Appendix A contains information and details about the accident progression analysis. Appendix A.1 contains a detailed description and listing of the Accident Progression Event Tree (APET) and the binner that groups the outcomes of evaluating the APET. App...

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 describes the ...

A case study modeling the thrust reverser system (TRS) in the context of the fatal accident of a Boeing 767 is presented to illustrate the application of Probabilistic Safety Assessment methods. A simplified risk model consisting of an event tree with supporting fault trees was developed to represent the progression of the ...

Operator Action Event Trees for transient and LOCA initiated accident sequences at the Zion 1 PWR have been developed and documented. These trees logically and systematically portray the role of the operator throughout the progression of the accident. The...

The recent interest in severe accidents in nuclear power plants has changed the focus from design basis events to the consequences of events beyond the design basis. In the General Electric BWRs, introduction of neutron absorbers into the reactor terminates the progression of ATWS events to ...

The primary purpose of this report is to document AIPA studies performed on the HTGR since issuance of the eight volumes. Implementation of the R and D recommendations is discussed, which includes consideration of new initiating events and accident sequen...

In the unlikely event of a core meltdown accident, an important safety issue is the potential for steam explosions and their effects on the accident progression. Steam explosion phenomena can be divided into three stages: (a) mixing of the molten fuel and...

In a recently published paper (Campbell and Ott, 1979), a general methodology was proposed for the statistical evaluation of design-error related accidents. The evaluation aims at an estimate of the combined residual frequency of yet unknown types of accidents lurking in a certain technological system. Here, the original methodology is extended, as to ...

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)

Software & Copyright Submittal The tool used to analyze the progression of accidents in the DWPF is called an Accident Progression Event Tree (APET). The APET methodology groups analyzed progressions into a series of bins, based on similarities in their characteristics. ...

Operator Action Event Trees for transient and LOCA initiated accident sequences at the Zion 1 PWR have been developed and documented. These trees logically and systematically portray the role of the operator throughout the progression of the accident. The documentation includes a delineation of the required ...

This paper presents a comparison of calculations of severe accident progression for several postulated accident sequences for representative Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) nuclear power plants performed with the MELCOR 1.8.3 and the MAAP4 computer codes. The PWR system examined in this study is a 1100 ...

In present, the development and analysis of Accident Progression Event Trees (APETs) are performed in a manner that is computationally time consuming, difficult to reproduce and also can be phenomenologically inconsistent. One of the principal deficiencies lies in the static nature of conventional APETs. In the conventional ...

In order to establish a method of probabilistic safety analysis for passive safety features, the event-tree (E/T) of ULOF accident sequences in the early stage of accident progression was constructed for an 600 MWe LMFBR model plant equipped with passive ...

Event trees have been constructed for all phases of LMFBR accidents. The trees proved useful for identifying meaningful initiating accident categories and containment responses. In these areas, quantification appears feasible, given an adequate data base. Event trees were also used to represent in-core ...

This study describes the predicted response of Unit One at the Browns Ferry Nuclear Plant to a postulated complete failure to scram following a transient occurrence that has caused closure of all Main Steam Isolation Valves (MSIVs). This hypothetical event constitutes the most severe example of the type of accident classified as Anticipated Transient ...

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...

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 ...

Boiling water reactors (BWRs) incorporate many unique structural features that make their expected response under severe accident conditions very different from that predicted in the case of pressurized water reactor accident sequences. The effect of the BWR procedural and structural differences upon the progression of a severe ...

This paper describes a safety analysis of a transfer process for high-level radioactive and toxic waste. The analysis began with a hazard assessment that used elements of What If, Checklist, Failure Modes and Effects Analysis, and Hazards and Operability Study (HAZOP) techniques to identify and rough-in accident sequences. Based on this preliminary analysis, the most ...

Accidents and unscheduled events associated with non-nuclear energy resources and technology are identified for each step in the energy cycle. Both natural and anthropogenic causes of accidents or unscheduled events are considered. Data concerning these accidents are summarized. ...

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. Consequence assessments are presented ...

The nuclear industry is now initiating a serious effort to define the elements of an accident management program at each utility with an operating reactor, which is a significant change in conditions from those in 1985, when the work of Di Salvo et al. was published. Each utility is now conducting an individual plant examination (IPE) to uncover plant vulnerabilities to severe ...

This report documents the initial planning, specification of objectives, uses of results, and plan of attack to be used in the Severe Accident Sequence Analysis Program at the Oak Ridge National Laboratory. A key aspect is the determination of timing of events and a method of displaying and tracking concurrent events. A ...

This LDRD project has produced a tool that makes probabilistic risk assessments (PRAs) of nuclear reactors - analyses which are very resource intensive - more efficient. PRAs of nuclear reactors are being increasingly relied on by the United States Nuclear Regulatory Commission (U.S.N.R.C.) for licensing decisions for current and advanced reactors. Yet, PRAs are produced much as they were 20 years ...

Changes in perspectives on fast reactor safety have occurred over the past ten years due both to technical progress and to the course of events. The major aspect of these changes is that they relate to basic design decisions that are largely, but not exclusively, related to safety considerations. Among the topics discussed are inherent safety, choice of ...

An analysis of containment environments during a postulated severe accident was performed for a pressurized water reactor (PWR) type nuclear power plant (NPP) of which electric power is 1400 MWe. Examined were four initiating events such as large break loss-of-coolant accident (LBLOCA), small break loss-of-coolant ...

Safe operation of SRS facilities continues to be the highest priority of the Savannah River Site (SRS). One of these facilities, the Defense Waste Processing Facility or DWPF, is currently undergoing cold chemical runs to verify the design and construction preparatory to hot startup in 1995. The DWPFF is a facility designed to convert the waste currently stored in tanks at the 200-Area tank farm ...

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...

This paper presents the results and insights gained from MELCOR analyses of two severe accident scenarios, a Loss of Coolant Accident (LOCA) and a Station Blackout (TMLB) in Oconee, a Babcock Wilcox (B W) designed PWR with a large dry containment, and comparisons with Source Term Code Package (STCP) calculations of the same sequences. Results include ...

This paper presents the results and insights gained from MELCOR analyses of two severe accident scenarios, a Loss of Coolant Accident (LOCA) and a Station Blackout (TMLB) in Oconee, a Babcock & Wilcox (B&W) designed PWR with a large dry containment, and comparisons with Source Term Code Package (STCP) calculations of the same sequences. Results ...

In the event of a core meltdown accident, one of the accident progression paths is fuel relocation to the lower reactor plenum. In the Heavy Water New Production Reactor (NPR-HWR) design, the reactor cavity is flooded with water. In such a design, decay heat removal to the water in the reactor cavity and thence to ...

In the event of a core meltdown accident, one of the accident progression paths is fuel relocation to the lower reactor plenum. In the Heavy Water New Production Reactor (NPR-HWR) design, the reactor cavity is flooded with water. In such a design, decay heat removal to the water in the reactor cavity and thence to ...

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...

A strategy has been developed for systematically addressing and handling the hazards posed by a transportation accident involving hazardous materials. The Accident Management Orientation Guide presents this system as a logic sequence of events in a color-...

Information is presented concerning accident definition and use of event trees, event tree methodology, potential accidents covered by the reactor safety study, analysis of potential accidents involving the reactor core, and analysis of potential accidents not involving the ...

It has become increasingly clear in recent years that the risk associated with nuclear power is driven by human performance. Although human errors have contributed heavily to the two core-melt events that have occurred at power reactors, effective performance during an event can also prevent a degraded situation from progressing to a ...

The reactor system is expected to achieve permanent subcriticality in a loss-of-flow (LOF) event by virtue of fuel removal from the core even under the hypothetical assumption that both shutdown systems fail to function. Based on the analysis performed by S.K. Rhow, et al., adequate fuel removal would occur in the CRBRP heterogeneous core during a meltout period after the ...

A new methodology is developed for modeling a system's evolution to support decisionmaking on alternative actions which affect the system's evolution. The methodology is based upon the goal tree success tree method for hierarchal decomposition of the system's objective. The goal tree success tree structure is used to identify the system's objective and supporting functions and the ...

In this paper the SCDAP/RELAPS severe accident analysis computer code, developed at the Idaho National Engineering Laboratory, is used to analyze the fourth in a series of debris formation experiments. The debris formation-four (DF-4) experiment deals with heatup and meltdown of a boiling water reactor (BWR)-representative fuel and control blade assembly segment, performed in ...

The source range monitor (SRM) data recorded during the first 4 h of the Three Mile Island Unit 2 (TMI-2) accident following reactor shutdown were analyzed. An effort to simulate the actual SRM response was made by performing a series of neutron transport calculations. Primary emphasis was placed on simulating the changes in SRM response to various system ...

The source range monitor (SRM) data recorded during the first 4 hours of the Three Mile Island Unit No. 2 (TMI-2) accident following reactor shutdown were analyzed. An effort to simulate the actual SRM response was made by performing a series of neutron transport calculations. Primary emphasis was placed on simulating the changes in SRM response to various system ...

This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phe...

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Home News & Events Press Releases Events Speeches & Testimony Across the Board Transportation Safety Most Wanted List Safety Alerts Safety Recommendations Safety Studies Accident...

Home News & Events Press Releases Events Speeches & Testimony Across the Board Transportation Safety Most Wanted List Safety Alerts Safety Recommendations Safety Studies Accident...

Studies and operating experience suggest that the risk of severe accidents during low power operation and/or shutdown (LP/S) conditions could be a significant fraction of the risk at full power operation. Two studies have begun at the Nuclear Regulatory Commission (NRC) to evaluate the severe accident progression from a risk ...

This report serves as the user`s manual for the FORTRAN code BINIAC. BINIAC is a utility code designed to format the output from the Defense Waste Processing Facility (DWPF) Accident Progression Event Tree (APET) methodology. BINIAC inputs the accident progression bins from the APET ...

The ARRAMIS risk and reliability analysis software suite developed by Sandia National Laboratories enables analysts to evaluate the safety and reliability of a wide range of complex systems whose failure results in high consequences. This software was originally designed to model the systems, responses, and phenomena associated with potential severe accidents at commercial ...

During 2008, the U.S. domestic airline departures exceeded 28,000 flights per day. Thirty-nine or less than 0.2 of 1% of these flights resulted in operational incidents or accidents. However, even a low percentage of airline accidents and incidents continue to cause human suffering and property loss. The charge of this study was the comparison of U.S. ...

Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. ...

The response of structures to energetic events postulated to arise in a probabilistic risk assessment (PRA) of a Savannah River Site (SRS) production reactor is addressed. Energetic events that arise in PRAs can damage structures and therefore have a significant influence on subsequent accident progression. ...

The response of structures to energetic events postulated to arise in a probabilistic risk assessment (PRA) of a Savannah River Site (SRS) production reactor is addressed. Energetic events that arise in PRAs can damage structures and therefore have a significant influence on subsequent accident progression. ...

In this paper we present information that can be used in severe accident management by providing an improved understanding of the effects of water addition to a degraded core. This improved understanding is developed using a diagram showing a sequence of core damage states. Whenever possible, a temperature and a time after accident initiation are estimated ...

In this paper we present information that can be used in severe accident management by providing an improved understanding of the effects of water addition to a degraded core. This improved understanding is developed using a diagram showing a sequence of core damage states. Whenever possible, a temperature and a time after accident initiation are estimated ...

The objectives of the research program are to develop a computer program for calculating two-dimensional, transient, natural-convection phenomena, such as those arising from various postulated sodium spill accidents in LMFBR heat transfer vaults, head compartments, containment buildings, and secondary heat transfer systems; to develop experimental programs and conduct tests ...

An evaluation of core meltdown accidents in the Z/IP facilities has been performed. Containment event trees have been developed to relate the progression of a given accident to various potential containment building failure modes. An extensive uncertainty analysis related to core melt phenomenology has been ...

This report describes the results of safety-evaluation accidents selection by the probabilistic safety analysis method. The accident sequences following on nine initial events were analyzed by means of the event tree method. The occurrence probability (P)...

As part of the Severe Accident Risk Reduction Program, researchers at Sandia National Laboratories have constructed a group of containment event trees to be used in the analysis of key accident sequences for light water reactors (LWR) during postulated se...

...sequence of events leading to the accident or incident, to the extent...the consequences of a launch accident, launch incident, reentry accident, reentry incident, or other...adopt preventive measures for avoiding recurrence of the event....

...the event as either a launch accident or launch incident, and must...the consequences of a launch accident, launch incident or other...investigating the cause of a launch accident, launch incident or other...adopt preventive measures for avoiding recurrence of the event....

The inputs to the accident sequence evaluation include the system fault tree models and the event tree models. Each event tree sequence defines a unique accident sequence. The qualitative analysis of an accident sequence is concerned with determining the minimal cut sets of the ...

Analysis is made of many postulated accidents within the NS Savannah power plant. The accidents include reactivity accidents, mechanical accidents, and miscellaneous accidents. It is concluded that there is no appreciable hazard to the public or the crew even in the ...

This document supports the Tank Farms Documented Safety Analysis and presents the technical basis for the frequencies of externally initiated accidents. The consequences of externally initiated events are discussed in other documents that correspond to the accident that was caused by the external event. The ...

... event, such as a car accident or a fall. Return to top When should I call my doctor? Talk to ...

In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe accidents at commercial nuclear power plants in the US reported in NUREG-1150, the Severe Accident Risk Reduction Program (SARRP) has completed a revised calculation of the risk to the general public from severe accidents at ...

Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability of occurrence are typically handled without consequence through reliable engineering systems and good design practices. For accidents of lower probability, the initiating events are characterized by larger and more numerous challenges to ...

The purpose of this summary report is to present results from the safety analysis work that was performed in support of the ``Seismic Safety Issue Resolution Program Plan`` for the In-Tank Processing (ITP) Facility. Results from this effort include estimates of the consequences that postulated earthquakes might introduce. For beyond evaluation based earthquake (EBE) events, ...

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 accidents; they are process related ...

An assessment of accident energetics in LMFBR core-disruptive accidents is given with emphasis on the generic issues of energetic recriticality and energetic fuel-coolant interaction events. Application of a few general behavior principles to the oxide-fueled system suggests that such events are highly unlikely ...

Maurice Ravel (1875-1937), the great impressionist-classicist composer of many popular compositions, such as the Bol�ro, suffered from a progressive disease and died following an exploratory craniotomy by Clovis Vincent. The history of his progressive dementia and the contribution of a car accident, following which he was unable to ...

Probabilistic risk assessment methodology is applied to generate an evaluation of the relative likelihood of safe recovery following selected pressurized water reactor (PWR) design basis accidents for a Russian V213 nuclear power reactor. US-designed PWRs similar to the V213 are used for reference and comparison. This V213 risk assessment is based on comparison analyses of the ...

To Observe And Respond To Red Signal Caused 2008 Chatsworth Accident; Recorders In Cabs Recommended January 14, 2010 - NTSB To Meet On Final Report On 2008 Metrolink Accident...

... Prevent accidents; Ensure, demonstrate & verify compliance; Define procedures in case of accidents or unforeseen events. Module 6: FMPs. ...

Mar 30, 2011 ... Sequence of Major Events of the Challenger Accident. Image library of the STS- 51L Challenger mission at Johnson Space Center. ...

This report summarizes the accidents and unscheduled events which may occur during the extraction, production, transportation, and utilization of non-nuclear energy technologies....

An important goal of the US DOE Sodium Fast Reactor (SFR) program is to develop the technology necessary to increase safety margins in future fast reactor systems. Although no decision has been made yet about who will build the next demonstration fast reactor, it seems likely that the construction team will include a combination of international companies, and the safety design philosophy for the ...

The dilemma in adventure education is to eliminate unreasonable risks to participants without reducing the levels of excitement, challenge, and stress that are inherent in adventure programming. Most accidents in outdoor pursuits are caused by a combination of unsafe conditions; unsafe acts (usually on the part of the student); and error judgments (usually on the part of the ...

Investigation of transportation accidents usually involves some measurement of physical evidence at the scene. Accurate accident scene data facilitates reconstruction of the accident events and possible determination of the cause. The Calspan Scene Measurement System combines computer technology with civil ...

In-vessel core melt progression describes the progression of the state of a reactor core from core uncovery up to reactor vessel melt through in uncovered accidents or through temperature stabilization in accidents recovered by core reflooding. Melt progr...

The objective of the work reported in this paper was to simulate and analyze the in-vessel phenomena of core meltdown and melt progression during hypothetical station blackout accidents in Swedish boiling water reactors (BWRs). The analysis has been performed using the APRIL.MOD3X severe-accident code, with the initial ...

Dec 14, 2005 ... Like many high profile accidents, this collision was the consequence of a ... accidents, Collision, fatigue, Mir, piloting errors, Progress, ...

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

A risk-based logic model is suggested as an appropriate basis for better predicting accident progression and ensuing source terms to the environment from process upset conditions in complex chemical process facilities. Under emergency conditions, decision-makers may use the Accident Progression ...

A computer algorithm has been developed and implemented to search the Sequence Coding and Search System Licensee Event (LER) database for failures or conditions common to Accident Sequence Precursor (ASP) events. Use of the algorithm has greatly improved the efficiency and timeliness in identifying potential ASP ...

Technical Basis Document for the Nuclear Criticality Representative Accident and Associate Represented Hazardous Conditions. Revision 2 of RPP-12371 provides accident consequence estimates for a hypothetical criticality event in an above grade facility (e...

Event trees have been constructed for all phases of LMFBR accidents. The trees proved useful for identifying meaningful initiating accident categories and containment responses. In these areas, quantification appears feasible, given an adequate data base....

report into the accident was issued in 2004. It provides a relatively thorough analysis of the causes of adequate risk mitigation in the events leading to the �berlingen accident. At Linate, the multi concerns between the �berlingen and Linate accidents. Staffing issues not only affected the response

The Department of Energy has developed new capabilities to predict how an accident event would spread through a facility. These capabilities arose as a part of the development of a future generation accident code - CONACS. They can be used to predict the ...

The events surrounding the accident at the nuclear power station at Chernobyl in the USSR are examined. A description is given of the Chernobyl nuclear reactor and the Soviet Union's nuclear power program. A scenario of the cause of the accident is presen...

Dose calculation procedures to be used in the event of a truck transportation accident involving radioactive waste being shipped from a TVA facility. Two types of accidents are considered: one involving fire, and one involving a spill of packaged waste an...

Accident models play a critical role in accident investigation and analysis. Most traditional models are based on an underlying chain of events. These models, however, have serious limitations when used for complex, socio-technical systems. Previously, Le...

This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Available information on 61 reported nuclear ship events is considered. The ships are in almost all cases...

The assumptions, methods of analysis and results of the analysis of single tube accidents which have significant offsite radiological consequences are described. Those accidents described include: pressure tube flow blockage; fuel ejection; and pressure t...

This report summarizes the accidents and unscheduled events which may occur during the extraction, production, transportation, and utilization of non-nuclear energy technologies.

...there is a launch or reentry accident or incident during a permitted...event as a launch or reentry accident or incident, and must include...leading to the launch or reentry accident, or launch or reentry incident...adopt preventive measures for avoiding a recurrence of the...

Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. ...

In the unlikely event of a core meltdown accident, an important safety issue is the potential for steam explosions and their effects on the accident progression. Steam explosion phenomena can be divided into three stages: (a) mixing of the molten fuel and water; (b) triggering and spatial propagation of rapid fuel ...

Many DOE facilities potentially subject to compliance with offsite consequence criteria under the 40 CFR 68 Risk Management Program house significant inventories of toxic and flammable chemicals. The accident progression event tree methodology is suggested as a useful technical basis to define Worst-Case and Alternative Release ...

Probabilistic risk assessment techniques have been applied to obtain guidance in choosing nuclear safety research and development that is most worthwhile for high-temperature gas-cooled reactor (HTGR) nuclear power plants. The probabilistic techniques used are similar to those employed in the Reactor Safety Study for light water reactors (LWRs), WASH-1400, directed by Dr. N. C. Rasmussen. The ...

This paper explores severe accident phenomena relevant to large Canada deuterium uranium (CANDU) reactors. A loss of all engineered heat sinks because of a loss of all electrical power is used to illustrate these phenomena. The multi-unit [4 x 350 MW(electric)] Darling Nuclear Generation Station (DNGS) in Ontario, Canada, is analyzed assuming that the power is lost to one of ...

This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comments on the adequacy of the present USNRC design requirements. Results from early SPERT tests are reviewed and compared with results from recent computer simulations and PBF tests. A progression of fuel rod and cladding damage events is ...

This website provides a brief report on the nuclear accident at Three Mile Island in Pennsylvania in 1979. It summarizes the events leading to the accident, the resulting health effects, and the accident�s impact on the regulation of nuclear power reactors in the United States. It also provides a chronology of ...

This note provides new information regarding the market reaction toward electric utility stocks that resulted both from the accident at Three Mile Island, and the events predating and postdating the accident. The results suggest that some of the market reaction heretofore ascribed to the accident resulted instead ...

Blunt injury to the cardiac valves leads to progressive acute ventricular failure, which often requires urgent surgical management. In this case report, we describe an acute aortic valve rupture caused by air-bag inflation during an automobile accident. Laceration of an aortic valve cusp was treated successfully with urgent aortic valve replacement. A ...

Unlike computer simulation of an event, forensic engineering is the evaluation of recorded data and damaged as well as surviving components after an event to determine progressive causes of the event. Such an evaluation of the 1979 Three Mile Island Unit 2 accident indicates that gas began ...

Severe accident natural circulation flows have been investigated at the Idaho National Engineering Laboratory to better understand these flows and their potential impacts on the progression of a pressurized water reactor severe accident. Parameters affect...

In recent years, we have made steady progress in reducing ordnance accidents. However, these accidents are still a serious drain on Army combat readiness. The record shows that improving safety in ordnance operations pays off not only in reduced fatalitie...

After code damage during a severe accident in a nuclear reactor, the degraded core has to be cooled down and the decay heat should be removed in order to cease the accident progression and maintain a stable state. The cooling of core melt is divided into ...

The liberation of radioactive materials into various containment locations during a severe accident creates a radiation field that may have a significant impact on the accident progression. High radiation may not only impair the functioning of important e...

Contents: Methodology for ranking roadside hazard correction programs; Evaluation of highway safety projects using quality-control technique; Michigan dimensional accident surveillance (MIDAS) model--progress report; Accident characteristics before, durin...

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Risk ranking schemes have been used in safety analysis to distinguish lower risk accidents from higher risk accidents. This is necessary to identify those events that might warrant additional study or quantitative analysis and to ensure that any resources...

An international symposium on Radiodosimetry and Preventive Measures in the Event of a Nuclear Accident was held in Cracow, Poland, from 26 to 28 May 1994. The symposium was organized by the Polish Society for Nuclear Medicine, and co-sponsored by the IAE...

The sequence of events and the consequences of the nuclear reactor accident at Chernobyl, USSR in April 1986 are reviewed. The background material in nuclear reactor and nuclear explosion physics required for understanding these events is extensively explained, and the differences between U.S. and Chernobyl-type reactors are pointed ...

Following a brief review of ways in which a population can be exposed and the nature of countermeasures which can be applied in the event of an accident in a nuclear power station, the fundamental principles are described which must guide the action taken...

Information is presented concerning the public information chronology; Met Ed public relations; flow of public information during the accident at Three Mile Island; flow of public information on five key events during the accident at Three Mile Island; the journalist's perspective; content analysis of mass media coverage of ...

Information is presented concerning the public information chronology; MET ED public relations; flow of public information during the accident at Three Mile Island; flow of public information on five key events during the accident at Three Mile Island; the journalist's perspective; content analysis of mass media coverage of ...

Elements of risk in reactor accidents are discussed. Estimates of the public risk from nuclear-power-plant accidents hinge on three important factors: (1) the probability of specific events occurring that could lead to an accident involving radiation release; (2) the quantity, type, and timing of release of ...

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 design features. The methods are used to ...