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1
Evaluation of impact from Chernobyl accident.
1993-01-01

The impact on society of the Chernobyl accidents is assessed. The situation prior to Chernobyl with respect to regulations of radiation protection against the consequences of a major accident is considered. The development of the recommendations and regul...

National Technical Information Service (NTIS)

2
10 CFR 76.85 - Assessment of accidents.
2011-01-01

...2011-01-01 false Assessment of accidents. 76.85 Section 76.85 Energy...Safety § 76.85 Assessment of accidents. The Corporation shall perform an analysis of potential accidents and consequences to...

Code of Federal Regulations, 2011

3
Probablisitic Accident Consequence Uncertainty Analysis. Late Health Effects Uncertainty Assessment. Volume 2. Appendices.
1997-01-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was developed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. ...

National Technical Information Service (NTIS)

4
Probabilistic Accident Consequence Uncertainty Analysis: Uncertainty Assessment for Internal Dosimetry. Volume 2, Appendices.
1998-01-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. ...

National Technical Information Service (NTIS)

5
Probabilistic Accident Consequence Uncertainty Analysis. Uncertainty Assessment for Internal Dosimetry. Volume 1. Main Report.
1998-01-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. ...

National Technical Information Service (NTIS)

6
Probabilistic Accident Consequence Uncertainty Analysis. Late Health Effects Uncertainty Assessment. Volume 1. Main Report.
1997-01-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was developed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. ...

National Technical Information Service (NTIS)

7
MACCS usage at Rocky Flats Plant for consequence analysis of postulated accidents.
1993-01-01

The MELCOR Accident Consequence Code System (MACCS) has been applied to the radiological consequence assessment of potential accidents from a non-reactor nuclear facility. MACCS has been used in a variety of applications to evaluate radiological dose and ...

National Technical Information Service (NTIS)

8
Utilization of Dose Assessment Models to Facilitate off-Site Recovery Operations for Accidents at Nuclear Facilities.
1989-01-01

One of the most important uses of dose assessment models in response to accidents at nuclear facilities is to help provide guidance to emergency response managers for identifying, and mitigating, the consequences of an accident once the accident has been ...

National Technical Information Service (NTIS)

9
Accident-Generated Radioactive Particle Source Term Development for Consequence Assessment of Nuclear Fuel Cycle Facilities.
1983-01-01

Consequences of nuclear fuel cycle facility accidents can be evaluated using aerosol release factors developed at Pacific Northwest Laboratory. These experimentally determined factors are compiled and consequence assessment methods are discussed. Release ...

National Technical Information Service (NTIS)

10
Methodology for Accident Analyses in SAR'S.
1981-01-01

Consistent methodology should be adopted in accident analyses sections of SARs. These accident sections should describe both consequence and risk from potential accidents that could occur in a facility being assessed. These analyses should consider three ...

National Technical Information Service (NTIS)

11
10 CFR 76.85 - Assessment of accidents.
2009-01-01

...occurrences and accidents with existing systems and procedures intended to mitigate the release consequences, along with site characteristics, including meteorology, to evaluate the offsite radiological...

Code of Federal Regulations, 2010

12
Probabilistic Accident Consequence Uncertainty Analysis: Uncertainty Assessment for Deposited Materials and External Doses. Volume 2. Appendices.
1997-01-01

This volume is the second of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. Thes...

National Technical Information Service (NTIS)

13
Probabilistic Accident Consequence Uncertainty Analysis: Uncertainty Assessment for Deposited Material and External Doses. Volume 1. Main Report.
1997-01-01

This volume is the first of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These...

National Technical Information Service (NTIS)

14
The Chornobyl Accident: A Comprehensive Risk Assessment
2000-01-01

This work, the first by native Ukrainian scientists and specialists, views the Chernobyl nuclear accident from the perspective of risk assessment. It describes the accident, the shelter constructed to contain the destroyed reactor, the sites used for disposal and storage of radioactive waste, the environmental contamination, and the ...

NSDL National Science Digital Library

15
The Chornobyl Accident: A Comprehensive Risk Assessment
2000-01-01

This book provides a comprehensive of the April 1986 Chornobyl Nuclear Power Plant accident and its short and long-term effects in the fourteen years since the accident. Chapters include: cause and description of the accident; the Shelter constructed to contain the remains the destroyed reactor, radioactive wastes arising from the ...

Energy Citations Database

16
Assessing economic consequences of radiation accidents
1987-01-01

This project reviewed the literature on the economic consequences of accidents to determine the availability of assessment methods and data and their applicability to the high-level radioactive waste (HLW) disposal system before closure; determined needs for expansion, revision, or adaptation of methods and data for modeling economic ...

Energy Citations Database

17
Calculation Notes for Radiological and Toxicological Accident Consequences to Support EA for Sludge Storage at T Plant SNF subproject A.13 (b)
2001-03-12

Calculation notes used to derive radiological/toxicological consequences resulting from selected accident scenarios. This document supports the environmental assessment for sludge storage at T Plant

DOE Information Bridge

18
The health impact of major nuclear accidents: The case of Greece
1993-10-01

An assessment of the radiological consequences that would result for the population of Greece from postulated major nuclear accidents in the Kozloduy nuclear power station in Bulgaria is performed. Kozloduy lies at a distance of 225 km from the northern borders of Greece and contains six reactors, all of the Russian WWER type. The ...

Energy Citations Database

19
System response of a DOE Defense Program package in a transportation accident environment
1992-10-15

The system response in a transportation accident environment is an element to be considered in an overall Transportation System Risk Assessment (TSRA) framework. The system response analysis uses the accident conditions and the subsequent accident progression analysis to develop the accident ...

Energy Citations Database

20
Methodology for accident analyses in SAR's
1981-01-01

Consistent methodology should be adopted in accident analyses sections of SARs. These accident sections should describe both consequence and risk from potential accidents that could occur in a facility being assessed. These analyses should consider three general classes of ...

Energy Citations Database

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21
Structure shielding from cloud and fallout gamma ray sources for assessing the consequences of reactor accidents
1975-12-01

Radiation shielding provided by transportation vehicles and structures typical of where people live and work were estimated for cloud and fallout gamma-ray sources resulting from a hypothetical reactor accident. Dose reduction factors are recommended for a variety of situations for realistically assessing the consequences of reactor ...

Energy Citations Database

22
Generic considerations of LMFBR hypothetical accident energetics
1978-01-01

The paper provides a preliminary assessment of generic accident energetics issues associated with alternatives relative to the reference (U,Pu) oxide fuel in liquid metal fast breeder reactors. The alternatives considered include thorium- and uranium-based oxide, carbide and metal fuel types. This assessment is made within the context ...

Energy Citations Database

23
Importance of emergency response actions to reactor accidents within a probabilistic consequence assessment model
1997-03-01

An uncertainty and sensitivity analysis of early health consequences of severe accidents at nuclear power plants as a function of the emergency response parameters has been performed using a probabilistic consequence assessment code. The importance of various emergency response parameters in predicting the ...

DOE Information Bridge

24
Methods for nuclear air-cleaning-system accident-consequence assessment
1982-01-01

This paper describes a multilaboratory research program that is directed toward addressing many questions that analysts face when performing air cleaning accident consequence assessments. The program involves developing analytical tools and supportive experimental data that will be useful in making more realistic ...

Energy Citations Database

25
Probabilistic Risk Assessment Course Documentation. Volume 7. Environmental Transport and Consequence Analysis.
1985-01-01

Consequence models have been designed to assess health and economic risks from potential accidents at nuclear power plants. These models have been applied to an ever increasing variety of problems with ever increasing demands to improve modeling capabilit...

National Technical Information Service (NTIS)

26
MACCS usage at Rocky Flats Plant for consequence analysis of postulated accidents
1993-10-01

The MELCOR Accident Consequence Code System (MACCS) has been applied to the radiological consequence assessment of potential accidents from a non-reactor nuclear facility. MACCS has been used in a variety of applications to evaluate radiological dose and health effects to the public from ...

DOE Information Bridge

27
[Health after Fukushima. A current perspective].
2011-07-01

This short paper reflects on the current situation after the Fukushima nuclear accident and the potential health consequences of the disaster. We discuss perspectives related to radiation protection activities as well as to epidemiologic monitoring and research in the affected regions in order to assess long-term effects of the ...

PubMed

28
Survey of Strain-Rate Effects for Some Common Structural Materials Used in Radioactive Material Packaging and Transportation Systems.
1976-01-01

In safety evaluation of radioactive material packaging and transport systems during accidents mechanical property data for the structural materials under impact conditions are needed in order to assess the damage and consequences of the accident. This doc...

National Technical Information Service (NTIS)

29
Structure Shielding from Cloud and Fallout gamma Ray Sources for Assessing the Consequences of Reactor Accidents.
1975-01-01

Radiation shielding provided by transportation vehicles and structures typical of where people live and work were estimated for cloud and fallout gamma-ray sources resulting from a hypothetical reactor accident. Dose reduction factors are recommended for ...

National Technical Information Service (NTIS)

30
Probabilistic Risk Assessment Course Documentation. Volume 5. System Reliability and Analysis Techniques Session D - Quantification.
1985-01-01

The course focuses on the probabilistic quantification of accident sequences and the link between accident sequences and consequences. Previous sessions in this series have focused on the quantification of system reliability (Session A) and the developmen...

National Technical Information Service (NTIS)

31
Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities. Yucca Mountain Site Characterization Project.
1992-01-01

This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analys...

National Technical Information Service (NTIS)

32
NARAC: An Emergency Response Resource for Predicting the Atmospheric Dispersion and Assessing the Consequences of Airborne Radionuclides.
2005-01-01

Hazardous radioactive materials can be released into the atmosphere by accidents at nuclear power plants, fuel processing facilities, and other facilities, and by transportation accidents involving nuclear materials. In addition, the post-cold-war prolife...

National Technical Information Service (NTIS)

33
Health and Environmental Consequences of the Chernobyl Nuclear Power Plant Accident.
1987-01-01

An assessment of the impact of the Chernobyl accident on the Northern Hemisphere is presented in this report. It relies heavily on the USSR report presented to the International Atomic Energy Agency. There are gaps in present knowledge and, in some areas,...

National Technical Information Service (NTIS)

34
Depressurization as an Accident Management Strategy to Minimize the Consequences of Direct Containment Heating.
1990-01-01

Probabilistic Risk Assessments (PRAs) have identified severe accidents for nuclear power plants that have the potential to cause failure of the containment through direct containment heating (DCH). Prevention of DCH or mitigation of its effects may be pos...

National Technical Information Service (NTIS)

35
Comparison of Sodium Aerosol Codes.
1984-01-01

Although hypothetical fast reactor accidents leading to severe core damage are very low probability events, their consequences are to be assessed. During such accidents, one can envisage the ejection of sodium, mixed with fuel and fission products, from t...

National Technical Information Service (NTIS)

36
Chernobyl Nuclear Accident and Its Consequences.
1986-01-01

An AAEC Task Group was set up shortly after the accident at the Chernobyl Nuclear Power Plant to monitor and evaluate initial reports and to assess the implications for Australia. The Task Group issued a preliminary report on 9 May 1986. On 25-29 August 1...

National Technical Information Service (NTIS)

37
[Radiologic consequences and medico-biological problems 4 years after the accident at the Chernobyl Atomic Electric Power Station].
1992-01-01

The data on the assessment of the radiobiological situation and the results of clinical and epidemiological studies into the population health status, exposed to radiation because of the Chernobyl NPP accident are summarized. Appropriate regularities in soil contamination with 137Cs are ascertained. It has been shown that the disease incidence among the ...

PubMed

38
Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendix VI. Calculation of reactor accident consequences. [PWR and BWR
1975-10-01

Information is presented concerning the radioactive releases from the containment following accidents; radioactive inventory of the reactor core; atmospheric dispersion; reactor sites and meteorological data; radioactive decay and deposition from plumes; finite distance of plume travel; dosimetric models; health effects; demographic data; mitigation of radiation exposure; ...

Energy Citations Database

39
The radiological impact of the Chernobyl accident
1988-01-01

The purpose of this paper is to summarize the international assessments of the radiological impact of the Chernobyl accident. The Chernobyl accident was a technological disaster that went beyond the most pessimistic scenarios of nuclear engineers. It was more sever than a maximum credible accident to which nuclear ...

Energy Citations Database

40
Radiological Consequence of Chernobyl Nuclear Power Accident in Japan. Review of Radioecological Studies and the Dose Assessment on Japanese for the Period of 1 Year after the Accident.
1988-01-01

Two years have elapsed since the accident in Chernobyl nuclear power station shocked those concerned with nuclear power generation. The effect that this accident exerted on human environment has still continued directly and indirectly, and the reports on ...

National Technical Information Service (NTIS)

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41
Probabilistic risk assessment of disassembly procedures
1993-11-01

The purpose of this report is to describe the use of Probabilistic Risk (Safety) Assessment (PRA or PSA) at a Department of Energy (DOE) facility. PRA is a methodology for (i) identifying combinations of events that, if they occur, lead to accidents (ii) estimating the frequency of occurrence of each combination of events and (iii) estimating the ...

DOE Information Bridge

42
Application of accident progression event tree technology to the Savannah River Site Defense Waste Processing Facility SAR analysis
1993-12-31

The Accident Analysis in the Safety Analysis Report (SAR) for the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) has recently undergone an upgrade. Non-reactor SARs at SRS (and other Department of Energy (DOE) sites) use probabilistic techniques to assess the frequency of accidents at their facilities. This paper ...

Energy Citations Database

43
Review and assessment of package requirements (yellowcake) and emergency response to transportation accidents. [Low specific activity
1978-10-01

As a consequence of an accident involving a truck shipment of yellowcake, a joint NRC--DOT study was undertaken to review and assess the regulations and practices related to package integrity and to emergency response to transportation accidents involving low specific activity radioactive materials. Recommendations ...

Energy Citations Database

44
Savannah River Site K-Reactor Probabilistic Safety Assessment
1992-12-01

This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods employed to represent these ...

Energy Citations Database

45
Defense Programs Transportation Risk Assessment
1994-08-01

This paper provides an overview of the methodology used in a probabilistic transportation risk assessment conducted to assess the probabilities and consequences of inadvertent dispersal of radioactive materials arising from severe transportation accidents. The model was developed for the Defense Program ...

Energy Citations Database

46
Evaluacion de consecuencias de accidentes nucleares. Metodos de analisis probabilista de riesgo, estado actula y aplicaciones. (Evaluation of nuclear accidents consequences. Risk assessment methodologies, current status and applications).
1996-01-01

General description of the structure and process of the probabilistic methods of assessment the external consequences in the event of nuclear accidents is presented. attention is paid in the interface with Probabilistic Safety Analysis level 3 results (so...

National Technical Information Service (NTIS)

47
Accident Consequences and Risk Assessments Based on the Probabilistic Safety Study of a Nuclear Power Plant with a High Temperature Reactor (HTR-1160).
1982-01-01

Starting with the results of the probabilistic safety study of a nuclear power plant with a HTR-1160, accident consequences and risk assessments have been performed for the site location Schmehausen near Hamm (FRG). The calculations were accomplished usin...

National Technical Information Service (NTIS)

48
Accident Consequence Calculations and Risk Assessments for Pressurized Light Water Reactors with the Computer Code UFOMOD/B3.
1983-01-01

With respect to the application of the accident consequence model of the German Risk Study (GRS) for light water reactors to risk assessments of other reactor types (high temperature reactor HTR-1160, fast breeder reactor SNR-300), the improved version UF...

National Technical Information Service (NTIS)

49
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

50
ARAMIS project: a comprehensive methodology for the identification of reference accident scenarios in process industries.
2005-08-26

In the frame of the Accidental Risk Assessment Methodology for Industries (ARAMIS) project, this paper aims at presenting the work carried out in the part of the project devoted to the definition of accident scenarios. This topic is a key-point in risk assessment and serves as basis for the whole risk quantification. The first result ...

PubMed

51
HTGR accident initiation and progression analysis status report. Volume VI. Event consequences and uncertainties demonstrating safety R and D importance of fission product transport mechanisms
1976-01-01

Five accident conditions are considered in an analysis of their radiological consequences. The five accident conditions are core heatup resulting from loss of offsite power and earthquake; reheater tube leak; slow depressurization; rapid depressurization; and steam ingress from steam generator main bundle tube rupture. ...

Energy Citations Database

52
Summary of the CEC/USDOE workshop on uncertainty analysis
1990-06-01

There is uncertainty in all aspects of assessing the consequences of accidental releases of radioactive material, from understanding and describing the environmental and biological transfer processes to modeling emergency response. The need for an exchange of views and a comparison of approaches between the diverse disciplines led to the organization of a ...

Energy Citations Database

53
RASCAL (Radiological Assessment System for Consequence AnaLysis): A screening model for estimating doses from radiological accidents
1988-01-01

The Radiological Assessment System for Consequence AnaLysis (RASCAL) is a new MS-DOS-based dose assessment model which has been written for the US Nuclear Regulatory Commission for use during response to radiological emergencies. RASCAL is designed to provide crude estimates of the effects of an accident while the ...

DOE Information Bridge

54
Methodology of dose calculation for the SRS SAR
1991-07-01

The Savannah River Site (SRS) Safety Analysis Report (SAR) covering K reactor operation assesses a spectrum of design basis accidents. The assessment includes estimation of the dose consequences from the analyzed accidents. This report discusses the methodology used to perform the dose analysis ...

DOE Information Bridge

55
Summary of uncertainty analysis of dispersion and deposition modules of the MACCS and COSYMA consequence codes: A joint USNRC/CEC study
1993-10-01

This paper briefly describes an ongoing project designed to assess the uncertainty in offsite radiological consequence calculations of hypothetical accidents in commercial nuclear power plants. This project is supported jointly by the Commission of European Communities (CEC) and the US Nuclear Regulatory Commission (USNRC). Both ...

DOE Information Bridge

56
Review of methodology for accident consequence assessment
1978-09-01

This report reviews current methodologies for reactor accident consequence analysis and describes areas where modifications are warranted. Methodologies reviewed are: (1) Models in Regulatory Guides 1.109, 1.111 and 1.113 used for evaluation of compliance with 10 CFR 50 Appendix I; (2) Models in Regulatory Guides used for evaluation of ...

Energy Citations Database

57
Application of aerosol technology in LMFBR design
1980-01-01

Aerosol technology is applied in several areas in the safety assessment of liquid metal fast breeder reactors. This paper discusses the application of this technology in the assessment of the Clinch River Breeder Reactor Plant. The importance of considering aerosol effects is discussed for sodium fires, the assessment of site ...

Energy Citations Database

58
CEC workshop on methods for assessing the offsite radiological consequences of nuclear accidents

On Apr 15-19, 1985, in Luxembourg, the Commission of the European Communities (CEC), in collaboration with the Kernforschungszentrum Karlsruhe (KfK), Federal Republic of Germany, and the National Radiological Protection Board (NRPB), United Kingdom, presented a workshop on methods for assessing the offsite radiological consequences of nuclear ...

Energy Citations Database

59
From Chernobyl
1996-01-01

The lradiological a consequences of the Chernobyl accident Proceedings of the first international conference

E-print Network

60
Probabilistic Risk Assessment of disassembly procedures
1993-10-01

Probabilistic Risk (Safety) Assessment (PRA or PSA) is an analytic methodology for identifying the combination of events that, if they occur, lead to accidents. Accidents are defined as those events causing loss or injury to people, property, or the environment. PRA also provides a method for estimating the frequency of occurrence of ...

Energy Citations Database

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61
Re-Assessment of Road Accident Data-Analysis Policy: Applying Theory from Involuntary, High-Consequence, Low-Probability Events like Nuclear Power Plant Meltdowns to Voluntary, Low-Consequence, High-Probability Events like Traffic Accidents.
2002-01-01

This report examines the literature on involuntary, high-consequence, low-probability (IHL) events like nuclear power plant meltdowns to determine what can be applied to the problem of voluntary, low-consequence high-probability (VLH) events like traffic ...

National Technical Information Service (NTIS)

62
Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendix XI. Analysis of comments on the draft WASH-1400 report. [PWR and BWR
1975-10-01

Information is presented concerning comments on reactor safety by governmental agencies and civilian organizations; reactor safety study methodology; consequence model; probability of accident sequences; and various accident conditions.

DOE Information Bridge

63
LNG risk management
1980-12-01

A general methodology is presented for conducting an analysis of the various aspects of the hazards associated with the storage and transportation of liquefied natural gas (LNG) which should be considered during the planning stages of a typical LNG ship terminal. The procedure includes the performance of a hazards and system analysis of the proposed site, a probability analysis of ...

NASA Astrophysics Data System (ADS)

64
Chernobyl: an early report
1986-06-01

An overview and assessment of the nuclear accident at Chernobyl is presented. The authors have assembled data from throughout Europe to estimate upper bounds for the possible radiation releases from the accident, the exposures these may produce in humans, and the health consequences that may follow. Measurements of ...

Energy Citations Database

65
300-Area accident analysis for Emergency Planning Zones
1983-06-27

The Department of Energy has requested SRL assistance in developing offsite Emergency Planning Zones (EPZs) for the Savannah River Plant, based on projected dose consequences of atmospheric releases of radioactivity from potential credible accidents in the SRP operating areas. This memorandum presents the assessment of the offsite ...

Energy Citations Database

66
Savannah River Site reactor safety assessment. Draft.
1991-01-01

This report gives the results of a Savannah River Site (SRS) Production Reactor risk assessment. Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the repor...

National Technical Information Service (NTIS)

67
Primary Coolant System Response to an HTGR Core Heatup.
1977-01-01

Consequences of an unrestricted core heatup in an HTGR were assessed as part of the ERDA-funded probabilistic risk assessment study titled ''Accident Initiation and Progression Analysis'' (AIPA). The original objective of the AIPA study was to provide gui...

National Technical Information Service (NTIS)

68
Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 1: Main report
1997-06-01

This volume is the first of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear ...

DOE Information Bridge

69
Assessment of the environmental impact in Portugal of a potential nuclear accident

At the international level the Chernobyl accident reemphasized the importance of long-range air pollution effects and in Portugal the need for assessment of the likely environmental and socioeconomic impacts of a hypothetical accident in a Spanish nuclear power plant to anticipate eventual protective and mitigating actions was ...

Energy Citations Database

70
Assessment of possible consequences of a hypothetical reactivity accident associated with a {open_quotes}Topaz-2{close_quotes} spacecraft reactor entering water
1994-12-01

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 ...

Energy Citations Database

71
Forecasting consequences of accidental release: how reliable are current assessment models
1983-01-01

This paper focuses on uncertainties in model output used to assess accidents. We begin by reviewing the historical development of assessment models and the associated interest in uncertainties as these evolutionary processes occurred in the United States. This is followed by a description of the sources of uncertainties in ...

Energy Citations Database

72
Industrial accidents triggered by flood events: analysis of past accidents.
2009-10-15

Industrial accidents triggered by natural events (NaTech accidents) are a significant category of industrial accidents. Several specific elements that characterize NaTech events still need to be investigated. In particular, the damage mode of equipment and the specific final scenarios that may take place in NaTech ...

PubMed

73
Use of NUREG-1150 and IPEs in accident management.
1992-01-01

The fundamental objective of the accident management program is to assure, in the event of a severe accident at a nuclear plant, that the effectiveness of personnel and equipment is maximized in preventing or mitigating the consequences of the accident. T...

National Technical Information Service (NTIS)

74
A POTENTIAL APPLICATION OF UNCERTAINTY ANALYSIS TO DOE-STD-3009-94 ACCIDENT ANALYSIS
2007-05-10

The objective of this paper is to assess proposed transuranic waste accident analysis guidance and recent software improvements in a Windows-OS version of MACCS2 that allows the inputting of parameter uncertainty. With this guidance and code capability, there is the potential to perform a quantitative uncertainty assessment of ...

Energy Citations Database

75
The consequences and frequency of selected man-originated accident events. Final report
1980-06-01

Data are compiled for man-caused accidents where there were ten or more fatalities, thirty or more injuries, or three million dollars or more in property damage for the period, 1953 through 1973. Data are also summarized in various classifications, such as transportation, hazardous materials, etc. A bibliography is included. Discussions are made of the limitations on use of ...

Energy Citations Database

76
Utilization of dose assessment models to facilitate off-site recovery operations for accidents at nuclear facilities
1989-09-01

One of the most important uses of dose assessment models in response to accidents at nuclear facilities is to help provide guidance to emergency response managers for identifying, and mitigating, the consequences of an accident once the accident has been terminated. By combining results from ...

Energy Citations Database

77
CRBRP structural and thermal margin beyond the design base
1979-01-01

Although Hypothetical Core Disruptive Accidents (HCDAs) are not Design Basis Accidents for the Clinch River Breeder Reactor Plant, extensive assessments of HCDA consequences have been made. Prudent margins beyond the design base have been included in the design to further reduce the risk to the public from highly ...

DOE Information Bridge

78
RASCAL (Radiological Assessment System for Consequence AnaLysis): A Screening Model for Estimating Doses from Radiological Accidents.
1988-01-01

The Radiological Assessment System for Consequence AnaLysis (RASCAL) is a new MS-DOS-based dose assessment model which has been written for the US Nuclear Regulatory Commission for use during response to radiological emergencies. RASCAL is designed to pro...

National Technical Information Service (NTIS)

79
Consequences of a production reactor accident
1963-03-08

The purpose of this report is to estimate the consequences of a Hanford reactor accident with emphasis on the effects at distant points. The potential effects in Canada are estimated as well as the consequences within the United States.

DOE Information Bridge

80
Process for controlling accidents in chemical laboratories
1980-10-01

Most laboratory safety programs include inspections to identify hazards and thereby control accidents. There are certain elements that must be a part of a successful inspection and control process. These are a systematic and consistent inspection procedure, a reliable evaluation of identified hazards, and effective follow-up actions. Laboratory management, through its ...

DOE Information Bridge

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81
Experience with COSYMA in an international intercomparison of probabilistic accident consequence assessment codes
1996-03-01

The Commission of the European Communities and the Nuclear Energy Agency of the OECD have organized an international exercise to compare the predictions of accident consequence assessment codes, and to identify those features of the models which lead to differences in the predicted results. Alongside this, a further exercise was ...

Energy Citations Database

82
Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 1: Main report
1998-04-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the ...

Energy Citations Database

83
Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for deposited material and external doses. Volume 1: Main report
1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the ...

Energy Citations Database

84
Probabilistic accident consequence uncertainty analysis -- Early health effects uncertainty assessment. Volume 1: Main report
1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the ...

Energy Citations Database

85
Probabilistic accident consequence uncertainty analysis -- Late health effects uncertainty assessment. Volume 1: Main report
1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the ...

Energy Citations Database

86
Immediate medical consequences of nuclear accidents: lessons from Chernobyl
1987-08-07

The immediate medical response to the nuclear accident at the Chernobyl nuclear power station involved containment of the radioactivity and evacuation of the nearby population. The next step consisted of assessment of the radiation dose received by individuals, based on biological dosimetry, and treatment of those exposed. Medical care involved treatment ...

Energy Citations Database

87
Exploratory sensitivity study with the MACCS (MELCOR Accident Consequence Code System) Reactor Accident Consequence Model.
1990-01-01

An exploratory sensitivity study with the MELCOR Accident Consequence Code System (MACCS) is presented. This study was performed to provide (1) an indication of the possible impact of consequence modeling uncertainties on the results of an integrated prob...

National Technical Information Service (NTIS)

88
Support for Nuclear Explosive Safety Division, Department of Energy, Albuquerque Operations. Effects of a postulated uranium transportation accident.
1997-01-01

Transportation System Risk Assessments (TSRAs) document the degree of compliance of proposed DOE shipments of nuclear components with applicable federal regulations and the risk associated with the proposed shipments. TSRAs must often evaluate the consequ...

National Technical Information Service (NTIS)

89
Summary of an abridged assessment of shutdown risk for a Mark III boiling water reactor.
1992-01-01

An abridged accident progression and consequence analysis was performed on a selected portion of the refueling mode of operation at the Grand Gulf Nuclear Power Plant. In this abridged analysis simplified models were used to delineate the possible acciden...

National Technical Information Service (NTIS)

90
Run-off of Strontium with Melting Snow in Spring.
1986-01-01

When assessing the consequences of atmospheric releases caused by a large reactor accident, one usually finds that the major contributions to the dose are via nutrition and from exposure to radiation from radioactive materials deposited on ground. The exp...

National Technical Information Service (NTIS)

91
Radiological assessments of radionuclide releases. Foreign trip report, November 30, 1990-December 15, 1990.
1990-01-01

As a consequence of the Chernobyl accident, data have been obtained throughout the Northern Hemisphere on the concentrations of radionuclides in air, vegetation, soil, water, and foodstuffs that could be important means of human exposure. At the IAEA's in...

National Technical Information Service (NTIS)

92
Probabilistic Trajectory and Dose Analysis for Finland Due to Hypothetical Radioactive Releases at Sosnovyy Bor.
1988-01-01

The Chernobyl accident initiated a wide international interest in developing long range transport models for assessment of radiological consequences due to airborne releases. The Finnish TRADOS computer model had been developed to calculate long range atm...

National Technical Information Service (NTIS)

93
Preliminary Investigations of the Significance of the Ingestion Pathway Following Accidental Releases with Actinides.
1985-01-01

Preliminary accident consequence assessments have been performed with the computer code UFOMOD to study the significance of the ingestion pathway in accidental releases with actinides. The investigation was based on the release category K1 of the 'Risk Or...

National Technical Information Service (NTIS)

94
Launch Safety, Toxicity, and Environmental Effects of the High Performance Oxidizer ClF(5).
1994-01-01

An assessment is presented for the human toxicity, environmental, and ecological consequences resulting from accidental releases of ClF5 liquid propellant. Various accident scenarios are considered involving instantaneous releases of 2000 kg of propellant...

National Technical Information Service (NTIS)

95
HTGR accident initiation and progression analysis status report. Volume II. AIPA risk assessment methodology
1975-10-01

A comprehensive summary is presented of the methods and techniques used in risk analyses. Included are discussions of initiating event selection, event tree construction, probability evaluation, consequence evaluation, and presentation of results. (DG)

Energy Citations Database

96
General aspects of meteorology and wind flow patterns at the National Medical Cyclotron site, Camperdown, NSW, Australia.
1994-01-01

As part of an assessment into the consequences of a potential accident at the National Medical Cyclotron, Camperdown, NSW., Australia, two meteorological stations were installed to monitor the winds, temperatures and atmospheric dispersion conditions. The...

National Technical Information Service (NTIS)

97
Frequency Distributions of Activity Concentrations after Accidential Releases of Radionuclides.
1984-01-01

The increasing application of risk assessments for nuclear installations in decision making procedures also requires to analyse intermediate results of accident consequence calculations in detail. The activity concentrations to be expected are an importan...

National Technical Information Service (NTIS)

98
Elements of a National Emergency Response System for Nuclear Accidents.
1987-01-01

The purpose of this paper is to suggest elements for a general emergency response system, employed at a national level, to detect, evaluate and assess the consequences of a radiological atmospheric release occurring within or outside of national boundarie...

National Technical Information Service (NTIS)

99
Developing Criteria for Risk Assessment of Non-Reactor Nuclear Facilities.
1983-01-01

Nuclear facilities containing fissionable material generally require a comprehensive safety analysis. The risk as a function of the probability and consequence must be determined for accident scenarios. This paper discusses methodology for conducting such...

National Technical Information Service (NTIS)

100
An analysis of the impact of having uranium dioxide mixed in with plutonium dioxide
1998-10-21

An assessment was performed to show the impact on airborne release fraction, respirable fraction, dose conversion factor and dose consequences of postulated accidents at the Plutonium Finishing Plant involving uranium dioxide rather than plutonium dioxide.

DOE Information Bridge

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101
40 CFR 68.39 - Documentation.
2010-07-01

...AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Hazard Assessment § 68.39 ...shall maintain the following records on the offsite consequence analyses: (a) For worst-case scenarios, a...

Code of Federal Regulations, 2010

102
40 CFR 68.36 - Review and update.
2010-07-01

...AIR PROGRAMS (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Hazard Assessment...review and update the offsite consequence analyses at least once every five years...or operator shall complete a revised analysis within six months of the change and...

Code of Federal Regulations, 2010

103
Assessment of severe-accident mitigation strategies for a BWR (boiling water reactor) Mark-II Power Plant
1989-01-01

The in-depth reviews of risk assessments performed specifically for the Limerick and Shoreham plants have identified accident sequences that are important contributors to core damage frequency (CDF). These plants are boiling water reactors (BWRs) with Mark-II containment designs. Plant features and operator actions that have been found to be important for ...

Energy Citations Database

104
Internal dose assessment in radiation accidents.
2003-01-01

Although numerous models have been developed for occupational and medical internal dosimetry, they may not be applicable to an accident situation. Published dose coefficients relate effective dose to intake, but if acute deterministic effects are possible, effective dose is not a useful parameter. Consequently, dose rates to the organs of interest need to ...

PubMed

105
The Chernobyl Accident 20 Years On: An Assessment of the Health Consequences and the International Response
2006-09-30

BackgroundThe Chernobyl accident in 1986 caused widespread radioactive contamination and enormous concern. Twenty years later, the World Health Organization and the International Atomic Energy Authority issued a generally reassuring statement about the consequences. Accurate assessment of the consequences is ...

PubMed Central

106
Report on the accident at the Chernobyl Nuclear Power Station
1987-12-01

This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. Each organization has independently accepted responsibility for one or more chapters. The ...

Energy Citations Database

107
The assessment of nonroutine situations by pilots: a two-part process.
1987-11-01

A pilot encountering a nonroutine event must make a decision based on what may often result from a two-part process. The first is the diagnosis of the nature of the nonroutine event (Assessment A), followed by a determination of the potential consequences of that event (Assessment B). Analyses of aircraft accidents ...

PubMed

108
Radiological Assessment System for Consequence Analysis (RASCAL) Version 3.0.
1999-01-01

The Radiological Assessment System for Consequence AnaLysis, Version 3.0 (RASCAL 3.0) is the U.S. Nuclear Regulatory Commissions (NRC) main computational tool for use during radiological emergencies. RASCAL estimates doses from radiological accidents for ...

National Technical Information Service (NTIS)

109
Structural and containment response to LMFBR accidents
1978-01-01

The adequacy of the containment of fast reactors has been traditionally evaluated by analyzing the response of the containment to a spectrum of core disruptive accidents. The current approach in the U.S. is to consider fast reactor response to accidents in terms of four lines of assurance (LOAs). Thus, LOA-1 is to prevent accidents, ...

DOE Information Bridge

110
Structure, important features, and illustrative results of the new UFOMOD program system in assessing the radiological consequences of nuclear accidents
1991-05-01

This paper reports on the UFOMOD program system which is an advanced probabilistic accident consequence assessment (ACA) code. Its structure and modeling are based on the experience gained from applications of the old UFOMOD code during and after the German Risk Study Phase A, the results of scientific investigations performed within ...

Energy Citations Database

111
Source term and radiological consequences of the Chernobyl accident
1987-01-01

The objective of this work is to assess the source term and to evaluate the maximum hypothetical individual doses in European countries (including the Soviet Union) from the Chernobyl accident through the analyses of measurements of meteorological data, radiation fields, and airborne and deposited activity in these countries. Applying this information to ...

Energy Citations Database

112
Including uncertainty in hazard analysis through fuzzy measures
1997-12-01

This paper presents a method for capturing the uncertainty expressed by an Hazard Analysis (HA) expert team when estimating the frequencies and consequences of accident sequences and provides a sound mathematical framework for propagating this uncertainty to the risk estimates for these accident sequences. The uncertainty is readily ...

Energy Citations Database

113
Identification of the operating crew's information needs for accident management
1988-01-01

While it would be very difficult to predetermine all of the actions required to mitigate the consequences of every potential severe accident for a nuclear power plant, development of additional guidance and training could improve the likelihood that the operating crew would implement effective sever-accident management measures. The US ...

Energy Citations Database

114
Normal Accidents: Living with High�Risk Technologies
1999-01-01

This book examines what the author calls �normal� accidents � those that arise in high�risk technological systems from seemingly innocent mishaps � in order to illuminate the nature of the flaws in such systems� design and the need for improved risk assessment. The book begins with a chapter addressing the 1979 severe crisis at the Three Mile ...

NSDL National Science Digital Library

115
Radioecological consequences of a potential accident during transport of spent nuclear fuel along an Arctic coastline.
2008-12-24

This article presents results pertaining to a risk assessment of the potential consequences of a hypothetical accident occurring during the transportation by ship of spent nuclear fuel (SNF) along an Arctic coastline. The findings are based on modelling of potential releases of radionuclides, radionuclide transport and uptake in the ...

PubMed

116
Probabilistic risk assessment and nuclear waste transportation: A case study of the use of RADTRAN in the 1986 Environmental Assessment for Yucca Mountain
1990-12-01

The analysis of the risks of transporting irradiated nuclear fuel to a federal repository, Appendix A of the DOE Environmental Assessment for Yucca Mountain (DOE84), is based on the RADTRAN model and input parameters. The RADTRAN computer code calculates the radiation exposures and health effects under normal or incident-free transport, and over all credible ...

DOE Information Bridge

117
Accident analysis of railway transportation of low-level radioactive and hazardous chemical wastes: Application of the /open quotes/Maximum Credible Accident/close quotes/ concept
1988-09-01

The maximum credible accident (MCA) approach to accident analysis places an upper bound on the potential adverse effects of a proposed action by using conservative but simplifying assumptions. It is often used when data are lacking to support a more realistic scenario or when MCA calculations result in acceptable consequences. The MCA ...

Energy Citations Database

118
Predicting Consequences of Technological Disasters from Natural Hazard Events: Challenges and Opportunities Associated with Industrial Accident Data Sources
2009-04-01

The increased focus on the possibility of technological accidents caused by natural events (Natech) is foreseen to continue for years to come. In this case, experts in prevention, mitigation and preparation activities associated with natural events will increasingly need to borrow data and expertise traditionally associated with the technological fields to carry out the work. ...

NASA Astrophysics Data System (ADS)

119
Inventory of radioactive material in the event of an underground accident at the point of release, its pathway to Station A, and the consequence of off-site dose to the public. Waste Isolation Pilot Plant Safety Assessment Report.
1992-01-01

This report is a detailed review conducted by the Radiological Engineering Section at the Waste Isolation Pilot Plant (WIPP), and is based on the fire and spill accidents as detailed in the Waste Isolation Pilot Plant (WIPP) Final Safety Analysis Report (...

National Technical Information Service (NTIS)

120
Highway Safety Program Priorities Seminar. Proceedings Held at Fredericksburg, Virginia, July 18-20, 1969. Volume 5. Sped-Related Accident Countermeasures and Their Priorities.
1969-01-01

Contents: Speed consequences and countermeasures; Assessment and recommendations; Adverse effects of speed on system safety performance; Existing speed-related standards and regulations; Cost effectiveness of speed control devices; Selected accident count...

National Technical Information Service (NTIS)

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121
Human factors in high consequence manufacturing systems
1997-11-01

A high consequence system is often defined as one in which the potential exists for severe or catastrophic accidents. Familiar examples include nuclear power plants, airline and other mass transportation, dams and reservoirs, and large-scale food processing. Many manufacturing systems also qualify as high consequence systems. Much of ...

Energy Citations Database

122
Severe accident mitigation through containment design
1990-01-01

Recent US Department of Energy plans to construct a Heavy Water Reactor for the production of defense nuclear materials have created a unique opportunity to explore ways to mitigate severe accident concerns in the design stage. Drawing on an extensive background in USNRC-sponsored severe accident work, Sandia National Laboratories has been exploring a ...

Energy Citations Database

123
Radiological accidents potentially important to human health risk in the U.S. Department of Energy waste management program
1995-03-01

Human health risks as a consequence of potential radiological releases resulting from plausible accident scenarios constitute an important consideration in the US Department of Energy (DOE) national program to manage the treatment, storage, and disposal of wastes. As part of this program, the Office of Environmental Management (EM) is currently preparing a ...

DOE Information Bridge

124
Estimation Of Source Term For Indian PHWRS (KAPS) As Part Of PSA Level-2 Study
2006-07-01

Source Term (ST) is generally known as the amount of the radio-nuclides(fission products along with activation and Actinides) that can be released from a nuclear power plant in an accident. The ST can be more accurately defined as the quantity, timing, composition, chemical and physical form of radio-nuclides. The amount of radio-nuclides is a fundamental parameter to estimate ...

Energy Citations Database

125
APRIL.MOD3X - An interactive computer simulator of severe accidents in BWRs
1996-12-31

APRIL is a fast-running and user-friendly system code for interactive simulations of severe accidents in boiling water reactors (BWRs). The component models in the most recent version, APRIL.MOD3X, include the reactor core and pressure vessel, as well as the primary and secondary containments. Whereas APRIL.MOD3X is a fast-running code, the models are mechanistically based and ...

Energy Citations Database

126
MODIFIED RECORD OF DECISION NATIONAL AERONAUTICS ... - Science@NASA

Jan 11, 2011 ... trajectories and potential reentry accidents and environments. .... Environmental Consequences of Potential Accidents ...

NASA Website

127
A discussion on the methodology for calculating radiological and toxicological consequences for the spent nuclear fuel project at the Hanford Site
1999-07-14

This report contains technical information used to determine accident consequences for the Spent Nuclear Fuel Project safety documents. It does not determine accident consequences or describe specific accident scenarios, but instead provides generic information.

DOE Information Bridge

128
10 CFR 70.50 - Reporting requirements.
2011-01-01

...mitigate the consequences of an accident; (ii) The equipment...relied on to prevent potential accidents or mitigate their consequences...relied on to prevent potential accidents or mitigate their consequences...evaluated in the Integrated Safety Analysis. (d) The ...

Code of Federal Regulations, 2011

129
Value/impact analysis for evaluating alternative mitigation systems
1988-01-01

Methods are developed for assessing the cost effectiveness of proposed systems and strategies for mitigating the consequences of severe nuclear accidents. Such mitigation systems consist mostly of devices for improving the ability of a reactor containment to survive such an accident and retain all radioactive ...

Energy Citations Database

130
Material transport models for accident-induced flow in nuclear fuel cycle facilities
1985-11-01

Assessment of the environmental consequences of an accident in a fuel cycle facility ultimately involves calculating the atmospheric dispersion of radioactive materials and estimating the radiation dose to the surrounding population. Some uncertainty lies in the estimate of the nuclear facility source term to be used for atmospheric ...

Energy Citations Database

131
Qualitative methods for assessing risk
1995-04-01

The Department of Energy`s (DOE) non-nuclear facilities generally require only a qualitative accident analysis to assess facility risks in accordance with DOE Order 5481.1B, Safety Analysis and Review System. Achieving a meaningful qualitative assessment of risk necessarily requires the use of suitable non-numerical ...

Energy Citations Database

132
Severe accident management. Prevention and Mitigation.
1992-01-01

Effective planning for the management of severe accidents at nuclear power plants can produce both a reduction in the frequency of such accidents as well as the ability to mitigate their consequences if and when they should occur. This report provides an ...

National Technical Information Service (NTIS)

133
Scenario of the Accident of Chernobyl. Technical Aspects and Safety.
1986-01-01

After some indications on the Chernobylsk power plant and the characteristics of the RBMK series, the scenario of the accident is developed. The immediate consequences and the control of the accident are commented before concluding on more general lessons...

National Technical Information Service (NTIS)

134
Hypothetical core disruptive accident
1975-07-01

The hypothetical core disruptive accident in an LMFBR is discussed under the following main headings: reactor dynamics; mechanical consequences; and post- accident heat removal. 79 references. (DCC)

Energy Citations Database

135
Chernobyl Nuclear Accident and Its Consequences in Greece.
1986-01-01

In this report information about the nuclear accident at Chernobyl and the radioactivity burdening of Greece from the radioactive releases of the accident are presented. The main characteristics of the RBMK-1000 reactor and the flow pattern of the radioac...

National Technical Information Service (NTIS)

136
Chernobyl Accident and Denmark.
1986-01-01

The report describes the Chernobyl accident and its consequences for Denmark in particular. It was commissioned by the Secretary of State for the Environment. The event at the accident site, the release and dispersal of radioactive substances into the atm...

National Technical Information Service (NTIS)

137
Nuclear power and probabilistic safety assessment (PSA): past through future applications
1995-03-01

Nuclear power reactor safety in the United States is about to enter a new era -- an era of risk- based management and risk-based regulation. First, there was the age of `prescribed safety assessment,' during which a series of design-basis accidents in eight categories of severity, or classes, were postulated and analyzed. Toward the end of that era, it was ...

NASA Astrophysics Data System (ADS)

138
Considerations in the assessment of the consequences of effluents from mixed oxide fuel fabrication plants
1975-06-01

The purpose of this study was to provide information and identify parameters relevant to assessing the consequences to man and his environment of large scale mixed plutonium-uranium oxide fuel fabrication plants which will be needed in the next 10 to 15 years. The report identifies the pertinent parameters, values, factors and methods which ...

Energy Citations Database

139
Consequences in Sweden of the Chernobyl Accident.
1986-01-01

It summarizes the consequences in Sweden of the Chernobyl accident, describes the emergency response, the basis for decisions and countermeasures, the measurement strategies, the activity levels and doses and countermeasures and action levels used. Past a...

National Technical Information Service (NTIS)

140
The Three Mile Island Nuclear Accident: Lessons and Implications
1981-01-01

A compilation of reports from an April 1980 conference on the Three Mile Island (TMI) accident (1979), this book assesses the incident and its immediate consequences as well as �one�year later� accounts by many of the major participants in the event. Research presented ranges from scientific findings regarding health impacts to ...

NSDL National Science Digital Library

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141
Application of RELAP/SCDAPSIM and COCOSYS Codes for Severe Accident Analysis in RBMK-1500 Reactor
2006-07-01

Regardless low probability of occurrence the severe accident phenomena are investigated for all types of nuclear reactors in the world because the consequences of such accident could be catastrophic. Most of research is performed for the prevailing vessel-type light water reactors like PWRs and BWRs. Less research is performed for the ...

Energy Citations Database

142
Projected Consequence for Potential Sabotage Events Related to Spent Fuel Shipments
1999-08-18

There is a growing interest in understanding the potential consequences of malevolent acts against shipments of nuclear waste and/or material. Recently, Sandia National Laboratories (SNL) conducted a study' to evaluate the potential source terms available for release in a sabotage event for spent fuel shipments. Using these source terms, we developed an approach to ...

Energy Citations Database

143
An extended critical review of twenty years of countermeasures used in agriculture after the Chernobyl accident.
2007-06-15

A wide range of different countermeasures has been used to mitigate the consequences of the Chernobyl accident for agriculture in affected regions in Belarus, Russia and Ukraine. The paper comprehensively brings together key data on countermeasure application over twenty years for all three countries and critically evaluates the response to the ...

PubMed

144
Aircraft Accident Survivability: Rotary Wing Aircraft
2005-10-01

... Descriptors : *MILITARY AIRCRAFT, *SURVIVABILITY, *HELICOPTERS, *AVIATION ACCIDENTS, DAMAGE ASSESSMENT, TOLERANCE ...

DTIC Science & Technology

145
Assessment of an explosive LPG release accident: a case study.
2007-11-29

In the present paper, an accident occurred during a liquefied petroleum gas (LPG) tank filling activity has been taken into consideration. During the transfer of LPG from the source road tank car to the receiving fixed storage vessel, an accidental release of LPG gave rise to different final consequences ranging from a pool fire, to a fireball and to the ...

PubMed

146
Analysing an accident related to orphan sources including dose assessment.
2006-10-03

This paper discusses an accident, which occurred in one of the radiation application centres in Iran, follow-up investigations as well as lessons learnt. In January 2004 the Regulatory Authority was informed through a university radiation protection officer of an accident regarding orphan sources. Investigations revealed that one Am-Be and three (137)Cs ...

PubMed

147
Investigating and reporting accidents effectively
1989-01-01

This booklet is written to help the untrained accident investigator perform a type C'' accident investigation. It is designed to identify the philosophy of accident investigation, the steps involved, the potential problems in the investigation, and give instruction for completing the DOE 5484 X form. A hypothetical ...

Energy Citations Database

148
Investigating and reporting accidents effectively
1989-12-31

This booklet is written to help the untrained accident investigator perform a type ``C`` accident investigation. It is designed to identify the philosophy of accident investigation, the steps involved, the potential problems in the investigation, and give instruction for completing the DOE 5484 X form. A hypothetical ...

Energy Citations Database

149
A comparative analysis of accident risks in fossil, hydro, and nuclear energy chains
2008-07-01

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 ...

Energy Citations Database

150
Richland five-year O2 R and D Program: Nuclear safety program
1966-06-01

The Nuclear Safety Mission consists of a broad, integrated program of experimental and analytical studies designed to permit more accurate assessment of the consequences of accidents at Hanford nuclear facilities. Information obtained will assist in the design of facilities to further mitigate the consequences of ...

Energy Citations Database

151
Cellular automata-based forecasting of the impact of accidental fire and toxic dispersion in process industries.
2006-04-19

The strategies to prevent accidents from occurring in a process industry, or to minimize the harm if an accident does take place, always revolve around forecasting the likely accidents and their impacts. Based on the likely frequency and severity of the accidents, resources are committed towards preventing the ...

PubMed

152
Accident rates and types among self-employed private forest owners.
2010-06-01

Half of all Swedish forests are owned by private individuals, and at least 215,000 people work in these privately owned forest holdings. However, only lethal accidents are systematically monitored among self-employed forest workers. Therefore, data from the registries of the Swedish Work Environment Authority, the Labor Insurance Organization and the regional University ...

PubMed

153
Guidelines for the management of accidents involving microorganisms: a WHO memorandum.
1980-01-01

The response to an emergency resulting from an accident involving microorganisms, whether in a laboratory or during needs to be graded according to the degree of hazard to human or animal health created by the circumstances of the accident and the properties of the organisms concerned. A categorization of microorganisms by risk groups is proposed for the ...

PubMed

154
Proposal for computer investigation of LMFBR core meltdown accidents
1974-01-01

The environmental consequences of an LMFBR accident involving breach of containment are so severe that such accidents must not be allowed to happen. Present methods for analyzing hypothetical core disruptive accidents like a loss of flow with failure to scram cannot show conclusively that such ...

DOE Information Bridge

155
Guidelines for the management of accidents involving microorganisms: a WHO Memorandum*
1980-01-01

The response to an emergency resulting from an accident involving microorganisms, whether in a laboratory or during needs to be graded according to the degree of hazard to human or animal health created by the circumstances of the accident and the properties of the organisms concerned. A categorization of microorganisms by risk groups is proposed for the ...

PubMed Central

156
Safety assessment document for the dynamic test complex (Building 836)
1981-11-24

A safety assessment was performed to determine if potential accidents at the 836 Complex at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The credible accidents that might have an effect on these facilities or have off-site ...

DOE Information Bridge

157
Development of hydrogeological modelling approaches for assessment of consequences of hazardous accidents at nuclear power plants
1994-07-01

This paper introduces some modeling approaches for predicting the influence of hazardous accidents at nuclear reactors on groundwater quality. Possible pathways for radioactive releases from nuclear power plants were considered to conceptualize boundary conditions for solving the subsurface radionuclides transport problems. Some approaches to incorporate physical-and-chemical ...

Energy Citations Database

158
Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for deposited material and external doses. Volume 2: Appendices
1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the ...

Energy Citations Database

159
Probabilistic accident consequence uncertainty analysis -- Early health effects uncertainty assessment. Volume 2: Appendices
1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the ...

Energy Citations Database

160
Technical assessment: An independent safety assessment of Department of Energy nuclear reactor facilities
1981-02-01

Inherent in the design of DOE reactors under review are many features which provide significant protection against the likelihood of TMI-type accidents. In addition, other features in the design or operating characteristics would tend to limit or reduce the consequences of the accident. Some of these features were discussed earlier in ...

Energy Citations Database

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161
Overview of core disruptive accidents
1977-01-01

An overview of the analysis of core-disruptive accidents is given. These analyses are for the purpose of understanding and predicting fast reactor behavior in severe low probability accident conditions, to establish the consequences of such conditions and to provide a basis for evaluating consequence limiting ...

DOE Information Bridge

162
The safety of LNG systems
1978-01-01

An evaluation of the hazards, controls, and safety issues involved in the arrival and docking of LNG carriers and the transfer, storage, and vaporization operations ashore, analysis of alternative methodologies for risk quantification, and results of several recent risk assessment studies suggest that the probability of a large-scale accident involving the ...

Energy Citations Database

163
Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I
1990-09-19

This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems ...

Energy Citations Database

164
Application of spreadsheets to standardize transportation radiological risk assessments
1995-12-31

Because of the complexity, volume of data and calculations required, one preferred analytical tool to perform transportation risk assessments is the RADTRAN computer code. RADTRAN combines user-determined material, packaging, transportation, demographic and meteorological factors, with health physics data to calculate expected radiological consequences and ...

Energy Citations Database

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