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)
A dynamic food-chain model and program, DYFOM-95, for predicting the radiological consequences of nuclear accident has been developed. Processes caused by accident release and which will make an impact on radionuclide concentration in the edible parts of ...
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 ...
... Models for Nuclear Power Plant Accident Consequence ... and quantify the potential health effects of accidental ... from nuclear power plants have been ...
DTIC Science & Technology
Preliminary designs are described for models of the interaction of Zircaloy and hydrogen and the consequences of this interaction on the behavior of fuel rod cladding during severe accidents. The modeling of this interaction and its consequences involves ...
A general temperate latitude cyclonic rainstorm model is presented which describes the effects of washout and runoff on consequences of atmospheric releases of radioactive material from potential nuclear reactor accidents. The model treats the temporal an...
A preliminary model describing the effects of washout and runoff on the consequences of a nuclear reactor accident is presented. The most important new feature of this stratified model relative to the model in WASH-1400 is the spatial structure of rainsto...
A personal computer-based model, SMART, has been developed that uses an integral approach for calculating early offsite consequences from nuclear reactor accidents. The solution procedure uses simplified meteorology and involves direct analytic integratio...
A first version of models has been developed for predicting the number of occurrences of health effects induced by radiation exposure in nuclear reactor accidents. The models are based on the health effects models developed originally by Harvard Universit...
The FORTRAN-IV computer code UFOMOD calculates the radiological consequences of reactor accidents for risk studies, namely early deaths, latent cancer deaths and genetic significant doses. Different models for the atmospheric transport and deposition, the...
The objective of this report is to establish the radiological consequence analysis methodology for the postulated accidents which result in the radioactivity release to the ambient air. For this, reviewing were the methodology described in the Final Safet...
A number of important developments have occurred recently in the area of nucler reactor accident offsite consequence analysis, including improvements in modeling capabilities, model evaluation studies, and application of existing models to provide guidance for planning and decision making. A ...
Energy Citations Database
Uncertainties in health and economic consequence models stem principally from two types of uncertainties: limitations in the models and limitations in the data used in these models. This paper presents an overview of uncertainty and sensitivity analysis for reactor accident ...
This paper is concerned with the application of severe-accident codes to develop improved accident mitigation strategies for nuclear power plants employing boiling water reactors (BWRs). Specifically, the results of analyses using the APRIL.MOD3X code are presented for typical station blackout accidents. Issues discussed include the ...
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 ...
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 ...
The Federal Highway Administration is developing an Interactive Highway Safety Design Model (IHSDM) to assist highway geometric design engineers in considering the safety consequences of their design decisions. One element of the IHSDM will be an accident...
Models were developed for analyses of economic risks from unanticipated events which occur, or could occur, during US LWR plant operation. The models estimate the economic consequences of LWR forced outages and accidents and can be used together with esti...
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...
An atmospheric dispersion and consequence model called RADIS has been developed by the University of Hong Kong for nuclear accident consequence analysis. The model uses a two-dimensional plume trajectory derived from wind data for Hong Kong. Dose, health effects, and demographic ...
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 ...
DOE Information Bridge
This paper develops a concrete situation witch is the search for an evacuation distance in case of a road accident implying a chlorine tank. The methodological aspect is how implementing uncertainty analysis in deterministic models with random parameters....
Despite extensive safety analysis and application of safety measures, there is a frequent lament, 'Why do we continue to have accidents'. Two breakdowns are prevalent in risk management and prevention. First, accidents result from human actions that engin...
in this area and believes further improvements can be made by integrating the findings of the safety analyses was done to model releases of HF more realistically for the accident analysis section. Work continues that there are many postulated accident scenarios whose unmitigated consequences are considered Scenario ...
E-print Network
This report describes studies of accidents involving high-level radioactive waste before sealing the waste into a repository. The report summarizes work done in this area during Fiscal Year 1978 and supplements previous work. Models of accident probability, severity, and consequences are refined and extended.
The rate of release of radioactive materials from a containment during a severe accident has a significant impact on the consequences of the accident. One hypothesis for a containment leakage model states that the containment will develop a controlled, re...
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 ...
A preliminary model describing the effects of washout and runoff on the consequences of a nuclear reactor accident is presented. The most important new feature of this stratified model relative to the model in WASH-1400 is the spatial structure of rainstorms and runoff consisting of four levels ...
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 general temperate latitude cyclonic rainstorm model is presented which describes the effects of washout and runoff on consequences of atmospheric releases of radioactive material from potential nuclear reactor accidents. The model treats the temporal and spatial variability of precipitation processes. Predicted ...
about homeland security research. Browse these EPA Emergency Response subtopics Accidents Accident Preparedness, Accident Prevention, Chemical Accidents, Radiation Accidents...
Science.gov Websites
The objectives of this work were to evaluate the consequences of a postulated accident to onsite security personnel stationed near the facility during operations of the Godiva IV critical assembly and to identify controls needed to protect these personnel in case of an extreme criticality excursion equivalent to the design-basis ...
The lradiological a consequences of the Chernobyl accident Proceedings of the first international conference
Accident models play a critical role in accident investigation and analysis. Most traditional models
NASA Technical Reports Server (NTRS)
In this paper, a simple analytical code, QUASAR, is developed to analyze the phenomena related to severe subassembly accidents, such as a total instantaneous blockage event for a subassembly inlet. The code models failed and neighboring subassemblies, focusing mainly on the thermal consequences and the propagation potential of the ...
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 ...
Page 1. Naval Health Research Center Intelligence and Accidents: ... Accidents and Intelligence Intelligence and Accidents: A Multilevel Model ...
Models to be used for analyses of economic risks from events which may occur during LWR plant operation are developed in this study. The models include capabilities to estimate both onsite and offsite costs of LWR events ranging from routine plant outages...
The review was undertaken to assist the NRC in determining whether or not to revise the models. The models are presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major ...
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 accidents. ...
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.
following the Chernobyl accident ranged from 20 to 40 kBq m�2 . A diffusion model (called DSF) is presented Significant activities of radionuclides were deposited on the soil of Europe after the Chernobyl accident (May Cs in the soil (a consequence of the Chernobyl accident) in three areas of ...
An efficient weighted interpolation technique is used to generate a time series of wind fields from the measurements of seven strategically located weather stations in Greater Hong Kong. This wind-field model, HKWIND, is integrated with the atmospheric dispersion/consequence model RADIS to form a complete off-site nuclear ...
A sequel is presented to the previous Boerderijcahier (no. 7502) which discussed long-term effects of soil contamination in case of a nuclear power plant accident. In this report the short-term health effects are discussed. Models describing the local con...
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...
Much attention has been given in recent years to the modeling of the atmospheric dispersion of pollutants released from a point source. Numerous recommendations have been made concerning the choice of appropriate dispersion parameters. A series of calculations has been performed to determine the impact of these recommendations on the calculated ...
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...
Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the chronic exposure pathways associated with a severe ac...
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...
For reasons of numerical computation, the Gaussian plume model, which is used to describe the dispersion of released atmospheric contaminants, is replaced by a step function. In the U.S. Reactor Safety Study this function is a simple top-hat distribution....
SMAC (Simulated Model of Automobile Collisions) is a computerized program which recreates collision events between two automobiles. Its purpose is to provide a data bank from which information on the causes and consequences of these accidents can be drawn...
One-dimensional flame models are often used to predict the pressure transients caused by hydrogen combustion in containments during postulated severe accidents. In the absence of data, these models account for prevailing flame acceleration mechanisms, suc...
A closed-loop nonlinear driver control mathematical model was developed primarily to enable a better definition of prevailing preimpact conditions for use in studies aimed at minimizing the incidence and the consequences of single vehicle accidents throug...
"Accident Prevention. "Accident Mitigation. "Aviation System Monitoring and Modeling. Accident Prevention is attacking the issue of airplane accidents from ...
NASA Website
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 ...
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 ...
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.
The report describes dose-response models intended to be used in estimating the radiological health effects of nuclear power plant accidents. Models of early and continuing effects, cancers and thyroid nodules, and genetic effects are provided. Weibull do...
System safety professionals, both researchers and practitioners, who regularly read accident reports reap important benefits. These benefits include an improved ability to separate myths from reality, including both myths about specific accidents and ones concerning accidents in general; an increased understanding of the ...
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 ...
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
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 ...
A two-dimensional dispersion and consequence model called RADIS has been developed and used to perform a site-specific investigation of the consequences and risks for Hong Kong as a result of a potential accident at the Daya Bay Nuclear Power Station. The study uses the 1986 Hong Kong weather and demographic data ...
The occurrence of severe accidents in commercial nuclear power plants is forecast. A Random Escalation Model (REM) is proposed that uses accident data of both high and low levels of severity to forecast the most-severe ones, which are viewed as escalations of low-severity accidents. Information from safety studies ...
Radiological and toxicological consequences of spray leak accidents in Hanford liquid waste tank farm pits were previously estimated and reported in WHC-SD- WM-CN-048 Rev 1, Calculation Notes in Support of TWRS FSAR Spray Leak Accident Analysis (Hall 1996a) in support of the Tank Waste Remediation System (TWRS) Final Safety Analysis ...
A severe accident study was conducted to evaluate conservatively scoped source terms and radiological consequences to support the Advanced Neutron Source (ANS) Conceptual Safety Analysis Report (CSAR). Three different types of severe accident scenarios were postulated with a view of evaluating conservatively scoped source terms. The ...
A model has been developed which predicts the radiological consequences of the transportation of radioactive material in and around urban environments. This discussion of the model includes discussion of the following general topics: health effects from radiation exposure, urban area characterization, computation of dose resulting from ...
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 ...
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 ...
Four accidents are postulated and analyzed for interim storage of high-level, liquid radioactive wastes at a fuel reprocessing facility. Normal waste storage operation is based on wastes stored in steel drums, partially buried in concrete canyons, and equipped with heat exchangers for cooling and ventilation systems for removal of explosive gases and vapors. The ...
The radiological transportation risk & consequence program, RADTRAN, has recently added an updated loss of lead shielding (LOS) model to it most recent version, RADTRAN 6.0. The LOS model was used to determine dose estimates to first-responders during a spent nuclear fuel transportation accident. Results varied ...
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 ...
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...
The consequences of an earthquake-induced fire involving a tritium leak were analyzed using the GASFLOW computer code. Modeling features required by the analysis include ventilation boundary conditions, flow of a gas mixture in an enclosure containing obs...
The consequences of an earthquake-induced fire involving a tritium leak were analyzed using the GASFLOW computer code. Modeling features required by the analysis include ventilation boundary conditions, flow of a gas mixture in an enclosure containing obstacles, thermally induced buoyancy, and combustion phenomena.
Contents: Commodity and Vessel Traffic Forecasts; Effectiveness of Vessel Traffic Service Systems in Reducing Vessel Accidents; Navigational Risk Model Development; VTS Design Final Report; VTS Technology Survey; Unit Costs of Vessel Casualty Consequences...
In the intervening period since the first conception of the accident consequence model UFOMOD of the German Risk Study, new scientific information has accumulated. Important are the newest recommendations of the ICRP 30 concerning the calculation of the d...
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 dispersion ...
A new perspective on the consequences of a potential reactor accident are discussed. TMI accident showed that the release of hazardous radionuclide iodine-131 was radically different than specified in the NRC regulatory model. The reactor safety study (WASH-1400) also had many conservative assumptions (called ...
Jan 11, 2011 ... trajectories and potential reentry accidents and environments. .... Environmental Consequences of Potential Accidents ...
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. ...
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. ...
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 ...
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.
...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
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 either preventing or ...
MACCS, Chronic, Exposure Pathway, Models: Review the chronic exposure pathway models implemented in the MELCOR Accident Consequence Code System (MACCS) and compare those models to the chronic exposure pathway models implemented in similar codes developed ...
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...
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 ...
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...
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)
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...
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...
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...
... PHYSIOLOGY), MATHEMATICAL MODELS, PROTECTION, INSTRUMENTATION, MOTOR VEHICLE ACCIDENTS, AVIATION ACCIDENTS ...
Response-surface techniques have been developed for obtaining probability distributions of the consequences of postulated nuclear reactor accidents. In these techniques, probability distributions are assigned to the system and model parameters of the accident analysis. A limited number of parameter values (called ...
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 ...
This paper discusses salient aspects of methodology, assumptions, and modeling of various features related to estimation of source terms from two conservatively scoped severe accident scenarios in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for steaming-pool-type ...
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 Transportation Risk Assessment ...
From the results of gamma spectrometric measurements on soil profiles of different sites in Austria, the surface deposition of (sup 137)Cs as a consequence of the Chernobyl reactor accident was calculated. The activity deposit per square meter was found i...
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...
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 ...
Uncertainty distributions for specific parameters of the Cassini General Purpose Heat Source Radioisotope Thermoelectric Generator (GPHS-RTG) Final Safety Analysis Report consequence risk analysis were revised and updated. The revisions and updates were done for all consequence parameters for which relevant information exists from the joint project on ...
In the thirty-odd years that core-disruptive accidents have been analyzed, great advances have been made both in understanding the physical phenomena involved and in development of computational techniques to deal with them. More realistic modeling has tended to reduce predicted accident consequences. Some safety ...
The radiological analyses of extreme hypothetical accidents were performed almost wholly by computer techniques. Major analytical codes used were RIBD, CACECO, SPRAY, HAA, and COMRADEX. This paper describes the analyses, the modeling techniques, and transition programs that edited data output from one code into a form suitable for input to another. ...
The impact on spatial kinetics on the analysis of severe accidents initiated by the unprotected withdrawal of one or more control rods is investigated for a large heavy water reactor. Large inter- and intra-assembly power shifts are observed, and the importance of detailed geometrical modeling of fuel assemblies is demonstrated. Neglect of space-time ...
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. DWPFASTXL is an Excel spreadsheet that can be used to calculate radiological source ...
To ensure that the public health and safety are protected under any accident conditions in a Liquid Metal Fast Breeder Reactor (LMFBR), many accidents are analyzed for their potential consequences. The SAS4A code system, described in this paper, provides such an analysis capability, including the ability to analyze low probability ...
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 ...
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 assessment ...
This work explores the use of principal components analysis coupled to three-dimensional atmospheric transport and dispersion models for evaluating the environmental consequences of reactor accidents. This permits the inclusion of meteorological data from multiple sites and the effects of topography in the ...
ORNL's Advanced Neutron Source (ANS) will be a new user facility for all kinds of neutron research, centered around a research reactor of unprecedented neutron beam flux. A defense-in-depth philosophy has been adopted. In response to this commitment, ANS Project management has initiated severe accident analysis and related technology development efforts early-on in ...
ORNL`s Advanced Neutron Source (ANS) will be a new user facility for all kinds of neutron research, centered around a research reactor of unprecedented neutron beam flux. A defense-in-depth philosophy has been adopted. In response to this commitment, ANS Project management has initiated severe accident analysis and related technology development efforts early-on in the design ...
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 ...
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 ...
This report identifies the results of a program aimed at developing a computer code for use in the analysis of the behavior of iodine during steam generator tube rupture (SGTR) accidents in pressurized water reactors (PWR's). The program was directed towards the identification of the several processes that play a role in the transport and deposition behavior of iodine ...
Offsite response decision-making methods based on in-plant conditions are developed for use during severe reactor-accident situations. Dose projections are used to eliminate all LWR plant systems except the reactor core and the spent-fuel storage pool from consideration for immediate offsite emergency response during accident situations. A simple plant ...
The Nuclear Regulatory Commission has sponsored several studies to identify and quantify the potential health effects of accidental releases of radionuclides from nuclear power plants. The most recent health effects models resulting from these efforts wer...
The Nuclear Regulatory Commission uses MACCS2 (MELCOR Accident Consequence Code System, Version 2) for regulatory purposes such as planning for emergencies and cost-benefit analyses. MACCS2 uses a straight-line Gaussian model for atmospheric transport and...
The relocation impacts of an accidental release, scenario 1-RD-3 , are evaluated for the Savannah River Technology Center. The extent of the area potentially contaminated to a level that would result in doses exceeding the relocation protective action guide(PAG)is calculated. The maximum calculated distance downwind from the accident at which the relocation PAG is exceeded is ...
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 ...
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 ...
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 ...
Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the early health effects associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables ...
This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the ...
