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1
Fire and Thermal Effects of HD 1.3 Accidents: History ...
2010-07-01

... Title : Fire and Thermal Effects of HD 1.3 Accidents: History, Research, and Analysis. Descriptive Note : Conference paper. ...

DTIC Science & Technology

2
STRUCTURAL ANALYSIS OF A THERMAL INSULATION RETAINER ASSEMBLY

THERMAL INSULATION RETAINER ASSEMBLY. William H. Greene and Carl E. Gray, Jr. Langley Research Center. Introduction. In January 1989 an accident occurred in ...

NASA Website

3
ACCIDENTS IN AUSTRALIA: THE NEED FOR RESEARCH,

... Descriptors : (*AUSTRALIA, ACCIDENTS), (*ACCIDENTS, STATISTICAL ANALYSIS), MOTOR VEHICLE ACCIDENTS, INDUSTRIAL MEDICINE ...

DTIC Science & Technology

4
Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor.
1981-01-01

The document contains the experiment proposal and assembly proposal information for a series of parametric thermal hydraulics loss of coolant accident tests in the Canadian NRU reactor. These tests will establish the relationship between reflood delay tim...

National Technical Information Service (NTIS)

5
Intelligence and Accidents: A Multilevel Model
2006-05-06

Page 1. Naval Health Research Center Intelligence and Accidents: ... Accidents and Intelligence Intelligence and Accidents: A Multilevel Model ...

DTIC Science & Technology

6
Assessment of the thermal-hydraulic technology of the transition phase of a core-disruptive accident in a LMFBR
1982-11-01

The technology of thermal hydraulic aspects of the transition phase accident sequence in liquid metal fast breeder reactors has been reviewed. Previous analyses of the transition phase accident sequence have been reviewed and the current understanding of major thermal hydraulic phenomenology has been assessed. As a ...

Energy Citations Database

7
Self-mixing phenomenology in hypothetical core-disruptive accidents
1980-12-01

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 ...

DOE Information Bridge

8
Emergencies > Emergency Response > Consequence Management | Browse...
2011-01-20

about homeland security research. Browse these EPA Emergency Response subtopics Accidents Accident Preparedness, Accident Prevention, Chemical Accidents, Radiation Accidents...

Science.gov Websites

9
Thermal-structural response of EBR-II major components under reactor operational transients
1983-01-01

Until recently, the LMFBR safety research has been focused primarily on severe but highly unlikely accident, such as hypothetical-core-disruptive accidents (HCDA's), and not enough attention has been given to accident prevention, which is less severe but more likely sequence. The objective of the EBR-II ...

Energy Citations Database

10
Fission product source term research at Oak Ridge National Laboratory. [PWR; BWR
1985-01-01

The purpose of this work is to describe some of the research being performed at ORNL in support of the effort to describe, as realistically as possible, fission product source terms for nuclear reactor accidents. In order to make this presentation manageable, only those studies directly concerned with fission product behavior, as opposed to ...

Energy Citations Database

11
HAZARDS SUMMARY REPORT
1957-05-01

The reactor planned by UCNC is a pool-type research reactor to be located in Sterling Forest, near Tuxedo Park, New York. Operation will be at thermal power levels up to 5 Mw with a corresponding average thermal neutron flux of 3.3 x 10/sup 13/ n/cm/sup 2/sec. MTRtype fuel elements are used and are arranged on a grid ...

Energy Citations Database

12
Scoping study of spent fuel cask transportation accidents
1979-06-01

A scoping study of spent fuel cask transportation accidents was performed to provide the NRC with an assessment of existing information and to recommend, on a priority basis, the additional information that should be obtained to allow specification of increasingly realistic source terms. The scope was limited to the escape of radionuclides from the cask to the environment ...

DOE Information Bridge

13
PARAMETRIC STUDY OF THERMAL PROTECTION ...
1969-09-01

... (Author). Descriptors : (*AVIATION ACCIDENTS, RECORDS), (*MAGNETIC TAPE, THERMAL INSULATION), (*MAGNETIC RECORDING SYSTEMS ...

DTIC Science & Technology

14
Occupation, Personality, and Accidents: An Exploratory Study ...
2005-05-09

NAVAL HEALTH RESEARCH CENTER OCCUPATION, PERSONALITY, AND ACCIDENTS: ... Page 2. Occupation, Personality, and Accidents: ...

DTIC Science & Technology

15
General Aviation Night Fatal Accidents.
1997-09-01

... Title : General Aviation Night Fatal Accidents. ... Research determined that there is a significantly disproportionate number of night fatal accidents. ...

DTIC Science & Technology

16
Annual report of Power Reactor and Nuclear Fuel Development Corporation, fiscal year 1995.
1996-01-01

The operation of the experimental FBR 'Joyo', the trial operation and the accident of secondary sodium leak of the prototype FBR 'Monju', and the research and development of FBRs are reported. The prototype advanced thermal reactor 'Fugen' power station h...

National Technical Information Service (NTIS)

17
Reactor safety research programs. Quarterly progress report, October 1--December 31, 1977
1978-01-01

HTGR safety evaluation included studies on fission product release; materials, chemistry, and instrumentation; structural evaluation; and analytical safety evaluation. LMFBR safety evaluation included studies on accident sequences, technical coordination of structural integrity, and SSC code development and validation. LWR safety studies included ...

Energy Citations Database

18
Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor.
1981-01-01

A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects on pressurized water reactor (PWR) test fuel bundles. This Experiment Operation Plan (EOP) Addendum 2, together with the referenced EOP, descri...

National Technical Information Service (NTIS)

19
Accident Analysis for a Postulated Large Research and Development Laboratory Fire
2000-08-21

An accident analysis has updated for a large radiological laboratory, the Savannah River Technology Center (SRTC), at the Savannah River Site (SRS). The significant features of this analysis including analysis of the material-at-risk, the governing phenomena and an alternative study evaluating the thermal plume portion of the scenario are discussed.

DOE Information Bridge

20
Recreational Boat Collision Accident Research. Volume 1,
1992-10-01

... Abstract : This report is the result of three years of research on the subject of recreational boat collision accident reconstruction. ...

DTIC Science & Technology

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21
Survey of thermal-hydraulic models of commercial nuclear power plants
1992-12-01

A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC's current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on ...

Energy Citations Database

22
Survey of thermal-hydraulic models of commercial nuclear power plants
1992-12-01

A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC`s current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model ...

Energy Citations Database

23
Steady-state thermal hydraulic analysis and flow channel blockage accident analysis of JRR-4 silicide LEU core.
1996-01-01

JRR-4 is a light water moderated and cooled, graphite reflected pool type research reactor using high enriched uranium (HEU) plate-type fuels. Its thermal power is 3.5 MW. The core conversion program from HEU fuel to uranium-silicon-aluminum (U(sub 3)Si(s...

National Technical Information Service (NTIS)

24
Steady-state thermal hydraulic analysis and flow channel blockage accident analysis of JRR-3 silicide core.
1997-01-01

JRR-3 is a light water moderated and cooled, beryllium and heavy water reflected pool type research reactor using low enriched uranium (LEU) plate-type fuels. Its thermal power is 20 MW. The core conversion program from uranium-aluminum (UAl(sub x)-Al) di...

National Technical Information Service (NTIS)

25
Fuel behavior comparison for a research reactor
2006-06-01

The paper presents the behavior and properties analysis of the low enriched uranium fuel, which will be loaded in the Romanian TRIGA 14 MW steady state research reactor compared with the original high enriched uranium fuel. The high and low enriched uranium fuels have similar thermal properties, but different nuclear properties. The ...

NASA Astrophysics Data System (ADS)

26
Aircraft Safety R&D

... Program has two different focus areas: accident prevention and accident mitigation. Accident prevention research concentrates on the following issues: ...

NASA Website

27
Accident Research: The Human Element in Industrial Accidents.
1973-01-01

The author reviews previous research published in the area of industrial accidents. The review is limited to those studies which have established some behavioral cause in the impact of accidents. The effect of individual differences of the employee as a c...

National Technical Information Service (NTIS)

28
The importance of fragment size distribution on underwater aluminum ignition
1993-01-01

In the study of postulated severe accidents for uranium-aluminum-fueled research reactors, it is necessary to consider the possibility and consequences of fuel/coolant interactions. In the event of a severe accident, where the fuel melts and comes into contact with the coolant, an explosion of considerable violence may occur due to the ...

Energy Citations Database

29
Why System Safety Professionals Should Read Accident Reports
2006-01-01

System safety professionals, both researchers and practitioners, who regularly read accident reports

NASA Technical Reports Server (NTRS)

30
SPACECRAFT ACCIDENTS - Glenn Research Center

SPACECRAFT ACCIDENTS: EXAMINING THE PAST, IMPROVING THE FUTURE Apollo 13. Bryan Palaszewski. working with the. Digital Learning Network ...

NASA Website

31
FURTHER ATTEMPTS AT CODING AIRCRAFT ACCIDENTS.
1957-07-31

... Accession Number : AD0620258. Title : FURTHER ATTEMPTS AT CODING AIRCRAFT ACCIDENTS. Descriptive Note : Research rept.,. ...

DTIC Science & Technology

32
Evaluation of the Thermal Response of the 5-DHLWaste Package-Hypothetical Fire Accident
2001-11-03

The purpose of this calculation is to determine the thermal response of the 5-defense high level waste (DHLW)/Department of Energy (DOE) codisposal waste package (WP) to the hypothetical fire accident. The objective is to calculate the temperature response of the DHLW glass to the hypothetical short-term fire defined in 10 CFR 71, Section 73(c)(4), ...

Energy Citations Database

33
Fire and Thermal Effects of HD 1.3 Accidents: History ...
2010-07-01

... For a given accident progression, the potential for direct flame ... This may require performing heat transfer analysis for exposed structural members ...

DTIC Science & Technology

34
EPA: Response to the Columbia Shuttle Accident
2007-10-03

by the Columbia Accident Investigation Board (Feb. 13, 2003) Thermal Analysis Shows Hot Plasma Possible in Columbia Left Wheel Well Area February 13, 2003 - NASA Press...

Science.gov Websites

35
Development of detectability limits for on-orbit inspection of space shuttle wing leading edge
2005-03-01

At the conclusion of the Columbia Accident Investigation, one of the recommendations of the Columbia Accident Investigation Board (CAIB) was that NASA develop and implement an inspection plan for the Reinforced Carbon-Carbon (RCC) system components. To address these issues, a group of scientists and engineers at NASA Langley Research ...

NASA Astrophysics Data System (ADS)

36
Computational Assessment of the GT-MHR Graphite Core Support Structural Integrity in Air-Ingress Accident Condition
2008-10-01

The objective of this project was to perform stress analysis for graphite support structures of the General Atomics� 600 MWth GT-MHR prismatic core design using ABAQUS ® (ver. 6.75) to assess their structural integrity in air-ingress accident conditions where the structure weakens over time due to oxidation damages. The graphite support structures of prismatic type GT-MHR ...

Energy Citations Database

37
Computational Assessment of the GT-MHR Graphite Core Support Structural Integrity in Air-Ingress Accident Condition
2008-10-01

The objective of this project was to perform stress analysis for graphite support structures of the General Atomics� 600 MWth GT-MHR prismatic core design using ABAQUS � (ver. 6.75) to assess their structural integrity in air-ingress accident conditions where the structure weakens over time due to oxidation damages. The graphite support structures of prismatic type GT-MHR ...

DOE Information Bridge

38
Ocular injuries from laser accidents
1996-04-01

Ocular injuries resulting from exposure to laser beams are relatively uncommon since there is normally a low probability of a relatively small-diameter laser beam entering the pupil of an eye. This has been the accident experience to date with lasers used in the research laboratory and in industry. A review of the accident data ...

NASA Astrophysics Data System (ADS)

39
Coupling of Time-Dependent Neutron Transport Theory with the Thermal Hydraulics Code ATHLET and Application to the Research Reactor FRM-II
2003-11-15

We introduce a new coupled neutronics/thermal hydraulics code system for analyzing transients of nuclear power plants and research reactors, based on a neutron transport theory approach. For the neutron kinetics, we have developed the code DORT-TD, a time-dependent extension of the well-known discrete ordinates code DORT. DORT-TD uses a fully implicit time ...

Energy Citations Database

40
Handbook of road safety research
1987-01-01

This book describes the road safety, accident investigation or vehicle and highway design. This book also discusses the nature and cause of road accidents. It discusses the following contents: Forward; Preface; The main features of the accident situation in Great Britain; The interacting roles of road environment, vehicle and road user ...

Energy Citations Database

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41
Present status of research activities in severe accident evaluation for nuclear power plants.
1992-01-01

The basis for securing nuclear safety is to prevent occurrence of accidents and to mitigate propagation of abnormal events or accidents to severe accidents. In practice, a nuclear power plant is designed and constructed so that abnormal events can be dete...

National Technical Information Service (NTIS)

42
Marine Accident Reports - Summary Format, Issue Number 4--July, 1979 through August, 1980.
1982-01-01

This publication contains summary reports of major marine accidents, adopted from August 1979 through June 1982. The summary reports present the probable cause and accident descriptions for the following accidents: Oceanographic Research Vessel PROFILER, ...

National Technical Information Service (NTIS)

43
Instrumentation Availability during Severe Accidents for a Boiling Water Reactor with a Mark I Containment.
1992-01-01

In support of the U.S. Nuclear Regulatory Commission Accident Management Research Program, the availability of instruments to supply accident management information during a broad range of severe accidents is evaluated for a Boiling Water Reactor with a M...

National Technical Information Service (NTIS)

44
Human Factor Variables and Fatal Vehicular Accidents: A Pilot Study.
1973-01-01

The report is one of the Multidisciplinary Traffic Accident Research special studies in human factor variables and fatal motor vehicle accidents in the greater Boston area. The results represent the initial findings related to 50 fatal motor vehicle accid...

National Technical Information Service (NTIS)

45
Frequency of Work Zone Accidents on Construction Projects.
2005-01-01

The overall objective of this research was to study work zone accidents in New York State, with particular attention to the occurrence and mitigation of rear-end vehicle accidents. The specific objectives were to recommend changes to the NYSDOT's accident...

National Technical Information Service (NTIS)

46
Analysis of US Civil Rotorcraft Accidents from 1990 to 1996 and Implications for a Safety Program.
2001-01-01

A NASA Ames Research Center analysis of rotorcraft accident data identified safety issues that could lead to a reduction in accidents. The primary source of data was summaries of National Transportation Safety Board (NTSB) accident reports. Lower cost hel...

National Technical Information Service (NTIS)

47
Accident Management for Severe Accidents.
1988-01-01

The management of severe accidents in light water reactors is receiving much attention in several countries. The reduction of risk by measures and/or actions that would affect the behavior of a severe accident is discussed. The research program that is be...

National Technical Information Service (NTIS)

48
Thermal Hydraulic Features of the TMI Accident.
1985-01-01

The TMI-2 accident resulted in extensive core damage and recent data confirms that the reactor vessel was challenged from molten core materials. A hypothesized TMI accident sencario is presented that consistently explains the TMI data and is also consiste...

National Technical Information Service (NTIS)

49
Experimental investigation of creep rupture of reactor vessel lower head
1997-12-01

This paper summarizes experiments on creep rupture of reactor pressure vessel (RPV) lower heads under the thermal and pressure loads of a core meltdown accident. Lower head failure (LHF) is of importance to accident assessment and accident management.

Energy Citations Database

50
IIST Passive Core Cooling on Pressurizer Top Break
2004-06-15

Two experiments for a small-break loss-of-coolant accident on a pressurizer top were conducted at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility to investigate the thermal-hydraulic behavior of a passive core cooling system (PCCS) in a Westinghouse pressurized water reactor (PWR). The test results ...

Energy Citations Database

51
Untersuchungen zum waermetechnischen Verhalten von WWR-M/M2-Brennelementen. (Studies into the thermal behaviour of WWR-M/M2 fuel assemblies).
1995-01-01

For assessment of the potential hazards in spent fuel tanks of the Rossendorf research reactor, experimental data were to be acquired describing the behaviour of the fuel assemblies in the event of a kerosine-fuelled fire. The accident model describing th...

National Technical Information Service (NTIS)

52
Thermal-Hydraulic Model Verification Calculations Using the LECK-V4 Program System of Tests within the Scope of the PWR Crash Program.
1980-01-01

Within the scope of an order placed by the Federal Ministry for Research and Technology with the Battelle Institute e.V./Frankfurt, tests for the determination of thermalhydraulic processes during a loss-of-coolant accident (LOCA) were carried out in a te...

National Technical Information Service (NTIS)

53
Fire and Thermal Effects of HD 1.3 Accidents: History, Research, and Analysis.
2010-01-01

The DoD 6055.9 Quantity-Distance requirements for Hazard Division 1.3 (HD 1.3) materials are based upon the total mass of materials present in a storage location. The QD itself is determined using the cube root of the mass. This approach is reasonable whe...

National Technical Information Service (NTIS)

54
Experiment Operations Plan for the MT-4 Experiment in the NRU (National Research Universal) Reactor.
1983-01-01

A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal op...

National Technical Information Service (NTIS)

55
Experiment Operations Plan for the MT-3 Experiment in the NRU (National Research Universal) Reactor.
1983-01-01

A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal op...

National Technical Information Service (NTIS)

56
JAEA Studies on High Burnup Fuel Behaviors during Reactivity-Initiated Accident and Loss-of-Coolant Accident
2007-07-01

The objectives of fuel safety research program at Japan Atomic Energy Agency (JAEA) are; to evaluate adequacy of present safety criteria and safety margins; to provide a database for future regulation on higher burnup UO{sub 2} and MOX fuels, new cladding and pellets; and to provide reasonably mechanistic computer codes for regulatory application. The JAEA program is comprised ...

Energy Citations Database

57
Fast breeder reactor safety
1976-01-01

The current state of knowledge with respect to the analysis of postulated accident sequences in fast breeder reactors, as well as some implications to fast reactor design, are reviewed. The accidents considered include loss of coolant flow and transient overpower, both with a postulated failure to scram. The associated accident ...

DOE Information Bridge

58
Winter Runway Research - NASA

Research Aims To Prevent Accidents On Hazardous Runways ... Most of those accidents involved fatalities. NASA supports a national goal to reduce the fatal ...

NASA Website

59
Fuel Rod Thermal Analysis of the Angra-1 Reactor During a Postulated Loss of Coolant Accident.
1982-01-01

A thermal analysis of a fuel element is performed, as subject to the most severe cooling conditions, such as those occurring during a postulated Loss of Coolant Accident in the Angra-I reactor. Our objective was to ascertain whether the cooling of the cor...

National Technical Information Service (NTIS)

60
Management of severe accidents. Perspectives on managing severe accidents in commercial nuclear power plants. Vol. 1
1985-05-01

Accident management is examined from several different perspectives. The emphasis is on the role of the operating crew and the technical support provided to them before, during, and after an accident. The relationship among accident management, risk management, and emergency management is examined. The roles played by industry, ...

Energy Citations Database

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61
Accident management for severe accidents
1988-01-01

The management of severe accidents in light water reactors is receiving much attention in several countries. The reduction of risk by measures and/or actions that would affect the behavior of a severe accident is discussed. The research program that is being conducted by the US Nuclear Regulatory Commission focuses on both in-vessel ...

DOE Information Bridge

62
Overview of the PBF test results. [PWR; BWR
1980-01-01

The Thermal Fuels Behavior Program (TFBP) of EG and G Idaho conducts fuel behavior research in the Power Burst Facility (PBF) at INEL and at the Halden Reactor in Norway. The fuels behavior research in the PBF is directed toward providing a detailed understanding of the response of light water reactor (LWR) nuclear fuel assemblies to ...

Energy Citations Database

63
SORS/NP1. Thermal Release of Radioactivity from MHTGR Core During Temp Excursion Accidents
1974-04-15

Estimates activity release from coated particles and heavy metal contamination in MHTGR cores due to thermal transients.

Energy Citations Database

64
Recreational Boat Collision Accident Research. Volume 1.
1992-01-01

This report is the result of three years of research on the subject of recreational boat collision accident reconstruction. The primary focus of the report is to develop techniques for reconstructing boat collision accidents based on physical evidence.

National Technical Information Service (NTIS)

65
Recent Developments in Burn Management and Research ...
1971-04-01

... Corporate Author : EUROPEAN RESEARCH OFFICE LONDON (ENGLAND). ... Research Council Burns Unit, Birmingham Accident Hospital, and the ...

DTIC Science & Technology

66
Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics
1993-03-01

This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 ...

Energy Citations Database

67
RESEARCH ON ABSORBEFACIENT SURFACES
1962-04-01

... NICKEL ALLOYS, OXIDES, PHOSPHATES, SURFACES, THERMAL CONDUCTIVITY, THERMAL INSULATION, THERMAL RADIATION. ...

DTIC Science & Technology

68
ENGINEERING RESEARCH-ECCOFOAM ' 'Q' ' THERMAL ...
1958-08-22

... (Author). Descriptors : *THERMAL CONDUCTIVITY, *THERMAL INSULATION, HEAT, STABILITY, TEMPERATURE. Distribution ...

DTIC Science & Technology

69
DIFFERENTIAL THERMAL ANALYSIS AS A RESEARCH ...
1961-10-01

... XEROX - DIFFERENTIAL THERMAL ANALYSIS AS A ... Application of Thermal Analysis to Clays and Illuminous Minerals, by S. Spiel. ...

DTIC Science & Technology

70
ANS sixth proceedings of the nuclear thermal hydraulics
1990-01-01

This book is covered under the following topics: Thermal Hydraulics of Severe Accidents; Thermal Hydraulics of Noncommercial Reactors; Thermal Hydraulic Aspects of Passive Safety and New-Generation Reactors; Method s In Reactor Physics and Thermal Hydraulics; Thermal ...

Energy Citations Database

71
Skid Resistance Research
1977-01-01

Skidding causes many traffic accidents. Streets and highways with skid-resisting surfaces reduce the

NASA Technical Reports Server (NTRS)

72
Recreational Boat Collision Accident Research, Volume 2. ...
1992-10-01

... Subject Categories : COMPUTER PROGRAMMING AND SOFTWARE MARINE ENGINEERING SAFETY ENGINEERING. ...

DTIC Science & Technology

73
Investigation of an Explosive Accident Using Simulation as a ...
1990-08-01

... Descriptive Note : Conference paper. Corporate Author : DEFENCE RESEARCH ESTABLISHMENT VALCARTIER (QUEBEC). ...

DTIC Science & Technology

74
Helicopter Safety Research
1999-01-01

In response to the President's challenge to reduce civil aviation accidents by a factor of 10 by the

NASA Technical Reports Server (NTRS)

75
Accident Proneness: A Research Review
1993-05-01

... prone" development ,[a folklore surrounding the notion of groups. ... each A factor contributing to the folklore was that year. ...

DTIC Science & Technology

76
A Review of Research and Development in Crashworthiness ...
1990-02-01

... AVIATION AIRCRAFT, LITERATURE SURVEYS, FLOORS, STRUCTURES, ACCIDENTS, SEATS, CRASHWORTHINESS, HIGH RATE, CANADA. ...

DTIC Science & Technology

77
Pressurized-thermal-shock tests
1981-01-01

Pressurized-thermal-shock experiments are required to validate methods of fracture analysis to establish the degree of conservatism or accuracy involved in predictions of flaw behavior under certain accident conditions. By using methods and facilities developed for this purpose we can simulate materials and loading regimes to evaluate the integrity of ...

DOE Information Bridge

78
Prediction of nonlinear structural response in LMFBR elevated-temperature piping
1984-06-01

The development of structural analysis capabilities to investigate possible accident initiations caused by structural degradation of liquid metal fast breeder reactor (LMFBR) piping is summarized. The ABAQUS finite element code is used to perform a nonlinear analysis of a bench mark problem proposed by the Pressure Vessel Research Committee. The problem is ...

Energy Citations Database

79
Thermal-hydraulic calculations for the conversion to LEU of a research reactor core
2008-07-15

The thermal-hydraulic analysis performed for the needs of the conversion of the open pool 5MW Greek Research Reactor (GRR-1) to a pure Low Enrichment (LEU) configuration is presented. The methodology was based on a complete set of neutronic calculations performed for the new core configuration, in compliance with pre-defined Operation Limiting Conditions. ...

Energy Citations Database

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