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

Graphite Oxidation Simulation in HTR Accident Conditions  

SciTech Connect (OSTI)

Massive air and water ingress, following a pipe break or leak in steam-generator tubes, is a design-basis accident for high-temperature reactors (HTRs). Analysis of these accidents in both prismatic and pebble bed HTRs requires state-of-the-art capability for predictions of: 1) oxidation kinetics, 2) air ?helium gas mixture stratification and diffusion into the core following the depressurization, 3) transport of multi-species gas mixture, and 4) graphite corrosion. This project will develop a multi-dimensional, comprehensive oxidation kinetics model of graphite in HTRs, with diverse capabilities for handling different flow regimes. The chemical kinetics/multi-species transport model for graphite burning and oxidation will account for temperature-related changes in the properties of graphite, oxidants (O2, H2O, CO), reaction products (CO, CO2, H2, CH4) and other gases in the mixture (He and N2). The model will treat the oxidation and corrosion of graphite in geometries representative of HTR core component at temperatures of 900°C or higher. The developed chemical reaction kinetics model will be user-friendly for coupling to full core analysis codes such as MELCOR and RELAP, as well as computational fluid dynamics (CFD) codes such as CD-adapco. The research team will solve governing equations for the multi-dimensional flow and the chemical reactions and kinetics using Simulink, an extension of the MATLAB solver, and will validate and benchmark the model's predictions using reported experimental data. Researchers will develop an interface to couple the validated model to a commercially available CFD fluid flow and thermal-hydraulic model of the reactor , and will perform a simulation of a pipe break in a prismatic core HTR, with the potential for future application to a pebble-bed type HTR.

Mohamed El-Genk

2012-10-19T23:59:59.000Z

2

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:...

3

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

4

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

5

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

6

Assessment of potential doses to workers during postulated accident conditions at the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

This qualitative hazard evaluation systematically assessed potential doses to workers during postulated accident conditions at the U.S. Department of Energy`s Waste Isolation Pilot Plant (WIPP). Postulated accidents included the spontaneous ignition of a waste drum, puncture of a waste drum by a forklift, dropping of a waste drum from a forklift, and simultaneous dropping of seven drums during a crane failure. The descriptions and estimated frequencies of occurrence for these accidents were developed by the Hazard and Operability Study for CH TRU Waste Handling System (WCAP 14312). The estimated materials at risk, damage ratios, airborne release fractions and respirable fractions for these accidents were taken from the 1995 Safety Analysis Report (SAR) update and from the DOE handbook Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities (DOE-HDBK-3010-94). A Monte Carlo simulation was used to estimate the range of worker exposures that could result from each accident. Guidelines for evaluating the adequacy of defense-in-depth for worker protection at WIPP were adopted from a scheme presented by the International Commission on Radiological Protection in its publication on Protection from Potential Exposure: A Conceptual Framework (ICRP Publication 64). Probabilities of exposures greater than 5, 50, and 300 rem were less than 10{sup -2}, 10{sup -4}, and 10{sup -6} per year, respectively. In conformance with the guidance of DOE standard 3009-94, Appendix A (draft), we emphasize that use of these evaluation guidelines is not intended to imply that these numbers constitute acceptable limits for worker exposure under accident conditions. However, in conjunction with the extensive safety assessment in the 1995 SAR update, these results indicate that the Carlsbad Area Office strategy for the assessment of hazards and accidents assures the protection of workers, as well as members of the public and the environment.

Hoover, M.D.; Newton, G.J. [Inhalation Toxicology Research Inst., Albuquerque, NM (United States); Farrell, R.F. [Dept. of Energy, Carlsbad, NM (United States)

1996-06-01T23:59:59.000Z

7

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

8

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....

9

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:...

10

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:...

11

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....

12

Hypothetical accident condition thermal analysis and testing of a Type B drum package  

SciTech Connect (OSTI)

A thermophysical property model developed to analytically determine the thermal response of cane fiberboard when exposed to temperatures and heat fluxes associated with the 10 CFR 71 hypothetical accident condition (HAC) has been benchmarked against two Type B drum package fire test results. The model 9973 package was fire tested after a 30 ft. top down drop and puncture, and an undamaged model 9975 package containing a heater (21W) was fire tested to determine content heat source effects. Analysis results using a refined version of a previously developed HAC fiberboard model compared well against the test data from both the 9973 and 9975 packages.

Hensel, S.J.; Alstine, M.N. van; Gromada, R.J. [Westinghouse Savannah River Co., Aiken, SC (United States)

1995-11-01T23:59:59.000Z

13

Hypothetical accident condition thermal analysis and testing of a Type B drum package  

SciTech Connect (OSTI)

A thermophysical property model developed to analytically determine the thermal response of cane fiberboard when exposed to temperatures and heat fluxes associated with the 10 CFR 71 hypothetical accident condition (HAC) has been benchmarked against two Type B drum package fire test results. The model 9973 package was fire tested after a 30 ft. top down drop and puncture, and an undamaged model 9975 package containing a heater (21W) was fire tested to determine content heat source effects. Analysis results using a refined version of a previously developed HAC fiberboard model compared well against the test data from both the 9973 and 9975 packages.

Hensel, S.J.; Alstine, M.N. Van; Gromada, R.J.

1995-07-01T23:59:59.000Z

14

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

SciTech Connect (OSTI)

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

Xu Wu; Piyush Sabharwall; Jason Hales

2014-07-01T23:59:59.000Z

15

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

SciTech Connect (OSTI)

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

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

1996-10-01T23:59:59.000Z

16

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...

17

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

18

Criticality safety assessment of a TRIGA reactor spent-fuel pool under accident conditions  

SciTech Connect (OSTI)

Additional criticality safety analysis of a pool-type storage for TRIGA spent fuel at the Jozef Stefan Institute in Ljubljana, Slovenia, is presented. Previous results have shown that subcriticality is not guaranteed for some postulated accidents (earthquake with subsequent fuel rack disintegration resulting in contact fuel pitch) under the assumption that the fuel rack is loaded with fresh 12 wt% standard fuel. To mitigate this deficiency, a study was done on replacing a certain number of fuel elements in the rack with cadmium-loaded absorber rods. The Monte Carlo computer code MCNP4A with an ENDF/B-V library and detailed three-dimensional geometrical model of the spent-fuel rack was used for this purpose. First, a minimum critical number of fuel elements was determined for contact pitch, and two possible geometries of rack disintegration were considered. Next, it was shown that subcriticality can be ensured when pitch is decreased from a rack design pitch of 8 cm to contact, if a certain number of fuel elements (8 to 20 out of 70) are replaced by absorber rods, which are uniformly mixed into the lattice. To account for the possibility that random mixing of fuel elements and absorber rods can occur during rack disintegration and result in a supercritical configuration, a probabilistic study was made to sample the probability density functions for random absorber rod lattice loadings. Results of the calculations show that reasonably low probabilities for supercriticality can be achieved (down to 10{sup {minus}6} per severe earthquake, which would result in rack disintegration and subsequent maximum possible pitch decrease) even in the case where fresh 12 wt% standard TRIGA fuel would be stored in the spent-fuel pool.

Glumac, B; Ravnik, M. [Jozef Stefan Inst., Ljubljana (Slovenia); Logar, M. [Univ. of Maribor (Slovenia). Faculty of Electrical Engineering and Computer Sciences

1997-02-01T23:59:59.000Z

19

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

20

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

Note: This page contains sample records for the topic "accident conditions view" 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

Dose evaluation in criticality accident conditions using transient critical facilities fueled with a fissile solution  

Science Journals Connector (OSTI)

......first verify the reliability of the measurement...is a pulse-type reactor fueled with 10...conditions in the TRACY reactor room. The results...measurement and analysis are shown in Table...31. Table 1. Analysis of measured and...is also a pulsed reactor similar to the TRACY......

T. Nakamura; K. Tonoike; Y. Miyoshi

2004-08-01T23:59:59.000Z

22

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

SciTech Connect (OSTI)

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

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

2006-07-01T23:59:59.000Z

23

View  

E-Print Network [OSTI]

Q we have yi = Gdi and the G–orthogonality condition of vectors si, si+1 can be written as ?isT i Gsi+1 = yT i si+1 = 0 (we assume that ?i = 0). This together with ...

2009-03-10T23:59:59.000Z

24

Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

1992-06-01T23:59:59.000Z

25

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.

26

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

27

A new view of flow topology and conditional statistics in turbulence  

Science Journals Connector (OSTI)

...simulation data, the statistics of the shape parameters...asymmetry of the joint probability density function of...segments. Conditional statistics based on these newly...asymmetry of the joint probability density function of...segments. Conditional statistics based on these newly...

2013-01-01T23:59:59.000Z

28

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.

29

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

30

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

E-Print Network [OSTI]

. . ACCIDENT DATA MODELS. . . . . . . . . . . . . . ROADSIDE SAFETY ANALYSIS PROGRAM . . 6 9 11 13 CHAPTER III STUDY DESIGN . 20 HAZARDS AND COUNTERMEASURES . . TYPICAL SITE CONDITIONS . . FIXED OBJECT HAZARD . BRIDGE RAIL ENDS . LUMINAIRE SUPPORTS... Rail and Guardrail Extruder. 34 12 Plan View of Bridge Rail and Crash Cushion. 13 Luminaire Typical Section. 14 Typical Embankment Section (Base Condition). 15 Typical Embankment Section (Sideslope=3:1). . 16 Typical Embankment Section (Sideslope...

Hayes, Carolyn A

1997-01-01T23:59:59.000Z

31

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

32

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

33

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

34

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

35

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

36

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...

37

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...

38

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

39

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

40

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

Note: This page contains sample records for the topic "accident conditions view" 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

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...

42

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; João M. P. Dias

2006-01-01T23:59:59.000Z

43

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...

44

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

45

April 2013 Most Viewed Documents for Fission And Nuclear Technologies |  

Office of Scientific and Technical Information (OSTI)

April 2013 Most Viewed Documents for Fission And Nuclear Technologies April 2013 Most Viewed Documents for Fission And Nuclear Technologies Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (null) 298 Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (null) 292 Graphite design handbook Ho, F.H. (1988) 216 System Definition and Analysis: Power Plant Design and Layout NONE (1996) 123 Flow-induced vibration of circular cylindrical structures Chen, S.S. (1985) 116 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United

46

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...

47

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

48

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

49

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

50

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

51

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

52

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

53

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

54

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

55

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

56

Most Viewed Documents - Fission and Nuclear Technologies | OSTI, US Dept of  

Office of Scientific and Technical Information (OSTI)

Most Viewed Documents - Fission and Nuclear Technologies Most Viewed Documents - Fission and Nuclear Technologies Metals design handbook Betts, W.S. (1988) Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. () Graphite design handbook Ho, F.H. (1988) Motor-operated valve (MOV) actuator motor and gearbox testing DeWall, K.; Watkins, J.C.; Bramwell, D. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)] (1997) Environmental Aspects, Objectives and Targets Identification Process R. Green (2002) Flow-induced vibration of circular cylindrical structures Chen, S.S. (1985) System Definition and Analysis: Power Plant Design and Layout NONE (1996) Materials and design bases issues in ASME Code Case N-47 Huddleston, R.L.; Swindeman, R.W. (Oak Ridge National Lab., TN (United

57

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

58

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

59

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

60

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)

Sætren, Thomas G.

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "accident conditions view" 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

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

62

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...

63

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...

64

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...

65

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

66

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...

67

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

68

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.

69

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...

70

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...

71

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...

72

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

73

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

74

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

75

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

76

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

77

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

78

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

79

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

80

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...

Note: This page contains sample records for the topic "accident conditions view" 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

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...

82

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...

83

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 -...

84

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...

85

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...

86

User_ViewRecords  

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

User Records User Records © 2011 SuccessFactors, Inc. - 1 - SuccessFactors Learning Confidential. All rights reserved. Job Aid: Viewing User Records Purpose The purpose of this job aid is to guide users through the step-by-step process of viewing their records. Each task demonstrates viewing of different records. Task A. View To-Do List Enter the web address (URL) of the user application into your browser Address field and press the Enter key. Enter your user ID in the User ID textbox. Enter your password in the Password textbox. Click Sign In. View To-Do List (filter, view) 7 Steps Task A View Completed Work 8 Steps Task B View Curriculum Status and Details 11 Steps Task C 3 3 1 2 2 1 SuccessFactors Learning v 6.4 User Job Aid Viewing User Records

87

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

SciTech Connect (OSTI)

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

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

2013-09-01T23:59:59.000Z

88

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

SciTech Connect (OSTI)

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

Joy L. Rempe; Darrell L. Knudson

2014-05-01T23:59:59.000Z

89

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

90

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

SciTech Connect (OSTI)

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

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

1996-05-01T23:59:59.000Z

91

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

92

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

93

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

94

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

95

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...

96

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

97

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

98

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

99

Views on Automation  

Science Journals Connector (OSTI)

Views on Automation ... Industrial managements, he feels, must allay workers' fears by showing how they can take pride in the greater accomplishment of automated plants. ...

1957-07-29T23:59:59.000Z

100

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

Note: This page contains sample records for the topic "accident conditions view" 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

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

SciTech Connect (OSTI)

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

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

1998-08-01T23:59:59.000Z

102

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...

103

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...

104

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...

105

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...

106

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...

107

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 ...

108

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 ...

109

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 ...

110

NEWS & VIEWS Glass dynamics  

E-Print Network [OSTI]

NEWS & VIEWS Glass dynamics Diverging views on glass transition Gregory B. mc.mckenna@ttu.edu T he glass transition is one of the most intriguing phenomena in the world of soft condensed matter. Despite decades of study, many aspects of the behaviour of glass-forming liquids remain elusive

Weeks, Eric R.

111

News and Views  

Science Journals Connector (OSTI)

......Model 8600 and 8700 gas chromatographs to...untended operation of the gas chromatograph under...0325) 311044. 133 News and Views Macintosh-compatible...speed of the Apple drives and a software incompatibility...for a corporate 134 News and Views licence...that Chem-X was the natural choice: 'Chem-X......

Alan H. Fielding

1990-04-01T23:59:59.000Z

112

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

113

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

114

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

115

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

SciTech Connect (OSTI)

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

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

1996-12-01T23:59:59.000Z

116

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

117

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

118

Running Boundary Condition  

E-Print Network [OSTI]

In this paper we argue that boundary condition may run with energy scale. As an illustrative example, we consider one-dimensional quantum mechanics for a spinless particle that freely propagates in the bulk yet interacts only at the origin. In this setting we find the renormalization group flow of U(2) family of boundary conditions exactly. We show that the well-known scale-independent subfamily of boundary conditions are realized as fixed points. We also discuss the duality between two distinct boundary conditions from the renormalization group point of view. Generalizations to conformal mechanics and quantum graph are also discussed.

Ohya, Satoshi; Tachibana, Motoi

2010-01-01T23:59:59.000Z

119

Running Boundary Condition  

E-Print Network [OSTI]

In this paper we argue that boundary condition may run with energy scale. As an illustrative example, we consider one-dimensional quantum mechanics for a spinless particle that freely propagates in the bulk yet interacts only at the origin. In this setting we find the renormalization group flow of U(2) family of boundary conditions exactly. We show that the well-known scale-independent subfamily of boundary conditions are realized as fixed points. We also discuss the duality between two distinct boundary conditions from the renormalization group point of view. Generalizations to conformal mechanics and quantum graph are also discussed.

Satoshi Ohya; Makoto Sakamoto; Motoi Tachibana

2010-05-25T23:59:59.000Z

120

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 "accident conditions view" 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

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...

122

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...

123

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...

124

DOE-ID FOIA Type A Accident Investigation Board Report - July 28, 1998  

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

Electronic Reading Room Documents Electronic Reading Room Documents Freedom of Information Act (FOIA) More on FOIA/Privacy Act Electronic Request Form Frequently Ask Questions Frequently Requested Documents Guides Helpful Links Points of Contact and Privacy Act Advisory Privacy Act Reading Room DOE-ID Public Reading Room Research Library You are here: DOE-ID Home > FOIA > Type A Accident Investigation Board Report - July 28, 1998 Type A Accident Investigation Board Report - July 28, 1998 Fatality and Multiple Injuries Resulting From Release of Carbon Dioxide at Building 648, Test Reactor Area Idaho National Engineering and Environmental Laboratory Files are provided in Adobe Acrobat format. If you experience problems reading these files please download the latest Adobe Acrobat reader at http://get.adobe.com/reader/ Download Acrobat Reader . Adobe Acrobat file Reader will allow you to view, navigate, and print these PDF files on all major computing platforms.

125

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

126

What you find is not always what you fix—How 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

127

Taking the long view  

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

Taking the long view Taking the long view Taking the long view on environmental stewardship A newly articulated mission for environmental stewardship at the Laboratory can be summed up in a simple phrase: clean up the past, control current operations, and create a sustainable future. March 20, 2012 Los Alamos Aerial Aerial view of a canyon in Los Alamos, New Mexico. Contact Environmental Communication & Public Outreach P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email "The future viability of the Lab hinges on demonstrating to public that we protect human health and the environment." Environmental stewardship strategy looks 50 years into the future As a way of integrating environmental protection activities into a comprehensive strategy, Kevin Smith, manager of the U.S. Department of

128

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

129

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

130

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

131

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

132

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

133

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

134

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

SciTech Connect (OSTI)

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

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

2011-06-21T23:59:59.000Z

135

Radiological protection issues arising during and after the Fukushima nuclear reactor accident  

Science Journals Connector (OSTI)

Following the Fukushima accident, the International Commission on Radiological Protection (ICRP) convened a task group to compile lessons learned from the nuclear reactor accident at the Fukushima Daiichi nuclear power plant in Japan, with respect to the ICRP system of radiological protection. In this memorandum the members of the task group express their personal views on issues arising during and after the accident, without explicit endorsement of or approval by the ICRP.While the affected people were largely protected against radiation exposure and no one incurred a lethal dose of radiation (or a dose sufficiently large to cause radiation sickness), many radiological protection questions were raised. The following issues were identified: inferring radiation risks (and the misunderstanding of nominal risk coefficients); attributing radiation effects from low dose exposures; quantifying radiation exposure; assessing the importance of internal exposures; managing emergency crises; protecting rescuers and volunteers; responding with medical aid; justifying necessary but disruptive protective actions; transiting from an emergency to an existing situation; rehabilitating evacuated areas; restricting individual doses of members of the public; caring for infants and children; categorising public exposures due to an accident; considering pregnant women and their foetuses and embryos; monitoring public protection; dealing with 'contamination' of territories, rubble and residues and consumer products; recognising the importance of psychological consequences; and fostering the sharing of information.Relevant ICRP Recommendations were scrutinised, lessons were collected and suggestions were compiled.It was concluded that the radiological protection community has an ethical duty to learn from the lessons of Fukushima and resolve any identified challenges. Before another large accident occurs, it should be ensured that inter alia: radiation risk coefficients of potential health effects are properly interpreted; the limitations of epidemiological studies for attributing radiation effects following low exposures are understood; any confusion on protection quantities and units is resolved; the potential hazard from the intake of radionuclides into the body is elucidated; rescuers and volunteers are protected with an ad hoc system; clear recommendations on crisis management and medical care and on recovery and rehabilitation are available; recommendations on public protection levels (including infant, children and pregnant women and their expected offspring) and associated issues are consistent and understandable; updated recommendations on public monitoring policy are available; acceptable (or tolerable) 'contamination' levels are clearly stated and defined; strategies for mitigating the serious psychological consequences arising from radiological accidents are sought; and, last but not least, failures in fostering information sharing on radiological protection policy after an accident need to be addressed with recommendations to minimise such lapses in communication.

Abel J González; Makoto Akashi; John D Boice Jr; Masamichi Chino; Toshimitsu Homma; Nobuhito Ishigure; Michiaki Kai; Shizuyo Kusumi; Jai-Ki Lee; Hans-Georg Menzel; Ohtsura Niwa; Kazuo Sakai; Wolfgang Weiss; Shunichi Yamashita; Yoshiharu Yonekura

2013-01-01T23:59:59.000Z

136

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

137

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

138

Air Conditioning  

Science Journals Connector (OSTI)

Air Conditioning ... CHEMISTS and engineers use air conditioning as a valuable tool in more than two hundred industries. ... Air conditioning is a tool with many facets. ...

MARGARET INGELS

1938-02-10T23:59:59.000Z

139

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

140

Prarie View RDF  

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

PRAIRIE VIEW RDF PRAIRIE VIEW RDF 2 Prairie View RDF  Located at JAAP (approx. 40 miles southwest of Chicago), 223 acres on 455 Acre Parcel  Will County Owner; Waste Management, Operator  Maximum 23-Year Life WM/Will County Methane to Energy Plant  Landfill Contract Signed w/WM in 1997 w/Gas-to- Energy Plant Clause  County Retains Gas Rights &WM Installs Gas Collection System  WM owns Methane to Energy Plant &Tax Credits 3 CONTRACT PHASE  DOE Grant Applied 6/09  County Board Approves DOE EECBG Strategy 11/09  1 Million DOE Funds to Methane to Energy Plant  Schiff Harden Hired to Negotiate Gas to Energy Contract  February 2010 County Board Authorizes Contract Execution 4 5 METHANE TO ENERGY PLANT DETAILS  Waste Management Required To

Note: This page contains sample records for the topic "accident conditions view" 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

View dependent fluid dynamics  

E-Print Network [OSTI]

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

Barran, Brian Arthur

2006-08-16T23:59:59.000Z

142

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":""}]}

143

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

144

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

145

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

146

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

147

News and Views  

Science Journals Connector (OSTI)

... -16. The discussions on road lighting, from the point of view both of the pedestrian and the car driver, were valuable, as they show how complex the problem is ... problem is, depending as it does on difficult questions of physiology and psychology. The pedestrian wants to see small obstructions on the road and the numbers on the houses; ...

1928-07-28T23:59:59.000Z

148

ParaView at NERSC  

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

ParaView ParaView ParaView Introduction ParaView is an open-source, multi-platform data analysis and visualization application. ParaView users can quickly build visualizations to analyze their data using qualitative and quantitative techniques. The data exploration can be done interactively in 3D or programmatically using ParaView's batch processing capabilities. ParaView was developed to analyze extremely large datasets using distributed memory computing resources. It can be run on supercomputers to analyze datasets of terascale as well as on laptops for smaller data. Remote Visualization with ParaView ParaView is a client-server application. The ParaView client (or simply paraview) will run on your desktop while the server will run at the remote supercomputing site. The following describes the steps you will take to

149

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

SciTech Connect (OSTI)

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

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

1990-01-01T23:59:59.000Z

150

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

E-Print Network [OSTI]

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

Bott, Charles Patrick

1992-01-01T23:59:59.000Z

151

Reactivity initiated accident test series Test RIA 1-4  

SciTech Connect (OSTI)

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

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

1980-05-01T23:59:59.000Z

152

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

153

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

154

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

155

Stereoscopic optical viewing system  

DOE Patents [OSTI]

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

Tallman, C.S.

1986-05-02T23:59:59.000Z

156

states apps list view | Data.gov  

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

states apps list view states apps list view States Data Apps Challenges Policies States You are here Data.gov » Communities » States List View Showing 1 - 5 of 5 results. Resources sort ascending Type Last Updated On TrashBackwards Trash Backwards will connect you with current recycling information, Do It Yourself reuse and upcycle tutorials that are easy to follow, reliable articles and infographics, upcycled products and durable alternatives to common single-use items, and links to non-profits and other groups who will benefit greatly from the stuff you're done with. Currently includes Massachusetts and Washington. Apps 02/27/2013 MoDOT's Traveler Information Map App With the launch of MoDOT's new Traveler Information Map mobile app, Missouri travelers can get the latest information on road conditions, work zones, flooding and incidents on their iPhones and Androids. Mobile 05/22/2013

157

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...

158

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...

159

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

160

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...

Note: This page contains sample records for the topic "accident conditions view" 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

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...

162

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...

163

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,...

164

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,...

165

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...

166

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...

167

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...

168

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)...

169

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...

170

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...

171

Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics  

SciTech Connect (OSTI)

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

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

2014-02-01T23:59:59.000Z

172

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).

173

Material Selection for Accident Tolerant Fuel Cladding  

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

Alternative cladding materials are being investigated for accident tolerance, which can be defined as >100X improvement (compared to current Zr-based alloys) in oxidation resistance in steam environments at ?1200°C for short (?4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800°C could not be reproduced. Both FeCrAl and MAX phase Ti2AlC form a protective alumina scale in steam. However, commercial Ti2AlC that is not single phase, formed a much thicker oxide at 1200°C in steam and significant TiO2, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475°C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich ?’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated. Keywords: Accident tolerant LWR Fuel cladding, FeCrAl, Mo, Ti2AlC, Al2O3, high temperature steam oxidation resistance

none,

2014-07-01T23:59:59.000Z

174

The View from HQ  

National Nuclear Security Administration (NNSA)

A publication of the Office of Advanced Simulation & Computing, NNSA Defense Programs A publication of the Office of Advanced Simulation & Computing, NNSA Defense Programs NA-ASC-500-07-Issue 3 May 2007 The View from HQ by Dimitri Kusnezov I have been spending much of my time these days thinking about science, technology and engineering and the role of the laboratories and how that will be reflected in the Complex of the future. This is on my mind for two reasons: one is my responsibility to

175

NUPlans Budgeting Grant Input View  

E-Print Network [OSTI]

NUPlans Budgeting Grant Input View FMS704 NUPlansGrantInputViewV2 Last updated 4/7/2014 - rb © 2014 Northwestern University FMS704 NUPlans Contributor Budgeting 1 of 5 NUPlans Grant Input View NUPlans enables schools and units with grant projects to input grant expense estimates per project for the next fiscal

Shull, Kenneth R.

176

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

177

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

178

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...

179

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...

180

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...

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


181

E-Print Network 3.0 - accident 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...

182

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...

183

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.

184

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

185

Protective laser beam viewing device  

DOE Patents [OSTI]

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

Neil, George R.; Jordan, Kevin Carl

2012-12-18T23:59:59.000Z

186

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

187

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 20–30 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

188

Initial Conditions  

Science Journals Connector (OSTI)

Before we can run a transient analysis, we must find the appropriate set of initial conditions for the variables. The most important requirement of initial conditions is that they do not contradict any of the ...

Michael Tiller Ph.D.

2001-01-01T23:59:59.000Z

189

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...

190

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...

191

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...

192

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...

193

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...

194

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...

195

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...

196

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...

197

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...

198

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...

199

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....

200

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...

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


201

E-Print Network 3.0 - accident 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...

202

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...

203

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...

204

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....

205

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....

206

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...

207

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,...

208

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...

209

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....

210

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...

211

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...

212

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...

213

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...

214

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...

215

The View from HQ  

National Nuclear Security Administration (NNSA)

  NA-ASC-500-07 Issue 2 January 2007 The View from HQ Sitting in airports and planes is risky beyond the obvious dangers now in the news. Uninter- rupted time to think may lead to new ideas. Instinct instructs us that when we hear Wash- ington has some new ideas, the result must be bad. After all, ideas suggest change, which is inherently disruptive. Today the notion of predictivity is on my mind as I am leaving the V&V 2007 meeting in Los Alamos. Predictivity is on my short list of overused, ill-defined words. Washington main- tains a full lexicon of such words-a fair number of which find their way into common usage.

216

False color viewing device  

DOE Patents [OSTI]

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

Kronberg, J.W.

1991-05-08T23:59:59.000Z

217

California's Energy Future - The View to 2050  

E-Print Network [OSTI]

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

2011-01-01T23:59:59.000Z

218

Accident Performance of Light Water Reactor Cladding Materials  

SciTech Connect (OSTI)

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

Nelson, Andrew T. [Los Alamos National Laboratory

2012-07-24T23:59:59.000Z

219

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

SciTech Connect (OSTI)

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

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

2014-12-30T23:59:59.000Z

220

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

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


221

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

SciTech Connect (OSTI)

The safe transport of spent nuclear fuel and high-level radioactive waste is an important aspect of the waste management system of the United States. The Nuclear Regulatory Commission (NRC) currently certifies spent nuclear fuel rail cask designs based primarily on numerical modeling of hypothetical accident conditions augmented with some small scale testing. However, NRC initiated a Package Performance Study (PPS) in 2001 to examine the response of full-scale rail casks in extreme transportation accidents. The objectives of PPS were to demonstrate the safety of transportation casks and to provide high-fidelity data for validating the modeling. Although work on the PPS eventually stopped, the Blue Ribbon Commission on America’s Nuclear Future recommended in 2012 that the test plans be re-examined. This recommendation was in recognition of substantial public feedback calling for a full-scale severe accident test of a rail cask to verify evaluations by NRC, which find that risk from the transport of spent fuel in certified casks is extremely low. This report, which serves as the re-assessment, provides a summary of the history of the PPS planning, identifies the objectives and technical issues that drove the scope of the PPS, and presents a possible path for moving forward in planning to conduct a full-scale cask test. Because full-scale testing is expensive, the value of such testing on public perceptions and public acceptance is important. Consequently, the path forward starts with a public perception component followed by two additional components: accident simulation and first responder training. The proposed path forward presents a series of study options with several points where the package performance study could be redirected if warranted.

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

2014-09-01T23:59:59.000Z

222

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

223

Cladding embrittlement during postulated loss-of-coolant accidents.  

SciTech Connect (OSTI)

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

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

2008-07-31T23:59:59.000Z

224

CFD modeling of debris melting phenomena during late phase Candu 6 severe accident  

SciTech Connect (OSTI)

The objective of this paper was to study the phase change of the debris formed on the Candu 6 calandria bottom in a postulated accident sequence. The molten pool and crust formation were studied employing the Ansys-Fluent code. The 3D model using Large Eddy Simulation (LES) predicts the conjugate, radiative and convective heat transfer inside and from the corium pool. LES simulations require a very fine grid to capture the crust formation and the free convection flow. This aspect (fine mesh requirement) correlated with the long transient has imposed the use of a slice from the 3D calandria geometry in order not to exceed the computing resources. The preliminary results include heat transfer coefficients, temperature profiles and heat fluxes through calandria wall. From the safety point of view it is very important to maintain a heat flux through the wall below the CHF assuring the integrity of the calandria vessel. This can be achieved by proper cooling of the tank water which contains the vessel. Also, transient duration can be estimated being important in developing guidelines for severe accidents management. The debris physical structure and material properties have large uncertainties in the temperature range of interest. Thus, further sensitivity studies should be carried out in order to better understand the influence of these parameters on this complex phenomenon. (authors)

Nicolici, S.; Dupleac, D.; Prisecaru, I. [Univ. Politehnica of Bucharest, 313 Splaiul Independentei, 060042, Bucharest (Romania)

2012-07-01T23:59:59.000Z

225

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

226

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

227

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

228

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

229

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

230

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,...

231

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...

232

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...

233

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...

234

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...

Félix Francisco Serrano Gallardo

2009-10-01T23:59:59.000Z

235

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

236

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...

237

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

238

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...

239

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...

240

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

Note: This page contains sample records for the topic "accident conditions view" 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

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...

242

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...

243

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

244

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...

245

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

246

The Adequacy of DOE Natural Phenomena Hazards Performance Goals from an Accident Analysis Perspective  

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

Adequacy of DOE Natural Adequacy of DOE Natural Phenomena Hazards Performance Goals from an Accident Analysis Perspective Jeff Kimball Defense Nuclear Facilities Safety Board Staff Department of Energy NPH Conference October 26, 2011 The views expressed are solely those of the author and no official support or endorsement of this presentation by the Defense Nuclear Facilities Safety Board or the federal government is intended or should be inferred. 1 OBJECTIVE: Assess whether the DOE NPH performance goal concept as used in the Documented Safety Analysis process is adequate or needs additional guidance Background * ANS Standard 2.26 and the concept of Seismic Design Categories (SDC) and Limit States (LS) * ASCE Standard 43-05 and the concept of Design Categories

247

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

248

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

249

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

250

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

251

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

252

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).

253

Prairie View A&M University Whole Campus Energy Analysis  

E-Print Network [OSTI]

-campus energy consumption at the Prairie View A&M Campus where whole-campus indices were developed that normalize for weather, conditioned area, and campus enrollment. The resultant indices were then used to estimate whole-campus energy savings resulting from.... This analysis develops indices that are normalized for weather, conditioned area, and campus enrollment. The resultant indices are then used to estimate energy savings from a guaranteed-savings contract at the Prairie View A&M Campus. j The next section...

Haberl, J. S.; Claridge, D. E.; Turner, W. D.

1991-01-01T23:59:59.000Z

254

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

SciTech Connect (OSTI)

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

McPherson, G D; Tolman, E L

1980-01-01T23:59:59.000Z

255

Chisolm View | Open Energy Information  

Open Energy Info (EERE)

Chisolm View Chisolm View Jump to: navigation, search Name Chisolm View Facility Chisolm View Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner GE Energy Financial Service / Enel Green Power North America Developer TradeWind Energy Energy Purchaser Alabama Power Company Location Hunter OK Coordinates 36.59527057°, -97.54501104° 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":36.59527057,"lon":-97.54501104,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

256

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

257

Managing Errors to Reduce Accidents in High Consequence Networked Information Systems  

SciTech Connect (OSTI)

Computers have always helped to amplify and propagate errors made by people. The emergence of Networked Information Systems (NISs), which allow people and systems to quickly interact worldwide, has made understanding and minimizing human error more critical. This paper applies concepts from system safety to analyze how hazards (from hackers to power disruptions) penetrate NIS defenses (e.g., firewalls and operating systems) to cause accidents. Such events usually result from both active, easily identified failures and more subtle latent conditions that have resided in the system for long periods. Both active failures and latent conditions result from human errors. We classify these into several types (slips, lapses, mistakes, etc.) and provide NIS examples of how they occur. Next we examine error minimization throughout the NIS lifecycle, from design through operation to reengineering. At each stage, steps can be taken to minimize the occurrence and effects of human errors. These include defensive design philosophies, architectural patterns to guide developers, and collaborative design that incorporates operational experiences and surprises into design efforts. We conclude by looking at three aspects of NISs that will cause continuing challenges in error and accident management: immaturity of the industry, limited risk perception, and resource tradeoffs.

Ganter, J.H.

1999-02-01T23:59:59.000Z

258

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

259

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

260

Printed 3D Multi-View Images  

Science Journals Connector (OSTI)

The technique to produce full-parallax 3D multi-view still pictures is described. The matrix of source views (from 6x6 to 15x15 views) is built from computer-generated images or...

Kim, Sung-Sik; Son, Kwang-Hun; Saveljev, V V; Son, Jung-Young

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "accident conditions view" 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

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

262

In-vessel Zircaloy oxidation/hydrogen generation behavior during severe accidents  

SciTech Connect (OSTI)

In-vessel Zircaloy oxidation and hydrogen generation data from various US Nuclear Regulatory Commission severe-fuel damage test programs are presented and compared, where the effects of Zircaloy melting, bundle reconfiguration, and bundle quenching by reflooding are assessed for common findings. The experiments evaluated include fuel bundles incorporating fresh and previously irradiated fuel rods, as well as control rods. Findings indicate that the extent of bundle oxidation is largely controlled by steam supply conditions and that high rates of hydrogen generation continued after melt formation and relocation. Likewise, no retardation of hydrogen generation was noted for experiments which incorporated control rods. Metallographic findings indicate extensive oxidation of once-molten Zircaloy bearing test debris. Such test results indicate no apparent limitations to Zircaloy oxidation for fuel bundles subjected to severe-accident coolant-boiloff conditions. 46 refs., 22 figs., 12 tabs.

Cronenberg, A.W. (Science and Engineering Associates, Inc., Albuquerque, NM (USA))

1990-09-01T23:59:59.000Z

263

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

264

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

265

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

SciTech Connect (OSTI)

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

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

2005-08-08T23:59:59.000Z

266

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

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

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

267

Comparison of US/FRG accident condition fuel failure and release models  

SciTech Connect (OSTI)

Although there are many differences between the High-Temperature Gas Cooled Reactor (HTGR) concepts being developed in the US and the High Temperature Reactor (HTR) concepts in the Federal Republic of Germany (FRG), the coated fuel particles are very similar. Significant benefits are achievable through cooperative research and exchange of information and data on the fuel performance and radionuclide retention in the coated fuel particles. This draft report describes cooperative work on HTGR safety research as agreed to in the "USA/FRG Umbrella Agreement for Cooperation in GCR Development: Safety Research Subprogram Plan," specifically, this work was conducted under Project Work Statement (PWS) S-6 titled "Fission Product Retention in Fuel," 9 refs., 12 figs., 4 tabs.

Bolin, J.; Dunn, T.

1989-05-29T23:59:59.000Z

268

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

E-Print Network [OSTI]

on the surfaces of the earth, buildings, and paved areas is very difficult to model. Factors which influence the behavior of the nuclides include external forces which cause weathering effects (soil erosion and penetration of the soil), chemical and physical... of the radionuclides into the soil is not disturbed by man (no soil cultivation). 5. Radionuclides with half-lives less than eight days need not be considered. 6. Radionuclides not having significant gamma emissions are not effective contributors to the total dose...

Meyer, Christopher Martin

1985-01-01T23:59:59.000Z

269

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

270

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

271

List View | Data.gov  

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

List View List View Safety Data/Tools Apps Challenges Resources Blogs Let's Talk Safety You are here Data.gov » Communities » Safety List View Interactive applications that visually display large datasets provide a portal to explore data and make discoveries. Federal agencies collect information on energy production, use, natural resources, and energy infrastructure logistics and this data can be used to create calculators, interactive maps, and other applications that leverage this data. These applications provide user communities the ability to highlight the energy issues that are occurring within their communities, aid businesses plan and analyze their proposed projects, and provide a baseline for analyzing how energy resources can be most optimally and efficiently used. This page

272

Wide field of view telescope  

DOE Patents [OSTI]

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

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

2008-01-15T23:59:59.000Z

273

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...

274

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,...

275

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...

276

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...

277

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...

278

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...

279

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...

280

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...

Note: This page contains sample records for the topic "accident conditions view" 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

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...

282

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...

283

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...

284

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...

285

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

286

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

287

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...

288

Limited View Angle Iterative CT Reconstruction  

E-Print Network [OSTI]

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

289

Census and viewing of organisms  

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

Census and viewing of organisms Census and viewing of organisms Name: m hariaczyi Status: N/A Age: N/A Location: N/A Country: N/A Date: Around 1993 Question: How many organisms exist in the world today? What is the most powerful microscope that could be used for viewing organism? Replies: The most powerful microscope is called an electron microscope, which can be used for viewing entire organisms, although few organisms are small enough to see all of them at high magnifications allowed by this microscope. So most often its used to look at fixed sections of organisms. Since the electron microscope only works in a vacuum, with no air, you cannot look at live organisms. To do that, probably the most powerful microscope is called a Nomarski, or in technical terms, a "differential interference contrast" microscope. This is a modification of a normal light microscope that allows better contrast in living tissue. It is not any more powerful than a light microscope, and is much less powerful than an electron microscope, but it allows you to see living things much better.

290

GoddardView Welcome Home!  

E-Print Network [OSTI]

GoddardView Welcome Home! Pg 2 - 3 History's Greatest Comet Hunter Pg 8 Employee Spotlight: Ernest Program Ends Amid Kudos - 6 Engineers Organize With A Desire To Inspire - 7 History's Greatest Comet on the runway at Edwards Air Force Base, California, after a safe landing August 9, 2005. Photo Credit: NASA 02

Christian, Eric

291

View  

Science Journals Connector (OSTI)

Mn, the concentration gradient that drives the diffusion is maintained by the precipitation of insoluble oxides. In the case of Cd, ... Cientifica e Tecnologica (

2000-10-07T23:59:59.000Z

292

View  

E-Print Network [OSTI]

May 18, 2012 ... bottleneck, long-time production simulations will be severely hampered ...... t ¼ 0.975, (g) t ¼ 1.0, (h) t ¼ 1.025, (i) t ¼ 1.275, (j) t ¼ 1.525, (k) t ¼ ...

S. Dong

2012-06-21T23:59:59.000Z

293

View  

E-Print Network [OSTI]

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

andrea,,,

294

View  

E-Print Network [OSTI]

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

2005-05-30T23:59:59.000Z

295

View  

Science Journals Connector (OSTI)

89-l 1268) ran the carbon analysis of the sediment trap material ..... vehicle camera system were analyzed with a ... tribution of distances with the computer pro-.

1999-12-21T23:59:59.000Z

296

View  

E-Print Network [OSTI]

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

2011-01-28T23:59:59.000Z

297

View  

E-Print Network [OSTI]

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

2010-03-14T23:59:59.000Z

298

View  

E-Print Network [OSTI]

Mar 14, 2006 ... ... of the paper is devoted to the development of background material for ..... Note that the optimization problem in the correction phase is solved over ...... In Phase I

2006-03-31T23:59:59.000Z

299

View  

E-Print Network [OSTI]

Mar 1, 2007 ... 2The logarithmic barrier for the half space {u ? Rn | a · u ? b} is ..... in the Uncapacitated Falicity Location Library (UflLib) [Hoe06]. .... For our test we use 36 unsolved UFL instances that come from two public sets of instances.

2007-03-01T23:59:59.000Z

300

View  

E-Print Network [OSTI]

cT w tj (cj z) + o (1) = wti (z) + o (1), since c-Ow(cz) = w(z) for any w E W and c > 0. We have obtained a contradiction with (2.29), which proves (2.28). If w t = w(' ...

2004-12-25T23:59:59.000Z

Note: This page contains sample records for the topic "accident conditions view" 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

View  

Science Journals Connector (OSTI)

Apr 15, 1976 ... terms of Hairston's hypothesis, to find that only the ... be a component of the search by grazers .... to stop searching and to enter into a state.

2000-01-05T23:59:59.000Z

302

View  

E-Print Network [OSTI]

which has a 0 infimum, but does not attain it. Here the certificates of the bad behavior of the system in (3.32) are. Z = (. 1 0. 0 0. ) , V = (. 0 1. 1 0. ) . Example 2.

2014-05-14T23:59:59.000Z

303

View  

E-Print Network [OSTI]

1. Introduction. The purpose of the present paper is to develop some new directions of investigation in ..... For each i = 1, ..., m, and g = (x1, ..., xr,mr ), we have.

2003-09-25T23:59:59.000Z

304

View  

E-Print Network [OSTI]

Definition 1 The persistency of a variable xi is defined to be the probability that xi = 1 in the ..... i , we know a limited set of marginal moments mr i . We let ? ...

2005-04-19T23:59:59.000Z

305

View  

E-Print Network [OSTI]

In [4], Devinatz, Hopkins, and Smith proved the nilpotence theorem, a remark- able result which provides algebraic means for detecting nilpotence in the ...

1997-12-15T23:59:59.000Z

306

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Science Journals Connector (OSTI)

carbon (C) and increased mixing energies, making CO, limitation less likely. .... Verde Reef (Vera Cruz, Mexico). ..... solar energy is more important in deter-.

2000-03-03T23:59:59.000Z

307

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E-Print Network [OSTI]

Sep 3, 2003 ... Superconductors are able to carry equilibrium currents without resistance. .... by an Ohm's law where ? is the electric conductivity and b1 is a ...

1910-31-00T23:59:59.000Z

308

Viewed  

Science Journals Connector (OSTI)

Oct 27, 1982 ... study area does not contain indigenous io- .... Zn Handbook ofgeochemistry. V. 7, part 4. Spring ... Lakes-physics, chemistry, geology. Springer.

2000-02-09T23:59:59.000Z

309

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Science Journals Connector (OSTI)

This lake is in the Kigezi Highlands, western Uganda, in a narrow steep-sided branching river valley about 20 km long that has been dammed and drowned by a.

Orcas

310

View  

Science Journals Connector (OSTI)

1943. Treatment of experimental data. Wiley,. New York, N.Y. 344 p. ZIIIN-ELDIN, Z. P. 1961. Plankton pigments in. East Lagoon, Galveston, Texas. Trans. Am.

Orcas

311

View  

E-Print Network [OSTI]

GLEV train, a new bullet train under development in Japan, is formulated as the ... conservation law and v ? c represents a constraint on the maximum capacity at each ... Railways Technical Research Institute, Kokubunji, Tokyo 185-8540 Japan ... optimization since 1984 when Karmarkar proposed the projective scaling ...

2002-10-31T23:59:59.000Z

312

View  

E-Print Network [OSTI]

the random consequences of the chosen action, h(x, ?), are preferred to those of a baseline random variable Z for all utility ...... Ground truth. Envelope. Figure 3: ...

2012-06-29T23:59:59.000Z

313

View  

E-Print Network [OSTI]

A major challenge in using optimization to make risk-averse decisions in the face of uncertainty is how to specify an acceptable level of risk. Recently, Dentcheva ...

2011-06-22T23:59:59.000Z

314

View  

E-Print Network [OSTI]

maximum acceptable risk that one is willing to take. ... of initial wealth allocated to the assets, CVaR?(?T x) measures the risk of a given allocation x, b. 1 ...

2009-03-26T23:59:59.000Z

315

View  

E-Print Network [OSTI]

acceptable level of risk. As shown in [2], Problem (3) is a difficult, in fact NP-hard, combinatorial problem. Following [17] and [21], we choose to tackle it by ...

2010-02-08T23:59:59.000Z

316

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E-Print Network [OSTI]

allowed to be violated an “acceptable” amount of time. There are no ... optimal investment strategies with a certain level of risk [10]. Up to this point most research ...

2008-05-24T23:59:59.000Z

317

View  

E-Print Network [OSTI]

in the primal problem. As it can be seen by the number of floating point operations needed to generate the approximation to the set of efficient points, the strategy.

318

View  

E-Print Network [OSTI]

Oct 29, 2008 ... serial machine in floating point is well below our needs. 3 Notation. We are given an m × d design matrix P of floating point numbers and an.

2008-10-28T23:59:59.000Z

319

View  

E-Print Network [OSTI]

function, and the nuclear norm. The support function is based on the graph of the product of a matrix with its transpose. Closed form expressions for the support ...

2014-08-28T23:59:59.000Z

320

View  

E-Print Network [OSTI]

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

2008-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "accident conditions view" 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

View  

E-Print Network [OSTI]

the UCT and reproves Huaxin Lin's theorem on the classification of nuclear tracially AF ... A deep conjecture of Elliott asserts that the simple separable nuclear ...

2004-06-29T23:59:59.000Z

322

View  

E-Print Network [OSTI]

job Ji is a function of its completion time, usually denoted by Ci. ..... For any t > max(P, d), there exists a value ? > 0 and a job index i? ? {1,...,n} such that, for any ...

2006-03-29T23:59:59.000Z

323

View  

E-Print Network [OSTI]

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

2006-02-28T23:59:59.000Z

324

View  

E-Print Network [OSTI]

Our original motivating application is in Electronics and arises in the development of pulse ...... In 8th International Symposium on Fundamentals of Computa-.

Christoph Buchheim,,,

325

View  

E-Print Network [OSTI]

Feb 28, 2012 ... and P. Dorta-González. Departamento de Métodos Cuantitativos en Econom?a y Gestión. Universidad de Las Palmas de Gran Canaria (Spain).

2012-02-28T23:59:59.000Z

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

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

330

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

331

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.

332

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

333

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 4 K 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 32 h. 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

334

Satellite Photograph Presents First Comprehensive View of Local Wind: The Santa Ana  

Science Journals Connector (OSTI)

...January 1973 Santa Ana wind condition reveals local atmospheric dynamics...imagery. The Santa Ana wind implies very specific...conservationists. A Santa Ana (a foehn type wind) may develop...Comprehensive View of Local Wind: The Santa Ana Abstract...

Leonard W. Bowden; Jates R. Huning; Charles F. Hutchinson; Claude W. Johnson

1974-06-07T23:59:59.000Z

335

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.

336

Prairie View A&M University Whole Campus Energy Report Update  

E-Print Network [OSTI]

. This updated report presents an analysis of whole-campus energy consumption at the Prairie View A&M Campus where whole-campus indices were developed that normalize for weather, conditioned area, and campus enrollment. The resultant indices were then used.... Introduction This report presents results of an analysis of energy consumption at the Texas A&M Prairie View Campus. This analysis develops indices that are normalized for weather, conditioned area, and campus enrollment. The resultant indices are then used...

Haberl, J. S.; Claridge, D. E.; Turner, W. D.

1992-01-01T23:59:59.000Z

337

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

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

338

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.

339

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

340

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

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


341

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

342

September 2013 Most Viewed Documents for Fission And Nuclear Technologies |  

Office of Scientific and Technical Information (OSTI)

Fission And Nuclear Technologies Fission And Nuclear Technologies Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 133 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United States)) (1992) 78 Graphite design handbook Ho, F.H. (1988) 76 Feed-pump hydraulic performance and design improvement, Phase I: research program design. Final report Brown, W.H.; Gopalakrishnan, S.; Fehlau, R.; Thompson, W.E.; Wilson, D.G. (1982) 69 Flow-induced vibration of circular cylindrical structures Chen, S.S. (1985)

343

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

344

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

345

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

346

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

347

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

348

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

349

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

350

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

351

Better Buildings Network View | November 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

352

Better Buildings Network View | October 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

353

Better Buildings Network View | September 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

354

Better Buildings Network View | January 2015  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

355

Better Buildings Network View | December 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

356

The Better Buildings Neighborhood View- Fall 2011  

Broader source: Energy.gov [DOE]

Better Buildings Neighborhood View, from the Better Buildings Neighborhood Program of the U.S. Department of Energy.

357

Better Buildings Network View | February 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

358

California's Energy Future - The View to 2050  

E-Print Network [OSTI]

Energy Future - The View to 2050 Bin Biofuel Technology Hydrogen Ethanol from sugar and starch (e.g. , corn,

2011-01-01T23:59:59.000Z

359

The Better Buildings Neighborhood View- July 2012  

Broader source: Energy.gov [DOE]

The Better Buildings Neighborhood View monthly newsletter from the U.S. Department of Energy's Better Buildings Neighborhood Program.

360

Better Buildings Network View | April 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

Note: This page contains sample records for the topic "accident conditions view" 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

Better Buildings Network View | May 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

362

Better Buildings Network View | March 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

363

Better Buildings Network View | June 2014  

Broader source: Energy.gov [DOE]

The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network.

364

Street Light View: Enriching Navigable Panoramic Street View Maps with Informative Illumination Thumbnails  

E-Print Network [OSTI]

1 Street Light View: Enriching Navigable Panoramic Street View Maps with Informative Illumination, Stony Brook University ABSTRACT Google Street View is a technology featured in Google Maps and Google Earth that provides panoramic and immersive views of street scenes in many cities around the world

Mueller, Klaus

365

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

SciTech Connect (OSTI)

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

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

2008-10-01T23:59:59.000Z

366

TotalView Parallel Debugger at NERSC  

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

Totalview Totalview Totalview Description TotalView from Rogue Wave Software is a parallel debugging tool that can be run with up to 512 processors. It provides both X Windows-based Graphical User Interface (GUI) and command line interface (CLI) environments for debugging. The performance of the GUI can be greatly improved if used in conjunction with free NX software. The TotalView documentation web page is a good resource for learning more about some of the advanced TotalView features. Accessing Totalview at NERSC To use TotalView at NERSC, first load the TotalView modulefile to set the correct environment settings with the following command: % module load totalview Compiling Code to Run with TotalView In order to use TotalView, code must be compiled with the -g option. We

367

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

368

A PHILOSOPHICAL VIEW OF CIVILIZATION  

Science Journals Connector (OSTI)

Publisher Summary Civilization comprises the dynamic interchange or “transaction” between three open entities—human nature, values and environment, physical and ideal—and can be understood only as their “emergence” or “transcendence.” The scientific and technological age views civilization in East or West largely in the context of man's control and manipulation of nature. The furniture and appurtenances of civilized living, the scaffolding and the frame-work rather than the mansion itself loom larger in the picture. However, the mansion of civilization is represented by the insights, appreciations, values and aspirations of mankind. It is these enduring experiences of the race which embody the essence of civilization and should obtain primary consideration in any adequate treatment. As the philosophy of science and technology makes a tour round the globe, the meanings, appreciations, and values that civilization actually experiences in its orientation to cosmos and to existence as a whole are discounted as metaphysical and religious—irrelevant for modern secular culture.

RADHAKAMAL MUKERJEE

2014-01-01T23:59:59.000Z

369

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

370

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

371

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

372

A View from the Bridge - DOE Perspective | Department of Energy  

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

A View from the Bridge - DOE Perspective A View from the Bridge - DOE Perspective Broad view of DOE's approach to addressing transportation sector oil dependence...

373

Better Buildings Network View | April 2014 | Department of Energy  

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

Network View | April 2014 Better Buildings Network View | April 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings...

374

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

375

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...

376

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...

377

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...

378

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...

379

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:...

380

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...

Note: This page contains sample records for the topic "accident conditions view" 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

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...

382

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...

383

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:...

384

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:...

385

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......

386

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...

387

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.

388

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...

389

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

390

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...

391

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...

392

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...

393

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...

394

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...

395

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...

396

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...

397

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,...

398

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...

399

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...

400

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...

Note: This page contains sample records for the topic "accident conditions view" 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 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...

402

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...

403

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...

404

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...

405

A SCOPING STUDY: Development of Probabilistic Risk Assessment Models for Reactivity Insertion Accidents During Shutdown In U.S. Commercial Light Water Reactors  

SciTech Connect (OSTI)

This report documents the scoping study of developing generic simplified fuel damage risk models for quantitative analysis from inadvertent reactivity insertion events during shutdown (SD) in light water pressurized and boiling water reactors. In the past, nuclear fuel reactivity accidents have been analyzed both mainly deterministically and probabilistically for at-power and SD operations of nuclear power plants (NPPs). Since then, many NPPs had power up-rates and longer refueling intervals, which resulted in fuel configurations that may potentially respond differently (in an undesirable way) to reactivity accidents. Also, as shown in a recent event, several inadvertent operator actions caused potential nuclear fuel reactivity insertion accident during SD operations. The set inadvertent operator actions are likely to be plant- and operation-state specific and could lead to accident sequences. This study is an outcome of the concern which arose after the inadvertent withdrawal of control rods at Dresden Unit 3 in 2008 due to operator actions in the plant inadvertently three control rods were withdrawn from the reactor without knowledge of the main control room operator. The purpose of this Standardized Plant Analysis Risk (SPAR) Model development project is to develop simplified SPAR Models that can be used by staff analysts to perform risk analyses of operating events and/or conditions occurring during SD operation. These types of accident scenarios are dominated by the operator actions, (e.g., misalignment of valves, failure to follow procedures and errors of commissions). Human error probabilities specific to this model were assessed using the methodology developed for SPAR model human error evaluations. The event trees, fault trees, basic event data and data sources for the model are provided in the report. The end state is defined as the reactor becomes critical. The scoping study includes a brief literature search/review of historical events, developments of a small set of comprehensive event trees and fault trees and recommendation for future work.

S. Khericha

2011-06-01T23:59:59.000Z

406

Diffusion modeling of fission product release during depressurized core conduction cooldown conditions  

SciTech Connect (OSTI)

A simple model for diffusion through the silicon carbide layer of TRISO particles is applied to the data for accident condition testing of fuel spheres for the High-Temperature Reactor program of the Federal Republic of Germany (FRG). Categorization of sphere release of {sup 137}Cs based on fast neutron fluence permits predictions of release with an accuracy comparable to that of the US/FRG accident condition fuel performance model. Calculations are also performed for {sup 85}Kr, {sup 90}Sr, and {sup 110m}Ag. Diffusion of cesium through SiC suggests that models of fuel failure should consider fuel performance during repeated accident condition thermal cycling. Microstructural considerations in models in fission product release are discussed. The neutron-induced segregation of silicon within the SiC structure is postulated as a mechanism for enhanced fission product release during accident conditions. An oxygen-enhanced SiC decomposition mechanism is also discussed. 12 refs., 11 figs., 2 tabs.

Martin, R.C.

1990-01-01T23:59:59.000Z

407

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

408

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

409

A New Ontological View of the Quantum Measurement Problem  

E-Print Network [OSTI]

A new ontological view of the quantum measurement processes is given, which has bearings on many broader issues in the foundations of quantum mechanics as well. In this scenario a quantum measurement is a non-equilibrium phase transition in a ``resonant cavity'' formed by the entire physical universe including all of its material and energy content. A quantum measurement involves the energy and matter exchange among not only the system being measured and the measuring apparatus but also the global environment of the universe resonant cavity, which together constrain the nature of the phase transition. Strict realism, including strict energy and angular momentum conservation, is recovered in this view of the quantum measurement process beyond the limit set by the uncertainty relations, which are themselves derived from the exact commutation relations for quantum conjugate variables. Both the amplitude and the phase of the quantum mechanical wavefunction acquire substantial meanings in the new ontology, and the probabilistic element is removed from the foundations of quantum mechanics, its apparent presence in the quantum measurement being solely a result of the sensitive dependence on initial/boundary conditions of the phase transitions of a many degree-of-freedom system which is effectively the whole universe. Vacuum fluctuations are viewed as the ``left over'' fluctuations after forming the whole numbers of nonequilibrium resonant modes in the universe cavity. This new view on the quantum processes helps to clarify many puzzles in the foundations of quantum mechanics.

Xiaolei Zhang

2005-06-13T23:59:59.000Z

410

March 2014 Most Viewed Documents for Fission And Nuclear Technologies...  

Office of Scientific and Technical Information (OSTI)

J. (1978) 30 > Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. PWR and BWR Not Available (1975)...

411

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

Broader source: Energy.gov [DOE]

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

412

The Better Buildings Neighborhood View- October 2012  

Broader source: Energy.gov [DOE]

The Better Buildings Neighborhood View monthly newsletter from the U.S. Department of Energy's Better Buildings Neighborhood Program - October 2012

413

Fibrations and universal view updatability Michael Johnson  

E-Print Network [OSTI]

Fibrations and universal view updatability Michael Johnson Computing Department, Macquarie methods to manage the complexity. Dampney and Johnson [25] first showed how data models based on entity

Johnson, Michael

414

Fibrations and universal view updatability Michael Johnson  

E-Print Network [OSTI]

Fibrations and universal view updatability Michael Johnson Computing Department, Macquarie and Johnson [25] first showed how data models based on entity-relationship (ER) diagrams [10] are enhanced

Rosebrugh, Robert

415

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

416

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

417

U-008: Symantec Data Loss Prevention Bugs in KeyView Filter Lets Remote  

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

08: Symantec Data Loss Prevention Bugs in KeyView Filter Lets 08: Symantec Data Loss Prevention Bugs in KeyView Filter Lets Remote Users Deny Service U-008: Symantec Data Loss Prevention Bugs in KeyView Filter Lets Remote Users Deny Service October 11, 2011 - 8:00am Addthis PROBLEM: Symantec Data Loss Prevention Bugs in KeyView Filter Lets Remote Users Deny Service PLATFORM: Symantec Data Loss Prevention Enforce/Detection Servers for Windows 10.x, 11.x ABSTRACT: A remote user can create a file that, when processed by the target filter, will cause partial denial of service conditions. reference LINKS: Symantec Security Advisory SYM11-013 SecurityTracker Alert ID: 1026157 IMPACT ASSESSMENT: Medium Discussion: Multiple vulnerabilities were reported in Symantec Data Loss Prevention. A remote user can cause denial of service conditions on the target system.A

418

137Cs in irrigation water and its effect on paddy fields in Japan after the Fukushima nuclear accident  

Science Journals Connector (OSTI)

Abstract There is concern that radiocesium deposited in the environment after the accident at the Fukushima Daiichi Nuclear Power Plant (FDNPP) in March 2011 will migrate to paddy fields through hydrological pathways and cause serious and long-lasting damage to the agricultural activities. This study was conducted in the Towa region of Nihonmatsu in the northern part of Fukushima Prefecture, Japan, (1) to quantify 137Cs in stream water used to irrigate paddy fields by separating the dissolved and particulate components in water samples and then fractionating the particulate components bonded in different ways using a sequential extraction procedure, and (2) to determine the amounts of radiocesium newly added to paddy fields in irrigation water relative to the amounts of radiocesium already present in the fields from the deposition of atmospheric fallout immediately after the FDNPP accident. Three catchments were studied, and the 137Cs activity concentrations in stream water samples were 79–198 mBq L? 1 under stable runoff conditions and 702–13,400 Bq L? 1 under storm runoff conditions. The residual fraction (F4, considered to be non-bioavailable) was dominant, accounting for 59.5–82.6% of the total 137Cs activity under stable runoff conditions and 69.4–95.1% under storm runoff conditions. The 137Cs newly added to paddy fields in irrigation water only contributed 0.03–0.05% of the amount already present in the soil (201–348 kBq m? 2). This indicates that the 137Cs inflow load in irrigation water is negligible compared with that already in the soil. However, the contribution from the potentially bioavailable fractions (F1 + F2 + F3) was one order of magnitude larger, accounting for 0.20–0.59%. The increase in the dissolved and soluble radiocesium fraction (F1) was especially large (3.0% to infinity), suggesting that radiocesium migration in irrigation water is increasing the accumulation of radiocesium in rice.

Natsuki Yoshikawa; Hitomi Obara; Marie Ogasa; Susumu Miyazu; Naoki Harada; Masanori Nonaka

2014-01-01T23:59:59.000Z

419

April 2013 Most Viewed Documents for Energy Storage, Conversion, And  

Office of Scientific and Technical Information (OSTI)

April 2013 Most Viewed Documents for Energy Storage, Conversion, And April 2013 Most Viewed Documents for Energy Storage, Conversion, And Utilization Seventh Edition Fuel Cell Handbook NETL (2004) 628 Continuously variable transmissions: theory and practice Beachley, N.H.; Frank, A.A. (null) 205 A study of lead-acid battery efficiency near top-of-charge and the impact on PV system design Stevens, J.W.; Corey, G.P. (1996) 173 Energy Saving Potentials and Air Quality Benefits of Urban HeatIslandMitigation Akbari, Hashem (2005) 153 Building a secondary containment system Broder, M.F. (1994) 144 An Improved Method of Manufacturing Corrugated Boxes: Lateral Corrugator Frank C. Murray Ph.D.; , Roman Popil Ph.D.; Michael Shaepe (formerly with IPST, now at Cargill. Inc) (2008) 141 Ammonia usage in vapor compression for refrigeration and air-conditioning in the United States

420

Most Viewed Documents - Environmental Sciences | OSTI, US Dept of Energy,  

Office of Scientific and Technical Information (OSTI)

Most Viewed Documents - Environmental Sciences Most Viewed Documents - Environmental Sciences Separation of heavy metals: Removal from industrial wastewaters and contaminated soil Peters, R.W.; Shem, L. (1993) Special Report on Emissions Scenarios : a special report of Working Group III of the Intergovernmental Panel on Climate Change Nakicenovic, Nebojsa; Alcamo, Joseph; Davis, Gerald; et al. (2000) CARBON DIOXIDE (REDUCTION) FUJITA,E. (2000) Ecological Screening Values for Surface Water, Sediment, and Soil Friday, G. P. (1999) Mitigation options for accidental releases of hazardous gases Fthenakis, V.M. (1995) Atmospheric Chemistry and Greenhouse Gases Ehhalt, D.; Prather, M.; Dentener, F.; et al. (2001) Ammonia usage in vapor compression for refrigeration and air-conditioning in the United States Fairchild, P.D.; Baxter, V.D. (1995)

Note: This page contains sample records for the topic "accident conditions view" 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

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.

422

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 ......................................................................................................................

423

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

424

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

425

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

426

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

427

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

428

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.

429

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

430

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

431

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

432

Mechanical property testing of irradiated zircaloy cladding under reactor transient conditions.  

SciTech Connect (OSTI)

Specimen geometries have been developed to determine the mechanical properties of irradiated Zircaloy cladding subjected to the mechanical conditions and temperatures associated with reactivity-initiated accidents (RIA) and loss-of-coolant accidents (LOCA). Miniature ring-stretch specimens were designed to induce both uniaxial and plane-strain states of stress in the transverse (hoop) direction of the cladding. Also, longitudinal tube specimens were also designed to determine the constitutive properties in the axial direction. Finite-element analysis (FEA) and experimental parameters and results were closely coupled to optimize an accurate determination of the stress-strain response and to induce fracture behavior representative of accident conditions. To determine the constitutive properties, a procedure was utilized to transform measured values of load and displacement to a stress-strain response under complex loading states. Additionally, methods have been developed to measure true plastic strains in the gauge section and the initiation of failure using real-time data analysis software. Strain rates and heating conditions have been selected based on their relevance to the mechanical response and temperatures of the cladding during the accidents.

Daum, R. S.; Majumdar, S.; Tsai, H.; Bray, T. S.; Billone, M. C.; Koss, D. A.; Motta, A. T.

2001-10-02T23:59:59.000Z

433

A Long View Of The Energy Market  

Science Journals Connector (OSTI)

A Long View Of The Energy Market ... Billionaire philanthropist and Microsoft Chairman Bill Gates and Nobel Prize-winning physicist and Energy Secretary Steven Chu hold similar views on the importance of finding new sources of inexpensive energy to better the plight of the world’s poor—as well as to make money. ...

JEFF JOHNSON

2012-03-19T23:59:59.000Z

434

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

435

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.

436

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, victim’s occupation, organs affected and load. Descriptive analysis was performed to compliment...

Bains, Amrit Anoop Singh

2010-10-12T23:59:59.000Z

437

User_Sup_ViewEmpMatrix  

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

an Employee Matrix (Supervisor) an Employee Matrix (Supervisor) © 2011 SuccessFactors, Inc. - 1 - SuccessFactors Learning Confidential. All rights reserved. Job Aid: Viewing an Employee Matrix (Supervisor) Purpose The purpose of this job aid is to guide supervisor users through the step-by-step process of viewing an employee matrix within SuccessFactors Learning. Task A. View an Employee Matrix From the Home page, click the My Employees tab. Click the Employee Matrix supervisor link. Click the Change Measures expand arrow ( ) to select criteria for comparison. View an Employee Matrix 8 Steps Task A 3 3 1 1 2 2 SuccessFactors Learning v 6.4 User Job Aid Viewing an Employee Matrix (Supervisor) © 2011 SuccessFactors, Inc. - 2 - SuccessFactors Learning Select a measure for the

438

Mountain View Grand | Open Energy Information  

Open Energy Info (EERE)

Grand Grand Jump to: navigation, search Name Mountain View Grand Facility Mountain View Grand Sector Wind energy Facility Type Small Scale Wind Facility Status In Service Owner Mountain View Grand Developer Sustainable Energy Developments Energy Purchaser Mountain View Grand Location Mountain View Grand Resort & Spa NH Coordinates 44.397987°, -71.590306° 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":44.397987,"lon":-71.590306,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

439

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.

440

Time dependence of the {sup 137}Cs resuspension factor on the Romanian territory after the Chernobyl accident  

SciTech Connect (OSTI)

On the basis of the radioactivity levels in aerosol and atmospheric deposition samples due to the Chernobyl accident, the resuspension factor of {sup 137}Cs as a four-parameter function has been inferred. The standard procedure to derive the dependence of resuspension on time assumes that the initial deposit is instantaneous. A simple method assuming a constant deposition rate over a fixed period has been proposed. Also, based on existing experimental data, an attempt was made to consider a realistic time dependence of the deposition rate to cope with the particular case of the Chernobyl accident. The differences between the two models are outlined. The Chernobyl direct deposit has been assumed to be the deposit measured between 30 April and 30 June 1986. The calculated values of the resuspension factor are consistent with the IAEA`s recommended model and depend on the rainfall that occurred in June 1986 and the site-specific disturbance conditions during the first 100 d following 1 July 1986 and only on artificial disturbance by humans and vehicles after that. 16 refs., 5 figs., 3 tabs.

Mihaila, B. [Institute of Environmental Research and Engineering, Bucharest (Romania); Cuculeanu, V. [National Institute of Meteorology and Hydrology, Bucharest (Romania)

1994-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "accident conditions view" 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

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

442

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

443

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

444

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

445

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

446

Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results  

SciTech Connect (OSTI)

In the ambit of the Severe Accident Network of Excellence Project (SARNET), funded by the European Union, 6. FISA (Fission Safety) Programme, one of the main tasks is the development and validation of the European Accident Source Term Evaluation Code (ASTEC Code). One of the reference codes used to compare ASTEC results, coming from experimental and Reactor Plant applications, is MELCOR. ENEA is a SARNET member and also an ASTEC and MELCOR user. During the first 18 months of this project, we performed a series of MELCOR and ASTEC calculations referring to a French PWR 900 MWe and to the accident sequence of 'Loss of Steam Generator (SG) Feedwater' (known as H2 sequence in the French classification). H2 is an accident sequence substantially equivalent to a Station Blackout scenario, like a TMLB accident, with the only difference that in H2 sequence the scram is forced to occur with a delay of 28 seconds. The main events during the accident sequence are a loss of normal and auxiliary SG feedwater (0 s), followed by a scram when the water level in SG is equal or less than 0.7 m (after 28 seconds). There is also a main coolant pumps trip when {delta}Tsat < 10 deg. C, a total opening of the three relief valves when Tric (core maximal outlet temperature) is above 603 K (330 deg. C) and accumulators isolation when primary pressure goes below 1.5 MPa (15 bar). Among many other points, it is worth noting that this was the first time that a MELCOR 1.8.5 input deck was available for a French PWR 900. The main ENEA effort in this period was devoted to prepare the MELCOR input deck using the code version v.1.8.5 (build QZ Oct 2000 with the latest patch 185003 Oct 2001). The input deck, completely new, was prepared taking into account structure, data and same conditions as those found inside ASTEC input decks. The main goal of the work presented in this paper is to put in evidence where and when MELCOR provides good enough results and why, in some cases mainly referring to its specific models (candling, corium pool behaviour, etc.) they were less good. A future work will be the preparation of an input deck for the new MELCOR 1.8.6. and to perform a code-to-code comparison with ASTEC v1.2 rev. 1. (author)

De Rosa, Felice [ENEA, Italian National Agency for New Technologies, Energy and the Environment (Italy)

2006-07-01T23:59:59.000Z

447

Landau's necessary density conditions for LCA groups  

E-Print Network [OSTI]

H. Landau's necessary density conditions for sampling and interpolation may be viewed as a general principle resting on a basic fact of Fourier analysis: The complex exponentials $e^{i kx}$ ($k$ in $\\mathbb{Z}$) constitute an orthogonal basis for $L^2([-\\pi,\\pi])$. The present paper extends Landau's conditions to the setting of locally compact abelian (LCA) groups, relying in an analogous way on the basics of Fourier analysis. The technicalities--in either case of an operator theoretic nature--are however quite different. We will base our proofs on the comparison principle of J. Ramanathan and T. Steger.

Gröchenig, K; Seip, K

2008-01-01T23:59:59.000Z

448

AP1000{sup R} severe accident features and post-Fukushima considerations  

SciTech Connect (OSTI)

The AP1000{sup R} passive nuclear power plant is uniquely equipped to withstand an extended station blackout scenario such as the events following the earthquake and tsunami at Fukushima without compromising core and containment integrity. The AP1000 plant shuts down the reactor, cools the core, containment and spent fuel pool for more than 3 days using passive systems that do not require AC or DC power or operator actions. Following this passive coping period, minimal operator actions are needed to extend the operation of the passive features to 7 days using installed equipment. To provide defense-in-depth for design extension conditions, the AP1000 plant has engineered features that mitigate the effects of core damage. Engineered features retain damaged core debris within the reactor vessel as a key feature. Other aspects of the design protect containment integrity during severe accidents, including unique features of the AP1000 design relative to passive containment cooling with water and air, and hydrogen management. (authors)

Scobel, J. H.; Schulz, T. L.; Williams, M. G. [Westinghouse Electric Company, LLC, 1000 Westinghouse Dr., Cranberry Township, PA 16066 (United States)

2012-07-01T23:59:59.000Z

449

TRACE/PARCS Core Modeling of a BWR/5 for Accident Analysis of ATWS Events  

SciTech Connect (OSTI)

The TRACE/PARCS computational package [1, 2] isdesigned to be applicable to the analysis of light water reactor operational transients and accidents where the coupling between the neutron kinetics (PARCS) and the thermal-hydraulics and thermal-mechanics (TRACE) is important. TRACE/PARCS has been assessed for itsapplicability to anticipated transients without scram(ATWS) [3]. The challenge, addressed in this study, is to develop a sufficiently rigorous input model that would be acceptable for use in ATWS analysis. Two types of ATWS events were of interest, a turbine trip and a closure of main steam isolation valves (MSIVs). In the first type, initiated by turbine trip, the concern is that the core will become unstable and large power oscillations will occur. In the second type,initiated by MSIV closure,, the concern is the amount of energy being placed into containment and the resulting emergency depressurization. Two separate TRACE/PARCS models of a BWR/5 were developed to analyze these ATWS events at MELLLA+ (maximum extended load line limit plus)operating conditions. One model [4] was used for analysis of ATWS events leading to instability (ATWS-I);the other [5] for ATWS events leading to emergency depressurization (ATWS-ED). Both models included a large portion of the nuclear steam supply system and controls, and a detailed core model, presented henceforth.

Cuadra A.; Baek J.; Cheng, L.; Aronson, A.; Diamond, D.; Yarsky, P.

2013-11-10T23:59:59.000Z

450

Reactivity initiated accident test series Test RIA 1-4 fuel behavior report. [PWR; BWR  

SciTech Connect (OSTI)

This report presents and discusses results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Nine preirradiated fuel rods in a 3 x 3 bundle configuration were subjected to a power burst while at boiling water reactor hot-startup system conditions. The test resulted in estimated axial peak, radial average fuel enthalpies of 234 cal/g UO/sub 2/ on the center rod, 255 cal/g UO/sub 2/ on the side rods, and 277 cal/g UO/sub 2/ on the corner rods. Test RIA 1-4 was conducted to investigate fuel coolability and channel blockage within a bundle of preirradiated rods near the present enthalpy limit of 280 cal/g UO/sub 2/ established by the US Nuclear Regulatory Commission. The test design and conduct are described, and the bundle and individual rod thermal and mechanical responses are evaluated. Conclusions from this final test and the entire PBF RIA Test Series are presented.

Cook, B.A.; Martinson, Z.R.

1984-09-01T23:59:59.000Z

451

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

452

Lake View Geothermal Facility | Open Energy Information  

Open Energy Info (EERE)

Page Page Edit with form History Facebook icon Twitter icon » Lake View Geothermal Facility Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Lake View Geothermal Facility General Information Name Lake View Geothermal Facility Facility Lake View Sector Geothermal energy Location Information Location The Geysers, California Coordinates 38.823527148671°, -122.78173327446° 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":38.823527148671,"lon":-122.78173327446,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

453

Berkeley Lab View -- March 28, 2008  

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

March 28th, 2008 Search the View Archive March 28th, 2008 Search the View Archive State of the Lab: New Initiatives, Construction Daniel Chemla (1940-2008): A Remembrance of His Career The View is Going Green DOE Excellence Award to Foundry Project Team Berkeley Lab View Here Comes BELLA: The BErkeley Lab Laser Acceleration Project Berkeley Lab Science Roundup State of the Lab: New Initiatives, Construction By Lynn Yarris image Photo by Roy Kaltschmidt, CSO Free electron lasers with attosecond capabilities, a high-energy electron accelerator less than a meter in length, the arrival of NERSC-6 and the departure of GELCO-4 were some of the highlights of Berkeley Lab Director Steve Chu's State-of-the-Lab address, which he delivered at the Building 50 Auditorium during the noon hour on March 10, with simulcast to the

454

JOBAID-VIEWING AN EMPLOYEE MATRIX (SUPERVISOR)  

Broader source: Energy.gov [DOE]

The purpose of this job aid is to guide supervisor users through the step-by-step process of viewing an employee matrix within SuccessFactors Learning.

455

Incorporating video into Google Mobile Street View  

E-Print Network [OSTI]

Mobile Street View is a compelling application but suffers from significant latency problems, especially in limited bandwidth circumstances. Currently, the application uses static images to display street level information. ...

Wright, Christina (Christina E.)

2010-01-01T23:59:59.000Z

456

1,425 Views Healthcare Technology  

E-Print Network [OSTI]

Molecules into Targeted Cells (/healthtech/1863- nanotechnology/6022- researchers;NANOTECHNOLOGY (/HEALTHTECH/1863-NANOTECHNOLOGY) May 22, 2013 View Comments (/healthtech/1863-nanotechnology/6022, diagnostics, and drug delivery toward the promise of personalized medicine." A paper describing the research

Espinosa, Horacio D.

457

Lab Breakthrough: Desiccant Enhanced Evaporative Air Conditioning |  

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

Desiccant Enhanced Evaporative Air Conditioning Desiccant Enhanced Evaporative Air Conditioning Lab Breakthrough: Desiccant Enhanced Evaporative Air Conditioning May 29, 2012 - 5:22pm Addthis This breakthrough combines desiccant materials, which remove moisture from the air using heat, and advanced evaporative technologies to develop a cooling unit that uses 90 percent less electricity and up to 80 percent less total energy than traditional air conditioning. This solution, called the desiccant enhanced evaporative air conditioner (DEVAP), also controls humidity more effectively to improve the comfort of people in buildings. View the entire Lab Breakthrough playlist. What are the key facts? Recent materials advances and liquid desiccant advances to design the compact and cost-effective DEVAP system. DEVAP uses 90 percent less electricity and up to 80 percent less

458

Lab Breakthrough: Desiccant Enhanced Evaporative Air Conditioning |  

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

Lab Breakthrough: Desiccant Enhanced Evaporative Air Conditioning Lab Breakthrough: Desiccant Enhanced Evaporative Air Conditioning Lab Breakthrough: Desiccant Enhanced Evaporative Air Conditioning May 29, 2012 - 5:22pm Addthis This breakthrough combines desiccant materials, which remove moisture from the air using heat, and advanced evaporative technologies to develop a cooling unit that uses 90 percent less electricity and up to 80 percent less total energy than traditional air conditioning. This solution, called the desiccant enhanced evaporative air conditioner (DEVAP), also controls humidity more effectively to improve the comfort of people in buildings. View the entire Lab Breakthrough playlist. What are the key facts? Recent materials advances and liquid desiccant advances to design the compact and cost-effective DEVAP system.

459

Jefferson and Hamilton as viewed by historians  

E-Print Network [OSTI]

JEFFERSON AND HAMILTON AS VIEHED BY HISTORIANS A Thesis Paul Edward Jungmeyer Submitted to the Graduate College of Texas A&M University in ' partial fulfillment of the requirement for the degree of MASTER OF ARTS August, 1970 Major Subject...: History JEFFERSON AND HAMILTON AS VIEWED BY HISTORIANS A Thesis by Paul Edward Jungmeyer Approved as to style and content by: (Chairman of Committee d i~) (Member) (M er) August, 1970 ABSTRACT JEFFERSON AND HAMILTON AS VIEWED BY HISTORIANS...

Jungmeyer, Paul Edward

2012-06-07T23:59:59.000Z

460

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-

Note: This page contains sample records for the topic "accident conditions view" 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

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

462

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

463

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

464

Natural convection phenomena in a nuclear power plant during a postulated TMLB' accident  

SciTech Connect (OSTI)

After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and understanding the phenomena that may occur in a PWR (Pressurized Water Reactor) accident which may lead to partial or total core meltdown and degradation. Natural convection is one of the important phenomena. In the present paper the results of two numerical simulations of (1) four-loop PWR and (2) three-loop PWR are presented. The simulations were performed with the COMMIX(2) computer code. Our analysis shows that in severe accident scenarios, natural convection phenomena does occur and that it helps to delay core degradation by transferring decay heat from the reactor core to other internal structures of the reactor system. The amount of heat transfer and delay in core degradation depends on the geometry and internal structures of the system and on the events of an accident.

Domanus, H.M.; Schmitt, R.C.; Sha, W.T.; Shah, V.L.; Han, J.T.

1987-01-01T23:59:59.000Z

465

The Adequacy of DOE Natural Phenomena Hazards Performance Goals from an Accident Analysis Perspective  

Broader source: Energy.gov [DOE]

The Adequacy of DOE Natural Phenomena Hazards Performance Goals from an Accident Analysis Perspective Jeff Kimball Defense Nuclear Facilities Safety Board Staff Department of Energy NPH Conference October 26, 2011

466

LOA-1: prevent accidents. Quarterly technical progress report, FRSP program - July through September 1981. [LMFBR  

SciTech Connect (OSTI)

Information related to LMFBR reactor safety is presented concerning common cause failures; shutdown by self-activated system; shutdown heat removal system operation; sodium burning; core catcher material interactions; accident release of sodium oxide aerosol; and LMFBR risk assessment.

Not Available

1981-01-01T23:59:59.000Z

467

E-Print Network 3.0 - accident progression event Sample Search...  

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

Computer Technologies and Information Sciences ; Biology and Medicine 20 34.02.99.M2.01 Post-Accident Testing Instructions Page 1 of 3 STANDARD ADMINISTRATIVE PROCEDURE Summary:...

468

Research on the Forecasting of Construction Accidents with the Cubic Exponential Smoothing Method  

Science Journals Connector (OSTI)

Construction accidents occur frequently and cause great loss to construction enterprises, the whole industry and the society. Therefore, it is significant to forecast the death tolls of construction engineering a...

Chao He; Xiaoli Yan; Yilang Huang

2014-01-01T23:59:59.000Z

469

E-Print Network 3.0 - accident rates Sample Search Results  

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

limiting the egress rate and causing a pile... increases. No Accidents - Effect of Penetration Rate 0 0.5 1 1.5 2 2.5 3 5 10 15 20 25 30 35 40 50 60 80 100... :...

470

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...

471

Episode Analysis of Deposition of Radiocesium from the Fukushima Daiichi Nuclear Power Plant Accident  

Science Journals Connector (OSTI)

Episode Analysis of Deposition of Radiocesium from the Fukushima Daiichi Nuclear Power Plant Accident ... Center for Regional Environment Research, National Institute for Environmental Studies, 16-2, Onogawa, Tsukuba, Ibaraki, 305-8506, Japan ...

Yu Morino; Toshimasa Ohara; Mirai Watanabe; Seiji Hayashi; Masato Nishizawa

2013-02-07T23:59:59.000Z

472

E-Print Network 3.0 - accidents du travail Sample Search Results  

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

tel... avril 2002 en l'tendant aux accidents du travail (Cass.Soc 110402, Hachadi cCamus industrie et autre... 'conomie et sociologie du ... Source: Ecole Polytechnique,...

473

E-Print Network 3.0 - accident du travail Sample Search Results  

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

tel... avril 2002 en l'tendant aux accidents du travail (Cass.Soc 110402, Hachadi cCamus industrie et autre... 'conomie et sociologie du ... Source: Ecole Polytechnique,...

474

Effect of helium injection on diffusion dominated air ingress accidents in pebble bed reactors  

E-Print Network [OSTI]

The primary objective of this thesis was to validate the sustained counter air diffusion (SCAD) method at preventing natural circulation onset in diffusion dominated air ingress accidents. The analysis presented in this ...

Yurko, Joseph Paul

2010-01-01T23:59:59.000Z

475

E-Print Network 3.0 - accident risk assessment Sample Search...  

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

and Medicine 3 An Internet-based, Searchable Database of Air Accidents N. Storey, B.Sc., Ph.D., FBCS, MIEE, C.Eng.; University of Warwick, Coventry, UK Summary: An...

476

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

477

Level 1 Accident Report of the March 1, 2010 Bobcat Fatality...  

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

Report of the March 1, 2010 Bobcat Fatality at BPA's White Bluffs Substation Level 1 Accident Report of the March 1, 2010 Bobcat Fatality at BPA's White Bluffs Substation March 31,...

478

E-Print Network 3.0 - aircraft accident cases 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: for Aeronautics (N.A.C.A.) to develop a common approach for the analysis and...

479

E-Print Network 3.0 - aircraft accidents 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: for Aeronautics (N.A.C.A.) to develop a common approach for the analysis and...

480

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

Note: This page contains sample records for the topic "accident conditions view" 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

Type B Accident Investigation Board Report on the July 25, 1997...  

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

July 25, 1997, Contract Brush Cutter Injury on the Ashe-Marion 2 500 kV Line Type B Accident Investigation Board Report on the July 25, 1997, Contract Brush Cutter Injury on the...

482

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

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

> >> Page: << < 1 2 3 4 5 > >> 41 Risk factors for injury accidents among moped and motorcycle riders Summary: hal-00543304,version1-6Dec2010 Author manuscript, published in...

483

Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Tests 1 and 2  

SciTech Connect (OSTI)

A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects of LOCA conditions on pressurized water reactor test fuel bundles. This experiment operation plan for the second and third experiments of the program will provide peak fuel cladding temperatures of up to 1172K (1650{degree}F) and 1061K (1450{degree}) respectively. for a long enough time to cause test fuel cladding deformation and rupture in both. Reflood coolant delay times and the reflooding rates for the experiments were selected from thermal-hydraulic data measured in the National Research Universal (NRU) reactor facilities and test train assembly during the first experiment.

Russcher, G. E.; Wilson, C. L.; Marshall, R, K.; King, L. L.; Parchen, L. J.; Pilger, J. P.; Hesson, G. M.; Mohr, C. L.

1981-09-01T23:59:59.000Z

484

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

485

Design consistency and driver error as reflected by driver workload and accident rates  

E-Print Network [OSTI]

DESIGN CONSISTENCY AND DRIVER ERROR AS REFLECTED BY DRIVER WORKLOAD AND ACCIDENT RATES A Thesis by MARK DOUGLAS WOOLDRIDGE Approved as to style and content by: Daniel B. Fambro (Chair of Committee) Raymond A. Krammes (Member) Olga J.... Pendleton (Member) James T. P. Yao (Head of Department) May 1992 ABSTRACT Design Consistency and Driver Error as Reflected by Driver Workload and Accident Rates (May 1992) Mark Douglas Wooldridge, B. S. , Texas A&M University Chair of Advisory...

Wooldridge, Mark Douglas

2012-06-07T23:59:59.000Z

486

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

487

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

488

Relating geometric design consistency and accident experience on two-lane rural highways  

E-Print Network [OSTI]

and accident experience on two-lane rural highways. Safety, operational, and driver behavioral studies were reviewed and compared to the concepts of the Messer procedure and other design consistency studies. This was done to critically evaluate the Messer... and one-half years of data. A variable called the effective workload value EWL derived from the Messer procedure was established as the measure of consistency used for analysis. The effective workload value and accident experience were used as input...

Glascock, Stephen Wade

2012-06-07T23:59:59.000Z

489

An accident analysis of the physical plant of the Agricultural and Mechanical College of Texas  

E-Print Network [OSTI]

AN ACCIDENT ANALYSIS OF THE PHYSICAL PLANT OF 'THE AGRICULTURAL AN9 ~CHANICAL COLLEGE OF TEXAS A Thesis Sy Gary James Allen Approved as to style and content by: airman of Comrntttee) H of epartxnent or Stu e t A vis r) August 1963... AN ACCIDENT ANALYSIS OF THE PHYSICAL PLANT DEPARTMENT OF THE AGRICULTURAL AND MECHANICAL COLLEGE OF TEXAS A Thesis Gary James Allen Submitted to the Graduate School of the Agricultural and Mechanical College of Teaas in partial fulfillment...

Allen, Gary James

2012-06-07T23:59:59.000Z

490

Better Buildings Network View | January 2014 | Department of...  

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

January 2014 Better Buildings Network View | January 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

491

Better Buildings Network View | March 2014 | Department of Energy  

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

March 2014 Better Buildings Network View | March 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

492

Better Buildings Network View | May 2014 | Department of Energy  

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

May 2014 Better Buildings Network View | May 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network....

493

Better Buildings Network View | September 2014 | Department of...  

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

September 2014 Better Buildings Network View | September 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

494

Better Buildings Network View | February 2014 | Department of...  

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

February 2014 Better Buildings Network View | February 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

495

Better Buildings Network View | June 2014 | Department of Energy  

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

June 2014 Better Buildings Network View | June 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network....

496

88 PART 2 LANDSCAPE DESIGN GUIDELINES AND PRECINCT PLANS View of Bailey Plaza looking North  

E-Print Network [OSTI]

of the future parcel north of Bailey Hall could become an important public space with long unobstructed views vistas from the Ag Quad to the west, restoring the original condition of this important space and its ANDREW DICKSON WHITE HOUSE FARRAND GARDEN BIG RED BARN KROCH LIBRARY OLIN LIBRARY SAGE CHAPEL DAY HALL

Keinan, Alon

497

Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions  

Science Journals Connector (OSTI)

Abstract The series of single rod tests was performed at KIT in framework of the new QUENCH-LOCA programme to investigate the properties of Zircaloy-4 claddings hydrogenated at temperatures of 900, 1000, 1100, and 1200 K to hydrogen contents between 600 and 10,000 wppm H. The impact of simultaneous annealing, phase transformation and hydriding processes on the material properties was investigated. Changes in microhardness revealed the distinct transition from annealing softening to hydrogen hardening. The intermediate stages of structure transformation during hydrogenation phase were registered. The X-ray diffractometry (XRD) analysis was applied to observe the existing phases in the tested samples including possibly precipitated hydrides as well as change in the lattice parameters a and c. The presence of ?- and ?-hydrides was clearly indicated by this method; however the dimensions of hydrides correspond rather to the nano-scale and could not be observed by optical microscopy. The evolution of XRD peak intensities and peak shift was analysed to estimate the texture change and concentration of dissolved hydrogen correspondingly. Tensile test examination of tube samples at room temperatures showed significant reduction of their residual ductility already at 700 wppm H.

Anton Pshenichnikov; Juri Stuckert; Mario Walter

2014-01-01T23:59:59.000Z

498

Valley View Wind Farm | Open Energy Information  

Open Energy Info (EERE)

Wind Farm Wind Farm Jump to: navigation, search Name Valley View Wind Farm Facility Valley View Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Juhl Wind Developer Valley View Transmission Energy Purchaser Xcel Energy Location Outside Chandler MN Coordinates 43.905808°, -96.020508° 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":43.905808,"lon":-96.020508,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

499

Business Apps List View | Data.gov  

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

Apps List View Apps List View BusinessUSA Data/Tools Apps Challenges Let's Talk BusinessUSA You are here Data.gov » Communities » BusinessUSA List View Showing 1 - 12 of 12 results. Resources sort ascending Type Last Updated On Traveling Entrepreneur Find green government opportunities for small businesses. The app based on your current location retrieves all the government programs and then allows you to share your favorite program on Facebook. Mobile 02/01/2012 Small Business Toolkit Small Business Toolbox provides a way to easily keep up-to-date on government programs, grants, awards, solicitations, and small business programs. Find the closest SBA district office, easily gathering license and permit information. Mobile 01/31/2012 SBIR.gov Awards Search This app allows users to search the SBIR awards database by agency, keyword, and year.

500

Toto the Robot Figure 1. Toto, front view. Figure 2. Toto, rear view.  

E-Print Network [OSTI]

Toto the Robot Figure 1. Toto, front view. Figure 2. Toto, rear view. Toto the Robot was created so in the back to allow the tape- recorder to be held inside, and the figure was spray-painted. With his metallic a robot, helps account for his lack of verbal charm. Second, some younger children may recognize in Toto

Indiana University