fukushima nuclear power plant accident though the extent of concrete damage is yet unknown. This video shows the top view of a churning molten pool of uranium oxide at 2000°C (3600°F) seen during an experiment at Argonne. Corium behaves much like lava.

88

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

89

MAAP-CANDU simulations of LOCA/LOECI accidents at Darlington NGS  

SciTech Connect (OSTI)

Severe accidents have been the subject of a great deal of analysis and research, particularly in the light water reactor community. Although severe accident analysis in Canada deuterium-uranium (CANDU) reactors has not been published abundantly, a significant body of research and analysis has been accumulated. This has occurred because CANDU has directly taken into consideration a set of severe accidents [e.g loss-of-coolant accidents (LOCAs) coincident with a loss-of-emergency-coolant injection (LOECI)] in the design basis. These accidents have served to define the design requirements that ensure the integrity of the heat transport system. The CANDU reactor design has inherent heat sinks such as the primary heat transport system, the secondary side, moderator system, and shielding system (shield tank and end shields). These heat sinks are significant and are able to moderate or terminate the progression of severe accidents that go beyond the design base cases. These types of accidents are typically analyzed at Ontario Hydro in conjunction with probabilistic safety analysis (PSA), where the severe accident consequences are analyzed by a series of conservative hand-calculation methods.

Kwee, M.T.; Choi, M.H.; Leung, R.K. [Ontario Hydro, Toronto, Ontario (Canada)

1996-12-31T23:59:59.000Z

90

An Integrated Accident & Consequence Analysis Approach for Accidental Releases through Multiple Leak Paths  

SciTech Connect (OSTI)

This paper presents a consequence analysis for a postulated fire accident on a building containing plutonium when the resulting outside release is partly through the ventilation/filtration system and partly through other pathways such as building access doorways. When analyzing an accident scenario involving the release of radioactive powders inside a building, various pathways for the release to the outside environment can exist. This study is presented to guide the analyst on how the multiple building leak path factors (combination of filtered and unfiltered releases) can be evaluated in an integrated manner starting with the source term calculation and proceeding through the receptor consequence determination. The analysis is performed in a two-step process. The first step of the analysis is to calculate the leak path factor, which represents the fraction of respirable radioactive powder that is made airborne that leaves the building through the various pathways. The computer cod e of choice for this determination is MELCOR. The second step is to model the transport and dispersion of powder material released to the atmosphere and to estimate the resulting dose that is received by the downwind receptors of interest. The MACCS computer code is chosen for this part of the analysis. This work can be used as model for performing analyses for systems similar in nature where releases can propagate to the outside environment via filtered and unfiltered pathways. The methodology provides guidance to analysts outlining the essential steps needed to perform a sound and defensible consequence analysis.

POLIZZI, LM

2004-04-28T23:59:59.000Z

91

Source terms for plutonium aerosolization from nuclear weapon accidents  

SciTech Connect (OSTI)

The source term literature was reviewed to estimate aerosolized and respirable release fractions for accidents involving plutonium in high-explosive (HE) detonation and in fuel fires. For HE detonation, all estimates are based on the total amount of Pu. For fuel fires, all estimates are based on the amount of Pu oxidized. I based my estimates for HE detonation primarily upon the results from the Roller Coaster experiment. For hydrocarbon fuel fire oxidation of plutonium, I based lower bound values on laboratory experiments which represent accident scenarios with very little turbulence and updraft of a fire. Expected values for aerosolization were obtained from the Vixen A field tests, which represent a realistic case for modest turbulence and updraft, and for respirable fractions from some laboratory experiments involving large samples of Pu. Upper bound estimates for credible accidents are based on experiments involving combustion of molten plutonium droplets. In May of 1991 the DOE Pilot Safety Study Program established a group of experts to estimate the fractions of plutonium which would be aerosolized and respirable for certain nuclear weapon accident scenarios.

Stephens, D.R.

1995-07-01T23:59:59.000Z

92

Going the Distance? NRC's Response to the National Academy of Science's Transportation Study  

SciTech Connect (OSTI)

In February 2006, the National Academy of Sciences (NAS) published the results of a 3 1/2-year study, titled Going the Distance, that examined the safety of transporting spent nuclear fuel (SNF) and high level waste (HLW) in the United States. NAS initiated this study to address what it perceived to be a national need for an independent, objective, and authoritative analysis of SNF and HLW transport in the United States. The study was co-sponsored by the U.S. Nuclear Regulatory Commission (NRC), the U.S. Department of Energy (DOE), the U.S. Department of Transportation (DOT), the Electric Power Research Institute and the National Cooperative Highway Research Program. This paper addresses some of the recommendations made in the NAS study related to the performance of SNF transportation casks in long duration fires, the use of full-scale package testing, and the need for an independent review of transportation security prior to the commencement of large scale shipping campaigns to an interim storage site or geologic repository. In conclusion: The NRC believes that the current regulations in 10 CFR Part 71 for the design of SNF and HLW transportation packages provide a very high level of protection to the public for very severe accidents and credible threat scenarios. As recommended by the NAS study, additional studies of accidents involving severe fires have been completed. These studies have confirmed that spent fuel casks would be expected to withstand very severe fires without the release of any fission products from the spent fuel. Additionally, changes in rail operating procedures such as the use of dedicated trains and prohibition on the co-location of SNF and flammable liquids in rail tunnels can further reduce the already low probability of severe rail accident fires involving SNF and HLW. (authors)

Easton, E.P.; Bajwa, C.S. [United States Nuclear Regulatory Commission, Washington, DC (United States)

2008-07-01T23:59:59.000Z

93

Accident Investigation at the Idaho National Laboratory Engineering  

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

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

94

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

95

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

96

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 900C 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

97

Offshore blow-out accidents : an analysis of causes of vulnerability exposing technological systems to accidents.  

E-Print Network [OSTI]

??This thesis is about understanding causes of vulnerabilities leading to specific type of accidents on offshore oil and gas installations. Blow-out accidents have disastrous potential (more)

Stren, Thomas G.

2007-01-01T23:59:59.000Z

98

A CANDU Severe Accident Analysis  

SciTech Connect (OSTI)

As interest in severe accident studies has increased in the last years, we have developed a set of simple models to analyze severe accidents for CANDU reactors that should be integrated in the EU codes. The CANDU600 reactor uses natural uranium fuel and heavy water (D2O) as both moderator and coolant, with the moderator and coolant in separate systems. We chose to analyze accident development for a LOCA with simultaneous loss of moderator cooling and the loss of emergency core cooling system (ECCS). This type of accident is likely to modify the reactor geometry and will lead to a severe accident development. When the coolant temperatures inside a pressure tube reaches 10000 deg C, a contact between pressure tube and calandria tube occurs and the residual heat is transferred to the moderator. Due to the lack of cooling, the moderator eventually begins to boil and is expelled, through the calandria vessel relief ducts, into the containment. Therefore the calandria tubes (fuel channels) will be uncovered, then will disintegrate and fall down to the calandria vessel bottom. After all the quantity of moderator is vaporized and expelled, the debris will heat up and eventually boil. The heat accumulated in the molten debris will be transferred through the calandria vessel wall to the shield tank water, which normally surrounds the calandria vessel. The phenomena described above are modelled, analyzed and compared with the existing data. The results are encouraging. (authors)

Negut, Gheorghe; Catana, Alexandru [Institute for Nuclear Research, 1, Compului Str., Mioveni, PO Box 78, 0300 Pitesti (Romania); Prisecaru, Ilie [University Politehnica Bucharest (Romania)

2006-07-01T23:59:59.000Z

99

Naval Spent Fuel Rail Shipment Accident Exercise Objectives ...  

Office of Environmental Management (EM)

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

100

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

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

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

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

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...

102

Analysis of accidents during flashing operations  

E-Print Network [OSTI]

occurred at intersections under flashing operation compared to those operating in the normal mode. A statistical analysis was conducted to determine the safety of flashing signal operation. No significant increases in accidents or accident severity were...

Obermeyer, Michael Edward

2012-06-07T23:59:59.000Z

103

Chernobyl Nuclear Accident | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Chernobyl Nuclear Accident | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

104

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

105

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

106

DOE - Safety of Radioactive Material Transportation  

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

Immersion Comparison Demonstrating target hardness. Comparison of the Fire Test to a Gasoline Tanker and Sedan collision under an Overpass Fire Test [FIRE test] Click to view picture Real-life Accident Comparison [FIRE scenario] Click to view picture Real-life scenarios that the above test is designed to protect against include being involved in an accident with a gasoline tanker truck, causing the gasoline contents to burn the package. The amount of fuel being burned is approximately 5000 gallons in a pool 30 feet in diameter. During this test, the package is fully engulfed in the fire and is not protected by a transporting vehicle. On October 9, 1997, a truck tractor pulling a cargo tank semitrailer was going under an overpass of the New York State Thruway in Yonkers, New York when it was struck by a sedan. The car hit the right side of the cargo tank in the area of the tank's external loading/unloading lines, releasing the 8800 gallons of gasoline they contained.

107

Spent Fuel Transportation Risk Assessment  

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

Fuel Transportation Risk Assessment Fuel Transportation Risk Assessment (SFTRA) Draft NUREG-2125 Overview for National Transportation Stakeholders Forum John Cook Division of Spent Fuel Storage and Transportation 1 SFTRA Overview Contents * Project and review teams * Purpose and goals * Basic methodology * Improvements relative to previous studies * Draft NUREG structure and format * Routine shipment analysis and results * Accident condition analysis and results * Findings and conclusions * Schedule 2 SFTRA Research and Review Teams * Sandia National Laboratory Research Team [$1.8M; 9/06-9/12] - Doug Ammerman - principal investigator - Carlos Lopez - thermal - Ruth Weiner - RADTRAN * NRC's SFTRA Technical Review Team - Gordon Bjorkman - structural

108

Projecting Fatalities in Crashes involving Older Drivers  

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

Crashes Crashes Projecting Fatalities in Crashes Involving Older Drivers Involving Older Drivers Oak Oak Ridge Ridge National Laboratory National Laboratory, USA USA Presented at Presented at the the 17th 17th World Congress of the International World Congress of the International Association Association for Accident and Traffic Medicine for Accident and Traffic Medicine May May 30, 30, 2000, 2000, Stockholm, Sweden Stockholm, Sweden ORNL ORNL P. P. Hu Hu D. D. Jones Jones T. T. Reuscher Reuscher R. R. Schmoyer Schmoyer T. T. Truett Truett General General Motors Motors Annette Annette Irwin Irwin U.S. U.S. DOTransportation DOTransportation Jesse Jesse Blatt Blatt Acknowledgements Acknowledgements Objective Objective This This research research is is funded funded by by a a Cooperative Cooperative Research

109

DOE - Safety of Radioactive Material Transportation  

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

Free Drop Comparison Crush Comparison Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Hypothetical Accident Conditions: Six tests as defined in 10 CFR Part 71.73 of the NRC transportation regulations were established to provide repeatable and definable conditions that encompass most real-life accidents. The real-life accidents on this page are comparisons to the environments that the regulatory hypothetical accidents protect against. The collision forces or fire temperature and duration that were present in each accident are similar to the conditions that spent fuel casks are designed to survive. Passenger Train and Semi-truck Trailer Collision [DROP scenario] Mack Truck and Subaru Collision [CRUSH scenario] Freight Train and Freight Train Collision

110

VEACON: A Vehicular Accident Ontology designed to improve safety on the roads  

Science Journals Connector (OSTI)

Vehicles are nowadays provided with a variety of new sensors capable of gathering information about themselves and from their surroundings. In a near future, these vehicles will also be capable of sharing all the harvested information, with the surrounding ... Keywords: Intelligent Transportation Systems (ITS), Ontologies, VANETs, Vehicular Networks, Vehicular accidents

Javier Barrachina; Piedad Garrido; Manuel Fogue; Francisco J. Martinez; Juan-Carlos Cano; Carlos T. Calafate; Pietro Manzoni

2012-11-01T23:59:59.000Z

111

FUKUSHIMA NUCLEAR ACCIDENT: PRELIMINARY ASSESSMENT OF THE RISKS TO NON-HUMAN BIOTA  

Science Journals Connector (OSTI)

......provided in the Tool as look-up effects tables for different wildlife groups. The basic equations for Tier 2 assessment are presented...released during the Fukushima nuclear accident were transported by wind over the ocean, towards the west coast of the USA(1, 6......

Abubakar Sadiq Aliyu; Ahmad Termizi Ramli; Nuraddeen Nasiru Garba; Muneer Aziz Saleh; Hamman Tukur Gabdo; Muhammad Sanusi Liman

2014-05-01T23:59:59.000Z

112

Computerized Accident/Incident Reporting System  

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

Accident Recordkeeping and Reporting Accident Recordkeeping and Reporting Accident/Incident Recordkeeping and Reporting CAIRS logo Computerized Accident Incident Reporting System CAIRS Database The Computerized Accident/Incident Reporting System is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE operations. Injury and Illness Dashboard The Dashboard provides an alternate interface to CAIRS information. The initial release of the Dashboard allows analysis of composite DOE-wide information and summary information by Program Office, and site. Additional data feature are under development. CAIRS Registration Form CAIRS is a Government computer system and, as such, has security requirements that must be followed. Access to the

113

The Skikda LNG accident: losses, lessons learned and safety climate assessment  

Science Journals Connector (OSTI)

The Skikda LNG accident was the worst petrochemical plant fire in Algeria, in which 27 employees died, 56 injured and cost $900 million. The accident was caused by several reasons: poor maintenance and poor general condition of unit 40, the site distribution of different units which caused domino effect and there is no perfect prevention, communication system on safety. The paper summarised the lessons from the Skikda LNG accident and assessed the health and safety management made following the accident. Also, a safety climate assessment is used to assess employees' perceptions at the new safety policy. The results showed that there is divergence between operators and executives because operators are not involved in the safety setting.

Roukia Ouddai; Hassane Chabane; Assia Boughaba; Mohamed Frah

2012-01-01T23:59:59.000Z

114

Transportation System Risk Assessment (TSRA) bounding release model  

SciTech Connect (OSTI)

Transportation System Risk Assessments (TSRAs) document the compliance of proposed shipments of nuclear components with applicable federal regulations as well as the associated risks involved. If a relatively simple bounding analysis can show that the consequences resulting from a worst case scenario are acceptably low, a more time intensive and costly risk analysis can be avoided. Therefore, a bounding release FORTRAN model has been developed to determine the consequences of a worst case non-criticality transportation accident. The consequences of three conservative bounding accidents are determined by the model: (1) direct radiation exposure, (2) airborne release of radiological and/or hazardous solid material, and (3) release of radiological and/or hazardous solid material into a waterway and subsequent uptake by an individual through drinking water. Program output includes the direct radiation exposure (mrem), maximum downwind concentration (mg/m{sup 3}), radiation dose (mrem) received as a result of the postulated airborne release of radiological material, intake (mg) due to inhalation, radiation dose (mrem) received by an individual resulting from a release of radiological material into a waterway and uptake into drinking water, and uptake (mg) due to ingestion. This report documents the methodologies and correlations used in the numerical model to perform the bounding consequence calculations.

Anderson, J.C.

1997-10-01T23:59:59.000Z

115

DOE Accident Prevention and Investigation Program  

Broader source: Energy.gov [DOE]

The Department of Energy (DOE) Accident Prevention and Investigation Program serves as a key DOE corporate safety resource for promoting accident PREVENTION through exchange of lessons learned and information for improvement of our integrated safety management system. The techniques and tools utilized in the investigation of "accidents" can be valuable in looking at leading indicators associated with our safety program, to determine the embedded precursors to accidents, and prevent them from occurring. The information obtained through application of these techniques and tools serve as benchmarks for others to utilize in evaluating their safety management systems.

116

Computerized Accident Incident Reporting System | Department...  

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

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...

117

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...

118

DOE Accident Prevention and Investigation Program | Department...  

Energy Savers [EERE]

The Corporate Safety Programs maintains the Accident Investigation and Prevention Handbook (DOE-HDBK-1208-2012) as part of a continuing effort to enhance quality and achieve...

119

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

120

SILENE Benchmark Critical Experiments for Criticality Accident Alarm Systems  

SciTech Connect (OSTI)

In October 2010 a series of benchmark experiments was conducted at the Commissariat a Energie Atomique et aux Energies Alternatives (CEA) Valduc SILENE [1] facility. These experiments were a joint effort between the US Department of Energy (DOE) and the French CEA. The purpose of these experiments was to create three benchmarks for the verification and validation of radiation transport codes and evaluated nuclear data used in the analysis of criticality accident alarm systems (CAASs). This presentation will discuss the geometric configuration of these experiments and the quantities that were measured and will present some preliminary comparisons between the measured data and calculations. This series consisted of three single-pulsed experiments with the SILENE reactor. During the first experiment the reactor was bare (unshielded), but during the second and third experiments it was shielded by lead and polyethylene, respectively. During each experiment several neutron activation foils and thermoluminescent dosimeters (TLDs) were placed around the reactor, and some of these detectors were themselves shielded from the reactor by high-density magnetite and barite concrete, standard concrete, and/or BoroBond. All the concrete was provided by CEA Saclay, and the BoroBond was provided by Y-12 National Security Complex. Figure 1 is a picture of the SILENE reactor cell configured for pulse 1. Also included in these experiments were measurements of the neutron and photon spectra with two BICRON BC-501A liquid scintillators. These two detectors were provided and operated by CEA Valduc. They were set up just outside the SILENE reactor cell with additional lead shielding to prevent the detectors from being saturated. The final detectors involved in the experiments were two different types of CAAS detectors. The Babcock International Group provided three CIDAS CAAS detectors, which measured photon dose and dose rate with a Geiger-Mueller tube. CIDAS detectors are currently in use at Y-12 in the newly constructed Highly Enriched Uranium Materials Facility. The second CAAS detector used a {sup 6}LiF TLD to absorb neutrons and a silicon detector to count the charge particles released by these absorption events. Lawrence Livermore National Laboratory provided four of these detectors, which had formerly been used at the Rocky Flats facility in the United States.

Miller, Thomas Martin [ORNL] [ORNL; Reynolds, Kevin H. [Y-12 National Security Complex] [Y-12 National Security Complex

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.


121

NUCLEAR POWER: Extent of Soviet accident uncertain  

Science Journals Connector (OSTI)

NUCLEAR POWER: Extent of Soviet accident uncertain ... Detailed, official information about the Chernobyl nuclear power-plant disaster as of late last week remained wrapped in the Soviet Union's usual shroud of secrecy. ... But there seems to be no doubt that it is the worst accident in the 43-year history of nuclear power. ...

1986-05-05T23:59:59.000Z

122

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

123

A review of the Melcor Accident Consequence Code System (MACCS): Capabilities and applications  

SciTech Connect (OSTI)

MACCS was developed at Sandia National Laboratories (SNL) under U.S. Nuclear Regulatory Commission (NRC) sponsorship to estimate the offsite consequences of potential severe accidents at nuclear power plants (NPPs). MACCS was publicly released in 1990. MACCS was developed to support the NRC`s probabilistic safety assessment (PSA) efforts. PSA techniques can provide a measure of the risk of reactor operation. PSAs are generally divided into three levels. Level one efforts identify potential plant damage states that lead to core damage and the associated probabilities, level two models damage progression and containment strength for establishing fission-product release categories, and level three efforts evaluate potential off-site consequences of radiological releases and the probabilities associated with the consequences. MACCS was designed as a tool for level three PSA analysis. MACCS performs probabilistic health and economic consequence assessments of hypothetical accidental releases of radioactive material from NPPs. MACCS includes models for atmospheric dispersion and transport, wet and dry deposition, the probabilistic treatment of meteorology, environmental transfer, countermeasure strategies, dosimetry, health effects, and economic impacts. The computer systems MACCS is designed to run on are the 386/486 PC, VAX/VMS, E3M RISC S/6000, Sun SPARC, and Cray UNICOS. This paper provides an overview of MACCS, reviews some of the applications of MACCS, international collaborations which have involved MACCS, current developmental efforts, and future directions.

Young, M.

1995-02-01T23:59:59.000Z

124

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...

125

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

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

operated and maintained by the site lessee, the United States Enrichment Corporation (USEC). Type B Accident Investigation of the July 12, 2007, Forklift and Pedestrian Accident...

126

Sandia National Laboratories: Waste Isolation Pilot Plant Accident...  

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

ClimateECEnergyComputational Modeling & SimulationWaste Isolation Pilot Plant Accident Investigation Analysis Support Waste Isolation Pilot Plant Accident Investigation Analysis...

127

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 -...

128

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

Energy Savers [EERE]

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...

129

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

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

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

130

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

131

Accident Investigation of the 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, Idaho  

Broader source: Energy.gov [DOE]

This report documents the Naval Reactors investigation into the collapse ofa partially-erected spent fuel storage building, Overpack Storage Expansion #2 (OSE2), at the Naval Reactors Facility. The Accident Investigation Board inspected the scene, collected physical and photographic evidence, interviewed involved personnel, and reviewed relevant documents to determine the key causes of the accident. Based on the information gathered during the investigation, the Board identified several engineering and safety deficiencies that need to be addressed to prevent recurrence.

132

Jefferson Orange Hardin Regional Transportation Study 2007 Metropolitan Transportation Plan - 2030  

E-Print Network [OSTI]

vehicle. ? Promote operational efficiency through the use of technological improvements. ? Support measures that reduce traffic congestion and peak hour travel demand. Goal #3: Enhance the Safety of the Transportation Community. Public safety is a... evacuation routes or prevent rail/vehicle accidents at railway crossings. Objectives: ? Promote programs and projects that reduce the number and severity of traffic accidents, especially at railroad crossings. ? Give priority to construction projects...

South East Texas Regional Planning Commission

2007-04-12T23:59:59.000Z

133

WIPP transportation exercise to test emergency response capablities for Midland-Odessa  

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

Transportation Exercise to Test Transportation Exercise to Test Emergency Response Capabilities for Midland-Odessa CARLSBAD, N.M., January 10, 2000 - Emergency response agencies from Midland and Odessa, Texas, will take part in a 1 p.m. (CST) training exercise Jan. 12 at the Ector County Coliseum. The graded exercise will help agencies determine whether emergency personnel are prepared to respond to a possible accident involving a shipment of transuranic radioactive waste headed for the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). "This is an excellent opportunity for emergency responders to test the skills they've learned," said Dale Childers, assistant chief of the Odessa Fire Department and emergency management coordinator for Ector County. "It will also help us determine what improvements,

134

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

135

Federally Led Accident Investigation Reports | Department of...  

Office of Environmental Management (EM)

Fire at the Waste Isolation Pilot Plant, Carlsbad NM The U.S. Department of Energy (DOE) Accident Prevention Investigation Board was appointed to investigate a fire at the...

136

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

137

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

138

DOE - Safety of Radioactive Material Transportation  

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

What are examples of severe testing? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. These full-scale tests, conducted at Sandia National Laboratories Transportation Programs, demonstrate how spent fuel casks perform in accident environments that are more similar to what may happen during actual shipments. Each of the tests included the transportation vehicle as well as the cask. The damage to the casks from these tests was less than the damage during the regulatory hypothetical accident tests, demonstrating that the regulatory tests are more severe. DESCRIPTION PHOTO DURING TEST PHOTO AFTER TEST PHOTO OF PACKAGE AFTER TEST VIDEO OF TEST CRASH TEST Cask rail car with a 74 ton Type B Package on it crashing into a 690 ton concrete block at 81 miles per hour [photo]

139

DOE - Safety of Radioactive Material Transportation  

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

What are full-scale tests? What are scale-model tests? What is computer analysis? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. A packaging is certified when it can survive a sequence of impact, crush, puncture, fire, and immersion tests designed to replicate transport accident conditions. Type B Packages must meet the testing requirements of: Compliance Testing, as defined in 10 CFR Part 71.85 and 10 CFR Part 71.87 Normal Conditions of Transport, Ten tests as defined in 10 CFR Part 71.71 Hypothetical Accident Conditions, Six tests as defined in 10 CFR Part 71.73 The ability of radioactive material packages to withstand testing environments can be demonstrated by full-scale testing, scale-model

140

Integration of numerical analysis tools for automated numerical optimization of a transportation package design  

SciTech Connect (OSTI)

The use of state-of-the-art numerical analysis tools to determine the optimal design of a radioactive material (RAM) transportation container is investigated. The design of a RAM package`s components involves a complex coupling of structural, thermal, and radioactive shielding analyses. The final design must adhere to very strict design constraints. The current technique used by cask designers is uncoupled and involves designing each component separately with respect to its driving constraint. With the use of numerical optimization schemes, the complex couplings can be considered directly, and the performance of the integrated package can be maximized with respect to the analysis conditions. This can lead to more efficient package designs. Thermal and structural accident conditions are analyzed in the shape optimization of a simplified cask design. In this paper, details of the integration of numerical analysis tools, development of a process model, nonsmoothness difficulties with the optimization of the cask, and preliminary results are discussed.

Witkowski, W.R.; Eldred, M.S.; Harding, D.C.

1994-09-01T23:59:59.000Z

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.


141

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

142

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

143

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

144

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

145

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...

146

SAF-230DE - Web Based Course: Accident Investigation Overview | Department  

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

SAF-230DE - Web Based Course: Accident Investigation Overview SAF-230DE - Web Based Course: Accident Investigation Overview SAF-230DE - Web Based Course: Accident Investigation Overview September 18, 2013 - 10:52am Addthis SAF-230DE - Web Based Course: Accident Investigation Overview The Office of Health Safety and Security (HSS) National Training Center (NTC) in collaboration with the HSS Accident Investigation Program (HS-24) has developed and released a course that provides an overview of the fundamentals of accident investigation. This course is intended to meet the every five year refresher training requirement for DOE Federal Accident Investigators under DOE Order 225.1B "Accident Investigations", and serves as an orientation to other DOE Federal Accident Investigation Board Members who need a basic knowledge of

147

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...

148

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...

149

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...

150

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...

151

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...

152

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 ...

153

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 ...

154

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 ...

155

Office of Secure Transportation Activities  

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

16th, 2012 16th, 2012 WIPP Knoxville, TN OFFICE OF SECURE TRANSPORTATION Agency Integration Briefing Our Mission To provide safe and secure ground and air transportation of nuclear weapons, nuclear weapons components, and special nuclear materials and conduct other missions supporting the national security of the United States of America. 3 5 OST's Commitment to Transportation Safety and Security Over three decades of safe, secure transport of nuclear weapons and special nuclear material to and from military locations and DOE facilities More than 140 million miles traveled Over three decades and 240,000 flight hours of accident-free flying Professionalism We conduct ourselves and our operations with the highest standards of professionalism and integrity.

156

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

157

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

158

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

159

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

160

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.


161

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...

162

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...

163

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

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

SAF-230DE - Web Based Course: Accident Investigation Overview SAF-230DE - Web Based Course: Accident Investigation Overview September 18, 2013 - 10:52am Addthis SAF-230DE - Web...

164

The accident site portable integrated video system  

SciTech Connect (OSTI)

This paper presents a high bandwidth fiber-optic communication system intended for post accident recovery of weapons. The system provides bi-directional multichannel, and multi-media communications. Two smaller systems that were developed as direct spin-offs of the larger system are also briefly discussed.

Jones, D.P.; Shirey, D.L.; Amai, W.A.

1995-12-31T23:59:59.000Z

165

A neutron dosemeter for nuclear criticality accidents  

Science Journals Connector (OSTI)

......emulsion was rapidly depleted of all its drops. In...emulsion was rapidly depleted of all its drops. The...around an accident at a uranium fuel factory in Tokai-mura...emulsion was rapidly depleted of all its drops. A...Quality Assurance, Health Care methods Radiation......

F. d'Errico; G. Curzio; R. Ciolini; A. Del Gratta; R. Nath

2004-08-01T23:59:59.000Z

166

An analysis to determine correlations of freeway traffic accidents with specific geometric design features  

E-Print Network [OSTI]

occurrence of accidents was cited by Gerlough (13) in the following summary of an accident analysis. The accident records of 45 equal sections of roadway which had simi- lar volumes were compared using the Poisson distribution. The number of accidents... occurrence of accidents was cited by Gerlough (13) in the following summary of an accident analysis. The accident records of 45 equal sections of roadway which had simi- lar volumes were compared using the Poisson distribution. The number of accidents...

Smith, Frank Miller

2012-06-07T23:59:59.000Z

167

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 de Fukushima. 3. La puissance résiduelle. 4. Perte de refroidissement et conséquences. 5

Skorobogatiy, Maksim

168

The temporal effect of traffic violations and accidents on accident occurrence  

E-Print Network [OSTI]

in the accident data analysis. Therefore, in Zylman's view the total lack of uniformity, completeness, and consistency makes data collec- ted on driver records from more than one jurisdiction highly question- able. He further notes that comparing biographical... in the accident data analysis. Therefore, in Zylman's view the total lack of uniformity, completeness, and consistency makes data collec- ted on driver records from more than one jurisdiction highly question- able. He further notes that comparing biographical...

McKemie, Martha Susan

2012-06-07T23:59:59.000Z

169

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

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

Monthly Accident Statistics Monthly Accident Statistics Latest Accident Statistics Accident Statistics (through December 2013) Archived Accident Statistics 2013 Through November Through October Through September Through August Through July Through June Through May Through April Through March Through February Through January 2012 Through December Through November Through October Through September Through August Through July Through June Through May Through February Through January 2011 Through December Through November Through October Through September Through August Through July Through June Through May Through April Through March Through February Through January 2010 Through December Through November Through October Through September Through August Through July Through June Through May Through April Through March Through February

170

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...

171

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 (

172

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 Japans 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

173

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

174

Assessment of Sulfate in Ohio Transportation Subgrades.  

E-Print Network [OSTI]

??The Ohio Department of Transportation (ODOT) recently implemented global chemical stabilization for new construction or repair involving major road projects. Pavement heave caused the failure (more)

Freese, Kevin M

2014-01-01T23:59:59.000Z

175

Accident, Maryland: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Accident, Maryland: Energy Resources Accident, Maryland: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 39.628696°, -79.319759° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.628696,"lon":-79.319759,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

176

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

177

ASSESSING CAUSAL FACTORS IN INDIVIDUAL ROAD ACCIDENTS  

E-Print Network [OSTI]

+k 1+k1+k k 2 k 1+k1+k rhv a v v a a2 v +rv a2 v +hv #12;Data Collection System · Advanced detection accident report: Happened on I-94 in downtown Minneapolis Happened during the afternoon peak period Vehicle 2 rear-ended vehicle 1 Driver 1 received `possible injury' Driver 2 reported as: `Following too

Minnesota, University of

178

Transportation Networks for Emergency Evacuations  

SciTech Connect (OSTI)

Evacuation modeling systems (EMS) have been developed to facilitate the planning, analysis, and deployment of emergency evacuation of populations at risk. For any EMS, data such as road network maps, traffic control characteristics, and population distribution play critical roles in delineating emergency zones, estimating population at risk, and determining evacuation routes. There are situations in which it is possible to plan in advance for an emergency evacuation including, for example, an explosion at a chemical processing facility or a radiological accident at a nuclear plant. In these cases, if an accident or a terrorist attack were to happen, then the best evacuation plan for the prevailing network and weather conditions would be deployed. In other instances -for example, the derailment of a train transporting hazardous materials-, there may not be any previously developed plan to be implemented and decisions must be made ad-hoc on if and how to identify and proceed with the best course of action to minimize losses. Although both cases require as a starting point the development of a transportation network model of the area at risk, which must include road capacity and topology, in the latter the available time to generate this network is extremely limited. This time constraint precludes the use of any traditional data gathering methodology and the network generation process has to rely on the use of GIS and stochastic modeling techniques. The generation of these transportation networks in real time is the focus of this entry.

Franzese, Oscar [ORNL; Liu, Cheng [ORNL

2008-01-01T23:59:59.000Z

179

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

SciTech Connect (OSTI)

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

Tusheva, P.; Schaefer, F.; Kliem, S. [Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstrasse 400, D-01328 Dresden (Germany)

2012-07-01T23:59:59.000Z

180

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

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

What you find is not always what you fixHow other aspects than causes of accidents decide recommendations for remedial actions  

Science Journals Connector (OSTI)

In accident investigation, the ideal is often to follow the principle what-you-find-is-what-you-fix, an ideal reflecting that the investigation should be a rational process of first identifying causes, and then implement remedial actions to fix them. Previous research has however identified cognitive and political biases leading away from this ideal. Somewhat surprisingly, however, the same factors that often are highlighted in modern accident models are not perceived in a recursive manner to reflect how they influence the process of accident investigation in itself. Those factors are more extensive than the cognitive and political biases that are often highlighted in theory. Our purpose in this study was to reveal constraints affecting accident investigation practices that lead the investigation towards or away from the ideal of what-you-find-is-what-you-fix. We conducted a qualitative interview study with 22 accident investigators from different domains in Sweden. We found a wide range of factors that led investigations away from the ideal, most which more resembled factors involved in organizational accidents, rather than reflecting flawed thinking. One particular limitation of investigation was that many investigations stop the analysis at the level of preventable causes, the level where remedies that were currently practical to implement could be found. This could potentially limit the usefulness of using investigations to get a view on the big picture of causes of accidents as a basis for further remedial actions.

Jonas Lundberg; Carl Rollenhagen; Erik Hollnagel

2010-01-01T23:59:59.000Z

182

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

183

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

184

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

185

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

186

Detection of radioxenon in Darwin, Australia following the Fukushima Dai-ichi nuclear power plant accident  

Science Journals Connector (OSTI)

Abstract A series of 133Xe detections in April 2011 made at the Comprehensive Nuclear-Test-Ban Treaty Organisation (CTBTO) International Monitoring System noble gas station in Darwin, Australia, were analysed to determine the most likely source location. Forward and backwards atmospheric transport modelling simulations using FLEXPART were conducted. It was shown that the most likely source location was the Fukushima Dai-ichi nuclear power plant accident. Other potential sources in the southern hemisphere were analysed, including the Australian Nuclear Science and Technology Organisation (ANSTO) radiopharmaceutical facility, but it was shown that sources originating from these locations were highly unlikely to be the source of the observed 133Xe Darwin detections.

Blake Orr; Michael Schppner; Rick Tinker; Wolfango Plastino

2013-01-01T23:59:59.000Z

187

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

188

TEPP Training - Modular Emergency Response Radiological Transportation  

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

Services » Waste Management » Packaging and Transportation » Services » Waste Management » Packaging and Transportation » Transportation Emergency Preparedness Program » TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) Once the jurisdiction has completed an evaluation of their plans and procedures, they will need to address any gaps in training. To assist, TEPP has developed the Modular Emergency Response Radiological Transportation Training (MERRTT) program. MERRTT provides fundamental knowledge for responding to transportation incidents involving radiological material and builds on training in existing hazardous materials curricula. MERRTT satisfies the training requirements outlined in the Waste Isolation Pilot

189

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

RMIR (Radioactive Materials Incident Report) Database Transportation RMIR (Radioactive Materials Incident Report) Database Transportation Accident and Incident Experience,1971-1999 Access Hazardous Materials Information System (HMIS) the primary source of national data for the Federal, state, and local governmental agencies responsible for the safety of hazardous materials transportation. Rail Transport Highway Transport Air Transport The Radioactive Material Incident Report (RMIR) Database was developed in 1981 at the Transportation Technology Center of Sandia National Laboratories (SNL) to support its research and development activities for the U.S. Department of Energy (DOE). This database contains information about radioactive materials transportation incidents that have occurred in the U.S. from 1971 through 1999. These data were drawn from the U.S.

190

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...

191

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

Office of Environmental Management (EM)

August 21, 2012, Contamination Incident at the Los Alamos Neutron Science Center at the Los Alamos National Laboratory Accident Investigation of the August 21, 2012, Contamination...

192

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

Office of Environmental Management (EM)

Los Alamos National Laboratory Accident Investigation of the August 21, 2012, Contamination Incident at the Los Alamos Neutron Science Center at the Los Alamos National Laboratory...

193

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

Office of Environmental Management (EM)

Idaho Falls, Idaho February 10, 2006 An accident at the Idaho National Laboratory (INL) was investigated in which a technician sustained a serious injury to his right hand...

194

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

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

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

195

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,...

196

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,...

197

Type B Accident Investigation Board Report Grout Injection Operator...  

Office of Environmental Management (EM)

TYPE B ACCIDENT INVESTIGATION BOARD REPORT GROUT INJECTION OPERATOR INJURY AT THE COLD TEST PIT SOUTH, IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY, OCTOBER 15, 2001...

198

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

Office of Environmental Management (EM)

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

199

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

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

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

200

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...

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

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

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

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

202

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).

203

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

SciTech Connect (OSTI)

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

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

1989-08-01T23:59:59.000Z

204

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 ?1200C for short (?4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800C could not be reproduced. Both FeCrAl and MAX phase Ti2AlC form a protective alumina scale in steam. However, commercial Ti2AlC that is not single phase, formed a much thicker oxide at 1200C in steam and significant TiO2, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich ? formation. The composition effects and critical limits to retaining protective scale formation at >1400C are still being evaluated. Keywords: Accident tolerant LWR Fuel cladding, FeCrAl, Mo, Ti2AlC, Al2O3, high temperature steam oxidation resistance

none,

2014-07-01T23:59:59.000Z

205

Radiological protection from radioactive waste management in existing exposure situations resulting from a nuclear accident  

Science Journals Connector (OSTI)

......Radiological Protection Policy for the Disposal of Radioactive...Contaminated Areas after a Nuclear Accident or a Radiation...SITUATIONS RESULTING FROM A NUCLEAR ACCIDENT. | In environmental remediation after nuclear accidents, radioactive......

Daisuke Sugiyama; Takatoshi Hattori

2013-01-01T23:59:59.000Z

206

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...

207

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...

208

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...

209

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...

210

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...

211

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.

212

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....

213

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.

214

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

215

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

216

Fukushima Daiichi Accident and Its Radiological Impact on the Environment  

Science Journals Connector (OSTI)

The Fukushima Daiichi nuclear accident is a topic of current media and public interest. It provides a means to motivate students to understand the fission process and the barriers that have been designed to prevent the release of fission products to the environment following a major nuclear powerreactor accident. The Fukushima Daiichi accident further encourages a discussion of the effect of fission products upon the environment including the resulting contamination of air water soil animals fish milk and crops. Accident-generated radiation levels that caused the evacuation of people 2030 km from the facility further serve to foster student interest and desire to understand the science associated with the Fukushima Daiichi accident.

J. J. Bevelacqua

2012-01-01T23:59:59.000Z

217

UNEP-Low Carbon Transport in India | Open Energy Information  

Open Energy Info (EERE)

in India in India Jump to: navigation, search Name UNEP-Low Carbon Transport in India Agency/Company /Organization United Nations Environment Programme (UNEP) Sector Climate, Energy Focus Area Transportation Topics Low emission development planning Website http://www.unep.org/transport/ Program Start 2010 Program End 2013 Country India Southern Asia References Low Carbon Transport in India[1] UNEP-Low Carbon Transport in India Screenshot "India is currently the fourth largest greenhouse gas (GHG) emitter in the world, with its transport sector being the second largest contributor of CO2 emissions. The sector also provokes road congestion, local air pollution, noise and accidents, particularly in urban areas. Opportunities exist to make India's transport growth more sustainable by

218

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...

219

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...

220

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...

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,
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

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:...

222

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...

223

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...

224

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...

225

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...

226

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:...

227

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

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

a Summary: - Annex E - Consequence assessment of accident scenarios Annex F - HazOp and FMEA Tables and results 4... accident consequences (fatalities). Therefore, we suggest...

228

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...

229

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....

230

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...

231

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...

232

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....

233

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...

234

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...

235

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....

236

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....

237

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...

238

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,...

239

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...

240

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....

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

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...

242

E-Print Network 3.0 - accident management implementation Sample...  

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

5. Report accident to Risk Management Passenger Name: Address... Columbia University Vehicle Accident Report Keep this ... Source: Qian, Ning - Center for Neurobiology and...

243

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...

244

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...

245

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...

246

Transportation Demand  

Gasoline and Diesel Fuel Update (EIA)

page intentionally left blank page intentionally left blank 69 U.S. Energy Information Administration | Assumptions to the Annual Energy Outlook 2011 Transportation Demand Module The NEMS Transportation Demand Module estimates transportation energy consumption across the nine Census Divisions (see Figure 5) and over ten fuel types. Each fuel type is modeled according to fuel-specific technology attributes applicable by transportation mode. Total transportation energy consumption is the sum of energy use in eight transport modes: light-duty vehicles (cars and light trucks), commercial light trucks (8,501-10,000 lbs gross vehicle weight), freight trucks (>10,000 lbs gross vehicle weight), buses, freight and passenger aircraft, freight and passenger rail, freight shipping, and miscellaneous

247

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

248

Effects of spent fuel types on offsite consequences of hypothetical accidents  

SciTech Connect (OSTI)

Argonne National Laboratory (ANL) conducts experimental work on the development of waste forms suitable for several types of spent fuel at its facility on the Idaho National Engineering and Environmental Laboratory (INEEL) located 48 km West of Idaho Falls, ID. The objective of this paper is to compare the offsite radiological consequences of hypothetical accidents involving the various types of spent nuclear fuel handled in nonreactor nuclear facilities. The highest offsite total effective dose equivalents (TEDEs) are estimated at a receptor located about 5 km SSE of ANL facilities. Criticality safety considerations limit the amount of enriched uranium and plutonium that could be at risk in any given scenario. Heat generated by decay of fission products and actinides does not limit the masses of spent fuel within any given operation because the minimum time elapsed since fissions occurred in any form is at least five years. At cooling times of this magnitude, fewer than ten radionuclides account for 99% of the projected TEDE at offsite receptors for any credible accident. Elimination of all but the most important nuclides allows rapid assessments of offsite doses with little loss of accuracy. Since the ARF (airborne release fraction), RF (respirable fraction), LPF (leak path fraction) and atmospheric dilution factor ({chi}/Q) can vary by orders of magnitude, it is not productive to consider nuclides that contribute less than a few percent of the total dose. Therefore, only {sup 134}Cs, {sup 137}Cs-{sup 137m}Ba, and the actinides significantly influence the offsite radiological consequences of severe accidents. Even using highly conservative assumptions in estimating radiological consequences, they remain well below current Department of Energy guidelines for highly unlikely accidents.

Courtney, J. C.; Dwight, C. C.; Lehto, M. A.

2000-02-18T23:59:59.000Z

249

WIPP Transportation  

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

Transuranic Waste Transportation Container Documents Documents related to transuranic waste containers and packages. CBFO Tribal Program Information about WIPP shipments across...

250

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...

251

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...

252

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

253

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

254

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

255

WreckWatch: Automatic Traffic Accident Detection and Notification with Smartphones  

Science Journals Connector (OSTI)

Traffic accidents are one of the leading causes of fatalities in the US. An important indicator of survival rates after an accident is the time between the accident and when emergency medical personnel are dispatched to the scene. Eliminating the time ... Keywords: cyber-physical systems, mobile cyber-physical systems, smartphones, traffic accident detection

Jules White; Chris Thompson; Hamilton Turner; Brian Dougherty; Douglas C. Schmidt

2011-06-01T23:59:59.000Z

256

Tritium Precipitation in European Cities and in Osaka, Japan Owing to the Chernobyl Nuclear Accident  

Science Journals Connector (OSTI)

......Japan Owing to the Chernobyl Nuclear Accident Taeko Koga Hiroshige...Takeo Niwa Hiroshi Kawai Atomic Energy Research Institute, Kinki...before and after the Chernobyl nuclear plant accident by the time...after the accident. Chernobyl nuclear plant accident|Tritium precipitation......

Taeko Koga; Hiroshige Morishima; Takeo Niwa; Hiroshi Kawai

1991-09-01T23:59:59.000Z

257

Radiological Health Effects Models for Nuclear Power Plant Accident Consequence Analysis An Update (1990)  

Science Journals Connector (OSTI)

Technical Paper / Advances in Reactor Accident Consequence Assessment / Radiation Biology and Environment

John S. Evans

258

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,...

259

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

Office of Environmental Management (EM)

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

260

Accident Investigation Reports - Type B | Department of Energy  

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

ignited the right leg of his 100% cotton anticontamination (anti-c) coveralls and the plastic bootie. February 1, 2003 Type B Accident Investigation of the January 28, 2003, Fall...

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

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

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

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 the...

262

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

263

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

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

B Accident Investigation of the Arc Flash at Brookhaven National Laboratory, April 14, 2006 More Documents & Publications DOE-HDBK-1092-1998 DOE-HDBK-1092-2004 DOE-HDBK-1092-2013...

264

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

265

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...

266

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...

267

HEALTH EFFECTS OF THE NUCLEAR ACCIDENT AT THREE MILE ISLAND  

E-Print Network [OSTI]

within 50 miles of the nuclear power plant was estimated tothe radiation from the nuclear power plant accident. From anand the Peach Bottom nuclear power plants, like the general

Fabrikant, J.I.

2010-01-01T23:59:59.000Z

268

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...

269

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...

270

University Guidance for the REPORTING OF ACCIDENTS, DISEASES AND  

E-Print Network [OSTI]

University Guidance for the REPORTING OF ACCIDENTS, DISEASES AND DANGEROUS OCCURANCES HEALTH INJURY, HOSPITALISATION, DISEASE AND DANGEROUS OCCURRENCES.2 Reporting Over Three Days Absence Injury.........................................2 4.3 Reporting a Dangerous

271

Type B Accident Investigation Injury Resulting From Violent Exothermic...  

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

when the accident occurred. UT-Battelle at Grand Junction, Colorado, was the UT-Battelle satellite office responsible for the project. Field operations were being done by IT under...

272

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

273

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

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

teri.ehresman@inl.gov Bill Cabage (ORNL), 865-574-4399, cabagewh@ornl.gov Next-generation nuclear fuel withstands high-temperature accident conditions IDAHO FALLS - A safer...

274

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

275

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

276

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

277

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

278

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

279

DOE - Safety of Radioactive Material Transportation  

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

What are the requirements? What are the requirements? Safety Record Radioactive material has been shipped in the U. S. for more than 50 years with no occurrences of death or serious injury from exposure of the contents of these shipments. Hazardous Material Shipments for 1 Year Internationally 300 million United States 3 million DOE <1% or 5,000 (out of 3 million) [U.S. DOE NTP, 1999, Transporting Radioactive Materials] All radioactive shipments are regulated by the Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). Since transport accidents cannot be prevented, the regulations are primarily designed to: Insure safety in routine handling situations for minimally hazardous material Insure integrity under all circumstances for highly dangerous materials

280

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).

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

ENVIRONMENTAL ANALYSIS OF ILLINOIS COAL ENTRY INTO THE TRANSPORTATION MARKET.  

E-Print Network [OSTI]

??High oil prices and nationalist desires to reduce foreign dependency create opportunities for Illinois bituminous coal to be involved in the transportation market. Using Illinois (more)

Starkey, Darin Michael

2009-01-01T23:59:59.000Z

282

Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors  

Science Journals Connector (OSTI)

Abstract The CONSEN (CONServation of ENergy) code is a fast running code to simulate thermal-hydraulic transients, specifically developed for fusion reactors. In order to demonstrate CONSEN capabilities, the paper deals with the accident analysis of the magnet induced confinement bypass for ITER design 1996. During a plasma pulse, a poloidal field magnet experiences an over-voltage condition or an electrical insulation fault that results in two intense electrical arcs. It is assumed that this event produces two one square meters ruptures, resulting in a pathway that connects the interior of the vacuum vessel to the cryostat air space room. The rupture results also in a break of a single cooling channel within the wall of the vacuum vessel and a breach of the magnet cooling line, causing the blow down of a steam/water mixture in the vacuum vessel and in the cryostat and the release of 4K helium into the cryostat. In the meantime, all the magnet coils are discharged through the magnet protection system actuation. This postulated event creates the simultaneous failure of two radioactive confinement barrier and it envelopes all type of smaller \\{LOCAs\\} into the cryostat. Ice formation on the cryogenic walls is also involved. The accident has been simulated with the CONSEN code up to 32h. The accident evolution and the phenomena involved are discussed in the paper and the results are compared with available results obtained using the MELCOR code.

Gianfranco Caruso; Fabio Giannetti; Maria Teresa Porfiri

2013-01-01T23:59:59.000Z

283

Traces of fission products in southeast Spain after the Fukushima nuclear accident  

Science Journals Connector (OSTI)

Traces of 131I, 134Cs and 137Cs were measured after the Fukushima nuclear accident between 23 March and 13 April 2011 in southeast Spain. The movement of the radioactive cloud toward southeast Spain was reconstructed based on the backward and forward trajectory cluster analyses. Polar maritime air masses which had originated over North America transported the radioactive plume toward the southeast Spain. Aerosols, rainwater, vegetables and cheese were analyzed to determine the radioactive risk. The highest concentrations of 131I, 134Cs and 137Cs in air samples were 2.630.12mBq/m3; 0.100.03mBq/m3; 0.090.02mBq/m3, respectively. After precipitation on April 3rd, the maximum concentrations of 131I, 134Cs and 137Cs were detected in rainwater samples, 1.100.16mBq/L; 0.0220.003mBq/L; 0.050.03mBq/L, respectively. As a consequence, 131I was transferred to the human food chain, and found in chard and goat cheese, 0.970.20Bq/kg and 0.520.08Bq/kg, respectively. The traces of 131I, 134Cs and 137Cs detected in the different samples were so low, that there is no impact on human health or the environment in Spain after the Fukushima nuclear accident.

F. Piero Garca; M.A. Ferro Garca

2012-01-01T23:59:59.000Z

284

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

285

GASFLOW analysis of a tritium leak accident  

SciTech Connect (OSTI)

The consequences of an earthquake-induced fire involving a tritium leak were analyzed using the GASFLOW computer code. Modeling features required by the analysis include ventilation boundary conditions, flow of a gas mixture in an enclosure containing obstacles, thermally induced buoyancy, and combustion phenomena.

Farman, R.F.; Fujita, R.K. [Los Alamos National Lab., NM (United States); Travis, J.R. [Engineering and Scientific software, Inc. (Untied States)

1994-09-01T23:59:59.000Z

286

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

287

GASFLOW: A computational model to analyze accidents in nuclear containment and facility buildings  

SciTech Connect (OSTI)

GASFLOW is a finite-volume computer code that solves the time-dependent, compressible Navier-Stokes equations for multiple gas species. The fluid-dynamics algorithm is coupled to the chemical kinetics of combusting liquids or gases to simulate diffusion or propagating flames in complex geometries of nuclear containment or confinement and facilities` buildings. Fluid turbulence is calculated to enhance the transport and mixing of gases in rooms and volumes that may be connected by a ventilation system. The ventilation system may consist of extensive ductwork, filters, dampers or valves, and fans. Condensation and heat transfer to walls, floors, ceilings, and internal structures are calculated to model the appropriate energy sinks. Solid and liquid aerosol behavior is simulated to give the time and space inventory of radionuclides. The solution procedure of the governing equations is a modified Los Alamos ICE`d-ALE methodology. Complex facilities can be represented by separate computational domains (multiblocks) that communicate through overlapping boundary conditions. The ventilation system is superimposed throughout the multiblock mesh. Gas mixtures and aerosols are transported through the free three-dimensional volumes and the restricted one-dimensional ventilation components as the accident and fluid flow fields evolve. Combustion may occur if sufficient fuel and reactant or oxidizer are present and have an ignition source. Pressure and thermal loads on the building, structural components, and safety-related equipment can be determined for specific accident scenarios. GASFLOW calculations have been compared with large oil-pool fire tests in the 1986 HDR containment test T52.14, which is a 3000-kW fire experiment. The computed results are in good agreement with the observed data.

Travis, J.R. [Science Applications International Corp., Albuquerque, NM (United States); Nichols, B.D.; Wilson, T.L.; Lam, K.L.; Spore, J.W.; Niederauer, G.F. [Los Alamos National Lab., NM (United States)

1993-07-01T23:59:59.000Z

288

GASFLOW: A computational model to analyze accidents in nuclear containment and facility buildings  

SciTech Connect (OSTI)

GASFLOW is a finite-volume computer code that solves the time-dependent, compressible Navier-Stokes equations for multiple gas species. The fluid-dynamics algorithm is coupled to the chemical kinetics of combusting liquids or gases to simulate diffusion or propagating flames in complex geometries of nuclear containment or confinement and facilities' buildings. Fluid turbulence is calculated to enhance the transport and mixing of gases in rooms and volumes that may be connected by a ventilation system. The ventilation system may consist of extensive ductwork, filters, dampers or valves, and fans. Condensation and heat transfer to walls, floors, ceilings, and internal structures are calculated to model the appropriate energy sinks. Solid and liquid aerosol behavior is simulated to give the time and space inventory of radionuclides. The solution procedure of the governing equations is a modified Los Alamos ICE'd-ALE methodology. Complex facilities can be represented by separate computational domains (multiblocks) that communicate through overlapping boundary conditions. The ventilation system is superimposed throughout the multiblock mesh. Gas mixtures and aerosols are transported through the free three-dimensional volumes and the restricted one-dimensional ventilation components as the accident and fluid flow fields evolve. Combustion may occur if sufficient fuel and reactant or oxidizer are present and have an ignition source. Pressure and thermal loads on the building, structural components, and safety-related equipment can be determined for specific accident scenarios. GASFLOW calculations have been compared with large oil-pool fire tests in the 1986 HDR containment test T52.14, which is a 3000-kW fire experiment. The computed results are in good agreement with the observed data.

Travis, J.R. (Science Applications International Corp., Albuquerque, NM (United States)); Nichols, B.D.; Wilson, T.L.; Lam, K.L.; Spore, J.W.; Niederauer, G.F. (Los Alamos National Lab., NM (United States))

1993-01-01T23:59:59.000Z

289

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

290

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

291

Measuring the impact of nuclear accidents on energy policy  

Science Journals Connector (OSTI)

Abstract This paper investigates the effects of nuclear accidents on energy policy with the help of a panel dataset of 31 countries from 1965 to 2009, using annual data on the capacity of reactor construction starts, as well as the timing of three nuclear accidents scaled five or higher on the International Nuclear and Radiological Event Scale. After determining the extent of the accident impact in the different countries, I find that neither the Three Mile Island (TMI) nor the Lucens accidents had a worldwide negative effect on construction starts, while Chernobyl did. Three Mile Island had a lasting impact in the United States, however. I show that the effect of Chernobyl wore off in certain geographical clusters, after ten to thirty years. An accident is likely to have a negative and long lasting impact in the country where it happened, and possibly in countries affected by the direct consequences. I find that nuclear capacity enlargement shows a significant lock-in effect, but it was also driven by primary energy consumption and energy security considerations in the past five decades.

Zsuzsanna Csereklyei

2014-01-01T23:59:59.000Z

292

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

293

Accident Sequence Evaluation Program: Human reliability analysis procedure  

SciTech Connect (OSTI)

This document presents a shortened version of the procedure, models, and data for human reliability analysis (HRA) which are presented in the Handbook of Human Reliability Analysis With emphasis on Nuclear Power Plant Applications (NUREG/CR-1278, August 1983). This shortened version was prepared and tried out as part of the Accident Sequence Evaluation Program (ASEP) funded by the US Nuclear Regulatory Commission and managed by Sandia National Laboratories. The intent of this new HRA procedure, called the ''ASEP HRA Procedure,'' is to enable systems analysts, with minimal support from experts in human reliability analysis, to make estimates of human error probabilities and other human performance characteristics which are sufficiently accurate for many probabilistic risk assessments. The ASEP HRA Procedure consists of a Pre-Accident Screening HRA, a Pre-Accident Nominal HRA, a Post-Accident Screening HRA, and a Post-Accident Nominal HRA. The procedure in this document includes changes made after tryout and evaluation of the procedure in four nuclear power plants by four different systems analysts and related personnel, including human reliability specialists. The changes consist of some additional explanatory material (including examples), and more detailed definitions of some of the terms. 42 refs.

Swain, A.D.

1987-02-01T23:59:59.000Z

294

DOE - Safety of Radioactive Material Transportation  

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

Crush Comparison Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Comparison of the Free Drop Test to a Passenger Train and Semi-truck Trailer Collision Free Drop Test 3,000,000 lbs of force present in this package certification test. [DROP test] Click to view picture Real-life Accident Comparison 1,000,000 lbs of force present in this real-life accident. [DROP scenario] Click to view picture Real-life scenarios that are encompassed by the above test include: the package being struck by a train traveling 60 MPH the package falling off of a 30-foot high bridge onto solid rock or from a higher bridge onto a highway or railroad the package running into a bridge support or rock slope at 45 MPH. Packages are transported onboard trucks or rail cars, which absorb some of the impact energy, reducing the resulting damage to the packages from the accident. On May 2, 1995, an O&J Gordon Trucking Company truck consisting of a tractor and a lowbed semitrailer became lodged on a high-profile (hump) railroad grade crossing near Sycamore, South Carolina. About 35 minutes later, the truck was struck by southbound Amtrak train No. 81, Silver Star, en route from New York City to Tampa, Florida.

295

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

296

An application of probabilistic safety assessment methods to model aircraft systems and accidents  

SciTech Connect (OSTI)

A case study modeling the thrust reverser system (TRS) in the context of the fatal accident of a Boeing 767 is presented to illustrate the application of Probabilistic Safety Assessment methods. A simplified risk model consisting of an event tree with supporting fault trees was developed to represent the progression of the accident, taking into account the interaction between the TRS and the operating crew during the accident, and the findings of the accident investigation. A feasible sequence of events leading to the fatal accident was identified. Several insights about the TRS and the accident were obtained by applying PSA methods. Changes proposed for the TRS also are discussed.

Martinez-Guridi, G.; Hall, R.E.; Fullwood, R.R.

1998-08-01T23:59:59.000Z

297

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

298

Sec. Herrington Leads Delegation in Response to Chernobyl Accident |  

National Nuclear Security Administration (NNSA)

Sec. Herrington Leads Delegation in Response to Chernobyl Accident | Sec. Herrington Leads Delegation in Response to Chernobyl Accident | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Sec. Herrington Leads Delegation in Response to ... Sec. Herrington Leads Delegation in Response to Chernobyl Accident

299

Accident scenarios for marshalling yards in The Netherlands: private or public fire fighting  

Science Journals Connector (OSTI)

Since the introduction of the Seveso and Seveso II directive (1996), many Western European countries have had the opportunity to demand that installations processing hazardous materials have a private fire brigade. In the Netherlands, based on the Dutch company fire brigade decree, certain companies can be compelled to have a private fire brigade (BZK, 1990). Hazardous materials are processed at about 40 marshalling yards (belonging to the infraprovider ProRail) and therefore a company fire brigade might be compulsory. In the Rotterdam harbour area, for several years, a (juridical) discussion has been going on between the Rotterdam municipality and ProRail concerning the marshalling yards in this area. In August 2007, this dispute was brought to the highest court for such affairs in the Netherlands, the Administrative Jurisdiction Division of the Council of State. To provide input for this juridical process, an analysis was made for six ProRail marshalling yards, each processing hazardous materials. The results indicate that accident scenarios involving toxic and flammable substances are possible. Based upon the type, development and extent of the accidents, some of these credible scenarios determine the fire fighting quality and quantity, the so-called design scenarios. The Council of State relates the fire brigade capacity to the credible scenarios and not to the design scenarios. The result is that ProRail might be responsible for organising and financing private fire brigades at about 40 marshalling yards.

Nils Rosmuller

2008-01-01T23:59:59.000Z

300

NREL: Transportation Research - News  

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

News NREL provides a number of transportation and hydrogen news sources. Transportation News Find news stories that highlight NREL's transportation research, development, and...

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

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

302

Health Risks of Accidents at Nuclear Power Plants  

Science Journals Connector (OSTI)

To the Editor: Christodouleas et al. (June 16 issue) discuss the health risks of nuclear accidents but do not include the psychological and social effects of such events. Such casualties in Fukushima will far exceed any cases of physical illness. Having just returned from the region to assess mental... To the Editor: Christodouleas et al. (June 16 issue)1 discuss the health risks of nuclear accidents but do not include the psychological and social effects of such events. Such casualties in Fukushima will far exceed any cases of physical illness. Having ...

2011-09-08T23:59:59.000Z

303

Probabilistic risk assessment and nuclear waste transportation: A case study of the use of RADTRAN in the 1986 Environmental Assessment for Yucca Mountain  

SciTech Connect (OSTI)

The analysis of the risks of transporting irradiated nuclear fuel to a federal repository, Appendix A of the DOE Environmental Assessment for Yucca Mountain (DOE84), is based on the RADTRAN model and input parameters. The RADTRAN computer code calculates the radiation exposures and health effects under normal or incident-free transport, and over all credible accident conditions. The RADTRAN model also calculates the economic consequences of transportation accidents, though these costs were not included in the Department`s Environmental Assessment for the proposed Yucca Mountain repository.

Resnikoff, M. [Radioactive Waste Management Associates, New York, NY (United States)

1990-12-01T23:59:59.000Z

304

Emergency response planning for railroad transportation related spills of oil or other hazardous materials  

E-Print Network [OSTI]

In December 1984 an unintentional release of poison gas from a chemical plant in Bhopal, India killed over 2,500 people. Thousands of others were injured. Although this material was not in transportation at the time, this accident raised public...

Reeder, Geoffrey Benton

2012-06-07T23:59:59.000Z

305

Transportation Security  

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

For Review Only 1 Transportation Security Draft Annotated Bibliography Review July 2007 Preliminary Draft - For Review Only 2 Work Plan Task * TEC STG Work Plan, dated 8/2/06, Product #16, stated: "Develop an annotated bibliography of publicly-available documents related to security of radioactive material transportation." * Earlier this year, a preliminary draft annotated bibliography on this topic was developed by T-REX , UNM, to initially address this STG Work Plan Task. Preliminary Draft - For Review Only 3 Considerations in Determining Release of Information * Some "Publicly-available" documents could potentially contain inappropriate information according to standards set by DOE information security policy and DOE Guides. - Such documents would not be freely

306

Transportation Issues  

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

Issues Issues and Resolutions - Compilation of Laboratory Transportation Work Package Reports Prepared for U.S. Department of Energy Used Fuel Disposition Campaign Compiled by Paul McConnell Sandia National Laboratories September 30, 2012 FCRD-UFD-2012-000342 Transportation Issues and Resolutions ii September 2012 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any

307

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

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

' VISION 'Vision Problem?' DRIVEED 'Driver Education?'; FORMAT ACCIDENT DRIVEED YOUNG OLD YES... an accident is 1.1174(1+1.1174) 0.5277. Taking a similar person, except...

308

E-Print Network 3.0 - accident management measures Sample Search...  

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

Sample search results for: accident management measures Page: << < 1 2 3 4 5 > >> 1 An Internet-based, Searchable Database of Air Accidents N. Storey, B.Sc., Ph.D., FBCS, MIEE,...

309

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...

310

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...

311

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...

312

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...

313

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...

314

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...

315

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...

316

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...

317

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:...

318

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...

319

Calculation Notes for Subsurface Leak Resulting in Pool, TWRS FSAR Accident Analysis  

SciTech Connect (OSTI)

This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Subsurface Leaks Resulting in Pool.

Hall, B.W.

1996-09-25T23:59:59.000Z

320

Calculation notes for surface leak resulting in pool, TWRS FSAR accident analysis  

SciTech Connect (OSTI)

This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Surface Leaks Resulting in Pool.

Hall, B.W.

1996-09-25T23:59:59.000Z

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.


321

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...

322

MSIV leakage airborne iodine transport  

SciTech Connect (OSTI)

Gaseous iodine deposits on surfaces exposed to vapors. Basic chemical and physical principles predict this behavior, and several laboratory and in-plant measurements demonstrate the characteristic. An empirical model was developed that describes the deposition, resuspension, and transformation of airborne radioiodine molecular species as a stream containing these forms moves along its pathway. The model uses a data base of measured values of deposition and resuspension rates in its application and describes the conversion of the more reactive inorganic iodine species I[sub 2] to the less reactive organic species CH[sub 3]I as the iodine deposits and resuspends along the path. It also considers radioactive decay and chemical surface bonding during residence on surfaces. For the 8-day [sup 131]I, decay during the airborne portion of the transport is negligible. Verification of the model included measurement tests of long gaseous-activity sampling lines of different diameters, operated at different flow rates and stream temperatures. The model was applied to the streams at a boiling water reactor nuclear power plant to describe the transport through leaking main steam isolation valves (MSIVs), following a loss-of-coolant accident.

Cline, J.E. (Cline Associates Inc., Rockville, MD (United States))

1993-01-01T23:59:59.000Z

323

Potential of taxonomy to preserve and disseminate Fukushima accident information implemented by JAEA library  

Science Journals Connector (OSTI)

Regarding Fukushima accident, it would be true that the relevant information has not been provided well enough for the affected people in and over Japan, for instance, as often being mixed, confused, too difficult to access or disappearing through the internet or websites. In this regard, it is necessary be to terminologically develop ways to access such affected information, like a taxonomy, composed of semantically controlled terms on the related events forming lineage-like hierarchical structures. To come up with a potential taxonomy to preserve and disseminate the affected information, this paper describes a preliminary view on the terminological aspects and availability of IAEA/INIS for the information implemented by JAEA Library. It is necessary to make new aspects and terms derived from the affected information, such as 'beyond design basis', more detailed, scrutinised and involved in the schemes, terminological aspects and IAEA/INIS, in order to improve the taxonomic potential.

Katsuhiko Kunii; Keizo Itabashi; Shun Nagaya

2014-01-01T23:59:59.000Z

324

Policy Research TRANSPORTATION  

E-Print Network [OSTI]

Policy Research TRANSPORTATION CENTER Thestate's transportation system is central to its ability movement of goods to maintain and enhance global economic competitiveness. An effective transportation, TTI has identified the following set of initial transportation issues which must be better understood

325

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

326

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

327

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

328

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

E-Print Network [OSTI]

ANSI and/or OSHA requirements. USACE facilities shall use signs based upon the specifications opt to use signs meeting either the OSHA or ANSI standards for temporary use during the life and Tags; d. 29 CFR 1926.200; Accident Prevention Signs and Tags; e. ANSI/IEEE C95.2; f. ANSI Z136.1; g

US Army Corps of Engineers

329

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

Broader source: Energy.gov [DOE]

On March 2, 2010 at the request of the Bonneville Power Administration (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to investigate an accident in which a supplemental labor contractor was fatally injured in a Bobcat/backhoe accident at the White Bluffs Substation near Richland, Washington on March 1, 2010.

330

Manuscript to appear in Environment, Systems and Decisions CALCULATING NUCLEAR ACCIDENT PROBABILITIES  

E-Print Network [OSTI]

Manuscript to appear in Environment, Systems and Decisions CALCULATING NUCLEAR ACCIDENT there is no authoritative, comprehensive and public historical record of nuclear power plant accidents, we reconstructed a nuclear accident dataset from peer-reviewed and other literature. We found that, in a sample of five

Boyer, Edmond

331

The Savannah River National Laboratory's Response to the Graniteville, SC Train Accident  

SciTech Connect (OSTI)

The Savannah River National Laboratory's (SRNL) Weather INformation and Display (WIND) System was used to provide meteorological and atmospheric modeling/consequence assessment support to state and local agencies following the collision of two Norfolk Southern freight trains on the morning of January 6, 2005. This collision resulted in the release of several toxic chemicals to the environment, including chlorine. The dense and highly toxic cloud of chlorine gas that formed in the vicinity of the accident was responsible for nine fatalities and injuries to more than five hundred others. Transport model results depicting the forecast path of the ongoing release were made available to emergency managers in the county's Unified Command Center shortly after SRNL received a request for assistance. Support continued over the ensuing two days of the active response. The SRNL also provided weather briefings and transport/consequence assessment model results to responders from South Carolina Department of Health and Environmental control (SCDHEC), the Savannah River Site's (SRS) Emergency Operations Center (EOC), DOE Headquarters, and hazmat teams dispatched from the SRS.

Hunter, C. H.; Parker, M. J.; Buckley, R. L.; Weber, A. H.; Addis, R. P.

2005-10-21T23:59:59.000Z

332

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

333

Tree transport system  

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

Tree transport system Tree transport system Name: Paul K Harding Location: N/A Country: N/A Date: N/A Question: How can trees get that tall? How can the transport of water function that good? Normally one could think that trees can get only 10 m high because then the pressure of the air would be to weak to transport the water and a vacuum would occur. Or do trees use a system of one pump-system after another to solve that problem? Replies: Okay, the answer is two-fold. One, the column of water travelling up the trunk of the tree is only a couple of molecules wide, moving up from cell to cell. You can think of each cell as a "valve" if you will, holding the water and keeping it from flowing down the trunk (unless you WANT it to go that way, in the case of sugar laden water moving to storage areas in the roots) until it can be moved to the next cell up, and so on and so on. The second part involves diffusion. Cells can diffuse certain chemical compounds through their cell walls while simultaneously holding onto others. By having a gradient of increasing chemical concentration as you go up the trunk, you can cause a gradual diffusion of water up the trunk (since water travels relatively freely through the cell walls) and thereby creates and exception to the rule of 10 meters being the maximum height for a column of water -- you've effectively added energy to the system to "pump" water up the trunk.

334

Comparison of Average Transport and Dispersion Among a Gaussian, a  

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

Comparison of Average Transport and Dispersion Among a Gaussian, a Comparison of Average Transport and Dispersion Among a Gaussian, a Two-Dimensional, and a Three-Dimensional Model Comparison of Average Transport and Dispersion Among a Gaussian, a Two-Dimensional, and a Three-Dimensional Model The Nuclear Regulatory Commission's (NRC's) code for predicting off-site consequences, MACCS2 (Chanin, et al. 1998) (MELCOR Accident Consequence Code System, Version 2), uses a simplified model for atmospheric transport and d ispersion (ATD), that is, a straight-line Gaussian model. The MACCS2 calculations are used by the NRC for planning purposes, for cost-benefit analyses, and in level-3 probabilistic risk analyses (PRAs). The MACCS2 ATD model has been criticized as being overly simplistic, even for its purposes. The justification for its use has been

335

Major Transportation Accident Investigator Investigating human factors issues, using diplomatic ability,  

E-Print Network [OSTI]

science and the ability to design computer models and simulations of systems and environments include computer system designs, team training, collaborative work, effects of automation, and new reports and reviews for internal and regulatory purposes. Being able to write rapidly and accurately

Dukas, Reuven

336

International Energy Outlook 1999 - Transportation Energy Use  

Gasoline and Diesel Fuel Update (EIA)

transportation.gif (5350 bytes) transportation.gif (5350 bytes) Transportation energy use is projected to constitute more than half of the world’s oil consumption in 2020. Developing nations account for more than half the expected growth in transportation energy use in the IEO99 forecast. The International Energy Outlook 1999 (IEO99) presents a more detailed analysis than in previous years of the underlying factors conditioning long-term growth prospects for worldwide transportation energy demand. A nation’s transportation system is generally an excellent indicator of its level of economic development. In many countries, personal travel still means walking or bicycling, and freight movement often involves domesticated animals. High rates of growth from current levels in developing countries such as China and India still leave their populations

337

LEDSGP/Transportation Toolkit | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit < LEDSGP(Redirected from Transportation Toolkit) Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Developing Strategies for Clean, Efficient Transportation The Transportation LEDS Toolkit supports development planners, technical experts, and decision makers at national and local levels to plan and implement low emission transportation systems that support economic growth. This toolkit website helps users navigate a variety of resources in order to identify the most effective tools necessary to build and implement low

338

LEDSGP/Transportation Toolkit | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit < LEDSGP Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Developing Strategies for Clean, Efficient Transportation The Transportation Toolkit supports development planners, technical experts, and decision makers at national and local levels to plan and implement low-emission transportation systems that support economic growth. This toolkit helps users navigate a variety of resources to identify the most effective tools to build and implement low emission development strategies (LEDS) for the transport sector. Learn more in the report on

339

Category:Transportation Toolkits | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Category Edit History Facebook icon Twitter icon » Category:Transportation Toolkits Jump to: navigation, search Add a new Transportation Toolkit Pages in category "Transportation Toolkits" The following 86 pages are in this category, out of 86 total. A A Report on Worldwide Hydrogen Bus Demonstrations, 2002-2007 A Review of HOV Lane Performance and Policy Options in the United States - Final Report A Roadmap to Funding Infrastructure Development Adapting Urban Transport to Climate Change- Module 5f - Sustainable transport: a sourcebook for policy-makers in developing cities Africa's Transport Infrastructure Mainstreaming Maintenance and Management

340

Appendix V Public Involvement Plan  

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

V V Public Involvement Plan Revision No.: 6 February 2008 Federal Facility Agreement and Consent Order (FFACO) FFACO, Appendix V February 2008 i FFACO Public Involvement Plan U.S. Department of Energy National Nuclear Security Administration Nevada Site Office Las Vegas, Nevada U.S. Department of Defense Defense Threat Reduction Agency Detachment 1, Nevada Operations Mercury, Nevada U.S. Department of Energy Office of Legacy Management Grand Junction, Colorado FFACO, Appendix V February 2008 ii Preface The Public Involvement Plan serves two purposes: it provides a broad public involvement strategy, and fulfills requirements contained in the Federal Facility Agreement and Consent Order (FFACO) relating to public awareness and participation. Under the FFACO, agreed to by

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341

Public Involvment Plan - Rifle, Colorado  

Office of Legacy Management (LM)

4-TAR 4-TAR MAC-GWRIF 7.1 UMTRA Ground Water Project Public Involvement Plan for the Environmental Assessment of Ground Water Compliance at the New and Old Rifle, Colorado, Uranium Mill Tailings Sites May 1999 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work performed under DOE Contract No. DE-AC13-96GJ87335 Public Involvement Plan for the Rifle UMTRA Sites Page 2 Introduction This Public Involvement Plan is tiered to the Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project Public Participation Plan dated October 1997. This Public Involvement Plan applies to both the Old and New Rifle, Colorado, UMTRA Project sites and details the activities that have been or will be carried out to meet the public participation requirements of the

342

Involving students in peer review  

E-Print Network [OSTI]

Involving students in peer review Case studies and practical strategies for university teaching Jon......................................................................................................................................................2 1. WHAT IS STUDENT PEER REVIEW? A CONCISE REVIEW OF THE LITERATURE....................3 BENEFITS OF PEER REVIEW

Pearce, Jon

343

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

344

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.

345

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

346

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

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

Plant Surpasses Five Years Without Lost-Time Plant Surpasses Five Years Without Lost-Time Accident Portsmouth Site Plant Surpasses Five Years Without Lost-Time Accident November 26, 2013 - 12:00pm Addthis BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident. BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident. Russ Hall, environment, safety and health supervisor, changes the DUF6 project sign to mark five years without a lost-time accident. Russ Hall, environment, safety and health supervisor, changes the DUF6 project sign to mark five years without a lost-time accident. BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident.

347

Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS | Department of  

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

Order 225.1B, ACCIDENT INVESTIGATIONS Order 225.1B, ACCIDENT INVESTIGATIONS Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS DOE O 225.1B prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and activities. The purpose of the accident investigation is to understand and identify the causes that contributed to the accident so those deficiencies can be addressed and corrected. This, in turn, is intended to prevent recurrence and promote improved environmental protection and safety and health of DOE employees, contractors, and the public. Moreover, accident investigations are used to promote the values and concepts of a learning organization. The department's integrated safety management (ISM) feedback and improvement

348

Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

Natural Gas Safety Natural Gas Safety after a Traffic Accident to someone by E-mail Share Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Facebook Tweet about Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Twitter Bookmark Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Google Bookmark Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Delicious Rank Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Digg Find More places to share Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on AddThis.com... More in this section... Natural Gas Basics Benefits & Considerations Stations Vehicles Availability Conversions Emissions

349

Transportation radiological risk assessment for the programmatic environmental impact statement: An overview of methodologies, assumptions, and input parameters  

SciTech Connect (OSTI)

The U.S. Department of Energy is considering a broad range of alternatives for the future configuration of radioactive waste management at its network of facilities. Because the transportation of radioactive waste is an integral component of the management alternatives being considered, the estimated human health risks associated with both routine and accident transportation conditions must be assessed to allow a complete appraisal of the alternatives. This paper provides an overview of the technical approach being used to assess the radiological risks from the transportation of radioactive wastes. The approach presented employs the RADTRAN 4 computer code to estimate the collective population risk during routine and accident transportation conditions. Supplemental analyses are conducted using the RISKIND computer code to address areas of specific concern to individuals or population subgroups. RISKIND is used for estimating routine doses to maximally exposed individuals and for assessing the consequences of the most severe credible transportation accidents. The transportation risk assessment is designed to ensure -- through uniform and judicious selection of models, data, and assumptions -- that relative comparisons of risk among the various alternatives are meaningful. This is accomplished by uniformly applying common input parameters and assumptions to each waste type for all alternatives. The approach presented can be applied to all radioactive waste types and provides a consistent and comprehensive evaluation of transportation-related risk.

Monette, F.; Biwer, B.; LePoire, D.; Chen, S.Y.

1994-02-01T23:59:59.000Z

350

Volume II - Accident and Operational Safety Analysis Handbook  

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

208-2012 208-2012 July 2012 DOE HANDBOOK Accident and Operational Safety Analysis Volume II: Operational Safety Analysis Techniques U.S. Department of Energy Washington, D.C. 20585 NOT MEASUREMENT SENSITIVE DOE-HDBK-1208-2012 i ACKNOWLEDGEMENTS This Department of Energy (DOE) Accident and Operational Safety Analysis Handbook was prepared under the sponsorship of the DOE Office of Health Safety and Security (HSS), Office of Corporate Safety Programs, and the Energy Facility Contractors Operating Group (EFCOG), Industrial Hygiene and Safety Sub-group of the Environmental Health and Safety Working Group. The preparers would like to gratefully acknowledge the authors whose works are referenced in this document, and the individuals who provided valuable technical insights and/or specific

351

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

352

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

353

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

354

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

355

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

356

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

357

KERENA safety concept in the context of the Fukushima accident  

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

358

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

359

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

SciTech Connect (OSTI)

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

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

2003-01-01T23:59:59.000Z

360

Community Involvement Fund | Department of Energy  

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

Community Involvement Community Involvement Fund Community Involvement Fund Community Involvement Fund Community Involvement Fund Community Involvement Fund Community Involvement Fund Community Involvement Fund Community Involvement Fund Community Involvement Fund Community Involvement Fund Overview The success of EM's legacy waste cleanup mission depends largely on the support of informed and engaged stakeholders. Cleanup activities have the potential to affect the health of the public, the environment, and the future of the communities that either host or are located near EM sites. Therefore, it is critical that EM receive public input from local citizens and community organizations prior to making cleanup decisions. In December 2010, EM partnered with the New Mexico Community Foundation

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

Transportation Security | ornl.gov  

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

Transportation Security SHARE Global Threat Reduction Initiative Transportation Security Cooperation Secure Transport Operations (STOP) Box Security of radioactive material while...

362

Transportation Security | Department of Energy  

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

Transportation Security Transportation Security Transportation Security More Documents & Publications Overview for Newcomers West Valley Demonstration Project Low-Level Waste...

363

Las Cruces MPO 2040 Metropolitan Transportation Plan  

E-Print Network [OSTI]

2-23 THOROUGHFARE INTERSECTION CRASH RATE MAP FOR THE CITY OF LAS CRUCES 26 2-24 PEDESTRIAN INVOLVED CRASH DENSITY 27 2-25 BICYCLE INVOLVED CRASH DENSITY 28 2-26 MOTORCYCLE INVOLVED CRASH DENSITY 29 2-27 MOTOR VEHICLE INVOLVED CRASH DENSITY 30 2...-28 MILES OF MULTI-USE PATHS 34 2-29 ROADRUNNER TRANSIT FIXED ROUTE MAP 35 2-30 ROADRUNNER FIXED ROUTE RIDERSHIP 36 2-31 ROADRUNNER PARATRANSIT RIDERSHIP 2-32 NMDOT PARK AND RIDE?GOLD ROUTE RIDERSHIP 38 iv TRANSPORT 2040 2-33 AVERAGE DAILY PASSENGER...

Las Cruces Metropolitan Planning Organization

2010-06-09T23:59:59.000Z

364

Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty assessment, main report  

SciTech Connect (OSTI)

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the risks presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents. In 1991, the US Nuclear Regulatory Commission (NRC) and the Commission of the European Communities (CEC) began a joint uncertainty analysis of the two codes. The ultimate objective of the joint effort was to develop credible and traceable uncertainty distributions for the input variables of the codes. Expert elicitation was identified as the best technology available for developing a library of uncertainty distributions for the selected consequence parameters. The study was formulated jointly and was limited to the current code models and to physical quantities that could be measured in experiments. Experts developed their distributions independently. To validate the distributions generated for the wet deposition input variables, samples were taken from these distributions and propagated through the wet deposition code model. Resulting distributions closely replicated the aggregated elicited wet deposition distributions. To validate the distributions generated for the dispersion code input variables, samples from the distributions and propagated through the Gaussian plume model (GPM) implemented in the MACCS and COSYMA codes. Project teams from the NRC and CEC cooperated successfully to develop and implement a unified process for the elaboration of uncertainty distributions on consequence code input parameters. Formal expert judgment elicitation proved valuable for synthesizing the best available information. Distributions on measurable atmospheric dispersion and deposition parameters were successfully elicited from experts involved in the many phenomenological areas of consequence analysis. This volume is the first of a three-volume document describing the project.

Harper, F.T.; Young, M.L.; Miller, L.A. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States); Lui, C.H. [Nuclear Regulatory Commission, Washington, DC (United States); Goossens, L.H.J.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Paesler-Sauer, J. [Research Center, Karlsruhe (Germany); Helton, J.C. [and others

1995-01-01T23:59:59.000Z

365

Matrix Heterogeneity Effects on Gas Transport and Adsorption in Coalbed and Shale Gas Reservoirs  

Science Journals Connector (OSTI)

In coalbeds and shales, gas transport and storage are important for accurate ... rates and for the consideration of subsurface greenhouse gas sequestration. They involve coupled fluid phenomena in ... transport, ...

Ebrahim Fathi; I. Ycel Akkutlu

2009-11-01T23:59:59.000Z

366

STUDENT EMPLOYMENT Student Involvement Outcomes  

E-Print Network [OSTI]

STUDENT EMPLOYMENT Student Involvement Outcomes reflective assessment High impact practices ASSOCIATED STUDENTS, CSUF, INC. Committed TO ON-CAMPUS ENGAGEMENT · SUPPORTING STUDENT SUCCESS · UNIFYING THE STUDENT VOICE · FOSTERING TITAN PRIDE #12;Organizational Structure Associated Students, CSUF, Inc. (ASI

de Lijser, Peter

367

Transport equations in tokamak plasmas  

SciTech Connect (OSTI)

Tokamak plasma transport equations are usually obtained by flux surface averaging the collisional Braginskii equations. However, tokamak plasmas are not in collisional regimes. Also, ad hoc terms are added for neoclassical effects on the parallel Ohm's law, fluctuation-induced transport, heating, current-drive and flow sources and sinks, small magnetic field nonaxisymmetries, magnetic field transients, etc. A set of self-consistent second order in gyroradius fluid-moment-based transport equations for nearly axisymmetric tokamak plasmas has been developed using a kinetic-based approach. The derivation uses neoclassical-based parallel viscous force closures, and includes all the effects noted above. Plasma processes on successive time scales and constraints they impose are considered sequentially: compressional Alfven waves (Grad-Shafranov equilibrium, ion radial force balance), sound waves (pressure constant along field lines, incompressible flows within a flux surface), and collisions (electrons, parallel Ohm's law; ions, damping of poloidal flow). Radial particle fluxes are driven by the many second order in gyroradius toroidal angular torques on a plasma species: seven ambipolar collision-based ones (classical, neoclassical, etc.) and eight nonambipolar ones (fluctuation-induced, polarization flows from toroidal rotation transients, etc.). The plasma toroidal rotation equation results from setting to zero the net radial current induced by the nonambipolar fluxes. The radial particle flux consists of the collision-based intrinsically ambipolar fluxes plus the nonambipolar fluxes evaluated at the ambipolarity-enforcing toroidal plasma rotation (radial electric field). The energy transport equations do not involve an ambipolar constraint and hence are more directly obtained. The 'mean field' effects of microturbulence on the parallel Ohm's law, poloidal ion flow, particle fluxes, and toroidal momentum and energy transport are all included self-consistently. The final comprehensive equations describe radial transport of plasma toroidal rotation, and poloidal and toroidal magnetic fluxes, as well as the usual particle and energy transport.

Callen, J. D.; Hegna, C. C.; Cole, A. J. [University of Wisconsin, Madison, Wisconsin 53706-1609 (United States)

2010-05-15T23:59:59.000Z

368

Strategic Freight Transportation Contract Procurement  

E-Print Network [OSTI]

Based Procurement for Transportation Services, Journal ofCoia, A. , Evolving transportation exchanges, World trade,an Auction Based Transportation Marketplace, Transportation

Nandiraju, Srinivas

2006-01-01T23:59:59.000Z

369

"Educating transportation professionals."  

E-Print Network [OSTI]

"Educating transportation professionals." Michael Demetsky Henry L. Kinnier Professor mjd of Virginia Charlottesville, VA 434.924.7464 Transportation Engineering & Management Research Our group works closely with the Virginia Center for Transportation Innovation and Research (VCTIR), located

Acton, Scott

370

Yucca Mountain transportation routes: Preliminary characterization and risk analysis; Volume 2, Figures [and] Volume 3, Technical Appendices  

SciTech Connect (OSTI)

This report presents appendices related to the preliminary assessment and risk analysis for high-level radioactive waste transportation routes to the proposed Yucca Mountain Project repository. Information includes data on population density, traffic volume, ecologically sensitive areas, and accident history.

Souleyrette, R.R. II; Sathisan, S.K.; di Bartolo, R. [Nevada Univ., Las Vegas, NV (United States). Transportation Research Center] [Nevada Univ., Las Vegas, NV (United States). Transportation Research Center

1991-05-31T23:59:59.000Z

371

Transportation Efficiency Resources  

Broader source: Energy.gov [DOE]

Transportation efficiency reduces travel demand as measured by vehicle miles traveled (VMT). While transportation efficiency policies are often implemented under local governments, national and...

372

Transportation and its Infrastructure  

E-Print Network [OSTI]

cost to mitigate transports GHG emissions. There are alsoenergy consumption and GHG mitigation, especially inParis, 2005. ECON, 2003: GHG Emissions from International

2007-01-01T23:59:59.000Z

373

Transportation and its Infrastructure  

E-Print Network [OSTI]

Transport and its infrastructure Chapter 5 Hybrid vehiclesincluding hybrid- Transport and its infrastructure Chapter 5infrastructure Gt CO 2 -eq 1 - Diesels (LDVs) 2 - Hybrids (

2007-01-01T23:59:59.000Z

374

Sustainability and Transport  

E-Print Network [OSTI]

2005. Integrating Sustainability into the Trans- portationTHOUGHT PIECE Sustainability and Transport by Richardof the concept of sustainability to transport planning. In

Gilbert, Richard

2006-01-01T23:59:59.000Z

375

Annotated bibliography of literature relating to wind transport of plutonium-contaminated soils at the Nevada Test Site  

SciTech Connect (OSTI)

During the period from 1954 through 1963, a number of tests were conducted on the Nevada Test Site (NTS) and Tonopah Test Range (TTR) to determine the safety of nuclear devices with respect to storage, handling, transport, and accidents. These tests were referred to as ``safety shots.`` ``Safety`` in this context meant ``safety against fission reaction.`` The safety tests were comprised of chemical high explosive detonations with components of nuclear devices. The conduct of these tests resulted in the dispersion of plutonium, and some americium over areas ranging from several tens to several hundreds of hectares. Of the various locations used for safety tests, the site referred to as ``Plutonium Valley`` was subject to a significant amount of plutonium contamination. Plutonium Valley is located in Area 11 on the eastern boundary of the NTS at an elevation of about 1036 m (3400 ft). Plutonium Valley was the location of four safety tests (A,B,C, and D) conducted during 1956. A major environmental, health, and safety concern is the potential for inhalation of Pu{sup 239,240} by humans as a result of airborne dust containing Pu particles. Thus, the wind transport of Pu{sup 239,240} particles has been the subject of considerable research. This annotated bibliography was created as a reference guide to assist in the better understanding of the environmental characteristics of Plutonium Valley, the safety tests performed there, the processes and variables involved with the wind transport of dust, and as an overview of proposed clean-up procedures.

Lancaster, N.; Bamford, R.

1993-12-01T23:59:59.000Z

376

Transport Co-benefits Calculator | Open Energy Information  

Open Energy Info (EERE)

Transport Co-benefits Calculator Transport Co-benefits Calculator Jump to: navigation, search LEDSGP green logo.png FIND MORE DIA TOOLS This tool is part of the Development Impacts Assessment (DIA) Toolkit from the LEDS Global Partnership. Tool Summary LAUNCH TOOL Name: Transport Co-benefits Calculator Agency/Company /Organization: Institute for Global Environmental Strategies Sector: Climate, Energy Complexity/Ease of Use: Moderate Website: www.iges.or.jp/en/archive/cp/activity20101108.html Cost: Free Related Tools Alternative Fuel and Advanced Technology Vehicles Pilot Program Emissions Benefit Tool SimCLIM SEAGA Intermediate Level Handbook ... further results Characterizes co-benefits in terms of accidents, emissions, travel time, and vehicle operating costs. Approach A co-benefits approach capitalizes on synergies between current local

377

Rate Adjustments and Public Involvement  

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

Rate Adjustments and Public Involvement Documents Rate Adjustments and Public Involvement Documents CRSP Transmission 9/16/2013 WAPA-161 FRN, CRSP transmission and ancillary services rates extension Letter announcing two-year extension to CRSP transmission and ancillary services rates Letter announcing revised CRSP transmission rates for FY 2014 Accompanying calculation table for FY 2014 CRSP transmission rate letter Letter announcing revised CRSP transmission rates for FY 2013 Letter announcing revised CRSP transmission rates for FY 2012 Letter announcing revised CRSP transmission rates for FY 2011 Letter announcing revised CRSP transmission rates for FY 2010 SLCA/IP 9/16/2013 WAPA-161 FRN, SLCA/IP firm power rate extension Letter announcing two-year extension to SLCA/IP firm power rate SLCA/IP Tentative Rate Adjustment Schedule

378

DOE Order Self Study Modules - DOE O 225.1B, Accident Investigation  

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

225.1B 225.1B ACCIDENT INVESTIGATIONS DOE O 225.1B Accident Investigations Familiar Level June 2011 1 June 2011 DOE ORDER O 225.1B ACCIDENT INVESTIGATIONS FAMILIAR LEVEL OBJECTIVES Given the familiar level of this module and the resources listed below, you will be able to: 1. State the purpose of implementing U.S. Department of Energy (DOE) O 225.1B. 2. Discuss the responsibilities of the heads of field elements for accident investigations. 3. Discuss the responsibilities of the appointing official in an accident investigation. 4. Discuss the responsibilities of the Accident Investigation Board Chairperson. 5. Discuss the criteria identified in appendix A of DOE O 225.1B. Note: If you think that you can complete the practice at the end of this level without

379

LEDSGP/Transportation Toolkit/Strategies | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit/Strategies < LEDSGP‎ | Transportation Toolkit(Redirected from Transportation Toolkit/Strategies) Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Avoid, Shift, Improve Framework The avoid, shift, improve (ASI) framework enables development stakeholders to holistically design low emissions transport strategies by assessing opportunities to avoid the need for travel, shift to less carbon-intensive modes, and improve on conventional technologies, infrastructure, and policies. Avoid Trips and Reduce Travel Demand

380

LEDSGP/Transportation Toolkit/Strategies/Improve | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit/Strategies/Improve < LEDSGP‎ | Transportation Toolkit‎ | Strategies(Redirected from Transportation Toolkit/Strategies/Improve) Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Avoid, Shift, Improve Framework The avoid, shift, improve (ASI) framework enables development stakeholders to holistically design low-emission transport strategies by assessing opportunities to avoid the need for travel, shift to less carbon-intensive modes, and improve on conventional technologies, infrastructure, and

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

Descriptions of selected accidents that have occurred at nuclear reactor facilities  

SciTech Connect (OSTI)

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

Bertini, H.W.

1980-04-01T23:59:59.000Z

382

Transportation Assessment Toolkit/Home | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » Transportation Assessment Toolkit/Home < Transportation Assessment Toolkit Jump to: navigation, search Home Transport Topics Ask an Expert Training Contact us What are the key actions necessary to implementing a transportation system LEDS? Action 1: Evaluate the existing transport system Action 2: Develop BAU scenario Action 3: Assess opportunities Avoid-Shift-Improve framework of strategies Action 4: Develop alternative scenarios Action 5: Prioritize and plan Action 6: Implement and monitor Transportation Assessment Toolkit Train licensed.png Transportation Assessment Toolkit Information licensed.png Transportation Assessment Toolkit Learning licensed.png

383

Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement  

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

Facts and Lessons of the Fukushima Nuclear Accident and Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints September 19, 2012 Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company Topics Covered: How Tsunami Struck Fukushima Sites Tsunami Height Estimation How we responded in the Recovery Process Safety Improvement and Further Enhancement of Nuclear Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints More Documents & Publications January2005 NNSANews Meeting Materials: June 15, 2011

384

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

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

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

385

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

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

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

386

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

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

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

387

E-Print Network 3.0 - accident analysis program Sample Search...  

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

Energy Storage, Conversion and Utilization ; Engineering 2 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: a sensitivity analysis was conducted to...

388

E-Print Network 3.0 - accident analysis calculations Sample Search...  

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

Energy Storage, Conversion and Utilization ; Engineering 2 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: . The objectives of this analysis were:...

389

E-Print Network 3.0 - assigned accident investigation Sample...  

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

at Berkeley Collection: Biology and Medicine ; Engineering 5 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: undertook a study to investigate and...

390

E-Print Network 3.0 - accident analysis structural Sample Search...  

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

Energy Storage, Conversion and Utilization ; Engineering 3 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: a sensitivity analysis was conducted to...

391

E-Print Network 3.0 - accident analysis Sample Search Results  

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

Texas Tech University Collection: Biology and Medicine 5 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: a sensitivity analysis was conducted to...

392

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

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

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

393

E-Print Network 3.0 - accident characteristics Sample Search...  

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

Engineering, University of Warwick Collection: Engineering 2 THE RELATIONSHIP BETWEEN TRAIN LENGTH AND ACCIDENT CAUSES AND RATES Summary: to incorporate three characteristics:...

394

E-Print Network 3.0 - accidents epidemiology trends Sample Search...  

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

works, when... September 15, 1830, when William Huskisson became the first victim of a train accident. ... Source: Ecole Polytechnique, Centre de mathmatiques Collection:...

395

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

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

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

396

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

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

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

397

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

Broader source: Energy.gov [DOE]

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

398

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

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

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

399

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

400

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

SciTech Connect (OSTI)

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

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

1994-02-01T23:59:59.000Z

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

E-Print Network 3.0 - accident loca testing Sample Search Results  

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

testing Search Powered by Explorit Topic List Advanced Search Sample search results for: accident loca testing Page: << < 1 2 3 4 5 > >> 1 Journal of Mobile Networks and...

402

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

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

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

403

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

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

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

404

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

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

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

405

Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS  

Broader source: Energy.gov [DOE]

DOE O 225.1B prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and...

406

E-Print Network 3.0 - accident prevention Sample Search Results  

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

OF CALIFORNIA -GENERAL SERVICES -RISK AND INSURANCE MANAGEMENT STATE DRIVER ACCIDENT REVIEW Summary: STD. 274 (REV. 12003) PLEASE PRINT OR TYPE SUPERVISOR'S REVIEW - FOR...

407

E-Print Network 3.0 - accident phenomenology cours Sample Search...  

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

phenomenology cours Search Powered by Explorit Topic List Advanced Search Sample search results for: accident phenomenology cours Page: << < 1 2 3 4 5 > >> 1 Avec Isabelle LUBAS...

408

E-Print Network 3.0 - accident response calculations Sample Search...  

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

effect of such variables needs to be calculated... in many countries. The majority of bicycle-motor vehicle (BMV) accidents occur at intersections. In order... to reduce the...

409

E-Print Network 3.0 - accident consequences health Sample Search...  

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

and Information Sciences 12 Risk factors for injury accidents among moped and motorcycle riders Summary: safety and public health programmes may reduce the number of PTW...

410

E-Print Network 3.0 - accident research programme Sample Search...  

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

Collection: Mathematics 4 Risk factors for injury accidents among moped and motorcycle riders Summary: safety and public health programmes may reduce the number of PTW...

411

E-Print Network 3.0 - accident area 1979-1992 Sample Search Results  

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

Delft Collection: Engineering 27 Risk factors for injury accidents among moped and motorcycle riders Summary: it occurred inside or outside a built-up area. One in four...

412

E-Print Network 3.0 - accident reporting system Sample Search...  

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

Guelph Collection: Engineering 29 Risk factors for injury accidents among moped and motorcycle riders Summary: on the exploitation of national data from the French police from...

413

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

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

and Information Sciences 65 Risk factors for injury accidents among moped and motorcycle riders Summary: : literature review and implementation workshop. Monash University...

414

E-Print Network 3.0 - accident investigation Sample Search Results  

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

Biology and Medicine 38 Risk factors for injury accidents among moped and motorcycle riders Summary: design which is the most used in order to investigate the above...

415

Assessment of ICARE/CATHARE V1 Severe Accident Code  

SciTech Connect (OSTI)

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

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

2006-07-01T23:59:59.000Z

416

Markov Model of Accident Progression at Fukushima Daiichi  

SciTech Connect (OSTI)

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

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

2012-11-11T23:59:59.000Z

417

Graduate Certificate in Transportation  

E-Print Network [OSTI]

Graduate Certificate in Transportation Nohad A. Toulan School of Urban Studies and Planning of Engineering and Computer Science integrated transportation systems. The Graduate Certificate in Transportation their capabilities. Students in the program can choose among a wide range of relevant courses in transportation

Bertini, Robert L.

418

TRANSPORTATION Annual Report  

E-Print Network [OSTI]

2003 CENTER FOR TRANSPORTATION STUDIES Annual Report #12;Center for Transportation Studies University of Minnesota 200 Transportation and Safety Building 511 Washington Avenue S.E. Minneapolis, MN publication is a report of transportation research, education, and outreach activities for the period July

Minnesota, University of

419

Career Map: Transportation Worker  

Broader source: Energy.gov [DOE]

The Wind Program's Career Map provides job description information for Transportation Worker positions.

420

Transportation Organization and Functions  

Broader source: Energy.gov [DOE]

Office of Packaging and Transportation list of organizations and functions, with a list of acronyms.

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

IDAHO NATIONAL LABORATORY TRANSPORTATION TASK REPORT ON ACHIEVING MODERATOR EXCLUSION AND SUPPORTING STANDARDIZED TRANSPORTATION  

SciTech Connect (OSTI)

Following the defunding of the Yucca Mountain Project, it is reasonable to assume that commercial used fuel will remain in storage for the foreseeable future. This report proposes supplementing the ongoing research and development work related to potential degradation of used fuel, baskets, poisons, and storage canisters during an extended period of storage with a parallel path. This parallel path can assure criticality safety during transportation by implementing a concept that achieves moderator exclusion (no in-leakage of moderator into the used fuel cavity). Using updated risk assessment insights for additional technical justification and relying upon a component inside of the transportation cask that provides a watertight function, a strong argument can be made that moderator intrusion is not credible and should not be a required assumption for criticality evaluations during normal conditions of transportation. A demonstrating testing program supporting a detailed analytical effort as well as updated risk assessment insights can provide the basis for moderator exclusion during hypothetical accident conditions. This report also discusses how this engineered concept can support the goal of standardized transportation.

D.K. Morton

2011-09-01T23:59:59.000Z

422

Multi-modal Transportation > Highway Transportation > Trucking > Railroad transportation > Public transit > Rural transportation > Rural transit > Freig pipeline transportation > Airport planning and development > Airport maintenance > Bicycle and pedestr  

E-Print Network [OSTI]

Multi-modal Transportation > Highway Transportation > Trucking > Railroad transportation > Public transit > Rural transportation > Rural transit > Freig pipeline transportation > Airport planning and development > Airport maintenance > Bicycle and pedestrian > Ports and waterways >>> Transportation ope

423

Detection, diagnosis, and treatment of accident conditions using response trees  

SciTech Connect (OSTI)

Response Trees were developed at the LOFT facility in 1978 and included in the Plant Operating Manual (POM) to assist reactor operators in selecting emergency procedures. In an emergency situation the operator would manually gather data and evaluate the trees to select the appropriate procedures. As a portion of the LOFT Augmented Operator Capability (AOC) Program, the response tree methodology has been extended so that a computer can be used to evaluate the trees and recommend an appropriate response for an accident. Techniques for diagnosing failures within a cooling mode have also been investigated. This paper summarizes these additions to the response tree methodology.

Nelson, W.R.

1980-01-01T23:59:59.000Z

424

Analysis of Three Mile Island-Unit 2 accident  

SciTech Connect (OSTI)

The Nuclear Safety Analysis Center (NSAC) of the Electric Power Research Institute has analyzed the Three Mile Island-2 accident. Early results of this analysis were a brief narrative summary, issued in mid-May 1979 and an initial version of this report issued later in 1979 as noted in the Foreword. The present report is a revised version of the 1979 report, containing summaries, a highly detailed sequence of events, a comparison of that sequence of events with those from other sources, 25 appendices, references and a list of abbreviations and acronyms. A matrix of equipment and system actions is included as a folded insert.

Not Available

1980-03-01T23:59:59.000Z

425

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

Broader source: Energy.gov [DOE]

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

426

Graduate Studies Transportation Systems Engineering  

E-Print Network [OSTI]

Graduate Studies Transportation Systems Engineering TRANSPORTATION SYSTEMS The transportation that transportation systems engineering can promote a thriving economy and a better quality of life by ensuring that transportation systems themselves affect the environment through operations, construction, and maintenance

Jacobs, Laurence J.

427

Introduction Transport in disordered graphene  

E-Print Network [OSTI]

Introduction Transport in disordered graphene Summary Ballistic transport in disordered graphene P, Gornyi, Mirlin Ballistic transport in disordered graphene #12;Introduction Transport in disordered graphene Summary Outline 1 Introduction Model Experimental motivation Transport in clean graphene 2

Fominov, Yakov

428

Involvement, attributions, and consumer responses to rebates  

Science Journals Connector (OSTI)

This paper examines effects of both purchasing involvement and product involvement on consumers' responses to rebates. In Part One, the study examines ... effects of involvement on consumer responses to a rebate ...

Kenneth A. Hunt; Susan M. Keaveney; Moonkyu Lee

1995-01-01T23:59:59.000Z

429

Jonesboro Metropolitan Planning Organization 2030 Long Range Transportation Plan  

E-Print Network [OSTI]

, and on the MPO website with instructions for making public comments. A final public involvement meeting was held September 27, 2005 as the special Policy Committee meeting in the Transportation Conference Room, City of Jonesboro, 519 West Washington Avenue... Transportation Plan 2-3 Chapter 2 Existing Conditions B. Employment Economic growth and an increase in employment have implications for the region's transportation system. The increase in industrial development makes access to these sites a key issue...

Jonesboro Metropolitan Planning Organization

430

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

Analysis Analysis Doug Ammerman, (505) 845-8158 Structural analysis utilizes computer design and analysis tools to provide package designers and certifiers with the most accurate method of determining package response to transportation environments. Computer analysis is an application of known engineering principles that take advantage of high-power computing capabilities in solving the response of computer models to various environments with complex mathematical calculations. It can be used for package certification by generating a computer model of a test object (package) and subjecting it to an accident environment to understand its response. A computer model must be constructed with the same weights, dimensions, hardnesses, specific heat, conduction, etc. as an

431

Accident Fault Trees for Defense Waste Processing Facility  

SciTech Connect (OSTI)

The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses to calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).

Sarrack, A.G.

1999-06-22T23:59:59.000Z

432

Novel Accident-Tolerant Fuel Meat and Cladding  

SciTech Connect (OSTI)

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

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

2013-09-01T23:59:59.000Z

433

NREL: Transportation Research - Sustainable Transportation Basics  

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

Department of Energy's Alternative Fuels Data Center (AFDC) provide an introduction to sustainable transportation. NREL research supports development of electric, hybrid,...

434

Transportation Baseline Schedule  

SciTech Connect (OSTI)

The 1999 National Transportation Program - Transportation Baseline Report presents data that form a baseline to enable analysis and planning for future Department of Energy (DOE) Environmental Management (EM) waste/material transportation. The companion 1999 Transportation Barriers Analysis analyzes the data and identifies existing and potential problems that may prevent or delay transportation activities based on the data presented. The 1999 Transportation Baseline Schedule (this report) uses the same data to provide an overview of the transportation activities of DOE EM waste/materials. This report can be used to identify areas where stakeholder interface is needed, and to communicate to stakeholders the quantity/schedule of shipments going through their area. Potential bottlenecks in the transportation system can be identified; the number of packages needed, and the capacity needed at receiving facilities can be planned. This report offers a visualization of baseline DOE EM transportation activities for the 11 major sites and the Geologic Repository Disposal site (GRD).

Fawcett, Ricky Lee; John, Mark Earl

2000-01-01T23:59:59.000Z

435

Type B Accident Investigation Board Report on the August 5, 1998, Load Haul Dump Accident at U16b Tunnel, Nevada Test Site  

Broader source: Energy.gov [DOE]

Thisis theType B Accident Investigation Board report of an industrial accident at the Nevada Test site (NTS), U16b tunnel in which a Bechtel Nevada (BN) employee suffered a compressed skull fracture as a result of being struck onthe head by a valve and fitting assembly on the end of a hose whichhad been broken from a water pipe by a moving piece of construction equipment.

436

Isotope Program Transportation | Department of Energy  

Office of Environmental Management (EM)

Isotope Program Transportation Isotope Program Transportation Isotope Program Transportation More Documents & Publications Nuclear Fuel Storage and Transportation Planning Project...

437

Nuclear Transportation Management Services | Department of Energy  

Office of Environmental Management (EM)

Nuclear Transportation Management Services Nuclear Transportation Management Services Nuclear Transportation Management Services More Documents & Publications Transportation and...

438

Transportation Issues and Resolutions Compilation of Laboratory...  

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

Transportation Issues and Resolutions Compilation of Laboratory Transportation Work Package Reports Transportation Issues and Resolutions Compilation of Laboratory Transportation...

439

Recommendations for Analyzing Accidents under the National Environmental Policy Act (July 2002)  

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

National National Environmental Policy Act RECOMMENDATIONS for ANALYZING ACCIDENTS under the NATIONAL ENVIRONMENTAL POLICY ACT N E P A July 2002 U.S. Department of Energy Environment, Safety and Health Office of NEPA Policy and Compliance Recommendations for Analyzing Accidents under NEPA Contents 1.0 Introduction ............................................................................................................................... 1 1.1 Definition............................................................................................................................ 1 1.2 Purpose.............................................................................................................................. 1 1.3 Sliding Scale ......................................................................................................................

440

POUR UNE CULTURE DES ACCIDENTS AU SERVICE DE LA SECURITE INDUSTRIELLE  

E-Print Network [OSTI]

-organisational character), locate it in the state of art with regards to accidentology, safety and risk cultures. FinallyPOUR UNE CULTURE DES ACCIDENTS AU SERVICE DE LA SECURITE INDUSTRIELLE FOR A CULTURE OF ACCIDENTS DEVOTED TO INDUSTRIAL SAFETY Nicolas DECHY Yves DIEN Michel LLORY INERIS EDF R&D IAO, Mas Saint

Paris-Sud XI, Université de

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

Major accidents scenarios used for LUP and off-site emergency planning : Importance of kinetic description  

E-Print Network [OSTI]

Major accidents scenarios used for LUP and off-site emergency planning : Importance of kinetic, INERIS shows a method enabling to integrate, as a second prioritisation criteria, the on-site and off-site. Keywords : Land Use Planning ; off-site emergency planning ; chemical accident scenario ; kinetic 1

Paris-Sud XI, Université de

442

Fuel-related accidents occur across the country at the rate of more than one per  

E-Print Network [OSTI]

Fuel-related accidents occur across the country at the rate of more than one per week. Fuel exhaustion, fuel starvation, or the failure to switch tanks at the correct time caused 120 accidents in 2002, these and other problems can be avoided with proper fueling procedures. RESPONSIBILITY STARTS WITH THE AIRPORT

Minnesota, University of

443

ROYAL HOLLOWAY, UNIVERSITY OF LONDON ACCIDENT/INCIDENT INVESTIGATION AND REPORTING  

E-Print Network [OSTI]

on employers to thoroughly investigate such occurrences and having done so, to take appropriate remedial actionROYAL HOLLOWAY, UNIVERSITY OF LONDON ACCIDENT/INCIDENT INVESTIGATION AND REPORTING PROCEDURE in the investigations or take the lead role on behalf of the College. #12;SECTION 1 Accident/Incident Investigation

Sheldon, Nathan D.

444

An Experimental Study into the Impact of Local Accident Information on Driver's Route Planning Behaviour  

E-Print Network [OSTI]

of previous accidents just as existing GPS tools provide data about average delays and fuel consumption behaviour. Experimental studies have shown the effects of attribution error, it is easy to believe into the effects that local accident information has on drivers' route planning tasks. Our results show

Johnson, Chris

445

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 failures and operator actions (or missing actions) related to the loss. But stopping after identifying

Leveson, Nancy

446

Proposed beryllium metal bounding airborne release fractions (ARFs)/rates (ARRs) and respirable fractions (RFs) for DOE facility accidents analyses  

Science Journals Connector (OSTI)

Beryllium metal has special properties for nuclear applications and is used widely within the Department of Energy (DOE) complex. Beryllium is toxic and has the potential to cause health effects (sensitization and chronic beryllium disease) to workers. Due to the type of processing involving large quantities of beryllium metal and powders and potential for significant airborne release under accident conditions, a comprehensive hazard analysis is required by DOE in a safety analysis document that evaluates potential accidents that can cause beryllium releases to the workplace and public or to the environment. The goal of the safety analysis is to identify and evaluate hazards so that appropriate controls or safeguards can be specified to protect the workers and public from potential accidents. A hazard assessment is also required to comply with 10 CFR Part 850, Chronic Beryllium Disease Prevention Program (1999) to protect the workers. DOE safety analyses include a quantitative estimate of releases and downwind concentrations for purposes of hazard classification and determination of the need for additional hazards analysis, accident analysis, and risk assessments. There are no complex-wide accepted Airborne Release Fractions (ARFs) and Respirable Fractions (RFs) that can be used to evaluate the potential downwind consequences of releases of beryllium under various accident conditions (e.g., spill, fire, stress, explosion, etc.). The purpose is to recommend DOE complex-wide \\{ARFs\\} and \\{RFs\\} that can be used to evaluate the potential downwind consequences of accidents. This paper proposes various values for \\{ARFs\\} and \\{RFs\\} that are based on review of the published information and data on the oxidation and ignition behavior of beryllium metal encased in a thin coat of non-porous, adherent oxide (blue oxide); the typical form of this material found in DOE facilities. Information is also presented as a function of the morphology of the metal (i.e., large, coherent, pieces; turnings/swarfs; chips/powder; and dust) because the surface to volume ratio is an important factor in evaluating both the amount of beryllium released and the potential for ignition of the metal that may increase the amount of release significantly. Guidance is also provided for the use of the DOE-HDBK-3010-94, Airborne Release Fractions/Rates and Respirable Fraction for Nonreactor Nuclear Facilities, values for oxide releases that result in a more liberal, allowable limiting airborne concentration for determining consequences and hazard classification of the facility. Detailed explanations of the proposed ARF/RF values for the various beryllium metal forms (large coherent pieces, chips/powder, turning/swarfs from processing, and dust) and other aspects of beryllium are provided in a report by Mishima et al. (April 2005). A short version of this report and a summary of the ARF/RF values are presented here.

Jofu Mishima; Terry L. Foppe; J.C. Laul

2008-01-01T23:59:59.000Z

447

Transportation | ornl.gov  

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

Transportation Transportation Power Electronics and Electric Machinery Fuels, Engines, Emissions Transportation Analysis Vehicle Systems Energy Storage Propulsion Materials Lightweight Materials Bioenergy Fuel Cell Technologies Clean Energy Home | Science & Discovery | Clean Energy | Research Areas | Transportation SHARE Transportation Research ORNL researcher Jim Szybist uses a variable valve-train engine to evaluate different types of fuels, including ethanol blends, and their effects on the combustion process in an internal combustion engine. Oak Ridge National Laboratory brings together science and technology experts from across scientific disciplines to partner with government and industry in addressing transportation challenges. Research objectives are

448

FINAL Transportation External Coordination Working Group (TEC)  

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

Transportation External Coordination Working Group (TEC) January 28-30, 2002 New Orleans, Louisiana Meeting Summary The Transportation External Coordination Working Group (TEC) held its 20 th semi-annual meeting January 28-30, 2002, in New Orleans, Louisiana. This was the tenth anniversary of TEC, and 102 attendees from national, State, Tribal, and local government organizations; industry and professional groups and other interested parties in the U.S. Department of Energy (DOE) programs, met to address a variety of issues related to DOE's radioactive materials transportation activities. The TEC process includes the involvement of these key stakeholders in developing solutions to DOE transportation issues through their actual participation in the work product. These members provide continuing and improved

449

Lateral variation of 134Cs and 137Cs concentrations in surface seawater in and around the Japan Sea after the Fukushima Dai-ichi Nuclear Power Plant accident  

Science Journals Connector (OSTI)

A total of 82 surface seawater samples was collected in the Japan Sea and the southwestern Okhotsk Sea before and after the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident. Analysis of 134Cs and 137Cs concentrations using low-background ?-spectrometry revealed that the 137Cs concentration of the samples collected in June 2011 was 1.52.8mBq/L, which is approximately 12 times higher than the pre-accident 137Cs level, while the 134Cs concentration was less than detectable to 1mBq/L. In addition to 134Cs being clearly detected (?1mBq/L), 137Cs concentration in water samples from the northeastern Japan Sea (22.8mBq/L) was also higher than that from the coast in the southwestern Japan Sea (?1.5mBq/L). These higher concentrations in the northeastern Japan Sea could be ascribed to the atmospheric transport of nuclides from the FDNPP as aerosols and subsequent transport and dilution after delivery to the sea surface.

M. Inoue; H. Kofuji; S. Nagao; M. Yamamoto; Y. Hamajima; K. Yoshida; K. Fujimoto; T. Takada; Y. Isoda

2012-01-01T23:59:59.000Z

450

Chemical accident databases: what they tell us and how they can be improved to establish national safety goals  

E-Print Network [OSTI]

The objectives of this research are to examine and critique eight chemical accident databases, document any trends in accident occurrences, develop a strategy for improving current databases, and to establish national safety goals on the basis...

McCray, Eboni Trevette

2012-06-07T23:59:59.000Z

451

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

Broader source: Energy.gov [DOE]

On June 28, 2013, an Accident Investigation Board was appointed to investigate an accident at the Department of Energy Germantown Headquarters facility, on June 1, 2013 that resulted in a fatality on June 24, 2013.

452

Midwestern Radioactive Materials Transportation Committee Agenda...  

Office of Environmental Management (EM)

Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation...

453

LEDSGP/Transportation Toolkit/Tools | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit/Tools < LEDSGP‎ | Transportation Toolkit(Redirected from Transportation Toolkit/Tools) Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Tools for Low Emission Development Strategies in Transportation Use one of the search methods below to find tools for building sustainable, low emission development strategies (LEDS) for your country's transportation system. These resources focus on strategies to limit air pollutants and greenhouse gas emissions. Learn more in the report on LEDS for transportation. If you are aware of a relevant technical resource not

454

LEDSGP/Transportation Toolkit/Training | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit/Training < LEDSGP‎ | Transportation Toolkit(Redirected from Transportation Toolkit/Training) Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Training for Low Emission Development Strategies in Transportation The LEDS GP Transport Working Group provides technical training and resources in the form of webinars, e-learning, live/recorded presentation videos, presentation files, and other knowledge exchange formats relevant to low emission development strategies in the transport sector. Below are

455

Radiological accident and incident in Thailand: lesson to be learned  

Science Journals Connector (OSTI)

......was transported to a safe storage at the OAEP (Figure-3...the 137Cs source to a safety storage at the Radioactive Waste Management Center, Thailand...including instructions relating to long-term storage or disposition, had been......

Nanthavan Ya-anant; Kanokrat Tiyapun; Kittiphong Saiyut

2011-07-01T23:59:59.000Z

456

Type A Accident Investigation Board Report on the April 3, 1995, Security Rappel Tower Fatality at the DOE Savannah River Site  

Broader source: Energy.gov [DOE]

The objectives of this investigation are twofold: to determine the cause and surrounding circumstances of this accident and to prevent the occurrence of similar accidents.

457

Study of Air Ingress Across the Duct During the Accident Conditions  

SciTech Connect (OSTI)

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

Hassan, Yassin

2013-05-06T23:59:59.000Z

458

Transportation Infrastructure and Sustainable Development  

E-Print Network [OSTI]

A Better Forecasting Tool for Transportation Decision-making, Mineta Transportation Institute, San Jose Stateat the 2008 meeting of the Transportation Research Board and

Boarnet, Marlon G.

2008-01-01T23:59:59.000Z

459

Transportation Analysis | Clean Energy | ORNL  

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

Transportation Analysis SHARE Transportation Analysis Transportation Analysis efforts at Oak Ridge National Laboratory contribute to the efficient, safe, and free movement of...

460

The universal radiative transport equation  

E-Print Network [OSTI]

THE UNIVERSAL RADIATIVE TRANSPORT EQUATION Rudolph W.The Universal Radiative Transport Equation Rudolph W.The various radiative transport equations used in general

Preisendorfer, Rudolph W

1959-01-01T23:59:59.000Z

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.


461

OVERVIEW OF PROPOSED TRANSPORTATION ENERGY  

E-Print Network [OSTI]

.......................................................................................................................4 PROPOSED CALIFORNIA TRANSPORTATION FUEL PRICE FORECASTS......... 6 Summary....................................................................................................6 Petroleum Transportation Fuel Price Forecast Assumptions .............................................................6 California Transportation Fuel Price Forecasts

462

transportation | OpenEI  

Open Energy Info (EERE)

transportation transportation Dataset Summary Description The 2009 National Household Travel Survey (NHTS) provides information to assist transportation planners and policy makers who need comprehensive data on travel and transportation patterns in the United States. The 2009 NHTS updates information gathered in the 2001 NHTS and in prior Nationwide Personal Transportation Surveys (NPTS) conducted in 1969, 1977, 1983, 1990, and 1995. Source U.S. Department of Transportation, Federal Highway Administration Date Released February 28th, 2011 (3 years ago) Date Updated Unknown Keywords NHTS TEF transportation Transportation Energy Futures travel trip Data application/zip icon Travel Day Trip File (zip, 42.6 MiB) application/zip icon Household File (zip, 5 MiB) application/zip icon Person File (zip, 17.4 MiB)

463

Transportation Management Workshop: Proceedings  

SciTech Connect (OSTI)

This report is a compilation of discussions presented at the Transportation Management Workshop held in Gaithersburg, Maryland. Topics include waste packaging, personnel training, robotics, transportation routing, certification, containers, and waste classification.

Not Available

1993-10-01T23:59:59.000Z

464

Packaging and Transportation Safety  

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

Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1.

1996-10-02T23:59:59.000Z

465

Packaging and Transportation Safety  

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

Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Canceled by DOE 460.1A

1995-09-27T23:59:59.000Z

466

Modelling transport fuel demand  

Science Journals Connector (OSTI)

Transport fuels account for an increasing share of oil ... interest to study the economics of the transport fuel market and thereby to evaluate the efficiency of the price mechanism as an instrument of policy in ...

Thomas Sterner; Carol A. Dahl

1992-01-01T23:59:59.000Z

467

Transportation Demand This  

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

Transportation Demand Transportation Demand This page inTenTionally lefT blank 75 U.S. Energy Information Administration | Assumptions to the Annual Energy Outlook 2013 Transportation Demand Module The NEMS Transportation Demand Module estimates transportation energy consumption across the nine Census Divisions (see Figure 5) and over ten fuel types. Each fuel type is modeled according to fuel-specific and associated technology attributes applicable by transportation mode. Total transportation energy consumption is the sum of energy use in eight transport modes: light-duty vehicles (cars and light trucks), commercial light trucks (8,501-10,000 lbs gross vehicle weight), freight trucks (>10,000 lbs gross vehicle weight), buses, freight and passenger aircraft, freight

468

Transportation and its Infrastructure  

E-Print Network [OSTI]

alternative means. In general, collective modes of transport use less energy and generate less GHGs than private cars.

2007-01-01T23:59:59.000Z

469

NREL: Transportation Research - Publications  

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

and fact sheets. Visit the following online resources to find publications about sustainable transportation research, development, and deployment. NREL Publications...

470

Hidden costs of the accident at Three Mile Island  

SciTech Connect (OSTI)

It has been possible to identify a significant drop in the performance of Pressurised Water Reactors (PWRs) in the western world following the accident at Three Mile Island (TMI). Although there are indications that the magnitude of the load factor reduction was slightly larger in the U.S., there is nevertheless strong evidence to suggest that the response was felt in all countries with operating PWRs. The effect did not, however, extend to other reactor systems; even the generically similar Boiling Water Reactor (BWR) suffered no drop in output. It is estimated that the costs, worldwide, of this fall in performance are of the same order as the TMI clean-up operation.

Evans, N.

1982-09-01T23:59:59.000Z

471

The role of chemical reactions in the Chernobyl accident  

SciTech Connect (OSTI)

It is shown that chemical reactions played an essential role in the Chernobyl accident at all of its stages. It is important that the reactor before the explosion was at maximal xenon poisoning, and its reactivity, apparently, was not destroyed by the explosion. The reactivity release due to decay of Xe-235 on the second day after the explosion led to a reactor power of 80-110 MW. Owing to this power, the chemical reactions of reduction of uranium, plutonium, and other metals at a temperature of about 2000 Degree-Sign C occurred in the core. The yield of fission products thus sharply increased. Uranium and other metals flew down in the bottom water communications and rooms. After reduction of the uranium and its separation from the graphite, the chain reaction stopped, the temperature of the core decreased, and the activity yield stopped.

Grishanin, E. I., E-mail: egrishanin@orexovo.net [Russian Research Center Kurchatov Institute (Russian Federation)

2010-12-15T23:59:59.000Z

472

Down syndrome clusters in Germany after the Chernobyl accident  

SciTech Connect (OSTI)

In two independent studies using different approaches and covering West Berlin and Bavaria, respectively, highly significant temporal clusters of Down syndrome were found. Both sharp increases occurred in areas receiving relatively low Chernobyl fallout and concomitant radiation exposures. Only for the Berlin cluster was fallout present at the time of the affected meiosis, whereas the Nuremberg cluster preceded the radioactive contamination by 1 month. Hypotheses on possible causal relationships are compared. Radiation from the Chernobyl accident is an unlikely factor, because the associated cumulative dose was so low in comparison with natural background. Microdosimetric considerations would indicate that fewer than 1 in 200 oocyte nuclei would have experienced an ionizing event from Chernobyl radioactivity. Given the lack of understanding of what causes Down syndrome, other than factors associated with increased maternal age, additional research into environmental and infectious risk factors is warranted. 23 refs., 4 figs., 2 tabs.

Burkart, W.; Grosche, B.; Schoetzau, A. [Institute for Radiation Hygiene, Oberschleissheim (Germany)

1997-03-01T23:59:59.000Z

473

Revised accident progression and risk analyses for NUREG-1150  

SciTech Connect (OSTI)

Preliminary III PRA analyses that support preparation of the Nuclear Regulatory Commission's Reactor Risk Reference Document (NUREG-1150) have been conducted at Sandia National Laboratories for four plants: Surry, Sequoyah, Peach Bottom and Grand Gulf. Brookhaven National Laboratories conducted the analysis for the Zion plant. Review of the preliminary analyses produced comments and criticisms from two committees (Kouts Committee and Kastenberg Committee), from industry, and from a variety of other sources. As a result, the final analyses currently under way at Sandia and Brookhaven will contain several improvements over the preliminary analyses. Of these the most significant improvement is in the methodology used to elicit expert opinion concerning highly uncertain questions about severe accident phenomena. 17 refs., 1 fig., 1 tab.

Gorham-Bergeron, E.D.; Haskin, F.E.; Hora, S.C.

1987-01-01T23:59:59.000Z

474

Improvements to the original NUREG-1150 accident sequence analyses  

SciTech Connect (OSTI)

Since the accident sequence analyses to support the draft NUREG-1150 were published (NUREG/CR-4550), comments have been received from the utilities, the Nuclear Regulatory Commission, the nuclear industry, and the public. It is the intent to incorporate comments to the extent possible, along with anticipated changes produced by the analysis teams. The purpose of this paper is to identify the important comments and issues that will be addressed for each plant during the reanalysis. There are a few general changes in the methodology that apply to all of the plants. The most important change is an improved uncertainty analysis, including a more comprehensive treatment of uncertainty issues and a more defensible approach to eliciting expert opinion on these issues. Another important change is the addition of external events to the analysis of the Surry and Peach Bottom plants. These and other changes are discussed in this paper. 8 refs.

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

1987-01-01T23:59:59.000Z

475

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

SciTech Connect (OSTI)

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

Chen, S.Y. [Environmental Science Division, Argonne National Laboratory, Argonne, IL (United States)

2012-07-01T23:59:59.000Z

476

Feature - Argonne involved with proposed Green Fuels Depot in Naperville  

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

involved in Naperville's proposed Green Fuels Depot involved in Naperville's proposed Green Fuels Depot Naperville's proposed Green Fuels Depot The proposed Green Fuels Depot would produce renewable fuels for Naperville's vehicle fleet. Using grass clippings to power next-generation vehicles - now that's green transportation. This is one of the ideas being considered at Naperville's newly proposed Green Fuels Depot. The project, which will require $4 million in funding to get started, would bring together Argonne National Laboratory, the city of Naperville, Packer Engineering and the College of DuPage for an innovative plan to produce renewable energy. "It's a golden opportunity for Argonne to be associated with one of our neighboring communities in promoting new technologies that we have pioneered here at the laboratory," said Glenn Keller, manager of vehicle

477

Microsoft Word - g151.1-1aFinal7-11-07.doc  

Office of Legacy Management (LM)

(e.g., aircraft crashes, offsite transportation accidents involving hazardous materials, pipeline explosions); and, terrorism, sabotage, or other malevolent acts. A spectrum of...

478

Technical evaluation: 300 Area steam line valve accident  

SciTech Connect (OSTI)

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

Not Available

1993-08-01T23:59:59.000Z

479

Northwestern University Transportation Center  

E-Print Network [OSTI]

Northwestern University Transportation Center 2011 Business Advisory Committee NUTC #12;#12;I have the pleasure of presenting our Business Advisory Committee members--a distinguished group of transportation industry lead- ers who have partnered with the Transportation Center in advancing the state of knowledge

Bustamante, Fabián E.

480

Louisiana Transportation Research Center  

E-Print Network [OSTI]

Louisiana Transportation Research Center LTRC www.ltrc.lsu.edu 2012-13 ANNUALREPORT #12;The Louisiana Transportation Research Center (LTRC) is a research, technology transfer, and training center administered jointly by the Louisiana Department of Transportation and Development (DOTD) and Louisiana State

Harms, Kyle 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.


481

TRANSPORTATION: THE POTENTIAL  

E-Print Network [OSTI]

INTERMODAL TRANSPORTATION: THE POTENTIAL AND THE CHALLENGE A Summary Report 2003 #12;June 2003 To the Reader This report summarizes the second James L. Oberstar Forum on Transportation Policy and Technology. Over two days, we explored the chal- lenges and opportunities in intermodal transportation, addressing

Minnesota, University of

482

PalladianDigest Transportation  

E-Print Network [OSTI]

PalladianDigest CONNECT. EMPOWER. GROW. Tackling Transportation Challenges Nebraska has been a vital link in the nation's transportation system since the days when carts, wagons to University of Nebraska­Lincoln research. That's fine with UNL transportation researchers, said Larry Rilett

Farritor, Shane

483

The RCK Domain of the KtrAB K+ Transporter: Multiple Conformations  

E-Print Network [OSTI]

that is propagated to the membrane-bound protein, leading to ion transport (Jiang et al., 2002a; Roosild et al., 2002 transporter is a complex of the KtrB membrane protein and KtrA, an RCK do- main. RCK domains regulate eukaryotic and prokaryotic membrane proteins involved in K+ transport. Conflicting functional models have

Gruner, Sol M.

484

Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios.

Green, J.R.

1995-01-31T23:59:59.000Z

485

TYPE A FISSILE PACKAGING FOR AIR TRANSPORT PROJECT OVERVIEW  

SciTech Connect (OSTI)

This paper presents the project status of the Model 9980, a new Type A fissile packaging for use in air transport. The Savannah River National Laboratory (SRNL) developed this new packaging to be a light weight (<150-lb), drum-style package and prepared a Safety Analysis for Packaging (SARP) for submission to the DOE/EM. The package design incorporates unique features and engineered materials specifically designed to minimize packaging weight and to be in compliance with 10CFR71 requirements. Prototypes were fabricated and tested to evaluate the design when subjected to Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC). An overview of the design details, results of the regulatory testing, and lessons learned from the prototype fabrication for the 9980 will be presented.

Eberl, K.; Blanton, P.

2013-10-11T23:59:59.000Z

486

Transport processes in space plasmas  

SciTech Connect (OSTI)

This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The project represents a comprehensive research effort to study plasma and field transport processes relevant for solar-terrestrial interaction, involving the solar wind and imbedded magnetic field and plasma structures, the bow shock of the Earth`s magnetosphere and associated waves, the Earth`s magnetopause with imbedded flux rope structures and their connection with the Earth, plasma flow in the Earth`s magnetotail, and ionospheric beam/wave interactions. The focus of the work was on the interaction between plasma and magnetic and electric fields in the regions where different plasma populations exist adjacent to or superposed on each other. These are the regions of particularly dynamic plasma behavior, important for plasma and energy transport and rapid energy releases. The research addressed questions about how this interaction takes place, what waves, instabilities, and particle/field interactions are involved, how the penetration of plasma and energy through characteristic boundaries takes place, and how the characteristic properties of the plasmas and fields of the different populations influence each other on different spatial and temporal scales. These topics were investigated through combining efforts in the analysis of plasma and field data obtained through space missions with theory and computer simulations of the plasma behavior.

Birn, J.; Elphic, R.C.; Feldman, W.C. [and others

1997-08-01T23:59:59.000Z

487

Transportation Business Plan  

SciTech Connect (OSTI)

The Transportation Business Plan is a step in the process of procuring the transportation system. It sets the context for business strategy decisions by providing pertinent background information, describing the legislation and policies governing transportation under the NWPA, and describing requirements of the transportation system. Included in the document are strategies for procuring shipping casks and transportation support services. In the spirit of the NWPA directive to utilize the private sector to the maximum extent possible, opportunities for business ventures are obvious throughout the system development cycle.

Not Available

1986-01-01T23:59:59.000Z

488

Dynamic accident modeling for high-sulfur natural gas gathering station  

Science Journals Connector (OSTI)

Abstract Dynamic accident modeling for a gas gathering station is implemented to prevent high-sulfur natural gas leakage and develop equipment inspection strategy. The progress of abnormal event occurring in the gas gathering station is modeled by the combination of fault tree and event sequence diagram, based on accident causal chain theory, i.e. the progress is depicted as sequential failure of safety barriers, then, the occurrence probability of the consequence of abnormal event is predicted. Consequences of abnormal events are divided into accidents and accident precursors which include incidents, near misses and so on. The Bayesian theory updates failure probability of safety barrier when a new observation (i.e. accident precursors or accidents data) arrives. Bayesian network then correspondingly updates failure probabilities of basic events of the safety barriers with the ability of abductive reasoning. Consequence occurrence probability is also updated. The results show that occurrence probability trend of different consequences and failure probability trend of safety barriers and basic events of the safety barriers can be obtained using this method. In addition, the critical basic events which play an important role in accidents occurrence are also identified. All of these provide useful information for the maintenance and inspection of the gas gathering station.

Qinglei Tan; Guoming Chen; Lei Zhang; Jianmin Fu; Zemin Li

2014-01-01T23:59:59.000Z

489

National Transportation Stakeholders Forum  

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

Transportation Stakeholders Forum Transportation Stakeholders Forum May 14-16, 2013 Tuesday, May 14 7:00 am - 5:00 pm Registration Niagara Foyer 7:00 am - 7:45 am Breakfast and Networking Grand A 8:00 am - 10:00 am National Updates for Transportation Stakeholder Groups and Guests - Panel Grand BC Moderator: John Giarrusso Jr., MA Emergency Management Agency / Northeast High-Level Radioactive Waste Transportation Task Force Co-Chair US Department of Energy, Office of Environmental Management - Steve O'Connor, Director, Office of Packaging & Transportation US Nuclear Regulatory Commission - Earl P. Easton, Senior Level Advisor (retired) and David W. Pstrak, Transportation and Storage Specialist, Division of Spent Fuel Storage and Transportation

490

Transportation System Requirements Document  

SciTech Connect (OSTI)

This Transportation System Requirements Document (Trans-SRD) describes the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of this document is to define the system-level requirements for Transportation consistent with the CRWMS Requirement Document (CRD). These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presents an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. The interface identification and description are published in the CRWMS Interface Specification.

Not Available

1993-09-01T23:59:59.000Z

491

Transportation risk assessment for ethanol transport  

E-Print Network [OSTI]

(California, Texas Gulf Coast, New England Atlantic Coast) will be of particular interest. The goal is to conduct a quantitative risk assessment on the pipeline, truck, and rail transportation modes to these areas. As a result of the quantitative risk...

Shelton Davis, Anecia Delaine

2009-05-15T23:59:59.000Z

492

Fusion Reactions Involving Radioactive Beams at GANIL  

Science Journals Connector (OSTI)

......February 2004 research-article Articles Fusion Reactions Involving Radioactive Beams...been used to produce exotic nuclei via fusion evaporation or to study reaction mechanisms...Physics Supplement No. 154, 2004 113 Fusion Reactions Involving Radioactive Beams......

Gilles de France

2004-02-01T23:59:59.000Z

493

Public Involvement and Communications Committee Summaries - Hanford...  

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

Hanford Advisory Board > Committee Meeting Information > Involvement and Communications Hanford Advisory Board Convening Report SSAB Guidance Membership Nomination and Appointment...

494

August 2003, Columbia Accident Investigation Report Volume I. Chapter 5-8  

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

9 7 9 7 R e p o r t V o l u m e I A u g u s t 2 0 0 3 Part Two Why The Accident Occurred Many accident investigations do not go far enough. They identify the technical cause of the accident, and then connect it to a variant of "operator error" - the line worker who forgot to insert the bolt, the engineer who miscalculated the stress, or the manager who made the wrong decision. But this is sel-

495

Social and economic effects of the accident at Three Mile Island  

SciTech Connect (OSTI)

The emphasis is on effects of the accident on the region of southcentral Pennsylvania that surrounds the station site. A variety of data sources were utilized including published documents and statistics, household surveys, other research about the accident, newspaper files, and interviews with key informants. Findings are grouped into the effects on (1) the regional economy, (2) institutions, and (3) individuals. The report focuses on the two-week emergency period immediately following the accident and on continuing effects through the end of September 1979. The report ends with the identification of potential longer-term effects.

Flynn, C.B.; Chalmers, J.A.

1980-01-01T23:59:59.000Z

496

External Costs of Transport in the U.S.  

E-Print Network [OSTI]

Epidemiological Studies of Air Pollution Health Impacts, indelay Accident Air pollution, health Air pollution, otherdelay Accident Air pollution, health Air pollution, other

Delucchi, Mark A.; McCubbin, Donald R.

2010-01-01T23:59:59.000Z

497

OXYGEN TRANSPORT CERAMIC MEMBRANES  

SciTech Connect (OSTI)

Conversion of natural gas to liquid fuels and chemicals is a major goal for the Nation as it enters the 21st Century. Technically robust and economically viable processes are needed to capture the value of the vast reserves of natural gas on Alaska's North Slope, and wean the Nation from dependence on foreign petroleum sources. Technologies that are emerging to fulfill this need are all based syngas as an intermediate. Syngas (a mixture of hydrogen and carbon monoxide) is a fundamental building block from which chemicals and fuels can be derived. Lower cost syngas translates directly into more cost-competitive fuels and chemicals. The currently practiced commercial technology for making syngas is either steam methane reforming (SMR) or a two-step process involving cryogenic oxygen separation followed by natural gas partial oxidation (POX). These high-energy, capital-intensive processes do not always produce syngas at a cost that makes its derivatives competitive with current petroleum-based fuels and chemicals. This project has the following 6 main tasks: Task 1--Design, fabricate and evaluate ceramic to metal seals based on graded ceramic powder/metal braze joints. Task 2--Evaluate the effect of defect configuration on ceramic membrane conductivity and long term chemical and structural stability. Task 3--Determine materials mechanical properties under conditions of high temperatures and reactive atmospheres. Task 4--Evaluate phase stability and thermal expansion of candidate perovskite membranes and develop techniques to support these materials on porous metal structures. Task 5--Assess the microstructure of membrane materials to evaluate the effects of vacancy-impurity association, defect clusters, and vacancy-dopant association on the membrane performance and stability. Task 6--Measure kinetics of oxygen uptake and transport in ceramic membrane materials under commercially relevant conditions using isotope labeling techniques.

Dr. Sukumar Bandopadhyay; Dr. Nagendra Nagabhushana

2001-12-01T23:59:59.000Z

498

LEDSGP/Transportation Toolkit/Training | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit/Training < LEDSGP‎ | Transportation Toolkit Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Training for Low Emission Development Strategies in Transportation The LEDS GP Transport Working Group provides technical training and resources in the form of webinars, e-learning, live/recorded presentation videos, presentation files, and other knowledge exchange formats relevant to low emission development strategies in the transport sector. Below are links to relevant online training/learning sites. To suggest additional

499

LEDSGP/Transportation Toolkit/Key Actions | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » LEDSGP/Transportation Toolkit/Key Actions < LEDSGP‎ | Transportation Toolkit(Redirected from Transportation Toolkit/Key Actions) Jump to: navigation, search LEDSGP Logo.png Transportation Toolkit Home Tools Training Contacts Key Actions for Low-Emission Development in Transportation Although no single approach or fixed process exists for low emission development strategies (LEDS), the following key actions are necessary steps for implementing LEDS in the transportation sector. Undertaking these actions requires flexibility to adapt to dynamic societal conditions in a

500

Transportation | Argonne National Laboratory  

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

Transportation Transportation From modeling and simulation programs to advanced electric powertrains, engines, biofuels, lubricants, and batteries, Argonne's transportation research is vital to the development of next-generation vehicles. Revolutionary advances in transportation are critical to reducing our nation's petroleum consumption and the environmental impact of our vehicles. Some of the most exciting new vehicle technologies are being ushered along by research conducted at Argonne National Laboratory. Our Transportation Technology R&D Center (TTRDC) brings together scientists and engineers from many disciplines across the laboratory to work with the U.S. Department of Energy (DOE), automakers and other industrial partners. Our goal is to put new transportation technologies on the road that improve