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Note: This page contains sample records for the topic "leaks damage accidents" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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1

Type B Accident Investigation of the Mineral Oil Leak Discovered on January 8, 2001, Resulting in Property Damage at the Atlas Facility, Los Alamos National Laboratory  

Broader source: Energy.gov [DOE]

This report is an independent product of the Type B Accident Investigation Board appointed by Acting Chief Operating Officer for Defense Programs, Ralph E. Erickson.

2

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

3

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

4

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

5

Analysis of potential for jet-impingement erosion from leaking steam generator tubes during severe accidents.  

SciTech Connect (OSTI)

This report summarizes analytical evaluation of crack-opening areas and leak rates of superheated steam through flaws in steam generator tubes and erosion of neighboring tubes due to jet impingement of superheated steam with entrained particles from core debris created during severe accidents. An analytical model for calculating crack-opening area as a function of time and temperature was validated with tests on tubes with machined flaws. A three-dimensional computational fluid dynamics code was used to calculate the jet velocity impinging on neighboring tubes as a function of tube spacing and crack-opening area. Erosion tests were conducted in a high-temperature, high-velocity erosion rig at the University of Cincinnati, using micrometer-sized nickel particles mixed in with high-temperature gas from a burner. The erosion results, together with analytical models, were used to estimate the erosive effects of superheated steam with entrained aerosols from the core during severe accidents.

Majumdar, S.; Diercks, D. R.; Shack, W. J.; Energy Technology

2002-05-01T23:59:59.000Z

6

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

SciTech Connect (OSTI)

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

POLIZZI, LM

2004-04-28T23:59:59.000Z

7

Guidelines for Setting up a Reflux Condenser Water leaks from a reflux condenser can destroy years of research data and cause thousands of dollars of damage to  

E-Print Network [OSTI]

Guidelines for Setting up a Reflux Condenser Water leaks from a reflux condenser can destroy years. To help prevent this common accident, wire or clamp all hose connections, secure the condenser outlet tubes into the inlet and outlet of the condenser. After fitting the tubes into the condenser (a

Brody, James P.

8

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

9

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

10

Precursors to potential severe core damage accidents: 1994, a status report. Volume 22: Appendix I  

SciTech Connect (OSTI)

Nine operational events that affected eleven commercial light-water reactors (LWRs) during 1994 and that are considered to be precursors to potential severe core damage are described. All these events had conditional probabilities of subsequent severe core damage greater than or equal to 1.0 {times} 10{sup {minus}6}. These events were identified by computer-screening the 1994 licensee event reports from commercial LWRs to identify those that could be potential precursors. Candidate precursors were then selected and evaluated in a process similar to that used in previous assessments. Selected events underwent engineering evaluation that identified, analyzed, and documented the precursors. Other events designated by the Nuclear Regulatory Commission (NRC) also underwent a similar evaluation. Finally, documented precursors were submitted for review by licensees and NRC headquarters and regional offices to ensure that the plant design and its response to the precursor were correctly characterized. This study is a continuation of earlier work, which evaluated 1969--1981 and 1984--1993 events. The report discusses the general rationale for this study, the selection and documentation of events as precursors, and the estimation of conditional probabilities of subsequent severe core damage for events. This document is bound in two volumes: Vol. 21 contains the main report and Appendices A--H; Vol. 22 contains Appendix 1.

Belles, R.J.; Cletcher, J.W.; Copinger, D.A.; Vanden Heuvel, L.N. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States); Dolan, B.W.; Minarick, J.W. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States); [Science Applications International Corp., Oak Ridge, TN (United States)

1995-12-01T23:59:59.000Z

11

Best Management Practice: Distribution System Audits, Leak Detection, and  

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

Best Management Practice: Distribution System Audits, Leak Best Management Practice: Distribution System Audits, Leak Detection, and Repair Best Management Practice: Distribution System Audits, Leak Detection, and Repair October 7, 2013 - 3:06pm Addthis A distribution system audit, leak detection, and repair programs help Federal facilities reduce water losses and make better use of limited water resources. Overview Federal facilities with large campus settings and expansive distribution systems can lose a significant amount of total water production and purchases to system leaks. Leaks in distribution systems are caused by a number of factors, including pipe corrosion, high system pressure, construction disturbances, frost damage, damaged joints, and ground shifting and settling. Regular distribution system leak detection surveys

12

Minimize Compressed Air Leaks  

Broader source: Energy.gov [DOE]

This tip sheet outlines a strategy for compressed air leak detection and provides a formula for cost savings calculations.

13

Design and fabrication of a maneuverable robot for in-pipe leak detection  

E-Print Network [OSTI]

Leaks in pipelines have been causing a significant amount of financial losses and serious damages to the community and the environment. The recent development of in-pipe leak detection technologies at Massachusetts Institute ...

Wu, You, S.M. Massachusetts Institute of Technology

2014-01-01T23:59:59.000Z

14

Natural Gas Pipeline Leaks Across Washington, DC Robert B. Jackson,,,  

E-Print Network [OSTI]

Natural Gas Pipeline Leaks Across Washington, DC Robert B. Jackson,,, * Adrian Down, Nathan G increased in recent decades, but incidents involving natural gas pipelines still cause an average of 17 fatalities and $133 M in property damage annually. Natural gas leaks are also the largest anthropogenic

Jackson, Robert B.

15

Improved gaseous leak detector  

DOE Patents [OSTI]

In a short path length mass-spectrometer type of helium leak detector wherein the helium trace gas is ionized, accelerated and deflected onto a particle counter, an arrangement is provided for converting the detector to neon leak detection. The magnetic field of the deflection system is lowered so as to bring the nonlinear fringe area of the magnetic field across the ion path, thereby increasing the amount of deflection of the heavier neon ions.

Juravic, F.E. Jr.

1983-10-06T23:59:59.000Z

16

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices A--D. Volume 2, Part 2  

SciTech Connect (OSTI)

During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the Potential risks during low Power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the Plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful. This document, Volume 2, Pt. 2 provides appendices A through D of this report.

Chu, T.L.; Musicki, Z.; Kohut, P. [Brookhaven National Lab., Upton, NY (United States)] [and others

1994-06-01T23:59:59.000Z

17

Reducing Your Leak Rate Without Repairing Leaks  

E-Print Network [OSTI]

out of a thirteen-minute cycle, which meant they sat idle 76.9 percent of the time. We decided to divide the pneumatic circuit on each machine into two circuits, install an automatic solenoid valve, and program the PLC to shut the air off.... In this case, we decided to install an automatic solenoid valve at each position, and program the PLC to shut the air off to the position when it wasn?t operating. This reduced the leak rate by approximately 1100 scfm from 1500 scfm to 400 scfm. ...

Beals, C.

2005-01-01T23:59:59.000Z

18

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix I, Volume 2, Part 5  

SciTech Connect (OSTI)

Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Lab. (BNL) and Sandia National Labs. (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this volume of the report is to document the approach utilized in the level-1 internal events PRA for the Surry plant, and discuss the results obtained. A phased approach was used in the level-1 program. In phase 1, which was completed in Fall 1991, a coarse screening analysis examining accidents initiated by internal events (including internal fire and flood) was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis.

Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J. [Brookhaven National Lab., Upton, NY (United States); Bley, D.; Johnson, D. [PLG Inc., Newport Beach, CA (United States); Holmes, B. [AEA Technology, Dorset (United Kingdom)] [and others

1994-06-01T23:59:59.000Z

19

Natural Gas Pipeline Leaks Across Washington, DC  

Science Journals Connector (OSTI)

Pipeline safety in the United States has increased in recent decades, but incidents involving natural gas pipelines still cause an average of 17 fatalities and $133 M in property damage annually. ... Along with reducing greenhouse gas emissions, repairing production and pipeline leaks would improve consumer health and safety and save money. ... (37) Several barriers to pipeline repair and replacement exist, however, as cost recovery for pipeline repairs by distribution companies is often capped by Public Utility Commissions (PUCs). ...

Robert B. Jackson; Adrian Down; Nathan G. Phillips; Robert C. Ackley; Charles W. Cook; Desiree L. Plata; Kaiguang Zhao

2014-01-16T23:59:59.000Z

20

SEALING SIMULATED LEAKS  

SciTech Connect (OSTI)

This report details the testing equipment, procedures and results performed under Task 7.2 Sealing Simulated Leaks. In terms of our ability to seal leaks identified in the technical topical report, Analysis of Current Field Data, we were 100% successful. In regards to maintaining seal integrity after pigging operations we achieved varying degrees of success. Internal Corrosion defects proved to be the most resistant to the effects of pigging while External Corrosion proved to be the least resistant. Overall, with limitations, pressure activated sealant technology would be a viable option under the right circumstances.

Michael A. Romano

2004-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

Rapid communication Mapping urban pipeline leaks: Methane leaks across Boston  

E-Print Network [OSTI]

Rapid communication Mapping urban pipeline leaks: Methane leaks across Boston Nathan G. Phillips a of methane (CH4) in the United States. To assess pipeline emissions across a major city, we mapped CH4 leaks signatures w20& lighter (m ¼ ?57.8&, ?1.6& s.e., n ¼ 8). Repairing leaky natural gas distribution systems

Jackson, Robert B.

22

Air Leaks in Unexpected Places  

Broader source: Energy.gov [DOE]

Sealing air leaks will help to decrease heating and cooling costs and make your home more comfortable.

23

Reducing Leaking Electricity  

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

4 4 Reducing Leaking Electricity Figure 1. Full and standby power draws of some compact audio systems. A surprisingly large number of appliances-from computer peripherals to cable TV boxes to radios-consume electricity even after they have been switched off. Other appliances, such as cordless telephones, remote garage door openers, and battery chargers don't get switched off but draw power even when they are not performing their principal functions. The energy used while the appliance is switched off or not performing its primary purpose is called "standby consumption" or "leaking electricity." This consumption allows TVs, VCRs and garage-door openers to be ready for instant-on with a remote control, microwave ovens to display a digital

24

Natural gas leak mapper  

DOE Patents [OSTI]

A system is described that is suitable for use in determining the location of leaks of gases having a background concentration. The system is a point-wise backscatter absorption gas measurement system that measures absorption and distance to each point of an image. The absorption measurement provides an indication of the total amount of a gas of interest, and the distance provides an estimate of the background concentration of gas. The distance is measured from the time-of-flight of laser pulse that is generated along with the absorption measurement light. The measurements are formated into an image of the presence of gas in excess of the background. Alternatively, an image of the scene is superimosed on the image of the gas to aid in locating leaks. By further modeling excess gas as a plume having a known concentration profile, the present system provides an estimate of the maximum concentration of the gas of interest.

Reichardt, Thomas A. (Livermore, CA); Luong, Amy Khai (Dublin, CA); Kulp, Thomas J. (Livermore, CA); Devdas, Sanjay (Albany, CA)

2008-05-20T23:59:59.000Z

25

Aspects of leak detection  

SciTech Connect (OSTI)

A requirement of a Leak before Break safety case is that the leakage from the through wall crack be detected prior to any growth leading to unacceptable failure. This paper sets out to review some recent developments in this field. It does not set out to be a comprehensive guide to all of the methods available. The discussion concentrates on acoustic emission and how the techniques can be qualified and deployed on operational plant.

Chivers, T.C. [Berkeley Technology Centre, Glos (United Kingdom)

1997-04-01T23:59:59.000Z

26

A regional simulation study on dispersion of nuclear pollution from the damaged Fukushima Nuclear Power Plant  

Science Journals Connector (OSTI)

A nuclear accident involving the leaking of radioactive pollutants occurred at the Fukushima Nuclear Power Plant in Japan, following an earthquake and subsequent tsunami on ... accident, this study simulates the ...

JianFang Fei; PengFei Wang; XiaoPing Cheng; XiaoGang Huang

2014-07-01T23:59:59.000Z

27

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1. Volume 5: Analysis of core damage frequency from seismic events during mid-loop operations  

SciTech Connect (OSTI)

In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1) and the other at Sandia National Laboratories studying a boiling water reactor (Grand Gulf). Both the Brookhaven and Sandia projects have examined only accidents initiated by internal plant faults--so-called ``internal initiators.`` This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling shutdown conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Surry Unit 1. All of the many systems modeling assumptions, component non-seismic failure rates, and human error rates that were used in the internal-initiator study at Surry have been adopted here, so that the results of the two studies can be as comparable as possible. Both the Brookhaven study and this study examine only two shutdown plant operating states (POSs) during refueling outages at Surry, called POS 6 and POS 10, which represent mid-loop operation before and after refueling, respectively. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POSs 6 and 10. The results of the analysis are that the core-damage frequency of earthquake-initiated accidents during refueling outages in POS 6 and POS 10 is found to be low in absolute terms, less than 10{sup {minus}6}/year.

Budnitz, R.J. [Future Resources Associates, Inc., Berkeley, CA (United States); Davis, P.R. [PRD Consulting (United States); Ravindra, M.K.; Tong, W.H. [EQE International, Inc., Irvine, CA (United States)

1994-08-01T23:59:59.000Z

28

Modeling and analysis framework for core damage propagation during flow-blockage-initiated accidents in the Advanced Neutron Source reactor at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

This paper describes modeling and analysis to evaluate the extent of core damage during flow blockage events in the Advanced Neutron Source (ANS) reactor planned to be built at ORNL. Damage propagation is postulated to occur from thermal conduction between dmaged and undamaged plates due to direct thermal contact. Such direct thermal contact may occur beause of fuel plate swelling during fission product vapor release or plate buckling. Complex phenomena of damage propagation were modeled using a one-dimensional heat transfer model. A parametric study was done for several uncertain variables. The study included investigating effects of plate contact area, convective heat transfer coefficient, thermal conductivity on fuel swelling, and initial temperature of the plate being contacted by the damaged plate. Also, the side support plates were modeled to account for their effects of damage propagation. Results provide useful insights into how variouss uncertain parameters affect damage propagation.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

1995-12-31T23:59:59.000Z

29

Tips: Sealing Air Leaks | Department of Energy  

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

Sealing Air Leaks Sealing Air Leaks Tips: Sealing Air Leaks May 16, 2013 - 5:03pm Addthis Sources of Air Leaks in Your Home. Areas that leak air into and out of your home cost you a lot of money. The areas listed in the illustration are the most common sources of air leaks. Sources of Air Leaks in Your Home. Areas that leak air into and out of your home cost you a lot of money. The areas listed in the illustration are the most common sources of air leaks. Air leaks can waste a lot of your energy dollars. One of the quickest energy-- and money-saving tasks you can do is caulk, seal, and weather strip all seams, cracks, and openings to the outside. Tips for Sealing Air Leaks Test your home for air tightness. On a windy day, carefully hold a lit incense stick or a smoke pen next to your windows, doors, electrical

30

Tips: Sealing Air Leaks | Department of Energy  

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

Tips: Sealing Air Leaks Tips: Sealing Air Leaks Tips: Sealing Air Leaks May 16, 2013 - 5:03pm Addthis Sources of Air Leaks in Your Home. Areas that leak air into and out of your home cost you a lot of money. The areas listed in the illustration are the most common sources of air leaks. Sources of Air Leaks in Your Home. Areas that leak air into and out of your home cost you a lot of money. The areas listed in the illustration are the most common sources of air leaks. Air leaks can waste a lot of your energy dollars. One of the quickest energy-- and money-saving tasks you can do is caulk, seal, and weather strip all seams, cracks, and openings to the outside. Tips for Sealing Air Leaks Test your home for air tightness. On a windy day, carefully hold a lit incense stick or a smoke pen next to your windows, doors, electrical

31

Modeling and analysis framework for core damage propagation during flow-blockage-initiated accidents in the Advanced Neutron Source Reactor at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

This paper describes modeling and analysis to evaluate the extent of core damage during flow blockage events in the Advanced Neutron Source (ANS) reactor planned to be built at the Oak Ridge National Laboratory (ORNL). Damage propagation is postulated to occur from thermal conduction between damaged and undamaged plates due to direct thermal contact. Such direct thermal contact may occur because of fuel plate swelling during fission product vapor release or plate buckling. Complex phenomena of damage propagation were modeled using a one-dimensional heat transfer model. A scoping study was conducted to learn what parameters are important for core damage propagation, and to obtain initial estimates of core melt mass for addressing recriticality and steam explosion events. The study included investigating the effects of the plate contact area, the convective heat transfer coefficient, thermal conductivity upon fuel swelling, and the initial temperature of the plate being contacted by the damaged plate. Also, the side support plates were modeled to account for their effects on damage propagation. The results provide useful insights into how various uncertain parameters affect damage propagation.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

1995-09-01T23:59:59.000Z

32

Investigating leaking underground storage tanks  

E-Print Network [OSTI]

INVESTIGATING LEAKING UNDERGROUND STORAGE TANKS A Thesis by DAVID THOMPSON UPTON 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 August 1989... Major Subject: Geology INVESTIGATING LEAKING UNDERGROUND STORAGE TANKS A Thesis by DAVID THOMPSON UPTON Approved as to sty)e and content by: P. A, Domenico (Chair of Committee) jj K. W. Brown (Member) C. C Mathewson (Member) J. H. S ng Head...

Upton, David Thompson

1989-01-01T23:59:59.000Z

33

Leak test adapter for containers  

DOE Patents [OSTI]

An adapter is provided for facilitating the charging of containers and leak testing penetration areas. The adapter comprises an adapter body and stem which are secured to the container's penetration areas. The container is then pressurized with a tracer gas. Manipulating the adapter stem installs a penetration plug allowing the adapter to be removed and the penetration to be leak tested with a mass spectrometer. Additionally, a method is provided for using the adapter.

Hallett, Brian H. (Elizabeth, PA); Hartley, Michael S. (Canonsburg, PA)

1996-01-01T23:59:59.000Z

34

Precursors to potential severe core damage accidents: 1992, a status report; Volume 18: Appendices B, C, D, E, F, and G  

SciTech Connect (OSTI)

This document is part of a report which documents 1992 operational events selected as accident sequence precursors. This report describes the 27 precursors identified from the 1992 licensee event reports. It also describe containment-related events; {open_quote}interesting{close_quote} events; potentially significant events that were considered impractical to analyze; copies of the licensee event reports which were cited in the cases above; and comments from the licensee and NRC in response to the preliminary reports.

NONE

1993-12-01T23:59:59.000Z

35

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

36

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.

37

Candu 6 severe core damage accident consequence analysis for steam generator tube rupture scenario using MAAP4-CANDU V4.0.5A: preliminary results  

SciTech Connect (OSTI)

This paper describes the preliminary results of the consequence analysis for a generic AECL CANDU 6 station, when it undergoes a postulated, low probability Steam Generator multiple Tube Rupture (SGTR) severe accident with assumed unavailability of several critical plant safety systems. The Modular Accident Analysis Program for CANDU (MAAP4-CANDU) code was used for this analysis. The SGTR accident is assumed to begin with the guillotine rupture of 10 steam generator tubes in one steam generator in Primary Heat Transport System (PHTS) loop 1. For the reference case, the following systems were assumed unavailable: moderator and shield cooling, emergency core cooling, crash cool-down, and main and auxiliary feed water. Two additional cases were analyzed, one with the crash cool-down system available, and another with the crash cool-down and the auxiliary feed water systems available. The three scenarios considered in this study show that most of the initial fission product inventory would be retained within the containment by various fission product retention mechanisms. For the case where the crash cool-down system was credited but the auxiliary feed water systems were not credited, the total mass of volatile fission products released to the environment including stable and radioactive isotopes was about four times more than in the reference case, because fission products could be released directly from the PHTS to the environment through the Main Steam Safety Valves (MSSVs), bypassing the containment. For the case where the crash cool-down and auxiliary feed water systems were credited, the volatile fission product release to the environment was insignificant, because the fission product release was substantially mitigated by scrubbing in the water pool in the secondary side of the steam generator (SG). (authors)

Petoukhov, S.M.; Awadh, B.; Mathew, P.M. [Chalk River Laboratories, Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2006-07-01T23:59:59.000Z

38

High sensitivity leak detection method and apparatus  

DOE Patents [OSTI]

An improved leak detection method is provided that utilizes the cyclic adsorption and desorption of accumulated helium on a non-porous metallic surface. The method provides reliable leak detection at superfluid helium temperatures. The zero drift that is associated with residual gas analyzers in common leak detectors is virtually eliminated by utilizing a time integration technique. The sensitivity of the apparatus of this disclosure is capable of detecting leaks as small as 1.times.10.sup.-18 atm cc sec.sup.-1.

Myneni, Ganapatic R. (Grafton, VA)

1994-01-01T23:59:59.000Z

39

High sensitivity leak detection method and apparatus  

DOE Patents [OSTI]

An improved leak detection method is provided that utilizes the cyclic adsorption and desorption of accumulated helium on a non-porous metallic surface. The method provides reliable leak detection at superfluid helium temperatures. The zero drift that is associated with residual gas analyzers in common leak detectors is virtually eliminated by utilizing a time integration technique. The sensitivity of the apparatus of this disclosure is capable of detecting leaks as small as 1 [times] 10[sup [minus]18] atm cc sec[sup [minus]1]. 2 figs.

Myneni, G.R.

1994-09-06T23:59:59.000Z

40

Leak detection on an ethylene pipeline  

SciTech Connect (OSTI)

A model-based leak detection system has been in operation on the Solvay et Cie ethylene pipeline from Antwerp to Jemeppe on Sambre since 1989. The leak detection system, which is the commercial product PLDS of Modisette Associations, Inc., was originally installed by the supplier. Since 1991, all system maintenance and configuration changes have been done by Solvay et Cie personnel. Many leak tests have been performed, and adjustments have been made in the configuration and the automatic tuning parameters. The leak detection system is currently able to detect leaks of 2 tonnes/hour in 11 minutes with accurate location. Larger leaks are detected in about 2 minutes. Leaks between 0.5 and 1 tonne per hour are detected after several hours. (The nominal mass flow in the pipeline is 15 tonnes/hour, with large fluctuations.) Leaks smaller than 0.5 tonnes per hour are not detected, with the alarm thresholds set at levels to avoid false alarms. The major inaccuracies of the leak detection system appear to be associated with the ethylene temperatures.

Hamande, A.; Condacse, V.; Modisette, J.

1995-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

A Cost Benefit Analysis of California's Leaking Underground Fuel Tanks  

E-Print Network [OSTI]

s Leaking Underground Fuel Tanks (LUFTs). Submitted to theCalifornias Underground Storage Tank Program. Submitted tos Leaking Underground Fuel Tanks by Samantha Carrington

Carrington-Crouch, Robert

1996-01-01T23:59:59.000Z

42

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

43

Modular, High-Volume Fuel Cell Leak-Test Suite and Process  

SciTech Connect (OSTI)

Fuel cell stacks are typically hand-assembled and tested. As a result the manufacturing process is labor-intensive and time-consuming. The fluid leakage in fuel cell stacks may reduce fuel cell performance, damage fuel cell stack, or even cause fire and become a safety hazard. Leak check is a critical step in the fuel cell stack manufacturing. The fuel cell industry is in need of fuel cell leak-test processes and equipment that is automatic, robust, and high throughput. The equipment should reduce fuel cell manufacturing cost.

Ru Chen; Ian Kaye

2012-03-12T23:59:59.000Z

44

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

45

Adversaries and Information Leaks Geoffrey Smith  

E-Print Network [OSTI]

Adversaries and Information Leaks (Tutorial) Geoffrey Smith School of Computing and Information-Verlag Berlin Heidelberg 2008 #12;384 G. Smith ­ The program c has direct access to the sensitive information

Smith, Geoffrey

46

Leak Path Factor Evaluation: A MELCOR Application for Nonreactor Nuclear Facilities  

SciTech Connect (OSTI)

This paper presents a Leak Path Factor (LPF) analysis for a postulated fire accident on a building containing plutonium powder when the resulting outside release is partly through the ventilation/filtration system and partly through other pathways such as building access doorways. When analyzing an accident scenario involving the release of radioactive powders inside a building, various pathways for the release to the outside environment can exist. This study is presented to show how the multiple building leak path factors (combination of filtered and unfiltered releases) can be evaluated in an integrated manner to assess the magnitude of the source term to be used in the consequence analysis. The core of the analysis is to calculate the leak path factor, which represents the fraction of respirable radioactive powder that is made airborne that leaves the building through the various pathways. The computer code of choice for this determination is MELCOR1. The analysis results can be used for the transport and dispersion of powder material released to the atmosphere and to estimate the resulting dose that is received by the downwind receptors of interest. This work can be used as model for performing analyses for systems similar in nature where releases can propagate to the outside environment via filtered and unfiltered pathways. This example provides guidance to analysts outlining the essential steps needed to perform a sound and defensible analysis.

POLIZZI, MARIO

2004-05-03T23:59:59.000Z

47

New findings on leak resistance of API 8-Round connectors  

SciTech Connect (OSTI)

In response to high interest concerning leak resistance in API 8-Round connectors, the API funded projects that have identified and assessed parameters affecting leak. Among these parameters are make-up, diameter, grade, and combined loads. Additional turns during make-up was found to increase leak resistance. Investigations concerning diameter and grade identified larger diameter and higher grade connectors as most susceptible to low leak pressures when compared to pipe body ratings. Finally, combined loads were found to be crucial to leak. Tension lowers the leak resistance of 8-Round connectors in a manner that renders hydrotesting insufficient for defining leak in some service conditions.

Schwind, B.E.; Wooley, G.R.

1986-01-01T23:59:59.000Z

48

Leak Testing and Implications of Operations to Locate Leak Horizons at West Hackberry Well 108  

SciTech Connect (OSTI)

The Strategic Petroleum Reserve site at West Hackberry, Louisiana has historically experienced casing leaks. Numerous West Hackberry oil storage caverns have wells exhibiting communication between the interior 10 3/4 x 20-inch (oil) annulus and the ''outer cemented'' 20 x 26-inch annulus. Well 108 in Cavern 108 exhibits this behavior. It is thought that one, if not the primary, cause of this communication is casing thread leaks at the 20-inch casing joints combined with microannuli along the cement casing interfaces and other cracks/flaws in the cemented 20 x 26-inch annulus. An operation consisting of a series of nitrogen leak tests, similar to cavern integrity tests, was performed on Cavern 108 in an effort to determine the leak horizons and to see if these leak horizons coincided with those of casing joints. Certain leaky, threaded casing joints were identified between 400 and 1500 feet. A new leak detection procedure was developed as a result of this test, and this methodology for identifying and interpreting such casing joint leaks is presented in this report. Analysis of the test data showed that individual joint leaks could be successfully identified, but not without some degree of ambiguity. This ambiguity is attributed to changes in the fluid content of the leak path (nitrogen forcing out oil) and possibly to very plausible changes in characteristics of the flow path during the test. These changes dominated the test response and made the identification of individual leak horizons difficult. One consequence of concern from the testing was a progressive increase in the leak rate measured during testing due to nitrogen cleaning small amounts of oil out of the leak paths and very likely due to the changes of the leak path during the flow test. Therefore, careful consideration must be given before attempting similar tests. Although such leaks have caused no known environmental or economic problems to date, the leaks may be significant because of the potential for future problems. To mitigate future problems, some repair scenarios are discussed including injection of sealants.

SATTLER, ALLAN R.; EHGARTNER, BRIAN L.; PIECHOCKI, ALAN

2002-06-01T23:59:59.000Z

49

SINGLE-SHELL TANKS LEAK INTEGRITY ELEMENTS/SX FARM LEAK CAUSES AND LOCATIONS - 12127  

SciTech Connect (OSTI)

Washington River Protection Solutions, LLC (WRPS) developed an enhanced single-shell tank (SST) integrity project in 2009. An expert panel on SST integrity was created to provide recommendations supporting the development of the project. One primary recommendation was to expand the leak assessment reports (substitute report or LD-1) to include leak causes and locations. The recommendation has been included in the M-045-9IF Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) as one of four targets relating to SST leak integrity. The 241-SX Farm (SX Farm) tanks with leak losses were addressed on an individual tank basis as part of LD-1. Currently, 8 out of 23 SSTs that have been reported to having a liner leak are located in SX Farm. This percentage was the highest compared to other tank farms which is why SX Farm was analyzed first. The SX Farm is comprised of fifteen SSTs built 1953-1954. The tanks are arranged in rows of three tanks each, forming a cascade. Each of the SX Farm tanks has a nominal I-million-gal storage capacity. Of the fifteen tanks in SX Farm, an assessment reported leak losses for the following tanks: 241-SX-107, 241-SX-108, 241-SX-109, 241-SX-111, 241-SX-112, 241-SX-113, 241-SX-114 and 241-SX-115. The method used to identify leak location consisted of reviewing in-tank and ex-tank leak detection information. This provided the basic data identifying where and when the first leaks were detected. In-tank leak detection consisted of liquid level measurement that can be augmented with photographs which can provide an indication of the vertical leak location on the sidewall. Ex-tank leak detection for the leaking tanks consisted of soil radiation data from laterals and drywells near the tank. The in-tank and ex-tank leak detection can provide an indication of the possible leak location radially around and under the tank. Potential leak causes were determined using in-tank and ex-tank information that is not directly related to leak detection. In-tank parameters can include temperature of the supernatant and sludge, types of waste, and chemical determination by either transfer or sample analysis. Ex-tank information can be assembled from many sources including design media, construction conditions, technical specifications, and other sources. Five conditions may have contributed to SX Farm tank liner failure including: tank design, thermal shock, chemistry-corrosion, liner behavior (bulging), and construction temperature. Tank design did not apparently change from tank to tank for the SX Farm tanks; however, there could be many unknown variables present in the quality of materials and quality of construction. Several significant SX Farm tank design changes occurred from previous successful tank farm designs. Tank construction occurred in winter under cold conditions which could have affected the ductile to brittle transition temperature of the tanks. The SX Farm tanks received high temperature boiling waste from REDOX which challenged the tank design with rapid heat up and high temperatures. All eight of the leaking SX Farm tanks had relatively high rate of temperature rise. Supernatant removal with subsequent nitrate leaching was conducted in all but three of the eight leaking tanks prior to leaks being detected. It is possible that no one characteristic of the SX Farm tanks could in isolation from the others have resulted in failure. However, the application of so many stressors - heat up rate, high temperature, loss of corrosion protection, and tank design - working jointly or serially resulted in their failure. Thermal shock coupled with the tank design, construction conditions, and nitrate leaching seem to be the overriding factors that can lead to tank liner failure. The distinction between leaking and sound SX Farm tanks seems to center on the waste types, thermal conditions, and nitrate leaching.

VENETZ TJ; WASHENFELDER D; JOHNSON J; GIRARDOT C

2012-01-25T23:59:59.000Z

50

Detecting Air Leaks | Department of Energy  

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

Detecting Air Leaks Detecting Air Leaks Detecting Air Leaks September 27, 2012 - 6:39pm Addthis For a thorough and accurate measurement of air leakage in your home, hire a qualified technician to conduct an energy assessment, particularly a blower door test. For a thorough and accurate measurement of air leakage in your home, hire a qualified technician to conduct an energy assessment, particularly a blower door test. You may already know where some air leakage occurs in your home, such as an under-the-door draft, but you'll need to find the less obvious gaps to properly air seal your home. For a thorough and accurate measurement of air leakage in your home, hire a qualified technician to conduct an energy assessment, particularly a blower door test. A blower door test, which depressurizes a home, can

51

Rankine cycle leak detection via continuous monitoring  

SciTech Connect (OSTI)

Rankine cycle power plants operate on a closed cycle in which heat is transferred from a high temperature reservoir to a low temperature sink while performing useful work. leaks in this cycle cause the loss of working fluid and/or corrosion of the power plant. Both of these constitute a loss of capital assets. A severe leak can reduce the efficiency of the cycle to the extent of creating an operating loss. PNL is undertaking the development of continuous monitoring techniques to protect rankine cycle plants from such losses. The location of these continuous monitors on an organic rankine cycle is described and shown schematically.

Kindle, Cecil H.

1982-10-08T23:59:59.000Z

52

Managing an Effective Leak Sealing Program  

E-Print Network [OSTI]

~L....-ST_EAM__ __L_EAK S_U_R_VE_Y_IF_U_R_M_A_N_IT_E_I.__J COMPANY NAME LOCATION DATE * SAMPLE * IFURMANITE REPRESENTATIVE: # , Z 3 4 A/~ I LOCATION TYPE DRAIN VALVE 2,'; R'CVR r:~OI ~ACK/"'~ BLOCK VALVE IZ"Ht>RN?NlClM/fE Fi...

Rinz, W. H.

1980-01-01T23:59:59.000Z

53

New system pinpoints leaks in ethylene pipeline  

SciTech Connect (OSTI)

A model-based leak detection, PLDS, developed by Modisette Associates, Inc., Houston has been operating on the Solvay et Cie ethylene pipeline since 1989. The 6-in. pipeline extends from Antwerp to Jemeppe sur Sambre, a distance of 73.5 miles and is buried at a depth of 3 ft. with no insulation. Except for outlets to flares, located every 6 miles for test purposes, there are no injections or deliveries along the pipeline. Also, there are block valves, which are normally open, at each flare location. This paper reviews the design and testing procedures used to determine the system performance. These tests showed that the leak system was fully operational and no false alarms were caused by abrupt changes in inlet/outlet flows of the pipeline. It was confirmed that leaks larger than 2 tonnes/hr. (40 bbl/hr) are quickly detected and accurately located. Also, maximum leak detection sensitivity is 1 tonne/hr. (20 bbl/hr) with a detection time of one hour. Significant operational, configuration, and programming issues also were found during the testing program. Data showed that temperature simulations needed re-examining for improvement since accurate temperature measurements are important. This is especially true for ethylene since its density depends largely on temperature. Another finding showed the averaging period of 4 hrs. was too long and a 1 to 2 hr. interval was better.

Hamande, A. [Solvay et Cie, Jemeppe sur Sambre (Belgium); Condacse, V.; Modisette, J. [Modisette Associates, Inc., Houston, TX (United States)

1995-04-01T23:59:59.000Z

54

Evaluating an experimental setup for pipe leak detection  

E-Print Network [OSTI]

An experimental setup with 4 inch inner diameter PVC pipe modules is designed to mimic a real life piping system in which to test possible leak detection mechanisms. A model leak detection mechanism is developed which ...

Garay, Luis I. (Luis Ignacio)

2010-01-01T23:59:59.000Z

55

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

56

Double Shell Tank AY-102 Radioactive Waste Leak Investigation  

SciTech Connect (OSTI)

PowerPoint. The objectives of this presentation are to: Describe Effort to Determine Whether Tank AY-102 Leaked; Review Probable Causes of the Tank AY-102 Leak; and, Discuss Influence of Leak on Hanfords Double-Shell Tank Integrity Program.

Washenfelder, Dennis J.

2014-04-10T23:59:59.000Z

57

Mineral formation during simulated leaks of Hanford waste tanks  

E-Print Network [OSTI]

Mineral formation during simulated leaks of Hanford waste tanks Youjun Deng a , James B. Harsh a handling by M. Gascoyne Abstract Highly-alkaline waste solutions have leaked from underground tanks mimicking tank leak conditions at the US DOE Hanford Site. In batch experiments, Si-rich solutions

Flury, Markus

58

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

59

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal floods during mid-loop operations. Volume 4  

SciTech Connect (OSTI)

The major objective of the Surry internal flood analysis was to provide an improved understanding of the core damage scenarios arising from internal flood-related events. The mean core damage frequency of the Surry plant due to internal flood events during mid-loop operations is 4.8E-06 per year, and the 5th and 95th percentiles are 2.2E-07 and 1.8E-05 per year, respectively. Some limited sensitivity calculations were performed on three plant improvement options. The most significant result involves modifications of intake-level structure on the canal, which reduced core damage frequency contribution from floods in mid-loop by about 75%.

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

1994-07-01T23:59:59.000Z

60

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

Note: This page contains sample records for the topic "leaks damage accidents" 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

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...

62

Distribution System Audits, Leak Detection, and Repair: Kirtland Air Force Base Leak Detection and Repair Program  

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

Best Management Practice Best Management Practice Case Study #3 Distribution System Audits, Leak Detection, and Repair Kirtland Air Force Base - Leak Detection and Repair Program Overview Kirtland Air Force Base (AFB) performed an award winning leak detection and repair program in 2006. The results of the project are saving Kirtland AFB 179 million gallons each year, which is over 16% of the total water use at the base. Kirtland AFB is located on 52,000 acres, southeast and adjacent to Albuquerque, New Mexico. The area is a high altitude desert, only receiving about 8 inches of rain each year. Kirtland AFB draws water from an under- ground aquifer via seven production wells through- out the base. The base also has access to water from the City of Albuquerque. The underground water

63

Distribution System Audits, Leak Detection, and Repair: Kirtland Air Force Base Leak Detection and Repair Program  

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

Best Management Practice Best Management Practice Case Study #3 Distribution System Audits, Leak Detection, and Repair Kirtland Air Force Base - Leak Detection and Repair Program Overview Kirtland Air Force Base (AFB) performed an award winning leak detection and repair program in 2006. The results of the project are saving Kirtland AFB 179 million gallons each year, which is over 16% of the total water use at the base. Kirtland AFB is located on 52,000 acres, southeast and adjacent to Albuquerque, New Mexico. The area is a high altitude desert, only receiving about 8 inches of rain each year. Kirtland AFB draws water from an under- ground aquifer via seven production wells through- out the base. The base also has access to water from the City of Albuquerque. The underground water

64

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...

65

Management of vacuum leak-detection processes, standards, and calibration  

SciTech Connect (OSTI)

Vacuum leak detection requires integrated management action to ensure the successful production of apparatus having required leak tightness. Implementation of properly planned, scheduled, and engineering procedures and test arrangements are an absolute necessity to prevent unexpected, impractical, technically inadequate, or unnecessarily costly incidents in leak-testing operations. The use of standard procedures, leak standards appropriate to the task, and accurate calibration systems or devices is necessary to validate the integrity of any leak-test procedure. In this paper, the need for implementing these practices is discussed using case histories of typical examples of large complex vacuum systems. Aggressive management practices are of primary importance throughout a project's life cycle to ensure the lowest cost; this includes successful leak testing of components. It should be noted that the opinions and conclusions expressed in this paper are those of the author and are not those of the Los Alamos National Laboratory or the Department of Energy.

Wilson, N.G.

1984-01-01T23:59:59.000Z

66

Long-life leak standard assembly. [Patent application  

DOE Patents [OSTI]

The present invention is directed to a portable leak standard assembly which is capable of providing a stream of high-purity reference gas at a virtually constant flow rate over an extensive period of time. The leak assembly comprises a high pressure reservoir coupled to a metal leak valve through a valve-controlled conduit. A reproducible leak valve useful in this assembly is provided by a metal tube crimped with a selected pressure loading for forming an orifice in the tube with this orifice being of a sufficient size to provide the selected flow rate. The leak valve assembly is formed of metal so that it can be baked-out in a vacuum furnace to rid the reservoir and attendent components of volatile impurities which reduce the efficiency of the leak standard.

Basford, J.A.; Mathis, J.E.; Wright, H.C.

1980-11-12T23:59:59.000Z

67

One-Piece Leak-Proof Battery  

DOE Patents [OSTI]

The casing of a leak-proof one-piece battery is made of a material comprising a mixture of at least a matrix based on polypropylene and an alloy of a polyamide and a polypropylene. The ratio of the matrix to the alloy is in the range 0.5 to 6 by weight. The alloy forms elongate arborescent inclusions in the matrix such that, on average, the largest dimension of a segment of the arborescence is at least twenty times the smallest dimension of the segment.

Verhoog, Roelof (Bordeaux, FR)

1999-03-23T23:59:59.000Z

68

Margins in high temperature leak-before-break assessments  

SciTech Connect (OSTI)

Developments in the defect assessment procedure R6 to include high-temperature mechanisms in Leak-before-Break arguments are described. In particular, the effect of creep on the time available to detect a leak and on the crack opening area, and hence leak rate, is discussed. The competing influence of these two effects is emphasized by an example. The application to Leak-before-Break of the time-dependent failure assessment diagram approach for high temperature defect assessment is then outlined. The approach is shown to be of use in assessing the erosion of margins by creep.

Budden, P.J.; Hooton, D.G.

1997-04-01T23:59:59.000Z

69

ANNUAL MAINTENANCE AND LEAK TESTING FOR THE 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

The purpose of this document is to provide step-by-step instructions for the annual helium leak test certification and maintenance of the 9975 Shipping Package.

Trapp, D.

2014-08-25T23:59:59.000Z

70

Results from the investigations on leaking electricity in the USA  

E-Print Network [OSTI]

on leaking electricity in the USA Alan Meier, Wolfgang Huber120 million VCRs in the USA. Data were collected for 69

Meier, Alan; Huber, Wolfgang

1997-01-01T23:59:59.000Z

71

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.

72

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

73

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

74

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

75

A second order autoregressive based technique for pipeline leak detection  

Science Journals Connector (OSTI)

Efficient leak detection techniques need to be characterized both by rapidity and robustness. This paper studies a simple detection method based on the second order autoregressive (AR) parameters of the pipeline signals- a trade-off between the two required ... Keywords: AR models, ROC curves, leak detection, pipeline monitoring

Marllene Daneti

2008-07-01T23:59:59.000Z

76

241-AY-102 Leak Detection Pit Drain Line Inspection Report  

SciTech Connect (OSTI)

This document provides a description of the design components, operational approach, and results from the Tank AY-102 leak detection pit drain piping visual inspection. To perform this inspection a custom robotic crawler with a deployment device was designed, built, and operated by IHI Southwest Technologies, Inc. for WRPS to inspect the 6-inch leak detection pit drain line.

Boomer, Kayle D. [Washington River Protection Solutions, LLC (United States); Engeman, Jason K. [Washington River Protection Solutions, LLC (United States); Gunter, Jason R. [Washington River Protection Solutions, LLC (United States); Joslyn, Cameron C. [Washington River Protection Solutions, LLC (United States); Vazquez, Brandon J. [Washington River Protection Solutions, LLC (United States); Venetz, Theodore J. [Washington River Protection Solutions, LLC (United States); Garfield, John S. [AEM Consulting (United States)

2014-01-20T23:59:59.000Z

77

A new blowdown compensation scheme for boiler leak detection  

E-Print Network [OSTI]

considers the blowdown effect in industrial boiler operation. This adds to the efficiency of recent advances tubes. In utility boilers, early de- tection of leaks is primarily a financial issue. High velocityA new blowdown compensation scheme for boiler leak detection A. M. Pertew ,1 X. Sun ,1 R. Kent

Marquez, Horacio J.

78

INFORMAL REPORT DETECTION OF INTERSTATE LIQUIDS PIPELINE LEAKS  

E-Print Network [OSTI]

BNL-65970 INFORMAL REPORT DETECTION OF INTERSTATE LIQUIDS PIPELINE LEAKS: FEASIBILITY EVALUATION R PIPELINE LEAKS: FEASIBILITY EVALUATION A Concept Paper Russell N. Dietz, Head Gunnar I. Senum Tracer with Battelle Memorial Institute and the Colonial Pipeline Company #12;ABSTRACT The approximately 200,000-mile

79

CFD simulation of leak in residential HVAC ducts  

Science Journals Connector (OSTI)

A three-dimensional computational fluid dynamics model was used to simulate fluid flow in a duct and its simulated leaks with six different air leak geometries placed respectively on its periphery. The k? turbulence model for high Reynolds numbers flows was used for that purpose and the Reynolds numbers were varied to simulate a variety of flow conditions between 27,000 and 82,000. The computer code was used to produce pressure drop data and leak flow rates across the holes necessary to compute the pressure loss coefficients, as well as to produce flow field and static pressure plots that offer insight into the physics of the flow field. The flow coefficient and pressure exponent (C and n) were found for different leak geometries by curve fitting the pressure and leak flow data derived from CFD simulations and were compared to available data in the literature.

Samir Moujaes; Radhika Gundavelli

2012-01-01T23:59:59.000Z

80

Pressure Change Measurement Leak Testing Errors  

SciTech Connect (OSTI)

A pressure change test is a common leak testing method used in construction and Non-Destructive Examination (NDE). The test is known as being a fast, simple, and easy to apply evaluation method. While this method may be fairly quick to conduct and require simple instrumentation, the engineering behind this type of test is more complex than is apparent on the surface. This paper intends to discuss some of the more common errors made during the application of a pressure change test and give the test engineer insight into how to correctly compensate for these factors. The principals discussed here apply to ideal gases such as air or other monoatomic or diatomic gasses; however these same principals can be applied to polyatomic gasses or liquid flow rate with altered formula specific to those types of tests using the same methodology.

Pryor, Jeff M [ORNL] [ORNL; Walker, William C [ORNL] [ORNL

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

Leak-Path Factor Analysis for the Nuclear Materials Storage Facility  

SciTech Connect (OSTI)

Leak-path factors (LPFs) were calculated for the Nuclear Materials Storage Facility (NMSF) located in the Plutonium Facility, Building 41 at the Los Alamos National Laboratory Technical Area 55. In the unlikely event of an accidental fire powerful enough to fail a container holding actinides, the subsequent release of oxides, modeled as PuO{sub 2} aerosols, from the facility and into the surrounding environment was predicted. A 1-h nondestructive assay (NDA) laboratory fire accident was simulated with the MELCOR severe accident analysis code. Fire-driven air movement along with wind-driven air infiltration transported a portion of these actinides from the building. This fraction is referred to as the leak-path factor. The potential effect of smoke aerosol on the transport of the actinides was investigated to verify the validity of neglecting the smoke as conservative. The input model for the NMSF consisted of a system of control volumes, flow pathways, and surfaces sufficient to model the thermal-hydraulic conditions within the facility and the aerosol transport data necessary to simulate the transport of PuO{sub 2} particles. The thermal-hydraulic, heat-transfer, and aerosol-transport models are solved simultaneously with data being exchanged between models. A MELCOR input model was designed such that it would reproduce the salient features of the fire per the corresponding CFAST calculation. Air infiltration into and out of the facility would be affected strongly by wind-driven differential pressures across the building. Therefore, differential pressures were applied to each side of the building according to guidance found in the ASHRAE handbook using a standard-velocity head equation with a leading multiplier to account for the orientation of the wind with the building. The model for the transport of aerosols considered all applicable transport processes, but the deposition within the building clearly was dominated by gravitational settling.

Shaffer, C.; Leonard, M.

1999-06-13T23:59:59.000Z

82

Analysis of a Nuclear Accident: Fission and Activation Product Releases from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel  

SciTech Connect (OSTI)

Measurements of several radionuclides within environmental samples taken from the Fukushima Daiichi nuclear facility and reported on the Tokyo Electric Power Company website following the recent tsunami-initiated catastrophe were evaluated for the purpose of identifying the source term, reconstructing the release mechanisms, and estimating the extent of the release. 136Cs/137Cs and 134Cs/137Cs ratios identified Units 1-3 as the major source of radioactive contamination to the surface soil close to the facility. A trend was observed between the fraction of the total core inventory released for a number of fission product isotopes and their corresponding Gibbs Free Energy of formation for the primary oxide form of the isotope, suggesting that release was dictated primarily by chemical volatility driven by temperature and reduction potential within the primary containment vessels of the vented reactors. The absence of any major fractionation beyond volatilization suggested all coolant had evaporated by the time of venting. High estimates for the fraction of the total inventory released of more volatile species (Te, Cs, I) indicated the damage to fuel bundles was likely extensive, minimizing any potential containment due to physical migration of these species through the fuel matrix and across the cladding wall. 238Pu/239,240Pu ratios close-in and at 30 km from the facility indicated that the damaged reactors were the major contributor of Pu to surface soil at the source but that this contribution likely decreased rapidly with distance from the facility. The fraction of the total Pu inventory released to the environment from venting units 1 and 3 was estimated to be ~0.003% based upon Pu/Cs isotope ratios relative to the within-reactor modeled inventory prior to venting and was consistent with an independent model evaluation that considered chemical volatility based upon measured fission product release trends. Significant volatile radionuclides within the spent fuel at the time of venting but not as yet observed and reported within environmental samples are suggested as potential analytes of concern for future environmental surveys around the site.

Schwantes, Jon M.; Orton, Christopher R.; Clark, Richard A.

2012-09-10T23:59:59.000Z

83

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...

84

Multibody Models for Vehicle Accident Reconstruction  

Science Journals Connector (OSTI)

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

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

2006-01-01T23:59:59.000Z

85

E-Print Network 3.0 - affects leak rate Sample Search Results  

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

and Utilization ; Renewable Energy 15 INFORMAL REPORT DETECTION OF INTERSTATE LIQUIDS PIPELINE LEAKS Summary: commercial technologies only provide on-line leak detection at...

86

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

87

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

88

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

89

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...

90

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

91

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

92

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

93

Robot design for leak detection in water-pipe systems  

E-Print Network [OSTI]

Leaks are major problem that occur in the water pipelines all around the world. Several reports indicate loss of around 20 to 30 percent of water in the distribution of water through water pipe systems. Such loss of water ...

Choi, Changrak

2012-01-01T23:59:59.000Z

94

Predicting Worker Exposure from a Glovebox Leak  

SciTech Connect (OSTI)

It is difficult to predict immediate worker radiological consequences from a hypothetical accident. This is recognized in DOE safety analysis guidance and the reason such guidance does not call for quantitative determinations of such consequences. However, it would be useful to at least have a means of systematically and formally quantifying worker dose to be able to identify the relative risks of various processes and to provide an order-of-magnitude impression of absolute consequences. In this report, we present such a means in the form of a simple calculation model that is easily applied and generates reasonable, qualitative dose predictions. The model contains a scaling parameter whose value was deduced from extensive laboratory ventilation flow rate measurements performed at Los Alamos National Laboratory (LANL) over the last several years and from recent indoor radioactive contamination dispersion measurements, also at LANL. Application of the model is illustrated with the aid of two example calculations.

H. Jordan; D. J. Gordon; J. J. Whicker; D. L. Wannigman

2001-05-01T23:59:59.000Z

95

Graphite Oxidation Simulation in HTR Accident Conditions  

SciTech Connect (OSTI)

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

Mohamed El-Genk

2012-10-19T23:59:59.000Z

96

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

97

Oil/gas collector/separator for underwater oil leaks  

DOE Patents [OSTI]

An oil/gas collector/separator for recovery of oil leaking, for example, from an offshore or underwater oil well. The separator is floated over the point of the leak and tethered in place so as to receive oil/gas floating, or forced under pressure, toward the water surface from either a broken or leaking oil well casing, line, or sunken ship. The separator is provided with a downwardly extending skirt to contain the oil/gas which floats or is forced upward into a dome wherein the gas is separated from the oil/water, with the gas being flared (burned) at the top of the dome, and the oil is separated from water and pumped to a point of use. Since the density of oil is less than that of water it can be easily separated from any water entering the dome.

Henning, Carl D. (Livermore, CA)

1993-01-01T23:59:59.000Z

98

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

99

Parameters for landfill-liner leak-rate model  

E-Print Network [OSTI]

PARAMETERS FOR LANDFILL-LINER LEAK-RATE MODEL A Thesis by STEVEN CARLTON BAHRT Submitted to the Graduate College of Texas ASM University i n partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 1985 Major... Subject: Civil Engineering PARAMETERS FOR LANDFILL-LINER LEAK-RATE MODEL A Thesis by STEVEN CARLTON BAHRT Approved as to style and content by: Rob nt Lytto (Co-Cha' man of C mmittee) ayne Dunl p (Member) Kink W. Brown (Co-Chairman of Committee...

Bahrt, Steven Carlton

2012-06-07T23:59:59.000Z

100

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

SciTech Connect (OSTI)

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

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

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

Cell damage seen from Chernobyl  

SciTech Connect (OSTI)

The 30 kilometer radius forbidden zone around the Chernobyl atomic plant serves as a sobering reminder of the world's worst nuclear accident. But for former Soviet biologists, it's also a unique natural laboratory. And one scientist, Nadejda Gulaya of Kiev's Pallaguine Institute of Biochemistry, has been doing studies that she claims offer surprising evidence of Chernobyl's after-effects. Prolonged exposure to radioactive fallout from the 1986 accident, she says, has caused damage to cell membranes in both animals and humans. For the past year, Gulaya has been comparing tissues from animals such as mink, pigs, and rodents inhabiting the Chernobyl area with those from other parts of Ukraine. Her conclusion: Exposure to radiation has, in many cases, caused alterations to membrane phospholipids. These changes, are similar to those that disrupt cellular metabolism following exposure to oxidizing free radicals. Gulaya also has preliminary data from human studies. She claims to have found similar alterations in the neurons of people who have died since being exposed to Chernobyl radiation. That leads her to speculate that the frequent psychiatric disorders may not just be from mental stress or radiophobia, but might reflect actual damage to the central nervous system.

Not Available

1992-07-24T23:59:59.000Z

102

Leak-rate of seals: comparison of theory with experiment  

E-Print Network [OSTI]

Seals are extremely useful devices to prevent fluid leakage. We present experimental results for the leak-rate of rubber seals, and compare the results to a novel theory, which is based on percolation theory and a recently developed contact mechanics theory. We find good agreement between theory and experiment.

B. Lorenz; B. N. J. Persson

2009-04-20T23:59:59.000Z

103

Leak Testing the DMT Cloud Condensation Nuclei Counter for  

E-Print Network [OSTI]

Saudi Arabia field project was funded by the Kingdom of Saudi Arabia through a contract with Weather housing. Don't try to tighten the metal fitting on the pump housing. #12;Hard Places to Find Leaks Saudi Operator Manual Rev D page 45. March 22, 2009 Saudi Arabia Down to 450 mb, climb to 500 mb took 311 seconds

Delene, David J.

104

Helium Leak Detector 140 00 141 00 142 00  

E-Print Network [OSTI]

140 11 141 11 for software version V 2.6 Technical Handbook TH 10.211/ 8.02 Leak Detection Vacuum in this handbook. The illustrations are not binding. Notes on how to use this handbook Important remarks concerning . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.2 Technical data . . . . . . . . . . . . . . . . . . . . . . . . 3 1.2.1 Physical data

Haviland, David

105

AIR SEALING Seal air leaks and save energy!  

E-Print Network [OSTI]

AIR SEALING Seal air leaks and save energy! W H A T I S A I R L E A K A G E ? Ventilation is fresh at stopping air leakage. It is critical to seal all holes and seams between these sheet goods with durable air that enters a house in a controlled manner to exhaust excess moisture and reduce odors

Oak Ridge National Laboratory

106

T Plant secondary containment and leak detection upgrades  

SciTech Connect (OSTI)

The W-259 project will provide upgrades to the 2706-T/TA Facility to comply with Federal and State of Washington environmental regulations for secondary containment and leak detection. The project provides decontamination activities supporting the environmental restoration mission and waste management operations on the Hanford Site.

Carlson, T.A.

1995-10-19T23:59:59.000Z

107

How Do You Find Thermal Leaks in Your Home? | Department of Energy  

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

How Do You Find Thermal Leaks in Your Home? How Do You Find Thermal Leaks in Your Home? How Do You Find Thermal Leaks in Your Home? March 31, 2011 - 7:30am Addthis On Monday, John told you about the thermal leak detector he purchased to help him find and seal leaks in his home. A thermal leak detector can be a great tool to help you find leaks in your own home, but it's not your only option. In addition to tools like this, you can also use some of our tips on do-it-yourself energy assessments, or you could get a professional energy assessment. How do you find thermal leaks in your home? Each Thursday, you have the chance to share your thoughts on a question about energy efficiency or renewable energy for consumers. Please e-mail your responses to the Energy Saver team at consumer.webmaster@nrel.gov.

108

Analysis and design of an in-pipe system for water leak detection  

E-Print Network [OSTI]

Leaks are a major factor for unaccounted water losses in almost every water distribution network. Pipeline leak may result, for example, from bad workmanship or from any destructive cause, due to sudden changes of pressure, ...

Chatzigeorgiou, Dimitris M

2010-01-01T23:59:59.000Z

109

CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings  

SciTech Connect (OSTI)

On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break.

Not Available

1984-08-01T23:59:59.000Z

110

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

111

WHAT YOU LOSE IS WHAT YOU LEAK INFORMATION LEAKAGE IN DECLASSIFICATION POLICIES  

E-Print Network [OSTI]

WHAT YOU LOSE IS WHAT YOU LEAK INFORMATION LEAKAGE IN DECLASSIFICATION POLICIES A. Banerjee, R MFPS 2007 What you lose is what you leak ­ p.1/19 #12;Overview By exploiting the strong relation declassification policy; Refine a given declassification policy; What you lose is what you leak ­ p.2/19 #12

Mastroeni, Isabella

112

Mobile Sensor Networks for Leak and Backflow Detection in Water Distribution Systems  

Science Journals Connector (OSTI)

Leak and backflow detection are essential aspects of Water Distribution System (WDS) monitoring. Most existing solutions for leak/backflow detection in WDSs focus on the placement of expensive static sensors located strategically. In contrast to these, ... Keywords: water distribution systems, mobile sensors, leak and backflow detection, optimization, algorithms, simulations

M. Agumbe Suresh, L. Smith, A. Rasekh, R. Stoleru, M. K. Banks, B. Shihada

2014-05-01T23:59:59.000Z

113

Cambium Damage  

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

Cambium Damage Cambium Damage Name: Jamie Location: N/A Country: N/A Date: N/A Question: If the bark from the lower part of trees (elm trees) is almost completly removed (in this case by animals)to a height of about 8ft, is it possible that the trees will still live? What can be done to help the trees? Replies: If the tree has been girdled, that is, the bark and cambium layer beneath it, has been removed completely around the tree, then it will die. If there is any portion of the bark remaining it may live, but if that remaining is small it probably will die fairly soon due to general decline. If the cambium layer has not been destroyed it may recover, but once the bark is stripped away it is most likely doomed because of the likelihood of invasion by fungi, insects, etc. A local forester or landscaper might be able to offer more help if they see it.

114

Preliminary analysis of graphite dust releasing behavior in accident for HTR  

SciTech Connect (OSTI)

The behavior of the graphite dust is important to the safety of High Temperature Gas-cooled Reactors. This study investigated the flow of graphite dust in helium mainstream. The analysis of the stresses acting on the graphite dust indicated that gas drag played the absolute leading role. Based on the understanding of the importance of gas drag, an experimental system is set up for the research of dust releasing behavior in accident. Air driven by centrifugal fan is used as the working fluid instead of helium because helium is expensive, easy to leak which make it difficult to seal. The graphite particles, with the size distribution same as in HTR, are added to the experiment loop. The graphite dust releasing behavior at the loss-of-coolant accident will be investigated by a sonic nozzle. (authors)

Peng, W.; Yang, X. Y.; Yu, S. Y.; Wang, J. [Inst. of Nuclear and New Energy Technology, Tsinghua Univ., Beijing100084 (China)

2012-07-01T23:59:59.000Z

115

Leake County, Mississippi: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Leake County, Mississippi: Energy Resources Leake County, Mississippi: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 32.8073509°, -89.4742177° 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":32.8073509,"lon":-89.4742177,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

116

Distributed Optical Sensor for CO2 Leak Detection  

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

Optical Sensor for CO Optical Sensor for CO 2 Leak Detection Opportunity Research is active on the technology "Distributed Optical Sensor for CO 2 Leak Detection," for which a Patent Application has been filed. This technology is available for licensing and/or further collaborative research from the U.S. Department of Energy's National Energy Technology Laboratory (NETL). Overview The availability of fossil fuels to provide clean, affordable energy is essential for domestic and global prosperity and security well into the 21st century. However, there are concerns over the impacts of greenhouse gases (GHGs) in the atmosphere-particularly carbon dioxide (CO 2 ). Carbon capture and storage in geologic formations is a promising technology to reduce the impact of CO

117

Calculation of SY tank annulus continuous air monitor readings after postulated leak scenarios  

SciTech Connect (OSTI)

The objective of this work was to determine whether or not a continuous air monitor (CAM) monitoring the annulus of one of the SY Tanks would be expected to alarm after three postulated leak scenarios. Using data and references provided by Lockheed Martin`s Tank Farm personnel, estimated CAM readings were calculated at specific times after the postulated scenarios might have occurred. Potential CAM readings above background at different times were calculated for the following leak scenarios: Leak rate of 0.01 gal/min; Leak rate of 0.03 gal/min (best estimate of the maximum probable leak rate from a single-shell tank); and Leak of 73 gal (equivalent to a {1/4}-in. leak on the floor of the annulus). The equation used to make the calculations along with descriptions and/or explanations of the terms are included, as is a list of the assumptions and/or values used for the calculations.

Kenoyer, J.L.

1998-08-01T23:59:59.000Z

118

MWTF jumper connector integral seal block development and leak testing  

SciTech Connect (OSTI)

In fiscal year 1993, tests of an o-ring/tetraseal retainer designed to replace a gasket-type seal used in PUREX-type process jumper connectors encouraged the design of an improved seal block. This new seal block combines several parts into one unitized component called an integral seal block. This report summarizes development and leak testing of the new integral seal block. The integral seal block uses a standard o-ring nested in a groove to accomplish leak tightness. This seal block eliminates the need to machine acme threads into the lower skirt casting and seal retainers, eliminates tolerance stack-up, reduces parts inventory, and eliminates an unnecessary leak path in the jumper connector assembly. This report also includes test data on various types of o-ring materials subjected to heat and pressure. Materials tested included Viton, Kalrez, and fluorosilicone, with some incidental data on teflon coated silicone o-rings. Test experience clearly demonstrates the need to test each seal material for temperature and pressure in its intended application. Some materials advertised as being {open_quotes}better{close_quotes} at higher temperatures did not perform up to expectations. Inspection of the fluorosilicone and Kalrez seals after thermal testing indicates that they are much more susceptible to heat softening than Viton.

Ruff, E.S.; Jordan, S.R.

1995-01-01T23:59:59.000Z

119

Electrical detection of liquid lithium leaks from pipe joints  

SciTech Connect (OSTI)

A test stand for flowing liquid lithium is under construction at Princeton Plasma Physics Laboratory. As liquid lithium reacts with atmospheric gases and water, an electrical interlock system for detecting leaks and safely shutting down the apparatus has been constructed. A defense in depth strategy is taken to minimize the risk and impact of potential leaks. Each demountable joint is diagnosed with a cylindrical copper shell electrically isolated from the loop. By monitoring the electrical resistance between the pipe and the copper shell, a leak of (conductive) liquid lithium can be detected. Any resistance of less than 2 k? trips a relay, shutting off power to the heaters and pump. The system has been successfully tested with liquid gallium as a surrogate liquid metal. The circuit features an extensible number of channels to allow for future expansion of the loop. To ease diagnosis of faults, the status of each channel is shown with an analog front panel LED, and monitored and logged digitally by LabVIEW.

Schwartz, J. A., E-mail: jschwart@pppl.gov; Jaworski, M. A.; Mehl, J.; Kaita, R.; Mozulay, R. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543-0451 (United States)

2014-11-15T23:59:59.000Z

120

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

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


121

ACCIDENT 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

122

Japanese Ratify Convention on Supplementary Compensation for Nuclear Damage (CSC)  

Broader source: Energy.gov [DOE]

"The Japanese ratification of the Convention on Supplementary Compensation for Nuclear Damage (CSC) marks an important milestone towards creating a global nuclear liability regime that will assure prompt and meaningful compensation in the event of a nuclear accident and will facilitate international cooperation on nuclear projects such as ongoing clean-up work at the Fukushima site."

123

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

E-Print Network [OSTI]

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

Stren, Thomas G.

2007-01-01T23:59:59.000Z

124

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

125

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...

126

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...

127

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...

128

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

129

Transport Calculation of Neutrons Leaked to the Surroundings of the Facilities by the JCO Criticality Accident in Tokai-mura  

Science Journals Connector (OSTI)

......for safety review documents18...levels of the standard error were...Processing Fig. 1. Plan of the geometrical...are 1U (1st uranium testing bldg...adjacent 2nd uranium testing building...indicate one standard deviation of...indicate one standard deviation of...report of the Uranium Processing......

Tetsuji Imanaka

2001-09-01T23:59:59.000Z

130

Transport Calculation of Neutrons Leaked to the Surroundings of the Facilities by the JCO Criticality Accident in Tokai-mura  

Science Journals Connector (OSTI)

......1a). Neutrons were generated...having the energy and angular spectrum obtained...of every neutron passing through...neu- tron energy. The arrangement...of total fissions that occurred...54 Mn are induced through...mainly by thermal neutrons......

Tetsuji Imanaka

2001-09-01T23:59:59.000Z

131

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 2, Part 1C: Analysis of core damage frequency from internal events for plant operational State 5 during a refueling outage, Main report (Sections 11--14)  

SciTech Connect (OSTI)

This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power analyses performed on Grand Gulf.

Whitehead, D. [Sandia National Labs., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Yakle, J. [Science Applications International Corp., Albuquerque, NM (United States)] [and others

1994-06-01T23:59:59.000Z

132

Bottom-Fill Method for Stopping Leaking Oil Wells  

E-Print Network [OSTI]

Hardware failure at the top of a deep underwater oil well can result in a catastrophic oil leak. The enormous pressure lifting the column of oil in that well makes it nearly impossible to stop from the top with seals or pressurization. We propose to fill the bottom of the well with dense and possibly streamlined objects that can descend through the rising oil. As they accumulate, those objects couple to the oil via viscous and drag forces and increase the oil's effective density. When its effective density exceeds that of the earth's crust, the oil will have essentially stopped flowing.

Bloomfield, Louis A

2010-01-01T23:59:59.000Z

133

Hanford Single-Shell Tank Leak Causes and Locations - 241-T Farm  

SciTech Connect (OSTI)

This document identifies 241-T Tank Farm (T Farm) leak causes and locations for the 100 series leaking tanks (241-T-106 and 241-T-111) identified in RPP-RPT-55084, Rev. 0, Hanford 241-T Farm Leak Inventory Assessment Report. This document satisfies the T Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L.; Harlow, Donald G.

2014-05-15T23:59:59.000Z

134

Hanford Single-Shell Tank Leak Causes and Locations - 241-C Farm  

SciTech Connect (OSTI)

This document identifies 241-C Tank Farm (C Farm) leak causes and locations for the 100 series leaking tanks (241-C-101 and 241-C-105) identified in RPP-RPT-33418, Rev. 2, Hanford C-Farm Leak Inventory Assessments Report. This document satisfies the C Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L.; Harlow, Donald G.

2013-07-30T23:59:59.000Z

135

Long-wave infrared imaging of vegetation for detecting leaking CO2 gas  

E-Print Network [OSTI]

Long-wave infrared imaging of vegetation for detecting leaking CO2 gas Jennifer E. Johnson Joseph A for detecting leaking CO2 gas Jennifer E. Johnson,a Joseph A. Shaw,a Rick Lawrence,b Paul W. Nugent,a Laura M of these calibrated imagers is imaging of vegetation for CO2 gas leak detection. During a four-week period

Shaw, Joseph A.

136

Hanford Single Shell Tank Leak Causes and Locations - 241-TX Farm  

SciTech Connect (OSTI)

This document identifies 241-TX Tank Farm (TX Farm) leak causes and locations for the 100 series leaking tanks (241-TX-107 and 241-TX-114) identified in RPP-RPT-50870, Rev. 0, Hanford 241-TX Farm Leak Inventory Assessment Report. This document satisfies the TX Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, C. L.; Harlow, D> G.

2014-07-22T23:59:59.000Z

137

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

138

Best Management Practice #3: Distribution System Audits, Leak Detection, and Repair  

Broader source: Energy.gov [DOE]

A distribution system audit, leak detection, and repair programs help Federal facilities reduce water losses and make better use of limited water resources.

139

Intelligent Coatings for Location And Detection of Leaks (IntelliCLAD...  

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

supplant widespread use of hydrocarbon-based fuels in what has been dubbed the "hydrogen economy," but odorization of hydrogen will not make a leak noticeable to humans...

140

E-Print Network 3.0 - acoustic leak detection Sample Search Results  

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

Processes Summary: - April 2-5, 2006 OBSERVER DESIGN USING BOUNDARY INJECTIONS FOR PIPELINE MONITORING AND LEAK DETECTION Ole... University of Science and Technology N-7491...

Note: This page contains sample records for the topic "leaks damage accidents" 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

T-726:Linux-2.6 privilege escalation/denial of service/information leak  

Broader source: Energy.gov [DOE]

Vulnerabilities have been discovered in the Linux kernel that may lead to a privilege escalation, denial of service or information leak.

142

Ultra high vacuum pumping system and high sensitivity helium leak detector  

DOE Patents [OSTI]

An improved helium leak detection method and apparatus are disclosed which increase the leak detection sensitivity to 10.sup.-13 atm cc s.sup.-1. The leak detection sensitivity is improved over conventional leak detectors by completely eliminating the use of o-rings, equipping the system with oil-free pumping systems, and by introducing measured flows of nitrogen at the entrances of both the turbo pump and backing pump to keep the system free of helium background. The addition of dry nitrogen flows to the system reduces backstreaming of atmospheric helium through the pumping system as a result of the limited compression ratios of the pumps for helium.

Myneni, Ganapati Rao (Yorktown, VA)

1997-01-01T23:59:59.000Z

143

Ultra high vacuum pumping system and high sensitivity helium leak detector  

DOE Patents [OSTI]

An improved helium leak detection method and apparatus are disclosed which increase the leak detection sensitivity to 10{sup {minus}13} atm cc/s. The leak detection sensitivity is improved over conventional leak detectors by completely eliminating the use of o-rings, equipping the system with oil-free pumping systems, and by introducing measured flows of nitrogen at the entrances of both the turbo pump and backing pump to keep the system free of helium background. The addition of dry nitrogen flows to the system reduces back streaming of atmospheric helium through the pumping system as a result of the limited compression ratios of the pumps for helium. 2 figs.

Myneni, G.R.

1997-12-30T23:59:59.000Z

144

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...

145

Hurricane-damaged Gulf of Mexico pipeline repaired with cold forging  

SciTech Connect (OSTI)

Damage to Texaco Pipeline Inc.'s Eugene Island Pipeline System (EIPS) in last year's Hurricane Andrew prompted a complex repair project unique for the Gulf of Mexico. Damage, suffered when the anchor of a runaway semisubmersible drilling rig crashed into the 20-in. EPIS during the height of the storm, caused the pipeline to fail under pressure within 48 hr. after start-up following the storm. The paper describes the importance of the EIPS; system safety; Andrew's damage; locating the leak; repair options; the chosen system; mechanical bonding; end connectors and ball flanges; and diving operations.

Lewis, G. (Texaco Pipeline Inc., Houma, LA (United States)); DeGruy, P. (Texaco Inc., New Orleans, LA (United States)); Avery, L. (Big Inch Marine Systems Inc., Lafayette, LA (United States))

1993-05-03T23:59:59.000Z

146

An alternative methodology to repair localized corrosion damage in metallic pipelines with epoxy resins  

Science Journals Connector (OSTI)

The present work is concerned with the analysis of epoxy repair systems for metallic pipelines undergoing elastic or inelastic deformations with localized corrosion damage that impair the serviceability. In the case of trough-thickness damage, the main focus is to assure an adequate application of the epoxy filler in such a way the pipe wont leak after repair. Such a procedure can be used or not associated with a composite sleeve that assures a satisfactory level of structural integrity. Examples concerning the use of repair systems in different damage situations are presented and analyzed showing the possibilities of practical use of the proposed methodology.

H.S. da Costa-Mattos; J.M.L. Reis; R.F. Sampaio; V.A. Perrut

2009-01-01T23:59:59.000Z

147

Estimation of Gas Leak Rates Through Very Small Orifices  

Office of Scientific and Technical Information (OSTI)

Estimation of Gas Leak Rates Estimation of Gas Leak Rates Through Very Small Orifices and Channels by Herbert J. Bomelburg February 1977 Prepared for the Nuclear Regulatory Commission -..- Pacific Northwest Laboratories Th% report was preparrd is an accceullt r.84 work spoi.wr~d by the Un~ted States Governmect. Kettker t > ~ United States nor the L'nited states 'rl:clczr 1tcgl;l;:cry Cornmiszion. :or ally c! their e m p i o y e ~ , nor any of chcrr contractors, subcontraao~r, a . tlveir rrn~invct?t-, r.~aies any H r r l a tty, cxpreji o r implied, or ?.;+~nics any !egA liability or rcrpocsibility for iirc accuracy. zcm:lc.~cn~ss 01 ~rscf.~!ccss -,f an). i?fzrxat-on, 3Poar.i:b4. prodiict cr I.m)cess disclosed, or repreen:.; :hi.: i;s i43? wott:rl n.;\ irlfringe pr ivzrc:i*l u w x o :ig.~ts.

148

Corrosion Evaluation of Tank 40 Leak Detection Box  

SciTech Connect (OSTI)

'Leak detection from the transfer lines in the tank farm has been a concern for many years because of the need to minimize exposure of personnel and contamination of the environment. The leak detection box (LDB) is one line of defense, which must be maintained to meet this objective. The evaluation of a failed LDB was one item from an action plan aimed at minimizing the degradation of LDBs. The Tank 40 LDB, which failed in service, was dug up and shipped to SRTC for evaluation. During a video inspection while in service, this LDB was found to have black tubercles on the interior, which suggested possible microbial involvement. The failure point, however, was believed to have occurred in the drain line from the transfer line jacket. Visual, metallurgical, and biological analyses were performed on the LDB. The analysis results showed that there was not any adverse microbiological growth or significant localized corrosion. The corrosion of the LDB was caused by exposure to aqueous environments and was typical of carbon steel pipes in soil environments.'

Mickalonis, J.I.

1999-07-29T23:59:59.000Z

149

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

150

Collision damage of jack-ups  

Science Journals Connector (OSTI)

North Sea collision accident records covering a period of ten years indicate that the risk of collisions involving jack-ups is not dissimilar to that for semi-submersibles or fixed jacket structures. However, jack-ups are much more flexible than jackets and have a much lower degree of redundancy. Their response to collisions and their ability to absorb impact energy is, therefore, expected to be considerably different in comparison to jackets. This paper examines available data and information regarding the capability of jack-ups to withstand collision impacts and investigates the level of local damage that can potentially be caused to jack-up legs due to accidental collisions.

Charles P. Ellinas; Raymond Kwok; Kevin A.J. Williams

1989-01-01T23:59:59.000Z

151

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

152

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

153

Low-cost multispectral vegetation imaging system for detecting leaking CO2 gas  

E-Print Network [OSTI]

Low-cost multispectral vegetation imaging system for detecting leaking CO2 gas Justin A. Hogan,1 sequestration sites for possible leaks of the CO2 gas from underground reservoirs, a low-cost multispectral are then flagged for closer inspection with in-situ CO2 sensors. The system is entirely self

Shaw, Joseph A.

154

Intermediate-Scale Laboratory Experiments of Subsurface Flow and Transport Resulting from Tank Leaks  

SciTech Connect (OSTI)

Washington River Protection Solutions contracted with Pacific Northwest National Laboratory to conduct laboratory experiments and supporting numerical simulations to improve the understanding of water flow and contaminant transport in the subsurface between waste tanks and ancillary facilities at Waste Management Area C. The work scope included two separate sets of experiments: Small flow cell experiments to investigate the occurrence of potential unstable fingering resulting from leaks and the limitations of the STOMP (Subsurface Transport Over Multiple Phases) simulator to predict flow patterns and solute transport behavior under these conditions. Unstable infiltration may, under certain conditions, create vertically elongated fingers potentially transporting contaminants rapidly through the unsaturated zone to groundwater. The types of leak that may create deeply penetrating fingers include slow release, long duration leaks in relatively permeable porous media. Such leaks may have occurred below waste tanks at the Hanford Site. Large flow experiments to investigate the behavior of two types of tank leaks in a simple layered system mimicking the Waste Management Area C. The investigated leaks include a relatively large leak with a short duration from a tank and a long duration leak with a relatively small leakage rate from a cascade line.

Oostrom, Martinus; Wietsma, Thomas W.

2014-09-30T23:59:59.000Z

155

Methods for Integrated Leak Detection Inference at CO2 Sequestration Sites  

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

Methods for Integrated Leak Detection Inference at CO2 Sequestration Sites Methods for Integrated Leak Detection Inference at CO2 Sequestration Sites Speaker(s): Mitchell Small Date: March 23, 2010 - 12:00pm Location: 90-3122 This seminar will explain a methodology for combining site characterization and soil CO2 monitoring for detecting leaks at geologic CO2 sequestration sites. Near surface CO2 fluxes resulting from a leak are simulated using the TOUGH2 model for different values of soil permeability, leakage rate and vadose zone thickness. Natural background soil CO2 flux rates are characterized by a Bayesian hierarchical model that predicts the background flux as a function of soil temperature. A presumptive leak is assumed if the monitored flux rate exceeds a critical value corresponding to a very high (e.g., 99%) prediction interval for the natural flux conditioned on

156

NETL: News Release - Field Testing Underway of Remote Sensor Gas Leak  

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

September 16, 2004 September 16, 2004 Field Testing Underway of Remote Sensor Gas Leak Detection Systems CASPER, WY-An extensive field test that will document and demonstrate how effective technologies are in remotely detecting natural gas leaks is being held September 13-17, as the Department of Energy simulates natural gas leaks along a predetermined course at DOE's Rocky Mountain Oilfield Testing Center (RMOTC). Low-flying aircraft, satellites and special ground vehicles carrying advanced leak detection sensors will participate as representatives of the gas industry and potential technology manufacturers observe the technologies in a real-world environment and evaluate their readiness for commercialization. The test plan was devised with strong input from an industry advisory board and test participants to compare the effectiveness of several gas-leak detection devices from ground, air and satellite based platforms.

157

NETL: News Release - Vehicle-Mounted Natural Gas Leak Detector Passes Key  

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

October 2, 2003 October 2, 2003 Vehicle-Mounted Natural Gas Leak Detector Passes Key "Road Test" Spots Natural Gas Leaks from 30 Feet Away At Speeds Approaching 20 Miles Per Hour Handheld Prototype Gas Detector Now Being Outfitted as a Van-Mounted Unit PSI has modified this early prototype of a handheld remote natural gas detector to operate from a moving vehicle. ANDOVER, MA - Physical Sciences Inc. (PSI) recently conducted a successful test of its mobile natural gas detector at the company's research facilities in Andover, Mass. PSI's prototype leak detector demonstrated its ability to spot natural gas leaks from a distance of up to 30 feet from a vehicle moving at speeds approaching 20 miles per hour. In the United States, significant resources are devoted annually to leak

158

Hanford Determines Double-Shell Tank Leaked Waste From Inner Tank |  

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

Determines Double-Shell Tank Leaked Waste From Inner Tank Determines Double-Shell Tank Leaked Waste From Inner Tank Hanford Determines Double-Shell Tank Leaked Waste From Inner Tank October 22, 2012 - 12:00pm Addthis Media Contacts Lori Gamache, ORP 509-372-9130 John Britton, WRPS 509-376-5561 RICHLAND - The Department of Energy's Office of River Protection (ORP), working with its Hanford tank operations contractor Washington River Protection Solutions, has determined that there is a slow leak of chemical and radioactive waste into the annulus space in Tank AY-102, the approximately 30-inch area between the inner primary tank and the outer tank that serves as the secondary containment for these types of tanks. This is the first time a double-shell tank (DST) leak from the primary tank into the annulus has been identified. There is no indication of waste in

159

Direct calculation of leak path factors for highly compartmentalized buildings  

SciTech Connect (OSTI)

The large, highly compartmentalized configurations of buildings at many Department of Energy (DOE) facilities call the validity of traditional, simplistic methods for estimating contaminant leak path factors (LPFs) into question. Conversely, rigorous calculation of LPFs using detailed flow-field analysis computer codes is impractical for routine analysis. This paper describes a recent application of a rigorous, yet practical, method of calculating LPFs for the Chemical and Metallurgical Research (CMR) Facility at Los Alamos National Laboratory (LANL). The approach involves computer simulation of airborne contaminant transport using the MELCOR computer code. MELCOR is a general-purpose, fluid flow and aerosol transport analysis code originally developed by the US Nuclear Regulatory Commission to evaluate the release, transport, and deposition of radionuclides in nuclear reactor systems. However, the fundamental mathematical models in the code and the modular code architecture make it suitable to the CMR analysis.

Leonard, M.T. [ITS Corp., Albuquerque, NM (United States); McClure, P.R. [Los Alamos National Lab., NM (United States)

1998-12-01T23:59:59.000Z

160

Quantification of undersea gas leaks from carbon capture and storage facilities, from pipelines and from methane seeps, by their acoustic emissions  

Science Journals Connector (OSTI)

...Quantification of undersea gas leaks from carbon capture and storage facilities, from...importance of leak detection from carbon capture and storage facilities and the...pipelines or leaks from facilities for carbon capture and storage) have the advantage...

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

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

162

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

163

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

164

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.

165

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...

166

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...

167

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...

168

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

169

Evaluation of personal dose equivalent using optically stimulated luminescent dosemeters in Marumori after the Fukushima nuclear accident  

Science Journals Connector (OSTI)

......luminescent dosemeters after the Fukushima nuclear accident. The cumulative...resulted in severe damage to the Fukushima Daiichi nuclear power plant...materials into the atmosphere. Aerial measurements carried out by...in Miyagi, a neighboring Fukushima prefecture, is located 46......

Hiroko Yoshida-Ohuchi; Noriyasu Hirasawa; Ikuo Kobayashi; Takeshi Yoshizawa

2013-05-01T23:59:59.000Z

170

Hanford Single-Shell Tank Leak Causes and Locations - 241-SX Farm  

SciTech Connect (OSTI)

This document identifies 241-SX Tank Farm (SX Farm) leak causes and locations for the 100 series leaking tanks (241-SX-107, 241-SX-108, 241-SX-109, 241-SX-111, 241-SX-112, 241-SX-113, 241-SX-114, and 241-SX-115) identified in RPP-ENV-39658, Rev. 0, Hanford SX-Farm Leak Assessments Report. This document satisfies the SX Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L. [Washington River Protection Solutions (United States); Harlow, Donald G. [Washington River Protection Solutions (United States)

2014-01-08T23:59:59.000Z

171

Hanford Single-Shell Tank Leak Causes and Locations - 241-BY and 241-TY Farm  

SciTech Connect (OSTI)

This document identifies 241-BY Tank Farm (BY Farm) and 241-TY Tank Farm (TY Farm) lead causes and locations for the 100 series leaking tanks (241-BY-103, 241-TY-103, 241-TY-104, 241-TY-105 and 241-TY-106) identified in RPP-RPT-43704, Hanford BY Farm Leak Assessments Report, and in RPP-RPT-42296, Hanford TY Farm Leak Assessments Report. This document satisfies the BY and TY Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L.; Harlow, Donald G.

2014-09-04T23:59:59.000Z

172

Demonstration of rapid and sensitive module leak certification for space station freedom. Final report  

SciTech Connect (OSTI)

A leak detection and quantification demonstration using perflurocarbon tracer (PFT) technology was successfully performed at the NASA Marshall Space Flight Center on January 25, 1991. The real-time Dual Trap Analyzer (DTA) at one-half hour after the start of the first run gave an estimated leak rate of 0.7 mL/min. This has since been refined to be 1.15 {plus_minus} 0.09 mL/min. The leak rates in the next three runs were determined to be 9.8 {plus_minus} 0.7, {minus}0.4 {plus_minus} 0.3, and 76 {plus_minus} 6 mL/min, respectively. The theory on leak quantification in the steady-state and time-dependent modes for a single zone test facility was developed and applied to the above determinations. The laboratory PFT analysis system gave a limit-of-detection (LOD) of 0.05 fL for ocPDCH. This is the tracer of choice and is about 100-fold better than that for the DTA. Applied to leak certification, the LOD is about 0.00002 mL/s (0.000075 L/h), a 5 order-of-magnitude improvement over the original leak certification specification. Furthermore, this limit can be attained in a measurement period of 3 to 4 hours instead of days, weeks, or months. A new Leak Certification Facility is also proposed to provide for zonal (three zones) determination of leak rates. The appropriate multizone equations, their solutions, and error analysis have already been derived. A new concept of seal-integrity certification has been demonstrated for a variety of controlled leaks in the range of module leak testing. High structural integrity leaks were shown to have a linear dependence of flow on {Delta}p. The rapid determination of leak rates at different pressures is proposed and is to be determined while subjecting the module to other external force-generating parameters such as vibration, torque, solar intensity, etc. 13 refs.

Dietz, R.N.; Goodrich, R.W. [Brookhaven National Lab., Upton, NY (United States)

1991-03-01T23:59:59.000Z

173

Demonstration of rapid and sensitive module leak certification for space station freedom  

SciTech Connect (OSTI)

A leak detection and quantification demonstration using perflurocarbon tracer (PFT) technology was successfully performed at the NASA Marshall Space Flight Center on January 25, 1991. The real-time Dual Trap Analyzer (DTA) at one-half hour after the start of the first run gave an estimated leak rate of 0.7 mL/min. This has since been refined to be 1.15 {plus minus} 0.09 mL/min. The leak rates in the next three runs were determined to be 9.8 {plus minus} 0.7, {minus}0.4 {plus minus} 0.3, and 76 {plus minus} 6 mL/min, respectively. The theory on leak quantification in the steady-state and time-dependent modes for a single zone test facility was developed and applied to the above determinations. The laboratory PFT analysis system gave a limit-of-detection (LOD) of 0.05 fL for ocPDCH. This is the tracer of choice and is about 100-fold better than that for the DTA. Applied to leak certification, the LOD is about 0.00002 mL/s (0.000075 L/h), a 5 order-of-magnitude improvement over the original leak certification specification. Furthermore, this limit can be attained in a measurement period of 3 to 4 hours instead of days, weeks, or months. A new Leak Certification Facility is also proposed to provide for zonal (three zones) determination of leak rates. The appropriate multizone equations, their solutions, and error analysis have already been derived. A new concept of seal-integrity certification has been demonstrated for a variety of controlled leaks in the range of module leak testing. High structural integrity leaks were shown to have a linear dependence of flow on {Delta}p. The rapid determination of leak rates at different pressures is proposed and is to be determined while subjecting the module to other external force-generating parameters such as vibration, torque, solar intensity, etc. 13 refs.

Dietz, R.N.; Goodrich, R.W. (Brookhaven National Lab., Upton, NY (United States))

1991-03-01T23:59:59.000Z

174

Effects of spent fuel types on offsite consequences of hypothetical accidents  

SciTech Connect (OSTI)

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

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

2000-02-18T23:59:59.000Z

175

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

176

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

177

U.S. strategic petroleum reserve Big Hill 114 leak analysis 2012.  

SciTech Connect (OSTI)

This report addresses recent well integrity issues related to cavern 114 at the Big Hill Strategic Petroleum Reserve site. DM Petroleum Operations, M&O contractor for the U.S. Strategic Petroleum Reserve, recognized an apparent leak in Big Hill cavern well 114A in late summer, 2012, and provided written notice to the State of Texas as required by law. DM has since isolated the leak in well A with a temporary plug, and is planning on remediating both 114 A- and B-wells with liners. In this report Sandia provides an analysis of the apparent leak that includes: (i) estimated leak volume, (ii) recommendation for operating pressure to maintain in the cavern between temporary and permanent fixes for the well integrity issues, and (iii) identification of other caverns or wells at Big Hill that should be monitored closely in light of the sequence of failures there in the last several years.

Lord, David L.; Roberts, Barry L.; Lord, Anna C. Snider; Sobolik, Steven Ronald; Park, Byoung Yoon; Rudeen, David Keith [GRAM, Inc., Albuquerque, NM

2013-06-01T23:59:59.000Z

178

UTILITIES PROBLEMS AND FAILURES Electrical or plumbing failure/Flooding/Water leak/Natural gas or  

E-Print Network [OSTI]

UTILITIES PROBLEMS AND FAILURES Electrical or plumbing failure/Flooding/Water leak/Natural gas or a generator? NOTIFY the University Police. FOLLOW evacuation procedures. NOTIFY Building Safety personnel

Fernandez, Eduardo

179

UTILITIES PROBLEMS AND FAILURES Electrical or plumbing failure/Flooding/Water leak/Natural gas  

E-Print Network [OSTI]

UTILITIES PROBLEMS AND FAILURES Electrical or plumbing failure/Flooding/Water leak/Natural gas. . What should I do if the if the building does not have emergency lighting or a generator? NOTIFY

Fernandez, Eduardo

180

PLC Software Program for Leak Detector Station A1 SALW-LD-ST-A1  

SciTech Connect (OSTI)

This document describes the software program for the programmable logic controller for the leak detector station ''SALW-LD-ST-A1''. The appendices contains a copy of the printout of the software program.

KOCH, M.R.

2001-01-25T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

Passive air cooling of liquid metal-cooled reactor with double vessel leak accommodation capability  

DOE Patents [OSTI]

A passive and inherent shutdown heat removal method with a backup air flow path which allows decay heat removal following a postulated double vessel leak event in a liquid metal-cooled nuclear reactor. The improved reactor design incorporates the following features: (1) isolation capability of the reactor cavity environment in the event that simultaneous leaks develop in both the reactor and containment vessels; (2) a reactor silo liner tank which insulates the concrete silo from the leaked sodium, thereby preserving the silo's structural integrity; and (3) a second, independent air cooling flow path via tubes submerged in the leaked sodium which will maintain shutdown heat removal after the normal flow path has been isolated.

Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

1995-01-01T23:59:59.000Z

182

Thermal Imaging of Vegetation to Detect CO2 Gas Leaking From Underground  

Science Journals Connector (OSTI)

Thermal imaging of vegetation has been used to detect CO2 gas leaking from an underground gas reservoir. Plant stress caused by increased soil gas concentration results in warmer...

Shaw, Joseph A; Johnson, Jennifer E; Lawrence, Rick; Nugent, Paul W

183

AIRBORNE, OPTICAL REMOTE SENSNG OF METHANE AND ETHANE FOR NATURAL GAS PIPELINE LEAK DETECTION  

SciTech Connect (OSTI)

Ophir Corporation was awarded a contract by the U. S. Department of Energy, National Energy Technology Laboratory under the Project Title ''Airborne, Optical Remote Sensing of Methane and Ethane for Natural Gas Pipeline Leak Detection'' on October 14, 2002. The scope of the work involved designing and developing an airborne, optical remote sensor capable of sensing methane and, if possible, ethane for the detection of natural gas pipeline leaks. Flight testing using a custom dual wavelength, high power fiber amplifier was initiated in February 2005. Ophir successfully demonstrated the airborne system, showing that it was capable of discerning small amounts of methane from a simulated pipeline leak. Leak rates as low as 150 standard cubic feet per hour (scf/h) were detected by the airborne sensor.

Jerry Myers

2005-04-15T23:59:59.000Z

184

Thermal Imaging of Canals for Remote Detection of Leaks: Evaluation in the United Irrigation District  

E-Print Network [OSTI]

This report summarizes our initial analysis of the potential of thermal imaging for detecting leaking canals and pipelines. Thermal imagery (video format) was obtained during a fly over of a portion of the main canal of United Irrigation District...

Huang, Yanbo; Fipps, Guy

185

BP Oil Spill Footage (High Def) - Leak at 4850' - June 3 2010...  

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

3 of 4) BP Oil Spill Footage (High Def) - Leak at 4850' - June 3 2010 (3 of 4) Addthis Description Footage of the BP Oil Spill Duration 0:19...

186

BP Oil Spill Footage (High Def) - Leak at 4850' - June 3 2010...  

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

2 of 4) BP Oil Spill Footage (High Def) - Leak at 4850' - June 3 2010 (2 of 4) Addthis Description Footage of the BP Oil Spill Duration 0:13...

187

BP Oil Spill Footage (High Def) - Leak at 4840' - June 3 2010...  

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

40' - June 3 2010 (1 of 4) BP Oil Spill Footage (High Def) - Leak at 4840' - June 3 2010 (1 of 4) Addthis Description Footage of the BP Oil Spill Duration 0:15...

188

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

189

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

190

if it is a gas leak, do not activate building alarms, use mobile phones, hand held radios, electronic equipment or light flammable material!  

E-Print Network [OSTI]

gas leak gas leak if it is a gas leak, do not activate building alarms, use mobile phones, hand held radios, electronic equipment or light flammable material! 1. If you discover a Gas Leak, shout and check that the nearest gas isolator switch is off. 4. Evacuate the building immediately, avoiding

Hickman, Mark

191

Model based detection of hydrogen leaks in a fuel cell stack Ari Ingimundarson and Anna G. Stefanopoulou and Denise McKay  

E-Print Network [OSTI]

Model based detection of hydrogen leaks in a fuel cell stack Ari Ingimundarson and Anna G. Stefanopoulou and Denise McKay Abstract-- Hydrogen leaks are potentially dangerous faults in fuel cell systems detection, leak detection, hydrogen leak- age. I. INTRODUCTION A common safety concern for fuel cell systems

Stefanopoulou, Anna

192

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...

193

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...

194

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...

195

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 -...

196

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...

197

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...

198

Leak Detection and H2 Sensor Development for Hydrogen Applications  

SciTech Connect (OSTI)

The objectives of this report are: (1) Develop a low cost, low power, durable, and reliable hydrogen safety sensor for a wide range of vehicle and infrastructure applications; (2) Continually advance test prototypes guided by materials selection, sensor design, electrochemical R&D investigation, fabrication, and rigorous life testing; (3) Disseminate packaged sensor prototypes and control systems to DOE Laboratories and commercial parties interested in testing and fielding advanced prototypes for cross-validation; (4) Evaluate manufacturing approaches for commercialization; and (5) Engage an industrial partner and execute technology transfer. Recent developments in the search for sustainable and renewable energy coupled with the advancements in fuel cell powered vehicles (FCVs) have augmented the demand for hydrogen safety sensors. There are several sensor technologies that have been developed to detect hydrogen, including deployed systems to detect leaks in manned space systems and hydrogen safety sensors for laboratory and industrial usage. Among the several sensing methods electrochemical devices that utilize high temperature-based ceramic electrolytes are largely unaffected by changes in humidity and are more resilient to electrode or electrolyte poisoning. The desired sensing technique should meet a detection threshold of 1% (10,000 ppm) H{sub 2} and response time of {approx_equal}1 min, which is a target for infrastructure and vehicular uses. Further, a review of electrochemical hydrogen sensors by Korotcenkov et.al and the report by Glass et.al suggest the need for inexpensive, low power, and compact sensors with long-term stability, minimal cross-sensitivity, and fast response. This view has been largely validated and supported by the fuel cell and hydrogen infrastructure industries by the NREL/DOE Hydrogen Sensor Workshop held on June 8, 2011. Many of the issues preventing widespread adoption of best-available hydrogen sensing technologies available today outside of cost, derive from excessive false positives and false negatives arising from signal drift and unstable sensor baseline; both of these problems necessitate the need for unacceptable frequent calibration.

Brosha, Eric L. [Los Alamos National Laboratory

2012-07-10T23:59:59.000Z

199

A LOW-COST GPR GAS PIPE & LEAK DETECTOR  

SciTech Connect (OSTI)

A light-weight, easy to use ground penetrating radar (GPR) system for tracking metal/non-metal pipes has been developed. A pre-production prototype instrument has been developed whose production cost and ease of use should fit important market niches. It is a portable tool which is swept back and forth like a metal detector and which indicates when it goes over a target (metal, plastic, concrete, etc.) and how deep it is. The innovation of real time target detection frees the user from having to interpret geophysical data and instead presents targets as dots on the screen. Target depth is also interpreted automatically, relieving the user of having to do migration analysis. In this way the user can simply walk around looking for targets and, by ''connecting the dots'' on the GPS screen, locate and follow pipes in real time. This is the first tool known to locate metal and non-metal pipes in real time and map their location. This prototype design is similar to a metal detector one might use at the beach since it involves sliding a lightweight antenna back and forth over the ground surface. The antenna is affixed to the end of an extension that is either clipped to or held by the user. This allows him to walk around in any direction, either looking for or following pipes with the antenna location being constantly recorded by the positioning system. Once a target appears on the screen, the user can locate by swinging the unit to align the cursor over the dot. Leak detection was also a central part of this project, and although much effort was invested into its development, conclusive results are not available at the time of the writing of this document. Details of the efforts that were made as a part of this cooperative agreement are presented.

David Cist; Alan Schutz

2005-03-30T23:59:59.000Z

200

Guest Editorial: Laser Damage  

SciTech Connect (OSTI)

Laser damage of optical materials, first reported in 1964, continues to limit the output energy and power of pulsed and continuous-wave laser systems. In spite of some 48 years of research in this area, interest from the international laser community to laser damage issues remains at a very high level and does not show any sign of decreasing. Moreover, it grows with the development of novel laser systems, for example, ultrafast and short-wavelength lasers that involve new damage effects and specific mechanisms not studied before. This interest is evident from the high level of attendance and presentations at the annual SPIE Laser Damage Symposium (aka, Boulder Damage Symposium) that has been held in Boulder, Colorado, since 1969. This special section of Optical Engineering is the first one devoted to the entire field of laser damage rather than to a specific part. It is prepared in response to growing interest from the international laser-damage community. Some papers in this special section were presented at the Laser Damage Symposium; others were submitted in response to the general call for papers for this special section. The 18 papers compiled into this special section represent many sides of the broad field of laser-damage research. They consider theoretical studies of the fundamental mechanisms of laser damage including laser-driven electron dynamics in solids (O. Brenk and B. Rethfeld; A. Nikiforov, A. Epifanov, and S. Garnov; T. Apostolova et al.), modeling of propagation effects for ultrashort high-intensity laser pulses (J. Gulley), an overview of mechanisms of inclusion-induced damage (M. Koldunov and A. Manenkov), the formation of specific periodic ripples on a metal surface by femtosecond laser pulses (M. Ahsan and M. Lee), and the laser-plasma effects on damage in glass (Y. Li et al). Material characterization is represented by the papers devoted to accurate and reliable measurements of absorption with special emphasis on thin films (C. Mhlig and S. Bublitz; B. Cho, E. Danielewicz, and J. Rudisill; W. Palm et al; and J. Lu et al.). Statistical treatment of measurements of the laser-damage threshold (J. Arenberg) and the relationship to damage mechanisms (F. Wagner et al.) represent the large subfield of laser-damage measurements. Various aspects of multilayer coating and thin-film characterization are considered in papers by B. Cho, J. Rudisill, and E. Danielewicz (spectral shift in multilayer mirrors) and R. Weber et al. (novel approach to damage studies based on third-harmonic generation microscopy). Of special interest for readers is the paper by C. Stolz that summarizes the results of four thin-film damage competitions organized as a part of the Laser Damage Symposium. Another paper is devoted to thermal annealing of damage precursors (N. Shen et al.). Finally, the influence of nano-size contamination on initiation of laser damage by ultrashort pulses is considered in paper of V. Komolov et al.

Vitaly Gruzdev, Michelle D. Shinn

2012-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

AUTOMATED LEAK DETECTION OF BURIED TANKS USING GEOPHYSICAL METHODS AT THE HANFORD NUCLEAR SITE  

SciTech Connect (OSTI)

At the Hanford Nuclear Site in Washington State, the Department of Energy oversees the containment, treatment, and retrieval of liquid high-level radioactive waste. Much of the waste is stored in single-shelled tanks (SSTs) built between 1943 and 1964. Currently, the waste is being retrieved from the SSTs and transferred into newer double-shelled tanks (DSTs) for temporary storage before final treatment. Monitoring the tanks during the retrieval process is critical to identifying leaks. An electrically-based geophysics monitoring program for leak detection and monitoring (LDM) has been successfully deployed on several SSTs at the Hanford site since 2004. The monitoring program takes advantage of changes in contact resistance that will occur when conductive tank liquid leaks into the soil. During monitoring, electrical current is transmitted on a number of different electrode types (e.g., steel cased wells and surface electrodes) while voltages are measured on all other electrodes, including the tanks. Data acquisition hardware and software allow for continuous real-time monitoring of the received voltages and the leak assessment is conducted through a time-series data analysis. The specific hardware and software combination creates a highly sensitive method of leak detection, complementing existing drywell logging as a means to detect and quantify leaks. Working in an industrial environment such as the Hanford site presents many challenges for electrical monitoring: cathodic protection, grounded electrical infrastructure, lightning strikes, diurnal and seasonal temperature trends, and precipitation, all of which create a complex environment for leak detection. In this discussion we present examples of challenges and solutions to working in the tank farms of the Hanford site.

CALENDINE S; SCHOFIELD JS; LEVITT MT; FINK JB; RUCKER DF

2011-03-30T23:59:59.000Z

202

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

203

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

204

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

205

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

206

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...

207

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

208

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

209

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

210

Ultrasensitive leak detection during ultrahigh vacuum evacuation by quadrupole mass spectrometer  

SciTech Connect (OSTI)

One must do ultrasensitive leak detection during ultrahigh-vacuum (UHV) evacuation, especially just before the device is sealed off from the vacuum system, to guarantee the longevity of the sealed high-vacuum or even UHV devices with small volume. A quadrupole mass spectrometer (QMS) with an UHV evacuation system can be used under accumulation mode to do the testing. Possible accumulate modes, as well as their advantages and shortcomings, are studied experimentally and discussed in this paper. We found that the opening action of the metal valve during accumulation mode always severely affects the height of the peak indicated by QMS and causes considerable errors. If we determine the leak rate by the peak area instead of the peak height, the situation is much improved. This method has proven quite useful in ensuring the tightness quality for complex sealed UHV devices with small volumes. Ultrasensitive leak detection has been carried out for such real evacuating devices, and a leak rate of 2x10{sup -14} Pa{center_dot}m{sup 3}/s was detected, which is far lower than its dynamic mode and the detection limit of the current advanced commercial leak detectors.

Chen Xu; Huang Tianbin; Wang Ligong; Jin Qiji; Cha Liangzhen [Department of Electronic Engineering, Tsinghua University, Beijing, 100084 (China)

2006-01-15T23:59:59.000Z

211

Flight Testing of an Advanced Airborne Natural Gas Leak Detection System  

SciTech Connect (OSTI)

ITT Industries Space Systems Division (Space Systems) has developed an airborne natural gas leak detection system designed to detect, image, quantify, and precisely locate leaks from natural gas transmission pipelines. This system is called the Airborne Natural Gas Emission Lidar (ANGEL) system. The ANGEL system uses a highly sensitive differential absorption Lidar technology to remotely detect pipeline leaks. The ANGEL System is operated from a fixed wing aircraft and includes automatic scanning, pointing system, and pilot guidance systems. During a pipeline inspection, the ANGEL system aircraft flies at an elevation of 1000 feet above the ground at speeds of between 100 and 150 mph. Under this contract with DOE/NETL, Space Systems was funded to integrate the ANGEL sensor into a test aircraft and conduct a series of flight tests over a variety of test targets including simulated natural gas pipeline leaks. Following early tests in upstate New York in the summer of 2004, the ANGEL system was deployed to Casper, Wyoming to participate in a set of DOE-sponsored field tests at the Rocky Mountain Oilfield Testing Center (RMOTC). At RMOTC the Space Systems team completed integration of the system and flew an operational system for the first time. The ANGEL system flew 2 missions/day for the duration for the 5-day test. Over the course of the week the ANGEL System detected leaks ranging from 100 to 5,000 scfh.

Dawn Lenz; Raymond T. Lines; Darryl Murdock; Jeffrey Owen; Steven Stearns; Michael Stoogenke

2005-10-01T23:59:59.000Z

212

A CT scan aided core-flood study of the leak-off process in oil-based drilling fluids :.  

E-Print Network [OSTI]

??An experimental study on the leak-off of oil based drilling fluid sandstone cores is reported. First we revised the theoretical models for the rheology of (more)

Van Overveldt, A.S.

2011-01-01T23:59:59.000Z

213

MEMOIRS OF A LEAK: Infiltrating Research for a Quarter of a Century  

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

MEMOIRS OF A LEAK: Infiltrating Research for a Quarter of a Century MEMOIRS OF A LEAK: Infiltrating Research for a Quarter of a Century Speaker(s): Max Sherman Date: November 16, 2000 - 12:00pm Location: Bldg. 90 Seminar Host/Point of Contact: David Faulkner Infiltration is the (usually uncontrolled) flow of air through leaks in the building envelope, driven by natural and mechanical pressures. Before the oil crises, there was not a lot of interest in infiltration. For houses and other envelope-dominated buildings, however, infiltration typically accounted for all of their ventilation needs and 1/3-1/2 of their space-conditioning load. Starting in the mid-70s there was a realization that this important problem was not well understood, but represented an important energy-saving opportunity. Research institutions around the world

214

Saltwell Leak Detector Station Programmable Logic Controller (PLC) Software Configuration Management Plan (SCMP)  

SciTech Connect (OSTI)

This document provides the procedures and guidelines necessary for computer software configuration management activities during the operation and maintenance phases of the Saltwell Leak Detector Stations as required by HNF-PRO-309, Rev. 1, Computer Software Quality Assurance, Section 2.4, Software Configuration Management. The software configuration management plan (SCMP) integrates technical and administrative controls to establish and maintain technical consistency among requirements, physical configuration, and documentation for the Saltwell Leak Detector Station Programmable Logic Controller (PLC) software during the Hanford application, operations and maintenance. This SCMP establishes the Saltwell Leak Detector Station PLC Software Baseline, status changes to that baseline, and ensures that software meets design and operational requirements and is tested in accordance with their design basis.

WHITE, K.A.

2000-11-28T23:59:59.000Z

215

SIXTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton{reg_sign} GLT O-rings used in the Model 9975 package has been ongoing for seven years at the Savannah River National Laboratory. Seventy tests using mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested periodically to determine if they meet the criterion of leak-tightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 33 GLT O-ring fixtures at 200-300 F. Room temperature leak test failures have been experienced in all of the GLT O-ring fixtures aging at 350 F and higher temperatures, and in 7 fixtures aging at 300 F. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 41-60 months, which is still bounding to O-ring temperatures during storage in K-Area Complex (KAC). Based on expectations that the fixtures aging at 200 F will remain leak-tight for a significant period yet to come, 2 additional fixtures began aging within the past year at an intermediate temperature of 270 F, with hopes that they may leak before the 200 F fixtures. High temperature aging continues for 6 GLT-S O-ring fixtures at 200-300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200-300 F for up to 26 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the Orings displayed a compression set ranging from 51-96%. This is greater than seen to date for packages inspected during KAC field surveillance (24% average). For GLT O-rings, separate service life estimates have been made based on the O-ring fixture leak test data and based on compression stress relaxation (CSR) data. These two predictive models show reasonable agreement at higher temperatures (350-400 F). However, at 300 F, the room temperature leak test failures to date experienced longer aging times than predicted by the CSR-based model. This suggests that extrapolations of the CSR model predictions to temperatures below 300 F will provide a conservative prediction of service life relative to the leak rate criterion. Leak test failure data at lower temperatures are needed to verify this apparent trend. Insufficient failure data exist currently to perform a similar comparison for GLT-S O-rings. Aging and periodic leak testing will continue for the remaining fixtures.

Daugherty, W.

2011-08-31T23:59:59.000Z

216

EXTENDED PERFORMANCE HANDHELD AND MOBILE SENSORS FOR REMOTE DETECTION OF NATURAL GAS LEAKS  

SciTech Connect (OSTI)

This report summarizes work performed by Physical Sciences Inc. (PSI) to advance the state-of-the-art of surveying for leaks of natural gas from transmission and distribution pipelines. The principal project goal was to develop means of deploying on an automotive platform an improved version of the handheld laser-based standoff natural gas leak detector previously developed by PSI and known as the Remote Methane Leak Detector or RMLD. A laser beam which interrogates the air for methane is projected from a spinning turret mounted upon a van. As the van travels forward, the laser beam scans an arc to the front and sides of the van so as to survey across streets and to building walls from a moving vehicle. When excess methane is detected within the arc, an alarm is activated. In this project, we built and tested a prototype Mobile RMLD (MRMLD) intended to provide lateral coverage of 10 m and one lateral scan for every meter of forward motion at forward speeds up to 10 m/s. Using advanced detection algorithms developed as part of this project, the early prototype MRMLD, installed on the back of a truck, readily detected simulated gas leaks of 50 liters per hour. As a supplement to the originally planned project, PSI also participated in a DoE demonstration of several gas leak detection systems at the Rocky Mountain Oilfield Testing Center (RMOTC) during September 2004. Using a handheld RMLD upgraded with the advanced detection algorithms developed in this project, from within a moving vehicle we readily detected leaks created along the 7.4 mile route of a virtual gas transmission pipeline.

Michael B. Frish; B. David Green; Richard T. Wainner; Francesca Scire-Scappuzzo; Paul Cataldi; Matthew C. Laderer

2005-05-01T23:59:59.000Z

217

The leak resistance of 2-inch N-80 API treaded tubular connection  

E-Print Network [OSTI]

THE LEAK RESISTANCE OF 2-INCH N-80 API THREAD TOBULAR CONNECTION A Thesis Peter D. Weiner Submitted to the Graduate School of the Agricultural and Mechanical College of Texas in Partial fulfillment of the requirements for the degree of MASTER... OF SCIENCE January 1961 Ma)or Subject: Mechanical Engineering THE LEAK RESISTANCE OF 2-INCH N-80 API THREADED TUBULAR COHHECTIOH A Thesis By Peter D. Weiner Approved as to style and content by: Chairman of ittee Head of Department January 1961...

Weiner, Peter Douglas

2012-06-07T23:59:59.000Z

218

The inspection of recovery boilers to detect factors that cause critical leaks  

SciTech Connect (OSTI)

Records compiled by the Black Liquor Recovery Boiler Advisory Committee (BLRBAC) include more than 140 recovery boiler explosions that occurred from 1948 to 1990. Although some incidents were due to improper boiler operation, many were caused by critical leaks arising from corrosion, erosion, metal fatigue, or other processes not directly under the control of the boiler operator. In this paper, the authors will examine the extent to which common boiler inspection practices can be expected to expose conditions like those that have led to critical leaks.

Bauer, D.G.; Sharp, W.B.A. (Westvaco Corp., Laurel Research Lab., Laurel, MD (United States))

1991-09-01T23:59:59.000Z

219

MORECA: A computer code for simulating modular high-temperature gas-cooled reactor core heatup accidents  

SciTech Connect (OSTI)

The design features of the modular high-temperature gas-cooled reactor (MHTGR) have the potential to make it essentially invulnerable to damage from postulated core heatup accidents. This report describes the ORNL MORECA code, which was developed for analyzing postulated long-term core heatup scenarios for which active cooling systems used to remove afterheat following the accidents can be assumed to the unavailable. Simulations of long-term loss-of-forced-convection accidents, both with and without depressurization of the primary coolant, have shown that maximum core temperatures stay below the point at which any significant fuel failures and fission product releases are expected. Sensitivity studies also have been done to determine the effects of errors in the predictions due both to uncertainties in the modeling and to the assumptions about operational parameters. MORECA models the US Department of Energy reference design of a standard MHTGR.

Ball, S.J. (Oak Ridge National Lab., TN (United States))

1991-10-01T23:59:59.000Z

220

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 "leaks damage accidents" 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

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

222

Large break loss-of-coolant accident analyses for the high flux isotope reactor  

SciTech Connect (OSTI)

The US Department of Energy's High Flux Isotope Reactor (HFIR) was analyzed to evaluate it's response to a spectrum of loss-of-coolant accidents (LOCAs) with potential for leading to core damage. The MELCOR severe accident analysis code (version 1.7.1) was used to evaluate the overall dynamic response of HFIR. Before conducting LOCA analyses, the steady-state thermal-hydraulic parameters evaluated by MELCOR for various loop sections were verified against steady-state operating data. Thereafter, HFIR depressurization tests were simulated to evaluate the system pressure change for a given depletion in coolant inventory. Interesting and important safety-related phenomena were observed. The current analyses (which should be considered preliminary) that occur over a period from 1 to 3 seconds do not lead to core wide fuel melting. Core fluid flashing during the initial rapid depressurization does cause fuel temperature excursions due to adiabatic-like heatup. 3 refs., 4 figs.

Taleyarkhan, R.P. (Oak Ridge National Lab., TN (USA))

1989-01-01T23:59:59.000Z

223

Reducing Radiation Damage  

SciTech Connect (OSTI)

This talk describes the use of a modified treatment sequence, i.e., radiation dose, geometry, dwell time, etc., to mitigate some of the deleterious effects of cancer radiotherapy by utilizing natural cell repair processes. If bad side effects can be reduced, a more aggressive therapy can be put into place. Cells contain many mechanisms that repair damage of various types. If the damage can not be repaired, cells will undergo apoptosis (cell death). Data will be reviewed that support the fact that a small dose of radiation will activate damage repair genes within a cell. Once the mechanisms are fully active, they will efficiently repair the severe damage from a much larger radiation dose. The data ranges from experiments on specific cell cultures using microarray (gene chip) techniques to experiments on complete organisms. The suggested effect and treatment is consistent with the assumption that all radiation is harmful, no matter how small the dose. Nevertheless, the harm can be reduced. These mechanisms need to be further studied and characterized. In particular, their time dependence needs to be understood before the proposed treatment can be optimized. Under certain situations it is also possible that the deleterious effects of chemotherapy can be mitigated and the damage to radiation workers can be reduced.

Blankenbecler, Richard

2006-06-05T23:59:59.000Z

224

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...

225

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...

226

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...

227

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...

228

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...

229

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 ...

230

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 ...

231

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 ...

232

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

233

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

234

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

235

Leak-rate of seals: effective medium theory and comparison with experiment  

E-Print Network [OSTI]

Seals are extremely useful devices to prevent fluid leakage. We present an effective medium theory of the leak-rate of rubber seals, which is based on a recently developed contact mechanics theory. We compare the theory with experimental results for seals consisting of silicon rubber in contact with sandpaper and sand-blasted PMMA surfaces.

B. Lorenz; B. N. J. Persson

2009-11-16T23:59:59.000Z

236

Location of Leaks in Pressure Testable Direct Burial Steam Distribution Conduits  

E-Print Network [OSTI]

to determine where the breach occurred. The breach can be detected using sulfur hexafluoride (SF6) tracer gas injected into the conduit. After injection, maintenance personnel walk the path of the steam line with an SF6 detector that precisely locates the leak...

Sittel, M. G.; Messock, R. K.

237

Method for sealing remote leaks in an enclosure using an aerosol  

DOE Patents [OSTI]

The invention is a method and device for sealing leaks remotely by means of injecting a previously prepared aerosol into the enclosure being sealed according to a particular sealing efficiency defined by the product of a penetration efficiency and a particle deposition efficiency. By using different limits in the relationship between penetration efficiency and flowrate, the same method according the invention can be used for coating the inside of an enclosure. Specifically the invention is a method and device for preparing, transporting, and depositing a solid phase aerosol to the interior surface of the enclosure relating particle size, particle carrier flow rate, and pressure differential, so that particles deposited there can bridge and substantially seal each leak, with out providing a substantial coating at inside surfaces of the enclosure other than the leak. The particle size and flow parameters can be adjusted to coat the interior of the enclosure (duct) without substantial plugging of the leaks depending on how the particle size and flowrate relationships are chosen.

Modera, Mark P. (Piedmont, CA); Carrie, Francois R. (Lyons, FR)

1999-01-01T23:59:59.000Z

238

Atmospheric emissions from the Deepwater Horizon spill constrain airwater partitioning, hydrocarbon fate, and leak rate  

E-Print Network [OSTI]

releases of gas and oil mixtures is initially determined by solubility and volatility of individual bioavailability of different fractions of the gasoil mixture, and to develop a comprehensive picture of the fate of leaked hydrocarbons in the marine environ- ment. Analysis of airborne atmospheric data shows massive

Toohey, Darin W.

239

Strontium and cesium radionuclide leak detection alternatives in a capsule storage pool  

SciTech Connect (OSTI)

A study was performed to assess radionuclide leak-detection systems for use in locating a capsule leaking strontium-90 or cesium-137 into a water-filled pool. Each storage pool contains about 35,000 L of water and up to 715 capsules, each of which contains up to 150 kCi strontium-90 or 80 kCi cesium-137. Potential systems assessed included instrumental chemical analyses, radionuclide detection, visual examination, and other nondestructive nuclear-fuel examination techniques. Factors considered in the assessment include: cost, simplicity of maintenance and operation, technology availability, reliability, remote operation, sensitivity, and ability to locate an individual leaking capsule in its storage location. The study concluded that an adaption of the spent nuclear-fuel examination technique of wet sipping be considered for adaption. In the suggested approoch, samples would be taken continuously from pool water adjacent to the capsule(s) being examined for remote radiation detection. In-place capsule isolation and subsequent water sampling would confirm that a capsule was leaking radionuclides. Additional studies are needed before implementing this option. Two other techniques that show promise are ultrasonic testing and eddy-current testing.

Larson, D.E.; Crawford, T.W.; Joyce, S.M.

1981-08-01T23:59:59.000Z

240

What are the potential impacts of a leak? a) To the aquifer,  

E-Print Network [OSTI]

and irrigation wells, c) In the sandhills geology, d) In the Platte River valley geology, e) In southern Nebraska pollution in the sandhills region, j) Financially (How much would remediation cost?). Response by Professor that a leak from this pipeline would not be a great amount and would be localized to an area of 10's to 100's

Nebraska-Lincoln, University of

Note: This page contains sample records for the topic "leaks damage accidents" 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

Oil spill nears the beaches of Florida, and the leak may not be plugged before Christmas  

E-Print Network [OSTI]

Oil spill nears the beaches of Florida, and the leak may not be plugged before Christmas By David Gardner Last updated at 11:32 AM on 3rd June 2010 BP's giant oil slick was bearing down on Florida holidaymakers a year visit Florida and state leaders fear the oil will devastate a tourist industry

Belogay, Eugene A.

242

FIFTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton{reg_sign} GLT O-rings used in the Model 9975 package has been ongoing for six years at the Savannah River National Laboratory. Sixty-seven mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested at nominal six month intervals to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 36 GLT O-ring fixtures at 200-350 F. Room temperature leak test failures have been experienced in 6 of the GLT O-ring fixtures aging at 300 and 350 F, and in all 3 of the GLT O-ring fixtures aging at higher temperatures. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 30-48 months, which is still bounding to O-ring temperatures during storage in KAMS. High temperature aging continues for 6 GLT-S O-ring fixtures at 200-300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 or 300 F for 19 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the Orings displayed a compression set ranging from 51-95%. This is significantly greater than seen to date for packages inspected during KAMS field surveillance (23% average). For GLT O-rings, service life based on the room temperature leak rate criterion is comparable to that predicted by compression stress relaxation (CSR) data at higher temperatures (350-400 F). While there are no comparable failure data yet at aging temperatures below 300 F, extrapolations of the data for GLT O-rings suggests the CSR model predictions provide a conservative prediction of service life relative to the leak rate criterion. Failure data at lower temperatures are needed to verify this apparent trend. Insufficient failure data exist currently to perform a similar comparison for GLT-S O-rings. Aging and periodic leak testing will continue for the remaining fixtures.

Daugherty, W.; Hoffman, E.

2011-04-11T23:59:59.000Z

243

FIFTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton{sup reg.} GLT O-rings used in the Model 9975 package has been ongoing for six years at the Savannah River National Laboratory. Sixty-seven mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested at nominal six month intervals to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 36 GLT O-ring fixtures at 200--350 F. Room temperature leak test failures have been experienced in 5 of the GLT O-ring fixtures aging at 300 and 350 F, and in all 3 of the GLT O-ring fixtures aging at higher temperatures. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 30--48 months, which is still bounding to O-ring temperatures during storage in KAMS. High temperature aging continues for 6 GLT-S O-ring fixtures at 200--300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 or 300 F for 19 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the O-rings displayed a compression set ranging from 51--95%. This is significantly greater than seen to date for packages inspected during KAMS field surveillance (23% average). For GLT O-rings, service life based on the room temperature leak rate criterion is comparable to that predicted by compression stress relaxation (CSR) data at higher temperatures (350--400 F). While there are no comparable failure data yet at aging temperatures below 300 F, extrapolations of the data for GLT O-rings suggests that CSR model predictions provide a conservative prediction of service life relative to the leak rate criterion. Failure data at lower temperatures is needed to verify this apparent trend. Insufficient failure data exist currently to perform a similar comparison for GLT-S O-rings. Aging and periodic leak testing will continue for the remaining fixtures.

Daugherty, W.; Hoffman, E.

2010-11-01T23:59:59.000Z

244

Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics  

SciTech Connect (OSTI)

The safe, reliable and economic operation of the nations 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 industrys 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

245

Engineering evaluation of alternatives: Managing the assumed leak from single-shell Tank 241-T-101  

SciTech Connect (OSTI)

At mid-year 1992, the liquid level gage for Tank 241-T-101 indicated that 6,000 to 9,000 gal had leaked. Because of the liquid level anomaly, Tank 241-T-101 was declared an assumed leaker on October 4, 1992. SSTs liquid level gages have been historically unreliable. False readings can occur because of instrument failures, floating salt cake, and salt encrustation. Gages frequently self-correct and tanks show no indication of leak. Tank levels cannot be visually inspected and verified because of high radiation fields. The gage in Tank 241-T-101 has largely corrected itself since the mid-year 1992 reading. Therefore, doubt exists that a leak has occurred, or that the magnitude of the leak poses any immediate environmental threat. While reluctance exists to use valuable DST space unnecessarily, there is a large safety and economic incentive to prevent or mitigate release of tank liquid waste into the surrounding environment. During the assessment of the significance of the Tank 241-T-101 liquid level gage readings, Washington State Department of Ecology determined that Westinghouse Hanford Company was not in compliance with regulatory requirements, and directed transfer of the Tank 241-T-101 liquid contents into a DST. Meanwhile, DOE directed WHC to examine reasonable alternatives/options for safe interim management of Tank 241-T-101 wastes before taking action. The five alternatives that could be used to manage waste from a leaking SST are: (1) No-Action, (2) In-Tank Stabilization, (3) External Tank Stabilization, (4) Liquid Retrieval, and (5) Total Retrieval. The findings of these examinations are reported in this study.

Brevick, C.H. [ICF Kaiser Hanford Co., Richland, WA (United States); Jenkins, C. [Westinghouse Hanford Co., Richland, WA (United States)

1996-02-01T23:59:59.000Z

246

Analysis of core damage frequency from internal events: Peach Bottom, Unit 2  

SciTech Connect (OSTI)

This document contains the internal event initiated accident sequence analyses for Peach Bottom, Unit 2; one of the reference plants being examined as part of the NUREG-1150 effort by the Nuclear Regulatory Commission. NUREG-1150 will document the risk of a selected group of nuclear power plants. As part of that work, this report contains the overall core damage frequency estimate for Peach Bottom, Unit 2, and the accompanying plant damage state frequencies. Sensitivity and uncertainty analyses provided additional insights regarding the dominant contributors to the Peach Bottom core damage frequency estimate. The mean core damage frequency at Peach Bottom was calculated to be 8.2E-6. Station blackout type accidents (loss of all ac power) were found to dominate the overall results. Anticipated Transient Without Scram accidents were also found to be non-negligible contributors. The numerical results are largely driven by common mode failure probability estimates and to some extent, human error. Because of significant data and analysis uncertainties in these two areas (important, for instance, to the most dominant scenario in this study), it is recommended that the results of the uncertainty and sensitivity analyses be considered before any actions are taken based on this analysis.

Kolaczkowski, A.M.; Lambright, J.A.; Ferrell, W.L.; Cathey, N.G.; Najafi, B.; Harper, F.T.

1986-10-01T23:59:59.000Z

247

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...

248

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...

249

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...

250

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...

251

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

252

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

253

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

254

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

255

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

256

Using simulation of accidents to assess resilience capacities of organizations  

E-Print Network [OSTI]

and analysis of such simulations (toxic leak in a refinery, fire in a road tunnel, terrorist attack Symposium on Resilience Engineering, Juan-les-Pins : France (2006)" #12;situation. Another limitation lies

Boyer, Edmond

257

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

258

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

259

Is the situation and immediate threat to life and health? Spill/Leak/Release Medical Emergency Fire or Flammable Gas Spill/Leak/Release Medical Emergency Fire or Flammable Gas Chemical Odor? Possible Fire / Natural Gas  

E-Print Network [OSTI]

? Possible Fire / Natural Gas (including chemicals and bio agents") (not including chemicals or bio agents Fire or Flammable Gas Spill/Leak/Release Medical Emergency Fire or Flammable Gas Chemical Odor

260

Hanford Double-Shell Tank AY-102 Radioactive Waste Leak Investigation Update - 15302  

SciTech Connect (OSTI)

Tank AY-102 was the first of 28 double-shell radioactive waste storage tanks constructed at the U. S. Department of Energys Hanford Site, near Richland, WA. The tank was completed in 1970, and entered service in 1971. In August, 2012, an accumulation of material was discovered at two sites on the floor of the annulus that separates the primary tank from the secondary liner. The material was sampled and determined to originate from the primary tank. This paper summarizes the changes in leak behavior that have occurred during the past two years, inspections to determine the capability of the secondary liner to continue safely containing the leakage, and the initial results of testing to determine the leak mechanism.

Washenfelder, D. J.; Johnson, J. M.

2014-12-22T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

The effect of the Fukushima nuclear accident on stock prices of electric power utilities in Japan  

Science Journals Connector (OSTI)

The purpose of this study is to investigate the effect of the accident at the Fukushima Daiichi nuclear power station, which is owned by Tokyo Electric Power Co. (TEPCO), on the stock prices of the other electric power utilities in Japan. Because the other utilities were not directly damaged by the Fukushima nuclear accident, their stock price responses should reflect the change in investor perceptions on risk and return associated with nuclear power generation. Our first finding is that the stock prices of utilities that own nuclear power plants declined more sharply after the accident than did the stock prices of other electric power utilities. In contrast, investors did not seem to care about the risk that may arise from the use of the same type of nuclear power reactors as those at the Fukushima Daiichi station. We also observe an increase of both systematic and total risks in the post-Fukushima period, indicating that negative market reactions are not merely caused by one-time losses but by structural changes in society and regulation that could increase the costs of operating a nuclear power plant.

Shingo Kawashima; Fumiko Takeda

2012-01-01T23:59:59.000Z

262

Development of a cold cathode ion source for a mass spectrometer type vacuum leak detector  

E-Print Network [OSTI]

DEVELOPMENT OF A COLD CATHODE ION SOURCE FOR A MASS SPECTROL'ETER TYPE VACUUM LEAK DETECTOR A Dissertation By Harold A. Thomas June 1947 Approval as to style and content recommended* Head Deparanent of Electrical Engineering DEVELOPMENT OF A... Investigation of Ion Source ? .......... 6 III. Investigation of Ion Energies ...................... 21 IV. Development of Lrass Spectrometer Tube Utilizing the Cold Cathode Ion S o u r c e ........ 41 V* Conclusions...

Thomas, Harold Albert

2013-10-04T23:59:59.000Z

263

Ecological Half-Lives of Radiocesium in 16 Species in Marine Biota after the TEPCOs Fukushima Daiichi Nuclear Power Plant Accident  

Science Journals Connector (OSTI)

The Fukushima Daiichi Nuclear Power Plant (FDNPP) accident of March 11, 2011 was the result of the Great East Japan Earthquake, a magnitude 9.0 earthquake, and the resultant tsunami, which severely damaged several reactors. ... Report of the Japanese Government to the IAEA Ministerial Conference on Nuclear SafetyThe Accident at TEPCOs Fukushima Nuclear Power Stations; NERH: Tokyo, Japan, 2011; http://www.kantei.go.jp/foreign/kan/topics/201106/iaea_houkokusho_e.html ... Results of Simulation of the Atmospheric Behavior of Radioactive Materials Released from the Fukushima Daiichi Nuclear Power Plant; NIES, Tsukuba, Japan; http://www.nies.go.jp/whatsnew/2011/20110825/20110825.html ...

Kayoko Iwata; Keiko Tagami; Shigeo Uchida

2013-06-14T23:59:59.000Z

264

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

SciTech Connect (OSTI)

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

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

1994-12-01T23:59:59.000Z

265

Aerosol penetration of leak pathways : an examination of the available data and models.  

SciTech Connect (OSTI)

Data and models of aerosol particle deposition in leak pathways are described. Pathways considered include capillaries, orifices, slots and cracks in concrete. The Morewitz-Vaughan criterion for aerosol plugging of leak pathways is shown to be applicable only to a limited range of particle settling velocities and Stokes numbers. More useful are sampling efficiency criteria defined by Davies and by Liu and Agarwal. Deposition of particles can be limited by bounce from surfaces defining leak pathways and by resuspension of particles deposited on these surfaces. A model of the probability of particle bounce is described. Resuspension of deposited particles can be triggered by changes in flow conditions, particle impact on deposits and by shock or vibration of the surfaces. This examination was performed as part of the review of the AP1000 Standard Combined License Technical Report, APP-GW-GLN-12, Revision 0, 'Offsite and Control Room Dose Changes' (TR-112) in support of the USNRC AP1000 Standard Combined License Pre-Application Review.

Powers, Dana Auburn

2009-04-01T23:59:59.000Z

266

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":""}]}

267

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

268

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

269

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

270

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

271

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

272

NINTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton GLT O-rings used in the Model 9975 package has been ongoing since 2004 at the Savannah River National Laboratory. One approach has been to periodically evaluate the leak performance of O-rings being aged in mock-up 9975 Primary Containment Vessels (PCVs) at elevated temperatures. Other methods such as compression-stress relaxation (CSR) tests and field surveillance are also on-going to evaluate O-ring behavior. Seventy tests using PCV mock-ups were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested periodically to determine if they continue to meet the leak-tightness criterion defined in ANSI standard N14.5-97. Due to material substitution, fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 23 GLT O-ring fixtures at 200 270 F. Room temperature leak test failures have been experienced in all of the GLT O-ring fixtures aging at 350 F and higher temperatures, and in 8 fixtures aging at 300 F. The earliest 300 F GLT O-ring fixture failure was observed at 34 months. The remaining GLT O-ring fixtures aging at 300 F have been retired from testing following more than 5 years at temperature without failure. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 72 - 96 months, which bounds O-ring temperatures anticipated during storage in K-Area Complex (KAC). Based on expectations that the 200 F fixtures will remain leak-tight for a significant period yet to come, 2 additional fixtures began aging in 2011 at 270 F, with hopes that they may reach a failure condition before the 200 F fixtures, thus providing additional time to failure data. High temperature aging continues for 6 GLT-S O-ring fixtures at 200 300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 - 300 F for 54 - 57 months. No additional O-ring failures have been observed since the last interim report was issued. Aging and periodic leak testing will continue for the remaining PCV fixtures. Additional irradiation of several fixtures is recommended to maintain a balance between thermal and radiation exposures similar to that experienced in storage, and to show the degree of consistency of radiation response between GLT and GLT-S O-rings.

Daugherty, W.

2014-08-06T23:59:59.000Z

273

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

274

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...

275

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...

276

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

277

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...

278

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...

279

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...

280

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,...

Note: This page contains sample records for the topic "leaks damage accidents" 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

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,...

282

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...

283

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...

284

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...

285

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)...

286

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...

287

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...

288

The concepts of leak before break and absolute reliability of NPP equipment and piping  

SciTech Connect (OSTI)

This paper describes the absolute reliability (AR) concept for ensuring safe operation of nuclear plant equipment and piping. The AR of a pipeline or component is defined as the level of reliability when the probability of an instantaneous double-ended break is near zero. AR analysis has been applied to Russian RBMK and VVER type reactors. It is proposed that analyses required for application of the leak before break concept should be included in AR implementation. The basic principles, methods, and approaches that provide the basis for implementing the AR concept are described.

Getman, A.F.; Komarov, O.V.; Sokov, L.M. [and others

1997-04-01T23:59:59.000Z

289

TACIS 91: Application of leak-before-break concept in VVER 440-230  

SciTech Connect (OSTI)

The applicability of the leak-before-break (LBB) concept for primary piping in the first generation of WWER type plants in Russia is investigated. The procedures for LBB behavior used in France and Germany are applied, and the evaluation is discussed within the framework of the European Technical Assistance for the Community of Independent States (TACIS) project. Emphasis is placed on experimental validation of national and international engineering practice for evaluating and optimizing existing installations. Design criteria of WWER plants are compared to western standard design.

Bartholome, G.; Faidy, C.; Franco, C. [and others

1997-04-01T23:59:59.000Z

290

A mathematical model for air brake systems in the presence of leaks  

E-Print Network [OSTI]

model for an air brake system in the presence of leaks. Brake systems in trucks are crucial for ensuring the safety of vehicles and passengers on the roadways. Most trucks in the US are equipped with S-cam drum brake systems and they are sensitive.... Overview Air brake systems are used in heavy commercial vehicles like buses, straight trucks and combination vehicles such as tractor-trailers[1]. More than 85% of the commer- cial vehicles in the US are equipped with S-cam drum brakes[2]. Proper...

Ramaratham, Srivatsan

2008-10-10T23:59:59.000Z

291

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).

292

Methods for detecting and locating leaks in containment facilities using electrical potential data and electrical resistance tomographic imaging techniques  

DOE Patents [OSTI]

Methods are provided for detecting and locating leaks in liners used as barriers in the construction of landfills, surface impoundments, water reservoirs, tanks, and the like. Electrodes are placed in the ground around the periphery of the facility, in the leak detection zone located between two liners if present, and/or within the containment facility. Electrical resistivity data is collected using these electrodes. This data is used to map the electrical resistivity distribution beneath the containment liner between two liners in a double-lined facility. In an alternative embodiment, an electrode placed within the lined facility is driven to an electrical potential with respect to another electrode placed at a distance from the lined facility (mise-a-la-masse). Voltage differences are then measured between various combinations of additional electrodes placed in the soil on the periphery of the facility, the leak detection zone, or within the facility. A leak of liquid though the liner material will result in an electrical potential distribution that can be measured at the electrodes. The leak position is located by determining the coordinates of an electrical current source pole that best fits the measured potentials with the constraints of the known or assumed resistivity distribution. 6 figs.

Daily, W.D.; Laine, D.L.; Laine, E.F.

1997-08-26T23:59:59.000Z

293

Methods for detecting and locating leaks in containment facilities using electrical potential data and electrical resistance tomographic imaging techniques  

DOE Patents [OSTI]

Methods are provided for detecting and locating leaks in liners used as barriers in the construction of landfills, surface impoundments, water reservoirs, tanks, and the like. Electrodes are placed in the ground around the periphery of the facility, in the leak detection zone located between two liners if present, and/or within the containment facility. Electrical resistivity data is collected using these electrodes. This data is used to map the electrical resistivity distribution beneath the containment liner between two liners in a double-lined facility. In an alternative embodiment, an electrode placed within the lined facility is driven to an electrical potential with respect to another electrode placed at a distance from the lined facility (mise-a-la-masse). Voltage differences are then measured between various combinations of additional electrodes placed in the soil on the periphery of the facility, the leak detection zone, or within the facility. A leak of liquid though the liner material will result in an electrical potential distribution that can be measured at the electrodes. The leak position is located by determining the coordinates of an electrical current source pole that best fits the measured potentials with the constraints of the known or assumed resistivity distribution.

Daily, William D. (Livermore, CA); Laine, Daren L. (San Antonio, TX); Laine, Edwin F. (Alamo, CA)

1997-01-01T23:59:59.000Z

294

Methods for detecting and locating leaks in containment facilities using electrical potential data and electrical resistance tomographic imaging techniques  

DOE Patents [OSTI]

Methods are provided for detecting and locating leaks in liners used as barriers in the construction of landfills, surface impoundments, water reservoirs, tanks, and the like. Electrodes are placed in the ground around the periphery of the facility, in the leak detection zone located between two liners if present, and/or within the containment facility. Electrical resistivity data is collected using these electrodes. This data is used to map the electrical resistivity distribution beneath the containment liner or between two liners in a double-lined facility. In an alternative embodiment, an electrode placed within the lined facility is driven to an electrical potential with respect to another electrode placed at a distance from the lined facility (mise-a-la-masse). Voltage differences are then measured between various combinations of additional electrodes placed in the soil on the periphery of the facility, the leak detection zone, or within the facility. A leak of liquid through the liner material will result in an electrical potential distribution that can be measured at the electrodes. The leak position is located by determining the coordinates of an electrical current source pole that best fits the measured potentials with the constraints of the known or assumed resistivity distribution.

Daily, William D. (Livermore, CA); Laine, Daren L. (San Anotonio, TX); Laine, Edwin F. (Penn Valley, CA)

2001-01-01T23:59:59.000Z

295

Material Selection for Accident Tolerant Fuel Cladding  

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

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

none,

2014-07-01T23:59:59.000Z

296

Unusual refinery boiler tube failures due to corrosion by sulfuric acid induced by steam leaks  

SciTech Connect (OSTI)

Corrosion by sulfuric acid in boilers is a low probability event because gas temperature and metal temperature of boiler tubes are high enough to avoid the condensation of sulfuric acid from flue gases. This degradation mechanism is frequently considered as an important cause of air preheaters materials degradation, where flue gases are cooled by heat transfer to the combustion air. Corrosion is associated to the presence of sulfuric acid, which condensates if metal temperature (or gas temperature) is below of the acid dew point. In economizer tubes, sulfuric acid corrosion is an unlikely event because flue gas and tube temperatures are normally over the acid dewpoint. In this paper, the failure analysis of generator tubes (similar to the economizer of bigger boilers) of two small oil-fired subcritical boilers is reported. It is concluded that sulfuric acid corrosion was the cause of the failure. The sulfuric acid condensation was due to the contact of flue gases containing SO{sub 3} with water-steam spray coming from leaks at the interface of rolled tube to the drum. Considering the information gathered from these two cases studied, an analysis of this failure mechanism is presented including a description of the thermodynamics condition of water leaking from the drum, and an analysis of the factors favoring it.

Lopez-Lopez, D.; Wong-Moreno, A. [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1998-12-31T23:59:59.000Z

297

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

298

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...

299

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...

300

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 "leaks damage accidents" 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

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...

302

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...

303

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.

304

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....

305

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

SciTech Connect (OSTI)

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

Young, M.

1995-02-01T23:59:59.000Z

306

Nuclear fuel cycle facility accident analysis handbook  

SciTech Connect (OSTI)

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

NONE

1998-03-01T23:59:59.000Z

307

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

308

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

309

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

310

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

311

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

312

Fukushima Daiichi Accident and Its Radiological Impact on the Environment  

Science Journals Connector (OSTI)

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

J. J. Bevelacqua

2012-01-01T23:59:59.000Z

313

Analysis of core damage frequency: Peach Bottom, Unit 2 internal events appendices  

SciTech Connect (OSTI)

This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. The mean core damage frequency is 4.5E-6 with 5% and 95% uncertainty bounds of 3.5E-7 and 1.3E-5, respectively. Station blackout type accidents (loss of all ac power) contributed about 46% of the core damage frequency with Anticipated Transient Without Scram (ATWS) accidents contributing another 42%. The numerical results are driven by loss of offsite power, transients with the power conversion system initially available operator errors, and mechanical failure to scram. 13 refs., 345 figs., 171 tabs.

Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L. (Science Applications International Corp., Albuquerque, NM (USA); Sandia National Labs., Albuquerque, NM (USA))

1989-08-01T23:59:59.000Z

314

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...

315

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...

316

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...

317

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:...

318

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...

319

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...

320

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...

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321

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...

322

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:...

323

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...

324

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...

325

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...

326

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....

327

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...

328

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...

329

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....

330

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...

331

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...

332

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....

333

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....

334

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...

335

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,...

336

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...

337

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....

338

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...

339

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...

340

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...

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


341

E-Print Network 3.0 - 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...

342

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...

343

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

344

BDS thin film damage competition  

SciTech Connect (OSTI)

A laser damage competition was held at the 2008 Boulder Damage Symposium in order to determine the current status of thin film laser resistance within the private, academic, and government sectors. This damage competition allows a direct comparison of the current state-of-the-art of high laser resistance coatings since they are all tested using the same damage test setup and the same protocol. A normal incidence high reflector multilayer coating was selected at a wavelength of 1064 nm. The substrates were provided by the submitters. A double blind test assured sample and submitter anonymity so only a summary of the results are presented here. In addition to the laser resistance results, details of deposition processes, coating materials, and layer count will also be shared.

Stolz, C J; Thomas, M D; Griffin, A J

2008-10-24T23:59:59.000Z

345

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

346

On the dependence of the leak-rate of seals on the skewness of the surface height probability distribution  

E-Print Network [OSTI]

Seals are extremely useful devices to prevent fluid leakage. We present experimental result which show that the leak-rate of seals depend sensitively on the skewness in the height probability distribution. The experimental data are analyzed using the critical-junction theory. We show that using the top-power spectrum result in good agreement between theory and experiment.

B. Lorenz; B. N. J. Persson

2010-04-07T23:59:59.000Z

347

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

348

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

349

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

350

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

351

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

352

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,...

353

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...

354

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...

355

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...

356

Tort Law in road accidents. The involvement of police vehicles  

Science Journals Connector (OSTI)

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

Flix Francisco Serrano Gallardo

2009-10-01T23:59:59.000Z

357

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

358

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...

359

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

360

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...

Note: This page contains sample records for the topic "leaks damage accidents" 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

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...

362

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

363

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...

364

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...

365

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

366

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...

367

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

368

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...

369

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

370

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

371

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

372

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

373

Numerical Simulation of Two-Phase Flow in Severely Damaged Core Geometries  

SciTech Connect (OSTI)

In the event of a severe accident in a nuclear reactor, the oxidation, dissolution and collapse of fuel rods is likely to change dramatically the geometry of the core. A large part of the core would be damaged and would look like porous medium made of randomly distributed pellet fragments, broken claddings and relocated melts. Such a complex medium must be cooled in order to stop the accident progression. IRSN investigates the effectiveness of the water re-flooding mechanism in cooling this medium where complex two-phase flows are likely to exist. A macroscopic model for the prediction of the cooling sequence was developed for the ICARE/CATHARE code (IRSN mechanistic code for severe accidents). It still needs to be improved and assessed. It appears that a better understanding of the flow at the pore scale is necessary. As a result, a direct numerical simulation (DNS) code was developed to investigate the local features of a two-phase flow in complex geometries. In this paper, the Cahn-Hilliard model is used to simulate flows of two immiscible fluids in geometries representing a damaged core. These geometries are synthesized from experimental tomography images (PHEBUS-FP project) in order to study the effects of each degradation feature, such as displacement and fragmentation of the fuel rods and claddings, on the two-phase flow. For example, the presence of fragmented fuel claddings is likely to enhance the trapping of the residual phase (either steam or water) within the medium which leads to less flow fluctuations in the other phase. Such features are clearly shown by DNS calculations. From a series of calculations where the geometry of the porous medium is changed, conclusions are drawn for the impact of rods damage level on the characteristics of two-phase flow in the core. (authors)

Meekunnasombat, Phongsan; Fichot, Florian [Institute of Radioprotection and Nuclear Safety - IRSN, BP 17 - 92262 Fontenay-aux-Roses Cedex 31, avenue de la Division Leclerc 92260 Fontenay-aux-Roses (France); Quintard, Michel [Institut de Mecanique des Fluides de Toulouse, 1 Allee du Professeur Camille Soula, 31400 Toulouse (France)

2006-07-01T23:59:59.000Z

374

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).

375

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

376

The depth of the oil/brine interface and crude oil leaks in SPR caverns  

SciTech Connect (OSTI)

Monitoring wellhead pressure evolution is the best method of detecting crude oil leaks in SPR caverns while oil/brine interface depth measurements provide additional insight. However, to fully utilize the information provided by these interface depth measurements, a thorough understanding of how the interface movement corresponds to cavern phenomena, such as salt creep, crude oil leakage, and temperature equilibration, as well as to wellhead pressure, is required. The time evolution of the oil/brine interface depth is a function of several opposing factors. Cavern closure due to salt creep and crude oil leakage, if present, move the interface upward. Brine removal and temperature equilibration of the oil/brine system move the interface downward. Therefore, the relative magnitudes of these factors determine the net direction of interface movement. Using a mass balance on the cavern fluids, coupled with a simplified salt creep model for closure in SPR caverns, the movement of the oil/brine interface has been predicted for varying cavern configurations, including both right-cylindrical and carrot-shaped caverns. Three different cavern depths and operating pressures have been investigated. In addition, the caverns were investigated at four different points in time, allowing for varying extents of temperature equilibration. Time dependent interface depth changes of a few inches to a few feet were found to be characteristic of the range of cases studied. 5 refs, 19 figs., 1 tab.

Heffelfinger, G.S.

1991-06-01T23:59:59.000Z

377

Conceptual design report for the project to install leak detection in FAST-FT-534/548/549  

SciTech Connect (OSTI)

This report provides conceptual designs and design recommendations for installing secondary containment and leak detection systems for three sumps at the Fluorinel and Storage Facility (FAST), CPP-666. The FAST facility is located at the Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering Laboratory (INEL). The three sumps receive various materials from the FAST water treatment process. This project involves sump upgrades to meet appropriate environmental requirements. The steps include: providing sump modifications or designs for the installation of leak chases and/or leakage accumulation, coating the sump concrete with a chemical resistant sealant (except for sump VES-FT-534 which is already lined with stainless steel) to act as secondary containment, lining the sumps with a primary containment system, and providing a means to detect and remove primary containment leakage that may occur.

Galloway, K.J.

1992-07-01T23:59:59.000Z

378

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

379

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

380

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

Note: This page contains sample records for the topic "leaks damage accidents" 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

Keeping track of the damage  

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

News Archives: News Archives: 2012 | 2011 | 2010 | 2009 2008 | 2007 | 2006 | 2005 2004 | 2003 | 2002 | 2001 2000 Subscribe to APS News rss feed Keeping track of the damage Scientists resolve long-standing mystery of ion-solid interactions Reprinted with kind permission from ScienceWise - Science Magazine of the Australian National University JANUARY 27, 2009 Bookmark and Share Dr. Patrick Kluth and Claudia Schnohr. Silica (silicon dioxide) is the most abundant mineral in the earth's crust and consequently is a core component in many rocks. It's quite common for such rocks to also contain natural traces of materials like uranium that undergo slow radioactive decay. This radioactivity produces energetic particles that smash through the surrounding silica creating tracks of localized damage in their wake.

382

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

383

Effects of improved modeling on best estimate BWR severe accident analysis  

SciTech Connect (OSTI)

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

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

1984-01-01T23:59:59.000Z

384

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

385

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

386

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

387

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

388

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

389

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

390

A SPECTROSCOPIC SEARCH FOR LEAKING LYMAN CONTINUUM AT z {approx} 0.7  

SciTech Connect (OSTI)

We present the results of rest-frame, UV slitless spectroscopic observations of a sample of 32 z {approx} 0.7 Lyman break galaxy (LBG) analogs in the COSMOS field. The spectroscopic search was performed with the Solar Blind Channel on the Hubble Space Telescope. We report the detection of leaking Lyman continuum (LyC) radiation from an active galactic nucleus-starburst composite. While we find no direct detections of LyC emission in the remainder of our sample, we achieve individual lower limits (3{sigma}) of the observed non-ionizing UV-to-LyC flux density ratios, f{sub {nu}} (1500 A)/f{sub {nu}}(830 A) of 20 to 204 (median of 73.5) and 378.7 for the stack. Assuming an intrinsic Lyman break of 3.4 and an intergalactic medium transmission of LyC photons along the line of sight to the galaxy of 85%, we report an upper limit for the relative escape fraction in individual galaxies of 0.02-0.19 and a stacked 3{sigma} upper limit of 0.01. We find no indication of a relative escape fraction near unity as seen in some LBGs at z {approx} 3. Our UV spectra achieve the deepest limits to date at any redshift for the escape fraction in individual sources. The contrast between these z {approx} 0.7 low escape fraction LBG analogs with z {approx} 3 LBGs suggests that either the processes conducive to high f{sub esc} are not being selected for in the z {approx}< 1 samples or the average escape fraction is decreasing from z {approx} 3 to z {approx} 1. We discuss possible mechanisms that could affect the escape of LyC photons.

Bridge, Carrie R.; Siana, Brian; Salvato, Mara; Rudie, Gwen C. [California Institute of Technology, 220-6, Pasadena, CA 91125 (United States); Teplitz, Harry I. [Infrared Processing and Analysis Center, MS 100-22, Caltech, Pasadena, CA 91125 (United States); Scarlata, Claudia; Colbert, James; Armus, Lee [Science Center, California Institute of Technology, 220-6, Pasadena, CA 91125 (United States); Conselice, Christopher J. [University of Nottingham, Nottingham, NG7 2RD (United Kingdom); Ferguson, Henry C.; Brown, Thomas M.; Giavalisco, Mauro [Space Telescope Science Institute, 3700 San Martin Drive, Baltimore, MD 21218 (United States); De Mello, Duilia F. [Department of Physics, Catholic University of America, 620 Michigan Avenue, Washington, DC 20064 (United States); Gardner, Jonathan P., E-mail: bridge@astro.caltech.ed [Astrophysics Science Division, Observational Cosmology Laboratory, Code 665, Goddard Space Flight Center, Greenbelt, MD 20771 (United States)

2010-09-01T23:59:59.000Z

391

Competition between mesoplasticity and damage under HCF Elasticity/damage shakedown concept  

E-Print Network [OSTI]

during all the sample lifetime of the plasticity and damage effects. The plasticity mechanisms induce in the framework of the continuum damage mechanics, according to the identified physical mechanisms during, the damage growth arrest. Keywords High cycle fatigue; Multiaxial loading; Continuum damage mechanics

Boyer, Edmond

392

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

393

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...

394

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,...

395

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...

396

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...

397

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...

398

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...

399

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...

400

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 "leaks damage accidents" 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 - 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...

402

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...

403

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...

404

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:...

405

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...

406

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...

407

Damage experiments in a cylindrical geometry  

SciTech Connect (OSTI)

Studying spallation damage with a cylindrical configuration allows for a natural recollection of the damaged material under proper driving conditions. Additionally, the damaged material can come to a complete rest without the application of further stopping forces. Specific areas of research include the damage initiation regime in convergent geometry, behavior of material recollected after damage, and effects of convergent geometry on the material response. Such experiments produce unique strain and shear stress states, motivating improvements in existing computational material models and increasing the predictive capabilities of codes. A LANL/VNIIEF joint experimental series has produced cylindrical aluminum failure initiation data and studied the behavior of material recollected after damage initiation and after complete failure. In addition to post-shot collection of the damaged target material for subsequent metallographic analysis, dynamic in-situ experimental diagnostics include velocimetry and transverse radial radiography. This paper will discuss the current experimental status.

Kaul, Ann M [Los Alamos National Laboratory

2010-09-21T23:59:59.000Z

408

Interface modeling to predict well casing damage for big hill strategic petroleum reserve.  

SciTech Connect (OSTI)

Oil leaks were found in well casings of Caverns 105 and 109 at the Big Hill Strategic Petroleum Reserve site. According to the field observations, two instances of casing damage occurred at the depth of the interface between the caprock and top of salt. This damage could be caused by interface movement induced by cavern volume closure due to salt creep. A three dimensional finite element model, which allows each cavern to be configured individually, was constructed to investigate shear and vertical displacements across each interface. The model contains interfaces between each lithology and a shear zone to examine the interface behavior in a realistic manner. This analysis results indicate that the casings of Caverns 105 and 109 failed by shear stress that exceeded shear strength due to the horizontal movement of the top of salt relative to the caprock, and tensile stress due to the downward movement of the top of salt from the caprock, respectively. The casings of Caverns 101, 110, 111 and 114, located at the far ends of the field, are predicted to be failed by shear stress in the near future. The casings of inmost Caverns 107 and 108 are predicted to be failed by tensile stress in the near future.

Ehgartner, Brian L.; Park, Byoung Yoon

2012-02-01T23:59:59.000Z

409

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

410

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

411

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

412

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

413

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.

414

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

415

Diffusion of fission products and radiation damage in SiC  

Science Journals Connector (OSTI)

A major problem with most of the present nuclear reactors is their safety in terms of the release of radioactivity into the environment during accidents. In some of the future nuclear reactor designs, i.e. Generation IV reactors, the fuel is in the form of coated spherical particles, i.e. TRISO (acronym for triple coated isotropic) particles. The main function of these coating layers is to act as diffusion barriers for radioactive fission products, thereby keeping these fission products within the fuel particles, even under accident conditions. The most important coating layer is composed of polycrystalline 3CSiC. This paper reviews the diffusion of the important fission products (silver, caesium, iodine and strontium) in SiC. Because radiation damage can induce and enhance diffusion, the paper also briefly reviews damage created by energetic neutrons and ions at elevated temperatures, i.e. the temperatures at which the modern reactors will operate, and the annealing of the damage. The interaction between SiC and some fission products (such as Pd and I) is also briefly discussed. As shown, one of the key advantages of SiC is its radiation hardness at elevated temperatures, i.e. SiC is not amorphized by neutrons or bombardment at substrate temperatures above 350C. Based on the diffusion coefficients of the fission products considered, the review shows that at the normal operating temperatures of these new reactors (i.e. less than 950C) the SiC coating layer is a good diffusion barrier for these fission products. However, at higher temperatures the design of the coated particles needs to be adapted, possibly by adding a thin layer of ZrC.

Johan B Malherbe

2013-01-01T23:59:59.000Z

416

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.

417

Nanofoams Response to Radiation Damage  

SciTech Connect (OSTI)

Conclusions of this presentation are: (1) np-Au foams were successfully synthesized by de-alloying process; (2) np-Au foams remain porous structure after Ne ion irradiation to 1 dpa; (3) SFTs were observed in irradiated np-Au foams with highest and intermediate flux, while no SFTs were observed with lowest flux; (4) SFTs were observed in irradiated np-Au foams at RT, whereas no SFTs were observed at LNT irradiation; (5) The diffusivity of vacancies in Au at RT is high enough so that the vacancies have enough time to agglomerate and thus collapse. As a result, SFTs were formed; (6) The high flux created much more damage/time, vacancies don't have enough time to diffuse or recombine. As a result, SFTs were formed.

Fu, Engang [Los Alamos National Laboratory; Serrano De Caro, Magdalena [Los Alamos National Laboratory; Wang, Yongqiang [Los Alamos National Laboratory; Nastasi, Michael [Nebraska Center for Energy Sciences Research, University of Nebraska-Lincoln, NE 68508; Zepeda-Ruiz, Luis [PLS, Lawrence Livermore National Laboratory, Livermore, CA 94551; Bringa, Eduardo M. [CONICET and Inst. Ciencias Basicas, Universidad Nacional de Cuyo, Mendoza, 5500 Argentina; Baldwin, Jon K. [Los Alamos National Laboratory; Caro, Jose A. [Los Alamos National Laboratory

2012-07-30T23:59:59.000Z

418

Corrosion-induced damage raises serious implications  

SciTech Connect (OSTI)

One of the most difficult and often underestimated aspects of pipeline rehabilitation is the assessment of corrosion-induced damage. This question involves evaluation of damage from prior service as well as consideration of conditions which may pose additional time-dependent degradation which could affect the future serviceability of the pipeline. The present study examines the assessment of pipeline damage and rehabilitation requirements through knowledge of materials of construction, operating conditions, field inspection and service records.

Kane, R.D.; Cayard, M.S. [CLI International, Inc., Houston, TX (United States)

1997-06-01T23:59:59.000Z

419

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

420

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.

Note: This page contains sample records for the topic "leaks damage accidents" 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

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

422

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

423

A sequential checklist for the assessment of natural attenuation of dissolved petroleum contaminant plumes from leaking underground storage tanks  

SciTech Connect (OSTI)

Estimates of the number of leaking underground storage tanks (UST) are measured in the hundreds of thousands in the United States alone. The discussion in this article largely pertains to the lighter motor fuels which contain aromatic petroleum hydrocarbons. These include benzene, toluene, ethylbenzene and xylenes (BTEX). The occurrence of dissolved BTEX groundwater contaminant plumes is most commonly associated with leaking gasoline USTs. However, their association with other petroleum products is not uncommon. this article and checklist provide guidance for completing UST assessments, which can support the decision-making process presented in the ASTM Emergency Standard Guide. Following the checklist will measure that the initial site assessment results in an accurate and functional characterization of the details and subtleties of the UST Source Impact Zone. This includes evaluating the UST area to identify release pathways for residual contamination in soil and groundwater. Based on the results obtained from the Source Impact Zone Evaluation, natural attenuation can be assessed for its applicability and performance.

De Rose, N. [Langan Engineering and Environmental Services, Inc., Doylestown, PA (United States)

1995-12-31T23:59:59.000Z

424

Results of Tank-Leak Detection Demonstration Using Geophysical Techniques at the Hanford Mock Tank Site-Fiscal Year 2001  

SciTech Connect (OSTI)

During July and August of 2001, Pacific Northwest National Laboratory (PNNL), hosted researchers from Lawrence Livermore and Lawrence Berkeley National laboratories, and a private contractor, HydroGEOPHYSICS, Inc., for deployment of the following five geophysical leak-detection technologies at the Hanford Site Mock Tank in a Tank Leak Detection Demonstration (TLDD): (1) Electrical Resistivity Tomography (ERT); (2) Cross-Borehole Electromagnetic Induction (CEMI); (3) High-Resolution Resistivity (HRR); (4) Cross-Borehole Radar (XBR); and (5) Cross-Borehole Seismic Tomography (XBS). Under a ''Tri-party Agreement'' with Federal and state regulators, the U.S. Department of Energy will remove wastes from single-shell tanks (SSTs) and other miscellaneous underground tanks for storage in the double-shell tank system. Waste retrieval methods are being considered that use very little, if any, liquid to dislodge, mobilize, and remove the wastes. As additional assurance of protection of the vadose zone beneath the SSTs, tank wastes and tank conditions may be aggressively monitored during retrieval operations by methods that are deployed outside the SSTs in the vadose zone.

Barnett, D BRENT.; Gee, Glendon W.; Sweeney, Mark D.

2002-03-01T23:59:59.000Z

425

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

426

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

427

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

428

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

429

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

430

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

431

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

432

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

433

AIR-RAID DAMAGED AND ELECTRICITY SUPPLY  

Science Journals Connector (OSTI)

... Review record instances of the air-raid damage sustained by overhead lines, cables, and substation equipment, and the steps taken to effect repairs and restore supply (see also NATUBE ... only a slight puncturing of the casing. As an indication of the amount of damage substation equipment can withstand, a switchboard which was blown right out by blast needed only ...

1942-03-28T23:59:59.000Z

434

Vibrationbased structural damage identification  

Science Journals Connector (OSTI)

...N. A. J. Lieven and D. J. Ewins Vibration-based structural damage identification...identification based upon changes in vibration characteristics is one of the few methods...last thirty years is first presented. Vibration-based damage detection is a primary...

2001-01-01T23:59:59.000Z

435

Damage from methamphetamine abuse documented  

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

Dennis Tartaglia, 212 481-7000, dennist@mbooth.com or Karen McNulty Walsh, 631 344-8350 go to home page Dennis Tartaglia, 212 481-7000, dennist@mbooth.com or Karen McNulty Walsh, 631 344-8350 go to home page 01-16 March 1, 2001 Researchers Document Brain Damage, Reduction in Motor and Cognitive Function from Methamphetamine Abuse "Speed" Shows More Neurotoxic Effects Than Heroin, Cocaine, or Alcohol UPTON, NY -- Two studies by researchers at the U.S. Department of Energy's Brookhaven National Laboratory provide evidence for the first time that abuse of methamphetamine -- the drug commonly known as "speed" -- is associated with physiological changes in two systems of the human brain. The changes are evident even for abusers who have not taken the drug for a year or more. The studies also found that methamphetamine abusers have reduced cognitive and motor functions, even at one year after quitting the drug. The findings appear in the March issue of the American Journal of Psychiatry.

436

Development of a Remote External Repair Tool for Damaged or Defective Polyethylene Pipe  

SciTech Connect (OSTI)

Current procedures for repairing polyethylene (PE) gas pipe require excavation, isolation, and removal of the damaged section of pipe followed by fusing a new section of pipe into place. These techniques are costly and very disruptive. An alternative repair method was developed at Timberline Tool with support from Oregon State University (OSU) and funding by the U. S. Department of Energy National Energy Technology Laboratory (DOE/NETL). This project was undertaken to design, develop and test a tool and method for repairing damaged PE pipe remotely and externally in situ without squeezing off the flow of gas, eliminating the need for large-scale excavations. Through an iterative design and development approach, a final engineered prototype was developed that utilizes a unique thermo-chemical and mechanical process to apply a permanent external patch to repair small nicks, gouges and punctures under line pressure. The project identified several technical challenges during the design and development process. The repair tool must be capable of being installed under live conditions and operate in an 18-inch keyhole. This would eliminate the need for extensive excavations thus reducing the cost of the repair. Initially, the tool must be able to control the leak by encapsulating the pipe and apply slight pressure at the site of damage. Finally, the repair method must be permanent at typical operating pressures. The overall results of the project have established a permanent external repair method for use on damaged PE gas pipe in a safe and cost-effective manner. The engineered prototype was subjected to comprehensive testing and evaluation to validate the performance. Using the new repair tool, samples of 4-inch PE pipe with simulated damage were successfully repaired under line pressure to the satisfaction of DOE/NETL and the following natural gas companies: Northwest Natural; Sempra Energy, Southwest Gas Corporation, Questar, and Nicor. However, initial results of accelerated age testing on repaired pipe samples showed that the high density polyethylene (HDPE) pipe patch material developed a small crack at the high stress areas surrounding the patched hole within the first 48 hours of hot water testing, indicating that the patch material has a 25-year lifespan. Based on these results, further research is continuing to develop a stronger repair patch for a satisfactory 50-year patch system. Additional tests were also conducted to evaluate whether any of the critical performance properties of the PE pipe were reduced or compromised by the repair technique. This testing validated a satisfactory 50-year patch system for the pipe.

Kenneth H. Green; Willie E. Rochefort; Nick Wannenmacher; John A. Clark; Kevin Harris

2006-06-30T23:59:59.000Z

437

A new damage testing system for detailed evaluation of damage behavior of bulk KDP and DKDP  

SciTech Connect (OSTI)

We describe a new damage testing approach and instrumentation that provides quantitative measurements of bulk damage performance versus fluence for several frequencies. A major advantage of this method is that it can simultaneously provide direct information on pinpoint density and size, and beam obscuration. This allows for more accurate evaluation of material performance under operational conditions. Protocols for laser conditioning to improve damage performance can also be easily and rapidly evaluated.This damage testing approach has enabled us to perform complex experiments toward probing the fundamental mechanisms of damage initiation and conditioning.

DeMange, P; Negres, R A; Carr, C W; Radousky, H B; Demos, S G

2004-11-17T23:59:59.000Z

438

Analysis of Underground Storage Tanks System Materials to Increased Leak Potential Associated with E15 Fuel  

SciTech Connect (OSTI)

The Energy Independence and Security Act (EISA) of 2007 was enacted by Congress to move the nation toward increased energy independence by increasing the production of renewable fuels to meet its transportation energy needs. The law establishes a new renewable fuel standard (RFS) that requires the nation to use 36 billion gallons annually (2.3 million barrels per day) of renewable fuel in its vehicles by 2022. Ethanol is the most widely used renewable fuel in the US, and its production has grown dramatically over the past decade. According to EISA and RFS, ethanol (produced from corn as well as cellulosic feedstocks) will make up the vast majority of the new renewable fuel requirements. However, ethanol use limited to E10 and E85 (in the case of flex fuel vehicles or FFVs) will not meet this target. Even if all of the E0 gasoline dispensers in the country were converted to E10, such sales would represent only about 15 billion gallons per year. If 15% ethanol, rather than 10% were used, the potential would be up to 22 billion gallons. The vast majority of ethanol used in the United States is blended with gasoline to create E10, that is, gasoline with up to 10% ethanol. The remaining ethanol is sold in the form of E85, a gasoline blend with as much as 85% ethanol that can only be used in FFVs. Although DOE remains committed to expanding the E85 infrastructure, that market will not be able to absorb projected volumes of ethanol in the near term. Given this reality, DOE and others have begun assessing the viability of using intermediate ethanol blends as one way to transition to higher volumes of ethanol. In October of 2010, the EPA granted a partial waiver to the Clean Air Act allowing the use of fuel that contains up to 15% ethanol for the model year 2007 and newer light-duty motor vehicles. This waiver represents the first of a number of actions that are needed to move toward the commercialization of E15 gasoline blends. On January 2011, this waiver was expanded to include model year 2001 light-duty vehicles, but specifically prohibited use in motorcycles and off-road vehicles and equipment. UST stakeholders generally consider fueling infrastructure materials designed for use with E0 to be adequate for use with E10, and there are no known instances of major leaks or failures directly attributable to ethanol use. It is conceivable that many compatibility issues, including accelerated corrosion, do arise and are corrected onsite and, therefore do not lead to a release. However, there is some concern that higher ethanol concentrations, such as E15 or E20, may be incompatible with current materials used in standard gasoline fueling hardware. In the summer of 2008, DOE recognized the need to assess the impact of intermediate blends of ethanol on the fueling infrastructure, specifically located at the fueling station. This includes the dispenser and hanging hardware, the underground storage tank, and associated piping. The DOE program has been co-led and funded by the Office of the Biomass Program and Vehicle Technologies Program with technical expertise from the Oak Ridge National Laboratory (ORNL) and the National Renewable Energy Laboratory (NREL). The infrastructure material compatibility work has been supported through strong collaborations and testing at Underwriters Laboratories (UL). ORNL performed a compatibility study investigating the compatibility of fuel infrastructure materials to gasoline containing intermediate levels of ethanol. These results can be found in the ORNL report entitled Intermediate Ethanol Blends Infrastructure Materials Compatibility Study: Elastomers, Metals and Sealants (hereafter referred to as the ORNL intermediate blends material compatibility study). These materials included elastomers, plastics, metals and sealants typically found in fuel dispenser infrastructure. The test fuels evaluated in the ORNL study were SAE standard test fuel formulations used to assess material-fuel compatibility within a relatively short timeframe. Initially, these material studies included test fuels of Fuel C,

Kass, Michael D [ORNL; Theiss, Timothy J [ORNL; Janke, Christopher James [ORNL; Pawel, Steven J [ORNL

2012-07-01T23:59:59.000Z

439

Pathogenic Mechanisms in Ischemic Damage: A Computational Study  

E-Print Network [OSTI]

Pathogenic Mechanisms in Ischemic Damage: A Computational Study Eytan Ruppin and Elad Ofer Depts of ischemic tissue damage during acute stroke. Two prime pathogenic mechanisms, cor- tical spreading the patterns of damage that arise if damage is caused by either mechanism are generated. These damaged tissue

Ruppin, Eytan

440

Intelligent-based Structural Damage Detection Model  

SciTech Connect (OSTI)

This paper presents the application of a novel Artificial Neural Network (ANN) model for the diagnosis of structural damage. The ANN model, denoted as the GRNNFA, is a hybrid model combining the General Regression Neural Network Model (GRNN) and the Fuzzy ART (FA) model. It not only retains the important features of the GRNN and FA models (i.e. fast and stable network training and incremental growth of network structure) but also facilitates the removal of the noise embedded in the training samples. Structural damage alters the stiffness distribution of the structure and so as to change the natural frequencies and mode shapes of the system. The measured modal parameter changes due to a particular damage are treated as patterns for that damage. The proposed GRNNFA model was trained to learn those patterns in order to detect the possible damage location of the structure. Simulated data is employed to verify and illustrate the procedures of the proposed ANN-based damage diagnosis methodology. The results of this study have demonstrated the feasibility of applying the GRNNFA model to structural damage diagnosis even when the training samples were noise contaminated.

Lee, Eric Wai Ming; Yu, K.F. [Department of Building and Construction, City University of Hong Kong, Tat Chee Avenue, Kowloon Tong (Hong Kong)

2010-05-21T23:59:59.000Z

Note: This page contains sample records for the topic "leaks damage accidents" 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

Polyhalogenated hydrocarbon refrigerants and refrigerant oils colored with fluorescent dyes and method for their use as leak detectors  

SciTech Connect (OSTI)

A leak detectable refrigeration composition is described comprising: (A) a refrigeration liquid selection from the group consisting of: (1) a polyhalogenated hydrocarbon refrigerant; (2) a refrigeration oil selected from the group consisting of naphthenic oils, paraffinic oils, alkylated benzenes, silicones, polyglycols, diesters or triesters of dicarboxylic or tricarboxylic acids, and polyalkyl silicate oils, and (3) a mixture of A(1) and A(2), and (B) a fluorescent dye compound or composition comprising the dye selected from the group consisting of: (1) a fluorescent dye selected from the group consisting of perylene, naphthoxanthene, monocyclic aromatic compounds having an organometallic compound, (2) a solution of fluorescent dye in a solvent, and (3) a mixture of B(1) and B(2). The fluorescent dye compound or composition is soluble in the refrigeration liquid. The concentration of the dye being at least 0.001 grams per 100 grams of the refrigeration liquid.

Parekh, M.

1988-07-19T23:59:59.000Z

442

Characterization of Vadose Zone Sediments from C Waste Management Area: Investigation of the C-152 Transfer Line Leak  

SciTech Connect (OSTI)

A geologic/geochemical investigation in the vicinity of UPR-200-E-82 was performed using pairs of cone-penetrometer probe holes. A total of 41 direct-push cone-penetrometer borings (19 pairs to investigate different high moisture zones in the same sampling location and 3 individual) were advanced to characterize vadose zone moisture and the distribution of contaminants. A total of twenty sample sets, containing up to two split-spoon liners and one grab sample, were delivered to the laboratory for characterization and analysis. The samples were collected around the documented location of the C-152 pipeline leak, and created an approximately 120-ft diameter circle around the waste site. UPR-200-E-82 was a loss of approximately 2,600 gallons of Cs-137 Recovery Process feed solution containing an estimated 11,300 Ci of cesium-137 and 5 Ci of technetium-99. Several key parameters that are used to identify subsurface contamination were measured, including: water extract pH, electrical conductivity, nitrate, technetium-99, sodium, and uranium concentrations and technetium-99 and uranium concentrations in acid extracts. All of the parameters, with the exception of electrical conductivity, were elevated in at least some of the samples analyzed as part of this study. Specifically, soil pH was elevated (from 8.69 to 9.99) in five samples collected northeast and southwest of the C-152 pipeline leak. Similarly, samples collected from these same cone-pentrometer holes contained significantly more water-extractable sodium (more than 50 ?g/g of dry sediment), uranium (as much as 7.66E-01 ?g/g of dry sediment), nitrate (up to 30 ?g/g of dry sediment), and technetium-99 (up to 3.34 pCi/g of dry sediment). Most of the samples containing elevated concentrations of water-extractable sodium also had decreased levels of water extractable calcium and or magnesium, indicating that tank-related fluids that were high in sodium did seep into the vadose zone near these probe holes. Several of the samples containing high concentrations of water-leachable uranium also contained high pore water corrected alkalinity (3.26E+03 mg/L as CaCO3), indicating that the elevated water-leachable uranium could be an artifact of uranyl-carbonate complexation of naturally occurring labile uranium. However, a mass scan of the water extract containing the highest concentration of uranium was performed via inductively coupled mass spectrometry over the range of 230 to 240 atomic mass units, and a discernable peak was observed at mass 236. Although the data is considered qualitative, the presence of uranium-236 in the 1:1 sediment:water extract is a clear indication that the sample contains contaminant uranium [Hanford reprocessed fuel waste]. After evaluating all the characterization and analytical data, there is no question that the vadose zone surrounding the C-152 pipeline leak site has been contaminated by waste generally sent to tanks. The two zones or regions that contained the largest amount of contaminants, either in concentration or by occurrence of several key constituents/contaminants of concern, were located: 1) between the 241-C-151 and 241-C-152 Diversion Boxes (near the location of UPR-200-E-82) and 2) directly across the C-152 waste site near the C-153 Diversion Box (near where a pipeline, which connects the two diversion boxes, is shown on old blue prints . Without the use of more sophisticated analytical techniques, such as isotope signature analysis of ruthenium fission product isotopes, it is impossible to determine if the contamination observed at these two locations are from the same waste source or are a result of different leak events.

Brown, Christopher F.; Serne, R. JEFFREY; Bjornstad, Bruce N.; Valenta, Michelle M.; Lanigan, David C.; Vickerman, Tanya S.; Clayton, Ray E.; Geiszler, Keith N.; Iovin, Cristian; Clayton, Eric T.; Kutynakov, I. V.; Baum, Steven R.; Lindberg, Michael J.; Orr, Robert D.

2007-02-05T23:59:59.000Z

443

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

444

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

445

Double-Shell Tank Visual Inspection Changes Resulting from the Tank 241-AY-102 Primary Tank Leak  

SciTech Connect (OSTI)

As part of the Double-Shell Tank (DST) Integrity Program, remote visual inspections are utilized to perform qualitative in-service inspections of the DSTs in order to provide a general overview of the condition of the tanks. During routine visual inspections of tank 241-AY-102 (AY-102) in August 2012, anomalies were identified on the annulus floor which resulted in further evaluations. In October 2012, Washington River Protection Solutions, LLC determined that the primary tank of AY-102 was leaking. Following identification of the tank AY-102 probable leak cause, evaluations considered the adequacy of the existing annulus inspection frequency with respect to the circumstances of the tank AY-102 1eak and the advancing age of the DST structures. The evaluations concluded that the interval between annulus inspections should be shortened for all DSTs, and each annulus inspection should cover > 95 percent of annulus floor area, and the portion of the primary tank (i.e., dome, sidewall, lower knuckle, and insulating refractory) that is visible from the annulus inspection risers. In March 2013, enhanced visual inspections were performed for the six oldest tanks: 241-AY-101, 241-AZ-101,241-AZ-102, 241-SY-101, 241-SY-102, and 241-SY-103, and no evidence of leakage from the primary tank were observed. Prior to October 2012, the approach for conducting visual examinations of DSTs was to perform a video examination of each tank's interior and annulus regions approximately every five years (not to exceed seven years between inspections). Also, the annulus inspection only covered about 42 percent of the annulus floor.

Girardot, Crystal L. [Washington River Protection Solutions, Richland, WA (United States); Washenfelder, Dennis J. [Washington River Protection Solutions, Richland, WA (United States); Johnson, Jeremy M. [USDOE Office of River Protection, Richland, WA (United States); Engeman, Jason K. [Washington River Protection Solutions, Richland, WA (United States)

2013-11-14T23:59:59.000Z

446

Damage spreading in the Ising model  

Science Journals Connector (OSTI)

We present two interesting results regarding damage spreading in ferromagnetic Ising models. First, we show that a damage spreading transition can occur in an Ising chain that evolves in contact with a thermal reservoir. Damage heals at low temperature and spreads at high T. The dynamic rules for the systems evolution for which such a transition is observed are as legitimate as the conventional rules (Glauber, Metropolis, heat bath). Our second result is that such transitions are not always in the directed percolation universality class.

Haye Hinrichsen and Eytan Domany

1997-07-01T23:59:59.000Z

447

Carbon Fiber Damage in Accelerator Beam  

E-Print Network [OSTI]

Carbon fibers are commonly used as moving targets in Beam Wire Scanners. Because of their thermomechanical properties they are very resistant to particle beams. Their strength deteriorates with time due to radiation damage and low-cycle thermal fatigue. In case of high intensity beams this process can accelerate and in extreme cases the fiber is damaged during a single scan. In this work a model describing the fiber temperature, thermionic emission and sublimation is discussed. Results are compared with fiber damage test performed on SPS beam in November 2008. In conclusions the limits of Wire Scanner operation on high intensity beams are drawn.

Sapinski, M; Guerrero, A; Koopman, J; Mtral, E

2009-01-01T23:59:59.000Z

448

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

449

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

450

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...

451

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...

452

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...

453

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...

454

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:...

455

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...

456

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...

457

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...

458

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...

459

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:...

460

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:...

Note: This page contains sample records for the topic "leaks damage accidents" 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

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......

462

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...

463

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.

464

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...

465

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

466

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...

467

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...

468

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...

469

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...

470

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...

471

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...

472

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...

473

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,...

474

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...

475

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...

476

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...

477

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...

478

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...

479

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...

480

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...

Note: This page contains sample records for the topic "leaks damage accidents" 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

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

482

Assessing United States hurricane damage under different environmental conditions  

E-Print Network [OSTI]

Hurricane activity between 1979 and 2011 was studied to determine damage statistics under different environmental conditions. Hurricanes cause billions of dollars of damage every year in the United States, but damage ...

Maheras, Anastasia Francis

2012-01-01T23:59:59.000Z

483

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

484

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

485

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

486

Formation damage in underbalanced drilling operations  

E-Print Network [OSTI]

Formation damage has long been recognized as a potential source of reduced productivity and injectivity in both horizontal and vertical wells. From the moment that the pay zone is being drilled until the well is put on production, a formation...

Reyes Serpa, Carlos Alberto

2012-06-07T23:59:59.000Z

487

Probabilistic evaluation of flood damage in buildings  

E-Print Network [OSTI]

Because the ocean level keeps rising and because hurricanes and storms become increasingly destructive in terms of damage and economic loss, the built environment has become very vulnerable to floods. Every city is building ...

Wathier, Claire-Marine

2014-01-01T23:59:59.000Z

488

Thin Film Femtosecond Laser Damage Competition  

SciTech Connect (OSTI)

In order to determine the current status of thin film laser resistance within the private, academic, and government sectors, a damage competition was started at the 2008 Boulder Damage Symposium. This damage competition allows a direct comparison of the current state of the art of high laser resistance coatings since they are tested using the same damage test setup and the same protocol. In 2009 a high reflector coating was selected at a wavelength of 786 nm at normal incidence at a pulse length of 180 femtoseconds. A double blind test assured sample and submitter anonymity so only a summary of the results are presented here. In addition to the laser resistance results, details of deposition processes, coating materials and layer count, and spectral results will also be shared.

Stolz, C J; Ristau, D; Turowski, M; Blaschke, H

2009-11-14T23:59:59.000Z

489

Restoration of Large Damage Volumes in Polymers  

Science Journals Connector (OSTI)

Restoration of Large...regenerative power of tissues...synthetic system that restores...hours. After restoration of impact damage...tripodal ligand system based on the...Ed., CRC Handbook of Chemistry...construction. Restoration of Large...

S. R. White; J. S. Moore; N. R. Sottos; B. P. Krull; W. A. Santa Cruz; R. C. R. Gergely

2014-05-09T23:59:59.000Z

490

A matrix damage accumulation model for laminated composites  

E-Print Network [OSTI]

affect the response of the compo- rsent. The efiects of damage are refiected through the property degradation of the structure as the subcritical damage accumulates. For laminated composites, this sub- critical damage takes the form of matrix cracks... identifies damage as dominant. cracks and fracture mechanics is applied to predict crack growth. The physical significance of the damage mode is retained with this approach. LJnfor- tunately, the damage states in composite materials contain a multitude...

Lo, David Chi Shing

2012-06-07T23:59:59.000Z

491

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Supporting MELCOR calculations, Volume 6, Part 2  

SciTech Connect (OSTI)

To gain a better understanding of the risk significance of low power and shutdown modes of operation, the Office of Nuclear Regulatory Research at the NRC established programs to investigate the likelihood and severity of postulated accidents that could occur during low power and shutdown (LP&S) modes of operation at commercial nuclear power plants. To investigate the likelihood of severe core damage accidents during off power conditions, probabilistic risk assessments (PRAs) were performed for two nuclear plants: Unit 1 of the Grand Gulf Nuclear Station, which is a BWR-6 Mark III boiling water reactor (BWR), and Unit 1 of the Surry Power Station, which is a three-loop, subatmospheric, pressurized water reactor (PWR). The analysis of the BWR was conducted at Sandia National Laboratories while the analysis of the PWR was performed at Brookhaven National Laboratory. This multi-volume report presents and discusses the results of the BWR analysis. The subject of this part presents the deterministic code calculations, performed with the MELCOR code, that were used to support the development and quantification of the PRA models. The background for the work documented in this report is summarized, including how deterministic codes are used in PRAS, why the MELCOR code is used, what the capabilities and features of MELCOR are, and how the code has been used by others in the past. Brief descriptions of the Grand Gulf plant and its configuration during LP&S operation and of the MELCOR input model developed for the Grand Gulf plant in its LP&S configuration are given.

Kmetyk, L.N.; Brown, T.D. [Sandia National Labs., Albuquerque, NM (United States)

1995-03-01T23:59:59.000Z

492

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

Broader source: Energy.gov [DOE]

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

493

Atomic-Scale Simulations of Cascade Overlap and Damage Evolution...  

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

Atomic-Scale Simulations of Cascade Overlap and Damage Evolution in Silicon Carbide. Atomic-Scale Simulations of Cascade Overlap and Damage Evolution in Silicon Carbide. Abstract:...

494

High-energy radiation damage in zirconia: modeling results ....  

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

energy radiation damage in zirconia: modeling results . High-energy radiation damage in zirconia: modeling results . Abstract: Zirconia has been viewed as a material of exceptional...

495

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 79198mBqL?1 under stable runoff conditions and 70213,400BqL?1 under storm runoff conditions. The residual fraction (F4, considered to be non-bioavailable) was dominant, accounting for 59.582.6% of the total 137Cs activity under stable runoff conditions and 69.495.1% under storm runoff conditions. The 137Cs newly added to paddy fields in irrigation water only contributed 0.030.05% of the amount already present in the soil (201348kBqm?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 0.200.59%. 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

496

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

497

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

498

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.

499

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

500

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