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)
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 ...
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 on the accident at the Chernobyl nuclear power plant discusses the medical consequences of the accident to personnel and emergency forces exposed to high levels of radiation. Data is presented on the rdiation doses to populations surrounding t...
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
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...
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...
SMART calculates early offsite consequences from nuclear reactor accidents. Once the air and ground concentrations of the radionuclide are estimated, the early dose to an individual is calculated via three pathways: cloudshine, short term groundshine, and inhalation.
Energy Citations Database
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...
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...
Department of Energy (DOE) accident analysis for establishing the required control sets for nuclear facility safety applies a series of simplifying, reasonably conservative assumptions regarding inputs and methodologies for quantifying dose consequences. ...
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 ...
The Nuclear Regulatory Commission has proposed a one-thousand-dollar per man-rem averted ALARA criterion. This report examines the relationship between population dose and health effects, as well as onsite and offsite damage. Examination of the consequences of potential accidents at two sites shows that a site with lower population ...
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 ...
The radiation levels and the ground contamination in May 1986 from the Chernobyl accident are reviewed. The radiation doses to the most exposed persons in Sweden from the accident is estimated to be 4 mSv for the year 1986. The report also discusses radia...
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 th...
This report presents the results of an evaluation of the probabilities and consequences of accidents involving shipments of radioactive materials (RAM) contained in multiple Type A packages. On the basis of previous studies as well as highway and air accident experience, the exposure doses from three generic ...
This report presents a set of precalculated doses based on a set of postulated accident releases and intended for use in emergency planning and emergency response. Doses were calculated for the PWR (Pressurized Water Reactor) accident categories of the Reactor Safety Study (WASH-1400) using the CRAC (Calculations ...
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. ...
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 ...
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 ...
This document quantifies the offsite radiological consequence of the bounding mixing of incompatible materials accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding accident is an inadvertent addition of acid to a waste tank containing high levels of caustic. Conservative ...
This document quantifies the offsite radiological consequence of the bounding mixing of incompatible materials accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding accident is an inadvertent addition of acid to a waste tank. Conservative inputs were applied in accordance ...
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 ...
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 ...
Four bounding accidents postulated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing a hydrogen explosion, and a fire breaching filter vessel and enclosure. Event trees and accident ...
Three bounding accidents postdated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing, and a hydrogen explosion. Event trees and accident probabilities are estimated. In all cases, the ...
The development of radiological consequence lookup tables for postulated releases of radionuclides commonly used at Savannah River Site (SRS) and other Department of Energy (DOE) facilities requires the use of the MELCOR Accident Consequence Code System (...
This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.
The after-Chernobyl irradiation doses of the Bulgarian population cause possible health consequences in the sphere of scholastic effects only. Different mental disturbances arise under certain conditions. There are plans for epidemiologic investigations o...
The potential consequences of the loss of a large spent fuel cask and of a single 6M plutonium shipping package into the sea for two specific accident cases are estimated. The radiation dose to man through the marine food chain following the loss of undam...
The RADionuclide Transport, Removal, And Dose (RADTRAD) code is designed for US Nuclear Regulatory Commission (USNRC) use to calculate the radiological consequences to the offsite population and to control room operators following a design-basis accident ...
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.
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 engineers referred ...
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 ...
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. ...
PubMed
COMRADEX4 was developed to evaluate potential radiological doses in the near (<10**4 meters) environment of radioactive releases, especially postulated accident releases. Consequence-mitigating natural phenomena and engineered safety features, such as aerosol deposition inside and outside containment, meteorological dispersion, ...
This document quantifies the offsite radiological consequence of the bounding waste transfer leak accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding waste transfer leak accident is a large pipe break into a pit. The calculation offsite dose does not ...
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 ...
Results of the previous one-dimensional thermal analysis of interim storage accidents are confirmed by more detailed two-dimensional calculations. Waste temperatures calculated for interim storage accidents are moderately sensitive to assumptions concerning canister spacing and are much less sensitive to boundary conditions at the canister top. For an ...
>From winter meeting of American Society of Mechanical Engineers; Detroit, Michigan, USA (11 Nov 1973). The probability of accidents occurring in the nuclear fuel cycle is examined by considering: projected number of shipments of nuclear materials for power reactors (excluding breeder and gascooled reactors); transport by truck, rail, aircraft, and barge; and ...
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 models are also developed and ...
The reactor accident at Chernobyl led to releases of large amounts of radioactive matter that was spread over the world and particularly over Europe. The radioactive material released gave rise to radiation doses originating from inhalation, external radiation from both the passing cloud and radioactive material deposited on the ground, and internal ...
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 ...
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 radioactivity in ...
This document quantifies the offsite radiological/consequence of the bounding waste transfer leak accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding waste transfer leak accident is a fine spray leak into the air. The calculation applies reasonably conservative input ...
This document quantifies the offsite radiological consequence of the bounding mixing of incompatible materials accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. Conservative input parameters were applied in accordance with the guidance provided. The calculated offsite dose does not ...
This document quantifies the offsite radiological consequence of the bounding waste transfer leak accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding waste transfer leak accident is a large pipe break into a pit. The calculated offsite dose does not ...
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 ...
The radiological transportation risk & consequence program, RADTRAN, has recently added an updated loss of lead shielding (LOS) model to it most recent version, RADTRAN 6.0. The LOS model was used to determine dose estimates to first-responders during a spent nuclear fuel transportation accident. Results varied according to the ...
of estimates of probability of stochastic effects of low radiation doses given at low dose rates. Effect lifetime dose estimates. Exposure pathway Project estimate Official estimate External exposure 60-130 m of years from the external irradiation and ingestion pathways. Estimates of dose commitments have been made
E-print Network
The transportation risk evaluation code RADTRAN 4 is designed to evaluate doses and risks associated with the transportation of radioactive materials (Ne92). RADTRAN 4 may be used to calculate dose consequences for incident-free transportation and dose risks for accidents. ...
It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of ...
NASA Astrophysics Data System (ADS)
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 marine environment. ...
This report documents a study to substantiate or modify the weather scenarios proposed by the Atomic Energy Control Board Staff Position Paper on meteorological acceptance criteria for estimating the potential radiological consequences of postulated accid...
This report documents a study to substantiate or modify the weather scenarios proposed in the AECB staff Position Paper on meteorological acceptance criteria for estimating the potential radiological consequences of postulated accidents (AECB, 1982) for s...
Dose calculations were performed using the MELCOR Accident Consequence Code System (MACCS) to support safety analyses for the Los Alamos Neutron Science Center (LANSCE) facility. The LANSCE facility is operated and maintained at Los Alamos National Labora...
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...
The consequences of the Chernobyl accident have been investigated by a comprehensive measuring program. Some of the results are presented. Dose commitments in Sweden, both collective and individual, are summed up. The measures which have been taken to red...
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...
Based on fallout measurements, additional radiation doses to the French population from external exposure to the plume, inhaled radioactivity and consumption of milk, meat and vegetables, have been estimated for the first period following the Chernobyl ac...
This summary is the results of the International Conference ''One decade after Chernobyl''. It includes topics on initial responses, radioactive releases, absorbed radiation doses and health effects, socio-economic impacts as well as safety of RBMK type r...
First published in 1955, this novel follows the consequences of a scientist�s exposure to a lethal dose of radiation while working on an atomic bomb project at Los Alamos, New Mexico in 1946. Inspired by an actual accident at that location, the book confronts the devastating consequences of radiation while ...
NSDL National Science Digital Library
This document quantifies the offsite radiological consequence of the bounding tank failure due to excessive loads accident for comparison with the 25 rem Evaluation Guideline established in WE-STK-3009, Appendix A. The bounding tank failure due to excessive loads accident is a single-shell tank failure due to excessive concentrated ...
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...
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 normal ...
about homeland security research. Browse these EPA Emergency Response subtopics Accidents Accident Preparedness, Accident Prevention, Chemical Accidents, Radiation Accidents...
Science.gov Websites
A full-scale PRA of a DOE production reactor has been completed that considers full release of tritium as part of the severe accident source term. Two classes of postulated reactor accidents, a loss-of-moderator pumping accident and a loss-of-coolant accident, are used to bound the expected ...
As a result of the Commissariat a l'Energie Atomique CRAC experimental program, which studied the phenomenology and the radiological consequences of a criticality excursion in fissile solution, the EDAC system has been developed. This system detects a criticality accident and warns personnel as early as possible by triggering the necessary ...
This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for ...
The lradiological a consequences of the Chernobyl accident Proceedings of the first international conference
The Radiological Assessment System for Consequence Analysis, Version 2.1 (RASCAL 2.1) has been developed for use during a response to radiological emergencies. The model estimates doses for comparison with U.S. Environmental Protection Agency (EPA) Protective Action Guides (PAGs) and thresholds for acute health effects. RASCAL was designed to be used by ...
The objective of this study was to estimate the dose due to transuranic nuclides released during the Chernobyl accident. Calculations have shown that most of this dose was formed prior to May 6, 1986 and was due to curium 242 and the plutonium isotopes. With a 162.8 day half-life, the curium 242 fraction is presently negligible, while ...
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 accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be ...
The assessment doses due to ingestion of (137)Cs and (90)Sr for the population suffering from the Chernobyl accident was performed on the basis of the new mechanistic ecological model for assessment of radiological consequences of agricultural lands contamination (EMARC). The EMARC model allows estimation of internal ...
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...
This report presents the results of a set of sensitivity studies designed to define the potential range of dose consequences from compressed air/gas system ruptures impacting contaminated tank farm pits. These accidents could potentially result in the uncontrolled release of radioactive hazardous material from tank farms. This includes ...
A critical review of 34 published severe radiological accidents in industrial gamma radiography, that happened in 15 countries, from 1960 to 1988, was performed. The most frequent causes, consequences and dose estimation methods were analysed, aiming to s...
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 (...
Children from ares affected by the Chernobyl accident have been receiving medical care in Cuba since 1990. The dosimetric and biomedical studies made include: measurement of (sup 137)Cs body content; internal, external, thyroid and total dose estimation; ...
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 CEC/USDOE Workshop on ...
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 ...
This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside ...
This document provides the toxicological dose caculations related to the toxic chemical releases from spill accidents at T Plant Facility.
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 materials. Value/impact ...
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 ...
The absorbed dose of low LET radiation that would be lethal (due to bone marrow failure) to 50% of an exposed human population is a matter for concern in planning for the consequences of an accident to a nuclear reactor and in the event of nuclear war. Since accidents with radiation-generating equipment or in the ...
This bibliography contains citations on the consequences of the radioactive fallout from the Chernobyl nuclear reactor accident. Transfrontier radioactive contamination, deposition of radioactive pollutants from the atmosphere, radionuclide concentrations in ground-level air and soil contamination, radionuclide concentrations in vegetation and food, ...
The knowledge about environmental sensitivity of the marine regions to radionuclide release can be used for the development of response strategies and improvement of design-maker systems. The present results are based on the consequences analysis after potential Russian submarine accident involving a modern vessel. The radioecological ...
A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and non-site specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on ...
All accidental criticality excursions are accompanied by neutron and gamma radiation that creates two possible types of radiation risk: (1) immediate risk for the personnel directly exposed; and (2) deferred risk in the case where an intervention team is required in the postaccident phase. These aspects, or more specifically dose measurement and the possibility of calling on ...
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 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 ...
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 ...
This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.The attached SD documents the originator`s analysis only. It shall not be used as ...
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 important to the current ...
PubMed Central
The risks associated with the transport of spent nuclear fuel by truck and rail have been reexamined and compared to results published in NUREG-O170 and the Modal Study. The full reexamination considered transport of PWR and BWR spent fuel by truck and rail in four generic Type B spent fuel casks. Because they are typical, this paper presents results only for transport of PWR spent fuel in ...
Ion exchange columns from the 309 Plutonium Recycle Test Reactor rupture loop must be shipped to the solid waste burial ground. The enclosed calculational note documents the calculations used to calculate the absorbed doses expected in the case of a postulated accident.
The collective dose due to normal operation of a reprocessing plant is considerably above the expected value of the collective dose in consequence of examined accidents in the reprocessing plant and in the model final stores. For 'integrated fuel disposal...
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 food pathways associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future ...
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 undertaken in which the ...
In nuclear preparedness, an essential requirement is the ability to adequately predict the likely consequences of a major accident situation. In this context it is very important to evaluate which contributions to dose are important, and which are not likely to have significance. As an example of this type of evaluation, a case study ...
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.
Recent concerns about possible low-grade chemical explosions or deflagrations in high-level waste (HLW) tanks has led to an intensive effort to assess the potential on- and off-site radiological consequences of such occurrences. This paper presents the results of work conducted at the Los Alamos National Laboratory (LANL) as part of the Hanford Site waste tank reanalysis ...
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...
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 ...
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 to be considered in ...
The purpose of this analysis is to calculate the offsite radiological consequence of the bounding flammable gas accident. DOE-STD-3009-94, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', requires the formal quantification of a limited subset of ...
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 ...
Department of Energy (DOE) accident analysis for establishing the required control sets for nuclear facility safety applies a series of simplifying, reasonably conservative assumptions regarding inputs and methodologies for quantifying dose consequences. Most of the analytical practices are conservative, have a technical basis, and are ...
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 ...
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 ...
We have performed a safety assessment of mercury and lead as possible hohlraum materials for Inertial Fusion Energy (IFE) targets, including for the first time a comparative analysis of the radiological and toxicological consequences of an accidental release. In order to calculate accident doses to the public, we have distinguished ...
This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to ...
Refinements to consequence modelling for hypothetical accidents in Fusion Power Plants have been explored. This leads to improved accuracy and a reduction in some of the conservatism inherent in previous calculations. Assumptions made in previous analyses for the Safety and Environmental Assessment of Fusion Power (SEAFP) are examined, with particular ...
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 ...
The design and safeguards of the Ames Laboratory Research Reactor and its associated facilities are reviewed. The causes and consequences of serious accidents are considered. It was found that the maximum credible accident for the ALRR is a quite melt-down of the aluminum core, which results from loss of D/ sub 2/O coolant. ...
AXAIRQ is the primary dose assessment code used at the Savannah River Site to predict downwind doses following a hypothetical atmospheric release of relatively short duration. Purpose is to perform calculations for safety-related documentation, and AXAIRQ strictly adheres to the guidance in US NRC Regulatory Guide 1.145 (USNRC 1982) entitled Atmospheric ...
Process engineering designs, major equipment and plant facilities to be utilized in commercial nuclear waste preparation and vitrification in the 324 Radiochemical Engineering Building are reviewed with regard to accident potential and consequences. This Safety Analysis Report Supplement compares calculated environmental doses ...
This report provides an evaluation of Hanford tank bump accident potential and consequences during waste retrieval operations. The purpose of this report is to consider the best available new information to support recommendations for safety controls. A new tank bump accident analysis for safe storage (Epstein et al. 2000) is extended ...
The Defense Programs (DP) Office of Engineering and Operations Support (DP-62) requested SAIC to organize and conduct a survey-level evaluation of 27 DP non-reactor nuclear facilities. The purpose of the evaluation was to provide a consistent scoping effort to estimate, with high confidence, bounding accident consequences for hazards associated with DP ...
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 ...
The safety of the Mirror Advanced Reactor Study (MARS) tandem mirror reactor is assessed. Only prompt consequences to the public at the plant boundary, which is taken to be 1000m, are considered. The major radioactive inventories in MARS reside in the first-wall/blanket structure, coolant, and tritium. The greatest radioactivity resides in the HT-9 first-wall/ blanket ...
This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are ...
Jan 11, 2011 ... trajectories and potential reentry accidents and environments. .... Environmental Consequences of Potential Accidents ...
NASA Website
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. ...
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 Radiological Assessment System for Consequence AnaLysis, Version 3.0 (RASCAL 3.0) is the U.S. Nuclear Regulatory Commission�s (NRC) main computational tool for use during radiological emergencies. RASCAL estimates doses from radiological accidents for comparison with Protective Action Guides and acute health effects thresholds. ...
The Radiological Assessment System for Consequence AnaLysis, Version 3.0 (RASCAL 3.0) is the U.S. Nuclear Regulatory Commission?s (NRC) main computational tool for use during radiological emergencies. RASCAL estimates doses from radiological accidents for comparison with Protective Action Guides and acute health effects thresholds. It ...
Most available environmental transport and dosimetry codes for radiological consequence analysis are designed primarily for estimating dose and health consequences to specific off-site individuals as well as the population as a whole from nuclear facilities operating under either normal or accident conditions. ...
The evaluation of the dose that a person received in a criticality accident can be difficult. Most accidents have occurred when the person was not wearing nuclear accident dosimetry and since the NRC no longer requires these dosimeters, future dose evalua...
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...
This report presents a comparison between two computerized methodologies for estimating the radiation dose to man from radionuclide releases to the atmosphere. The COMRADEX-IV code was designed to provide a means of assessing potential radiological consequences from postulated power reactor accidents. The AIRDOS-EPA code was developed ...
Argonne National Laboratory (ANL) conducts experimental work on the development of waste forms suitable for several types of spent fuel at its facility on the Idaho National Engineering and Environmental Laboratory (INEEL) located 48 km West of Idaho Falls, ID. The objective of this paper is to compare the offsite radiological consequences of hypothetical ...
This document quantifies the offsite radiological consequences of the bounding flammable gas accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding flammable gas accident is a detonation in a SST. The calculation applies reasonably conservative input parameters in accordance ...
The consequences of a dosimetric radiosurgery accident are not the same as a conventional radiotherapy accident. The objective of this study was to estimate the clinical and radiological outcome of patients treated by radiosurgery for metastasis during the period of the overexposure accident that occurred in the ...
It is difficult to predict immediate worker radiological consequences from a hypothetical accident. This is recognized in DOE safety analysis guidance and the reason such guidance does not call for quantitative determinations of such consequences. However, it would be useful to at least have a means of systematically and formally ...
Dose calculations were performed using the MELCOR Accident Consequence Code System (MACCS) to support safety analyses for the Los Alamos Neutron Science Center (LANSCE) facility. The LANSCE facility is operated and maintained at Los Alamos National Laboratory (LANL) and will be used to conduct experiments for the U.S. Department of ...
An active part in liquidation of the Chernobyl APS disaster consequences was taken by servicemen. The article deals with the so-called All-Army Register and its tasks which are as following: a long-term records of patients who have participated in this emergency situation and received various doses of radiation; control over the changes in their health ...
The results of medical examinations of the persons taking part in elimination of consequences of Chernobyl's disaster obtained by the specialists of Military-medical academy allowed to verify the conception of damage action of radiation and nonradiation complex of injury factors, to estimate well-information of stale and new biological indicators of radiation ...
The overview of the results of development, verification and application of the methods of individual retrospective physical dosimetry among population of settlements contaminated with radionuclides, which suffered from irradiation as a result of the accident in Chernobyl NPP, and among the population located in the vicinity of the Semipalatinsk nuclear test site is presented ...
This document presents the radiological dose and toxicological exposure calculations for an accident scenario involved with the ventilation system used to support salt well pumping single-shell tank 241-A-101. This tank has been listed on the Hydrogen Watch List.
The relocation impacts of an accidental release, scenario 1-RD-2.35, are evaluated for H-Separations. 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 ...
On April 26, 1986, the worst accident in the history of commercial nuclear power generation occurred at the Chernobyl Nuclear Power Station some 60 miles north of Kiev in the Ukraine. This paper describes the sequence of events that occurred and the consequences of the accident. There was extensive damage to the Unit 4 reactor and the ...
Transportation System Risk Assessments (TSRAs) document the compliance of proposed shipments of nuclear components with applicable federal regulations as well as the associated risks involved. If a relatively simple bounding analysis can show that the consequences resulting from a worst case scenario are acceptably low, a more time intensive and costly risk analysis can be ...
In this study 58 participants of the liquidation of the consequences of Chernobyl accident in 1986-1987 were investigated. All the patients complain of constant headaches, disorders of memory, general weakness, rapid fatigability, decreased sexual drive, emotional instability etc. The complex (comprehensive) modern methods of investigation were used to ...
Calculation of the radiation doses (207 to 436 r) received by 6 workers exposed during the Vinca (Yugoslavia) reactor accident is discussed. (H.H.D.)
Onsite and site boundary radiological consequences were estimated for a postulated accidental drop of an Interim Storage Cask (ISC) loaded 7 assemblies at the maximum available burnup. The postulated cask drop was assumed to occur from the maximum physically attainable height during crane movement of the cask. The resulting onsite and site boundary doses ...
Following the end of the Cold War, the mission of Rocky Flats Environmental Technology Site changed from production of nuclear weapons to cleanup. Authorization baseis documents for the facilities, primarily the Final Safety Analysis Reports, are being replaced with new ones in which accident scenarios are sorted into coarse bins of consequence and ...
A safety analysis study has been applied to the Ignitor machine using Probabilistic Safety Assessment. The main initiating events have been identified, and accident sequences have been studied by means of traditional methods such as Failure Mode and Effect Analysis (FMEA), Fault Trees (FT) and Event Trees (ET). The consequences of the radioactive ...
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 ...
The Chernobyl accident resulted in the contamination of the environment with long-lived radionuclides, including transuranium elements. The results, more accurate than the data, for the production of the basic long-lived radio-nuclides in the reactor core where the accident occurred. It is of interest to examine the Americium-241 contamination in greater ...
Evacuation, sheltering followed by population relocation, and iodine prophylaxis are evaluated as offsite public protective measures in response to nuclear reactor accidents involving core-melt. Evaluations were conducted using a modified version of the Reactor Safety Study consequence model. Models representing each measure were developed and are ...
Evacuation, sheltering followed by population relocation, and iodine prophylaxis are evaluated as offsite public protective measures in response to potential nuclear reactor accidents involving core-melt. Evaluations were conducted using a modified version of the Reactor Safety Study consequence model. Models representing each protective measure were ...
