Estimates of the potential airborne release of radioactive materials in transportation accidents are necessary to compare the safety in various shipping methods. To make such estimates, information is required on various aspects of the accident situation (physical and chemical characteristics of the source materials, forces/conditions ...

Fission product release analysis code, RACPAC (Fission Product Release Analysis Code from Fuel Particle in Accident Condition), was developed to calculate fractional release from the core during accident conditions of High Temperature Gas-cooled Reactor. ...

The source term literature was reviewed to estimate aerosolized and respirable release fractions for accidents involving plutonium in high-explosive (HE) detonation and in fuel fires. For HE detonation, all estimates are based on the total amount of Pu. F...

The purpose of this task was to support ESH-3 in providing Airborne Release Fraction and Respirable Fraction training to safety analysts at LANL who perform accident analysis, hazard analysis, safety analysis, and/or risk assessments at nuclear facilities. The task included preparation of materials for and the ...

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.

A series of full-scale experiments were conducted to characterize the release of simulated waste from waste containers packaged in a Transuranic Package Transporter (TRUPACT) subjected to a series of drop, puncture, and thermal environments. The measureme...

Curve-fitting techniques have been used to derive simple mathematical expressions for: (1) the force the drums are subjected to as a function of accident severity, based upon the range of breach force assigned to the eight accident severity categories; (2) radial drum crush as a function of static load; and (3) radial drum crush as a function of drum ...

This report presents supplemental information for the document Analysis of Accident Sequences and Source Terms at Waste Treatment, Storage, and Disposal Facilities for Waste Generated by US Department of Energy Waste Management Operations. Additional technical support information is supplied concerning treatment of transuranic waste by incineration and considering the ...

The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release ...

The Chernobyl nuclear reactor accident released considerable amounts of radioactive material into the environment, including a large amount of (137)Cs. A large fraction of the (137)Cs was deposited on the ground in the surrounding areas. Two atmospheric m...

Shipments of radioactive material (RAM) constitute but a small fraction of the total hazardous materials shipped in the United States each year. Public perception, however, of the potential consequences of a release from a transportation package containin...

...reasonable assurance that the radiation safety properties of the source...or device, a description of radiation safety features, the intended...fraction in the respirable size range would be lower than the release...area emergencies. (iv) Detection of accidents....

The theoretical and numerical data base development of the LARC-1 code is described. Four analytical models of fission product release from an HTGR core during the loss of forced circulation accident are developed. Effects of diffusion, adsorption and evaporation of the metallics and precursors are neglected in this first LARC model. Comparison of the ...

Provides information about reporting releases. Browse these EPA Reporting subtopics Accidents Accident Preparedness, Accident Prevention, Chemical Accidents, Radiation 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 the Radioisotope ...

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 the Radioisotope ...

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 the Radioisotope ...

Samples of commercial LWR fuel have been heated under simulated accident conditions to determine the extent and the chemical forms of fission product release. This project was sponsored by the USNRC under a broad program of reactor safety studies. Of the five tests discussed, the fractional releases of Kr, I, and ...

Accidents and potential accidents involving plutonium in processing facilities and accidents are briefly reviewed. Data available regarding plutonium aerosol released are used to access the release of plutonium aerosols in potentially serious accidents, and conclusions ...

Representative accident source terms patterned after the NUREG-1465 Source Term have been developed for high burnup fuel in BWRs and PWRs and for MOX fuel in a PWR with an ice-condenser containment. These source terms have been derived using nonparametric order statistics to develop distributions for the timing of radionuclide release during four ...

Most previous risk assessment studies have assumed catastrophic failure of containments for severe accidents which are predicted to exceed the containment yield stress. This investigation analyzes the progression of a severe accident in order to develop realistic containment temperature and pressure loading, utilizes models for containment leakage ...

This paper describes an approach to identifying source terms from possible accidents during the preclosure phase of a high-level nuclear waste repository. A review of the literature on repository safety analyses indicated that source term estimation is in a preliminary stage, largely based on judgement-based scoping analyses. The approach developed here was to partition the ...

This paper discusses fission product release from light-water-reactor-type fuel rods to the coolant loop during design basis accident tests. One of the tests was a power-cooling-mismatch test in which a single fuel rod was operated in film boiling beyond failure. Other tests discussed include reactivity initiated accident (RIA) tests, ...

Fission product release from fully irradiated light water reactor fuel under accident conditions and the chemical forms and behavior of the released material have been studied at high temperatures. This work has emphasized release from commercial fuels, but tracer-level tests using specific fission product species ...

Accidents and Acts of Terrorism? Click Here to Report Oil and Hazardous Substance Spills, Chemical Releases, Transportation Accidents, Liquid or Gas Pipeline Releases,...

In this study, risk-significant pressurized-water reactor severe accident sequences are examined using MELCOR 1.8.5 to explore the range of fission product releases to the reactor containment building. Advances in the understanding of fission product release and transport behavior and severe accident progression ...

The MELCOR code, developed by Sandia National Laboratories, is a fully integrated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs).A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simulated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng ...

Accidents and potential accidents involving plutonium in processing facilities and accidents are briefly reviewed. Data available regarding plutonium aerosol released are used to access the release of plutonium aerosols in potentially serious accidents, a...

The source term literature was reviewed to estimate aerosolized and respirable release fractions for accidents involving plutonium in high-explosive (HE) detonation and in fuel fires. For HE detonation, all estimates are based on the total amount of Pu. For fuel fires, all estimates are based on the amount of Pu oxidized. I based my ...

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 paper provides an overview of high-temperature gas-cooled reactor (HTR) fission product chemistry and its influence on source terms in core heatup accidents. These accidents are risk-dominating for medium-sized HTRs and are characterized by maximum core temperatures of {approximately}2500{degrees} C (2773 K) and a late-starting, slowly proceeding ...

The MELCOR code, developed by Sandia National Laboratories, is capable of simulating the severe accident phenomena of light water reactor nuclear power plants (NPPs). A specific large-break loss-of-coolant accident (LOCA) for Kuosheng NPP is simulated with the use of the MELCOR 1.8.4 code. This accident is induced by a double-ended ...

The Chernobyl accident released a large amount of highly fractionated radioactive debris, including approximately 89 PBq of /sup 137/Cs. We calculated the resulting collective dose commitment to the Northern Hemisphere via the pathways of external exposure and ingestion of radionuclides withd food. We developed a rural/urban model of ...

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 ...

Radionuclides released during core-concrete interactions (CCI) can make a major contribution to the severe accident source term. Despite recent advances in understanding, significant uncertainties remain in the prediction of these releases. In the present paper, selected chemical issues that play an important role are discussed and ...

The rail shipment of large quantities of radiocesium involves a potential accidental release of this material in a readily available form to the biosphere. The magnitude of the associated potential damage to man and his environment is evaluated in this report. The evaluation of the consequences of an accidental release of Cs-137 from the Shielded Transfer ...

This document provides the toxicological dose caculations related to the toxic chemical releases from spill accidents at T Plant Facility.

This document provides the toxicological dose caculations related to the toxic chemical releases from spill accidents at T Plant Facility.

emergencies, and aircraft accidents. The majority of technological emergencies will .... such as HAZMAT releases, aircraft accidents, hurricane operations, ...

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 non-reactor nuclear ...

Wanted List Safety Alerts Safety Recommendations Safety Studies Accident Investigations Current Investigations The Investigative Process Accident Dockets Accident Reports...

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 describes ship accident event trees, ship collision and ship fire frequencies, representative ships and shipping practices, a model of ship penetration depths during ship collisions, a ship fire spread model, cask to environment release fractions during ship collisions and fires, and illustrative consequence calculations.

The Parametric Source Term (PST) code has been developed for estimating radioactivity release fractions. The PST code is a framework of equations based on activity transport between volumes in the release pathway from the core, through the vessel, through the containment, and to the environment. The code is fast-running because it ...

Saftey assessments and environmental impact statements for facilities require an estimation of airborne releases. Aerosols generated by accidents are being investigated to develop the source terms for these releases. The lower boundry accidental release event would be a free fall spill of powders or liquids in ...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

As part of the Electric Power Research Institute (EPRI) program on steam generator degradation specific management (SGDSM), the nuclear industry is investigating the effects on plant risk of severe accidents involving steam generator tube leaks or ruptures. Such accidents fall into three classes: those caused by spontaneous, steam generator tube ruptures ...

Hazardous Waste Management (HWM) facilities are used in the handling and processing of solid and liquid radioactive, hazardous, mixed, and medical wastes generated at Lawrence Livermore National Laboratory (LLNL). Waste may be treated or stored in one of the HWM facility units prior to shipment off site for treatment or disposal. Planned facilities such as the Decontamination and Waste Treatment ...

The SeaRAM Program conducted for the US Department of Energy by Sandia National Laboratories has developed estimates of the frequencies of occurrence of ship fires and ship collisions, the fraction of all ship fires and ship collisions that might be sufficiently severe to challenge the integrity of a Type B spent fuel transportation cask, the magnitude of the radioactive ...

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 ...

This topical report contains technical information used to determine the accident consequences of releases of toxic chemical and gases for the Tank Farm Final Safety Analysis report (FSAR).It does not provide results for specific accident scenarios but does provide information for use in those calculations including chemicals to be ...

... Title : Glutamate and Dynorphin Release from a Subcellular Fraction Enriched in Hippocampal Mossy Fiber Synaptosomes. ...

For a sound evaluation of the consequences of a hypothetical nuclear reactor accident, a knowledge of the extent of fission product release from the fuel at anticipated temperatures and atmosphere conditions is required. Measurements of fission product release have been performed with a variety of nuclear fuels under various conditions ...

This paper describes accident analysis approaches (or strategies for success) for a postulated full-building fire affecting a large radiological laboratory building at Savannah River Technology Center (SRTC) at Savannah River Site (SRS). SRTC management and the SRS Department of Energy (DOE) field office (the "owners" of the facility and its safety analysis) specified that ...

Safety assessments and environmental impact statements for nuclear fuel cycle facilities require an estimate of potential airborne releases caused by accidents. Aerosols generated by accidents are being investigated by Pacific Northwest Laboratory to develop the source terms for these releases. An upper boundary ...

This report was written at the request of EG&G Rocky Flats, Inc. in support of joint emergency planning for the Rocky Flats Plant (RFP) by EG&G and the State of Colorado. The intent of the report is to provide the State of Colorado with an independent assessment of any respirable plutonium releases that might occur in the event of a severe fire at the plant. Fire ...

The paper presents the results of an experimental investigation on the formation mechanism and physical characterization of simulated nuclear aerosols that could likely be released during an HTGR core heat-up accident. Experiments were carried out in a high-temperature flow system consisting essentially of an inductively heated release ...

Accidental releases of radioactivity from fission reactors will consist of active vapors and aerosols. Composition of the released plume or cloud will depend on the energy of release and fission product volatility. In accidents at Windscale and SL-1, /sup 131/I was the predominant isotope present in both the ...

Iodine radionuclides constitute one of the most important fission products of uranium and plutonium. If the volatile forms would be released into the environment during a severe accident, a potential health hazard would then ensue. Understanding its behaviour is an important prerequisite for planning appropriate mitigation measures. Improved and extensive ...

... RELEASE, AIR FORCE, WATER POLLUTION, AIR QUALITY, PUBLIC HEALTH, TROPOSPHERE, ROCKET PROPELLANTS, ACCIDENTS ...

The national emergency plan for nuclear accidents is a plan of action designed to provide a response to accidents involving the release or potential release of radioactive substances into the environment, which could give rise to radiation exposure to the...

Brookhaven National Laboratory, under the auspices of the US Nuclear Regulatory Commission, is investigating accident management strategies which could help preserve containment integrity or minimize releases during a severe accident. The strategies consi...

... Descriptors : *BUILDINGS, *EXPLOSIONS, *ACCIDENTS ... ENGINEERING AND BUILDING TECHNOLOGY ... APPROVED FOR PUBLIC RELEASE. ...

Severe ship accidents and the probability of radioactive material release from spent reactor fuel casks were investigated previously. Other forms of RAM, e.g., plutonium oxide powder, may be shipped in large numbers of packagings rather than in one to a few casks. These smaller, more numerous packagings are typically placed in ISO containers for ease of ...

Considering the fact that to our experiences fire accidents are of highest significance for the operational safety of a repository for Radwaste, a broad research project has been carried out in Germany on behalf of BfS (Federal Office for Radiation Protection) to develop a comprehensive approach for the determination of release rates under fire conditions. ...

The release and transport of activated materials-of-construction in a fusion reactor during an accident scenario involving overheating and ingress of oxidants is an important area of safety research. This investigation quantified material release characteristics which result from surface oxide spallation and vaporization for the steel ...

A series of tests has been conducted with simulated LWR fuel as part of a program for determining the quantities and characteristics of radiologically significant fission products that can be released under postulated spent-fuel transportation accident (SFTA) conditions and successfully terminated loss-of-coolant accident (LOCA) ...

Two design-basis accidents for the AP-600 reactor are formulated and evaluate~ in which significant bypass of the principal pH control system occurs. Some iodine released from the reactor primary system is retained in the Incontainment Refaeling Water Storage Tank (IRWST) water, never entering the containment where trisodium phosphate produces a high pH. ...

The release of fission products, both gaseous and volatile metals, from TRIGA fuel is important for the analysis of possible accident conditions related to reactor operation and the design of future TRIGA fuel systems. Because of present national concerns over nuclear proliferation, it has become clear that future reactor fuels will, of necessity, utilize ...

The release and transport of activated materials-of-construction in a fusion reactor during an accident scenario involving overheating and ingress of oxidants is an important area of safety research. This investigation quantified material release characteristics that result from surface oxide spallation and vaporization from the steel ...

The value of the 133Xe/133mXe isometric activity ratio for the stationary regime of reactor work is about 35, and that for an instant fission (explosion) is about 11, which allowed estimation of the nuclear component of the instant (explosion) energy release during the NPP accident. Atmospheric xenon samples were taken at the trajectory of ...

Two types of hypothetical reactor catastrophe are considered. In the first of these, the Boiling Accident,'' it is assumed that a fraction of the radioactive material in a reactor is released to the atmosphere at a steady rate over a period of hours. In the second, the Puff ...

The release and transport of activated materials-of-construction in a fusion reactor during an accident scenario involving overheating and ingress of oxidants is an important area of safety research. This investigation quantified material release characte...

Fuel performance models based on empirical evidence are used to predict particle failure and fission product release in the design of high-temperature gas-cooled reactors (HTGRs). Advances in HTGR fuel performance models have improved the agreement between observed and predicted performance and contributed to an enhanced position of the HTGR with regard to investment risk and ...

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 ...

The objective of SIMMER qualification testing program is to assure that the mathematical models and input parameters are derived from experimental data, which, on the basis of criteria still to be established, are representative of the phenomena and processes governing the progression of a CDA in an LMFBR. At the present time, the work to meet this objective can be classified into three general ...

CONTAIN is an integrated containment thermohydraulic and aerosol transport code. The choice of the Surry plant provides an opportunity to compare the CONTAIN calculations to those recently performed by Battelle Columbus Laboratories. The accident sequence considered consists of a loss of coolant accident due to a large pipe break in the hot leg, followed ...

A typical safety analysis report (SAR) contains estimated frequencies.and consequences of various design basis accidents (DBA). However, the results are organized and presented in such a way that they are not conducive for summing up with mathematical rigor to express total or overall risk. This paper describes a mathematical formalism for deriving total risk indicators. The ...

Calculation of the potential off-site dose consequences of a major reactor accident at SRP requires knowledge of the inventory and behavior of the major volatile radionuclides present in a typical SRP reactor charge. This memorandum documents the fission product inventory data used for the 1982 version of the SRP reactor safety analysis report (SAR) and the assumptions made ...

This report quantifies what ''low activation'' means with regard to accident safety for naturally occurring elements from hydrogen through bismuth. The activation inventory from a neutron flux of 5 MW/m/sup 2/ for 4 years exposure at the first wall to a deuterium-tritium plasma was used for four figures of merit including: Prompt Dose Rating ...

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 ...

Shipments of radioactive material (RAM) constitute but a small fraction of the total hazardous materials shipped in the United States each year. Public perception, however, of the potential consequences of a release from a transportation package containing RAM has resulted in significant regulation of transport operations, both to ensure the integrity of a ...

This report reviews existing literature and knowledge on graphite burning and on stored energy accumulation and releases in order to assess what role, if any, a stored energy release can have in initiating or contributing to hypothetical graphite burning scenarios in research reactors. It also addresses the question of graphite ignition and self-sustained ...

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 accidents involving ...

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

Oct 8, 1996 ... Hazardous Waste Accidents (401 SDI Group): Definition: Number of accidents in hazardous waste handling facilities that released waste into ...

tests and reports significant releases of radioactivity into the environment. 1986 Chernobyl Accident ERAMS provides information about the accident and reports increased levels...

on lessons learned in providing family assistance following transportation accidents in an international context. "Following a major aviation or passenger rail accident...

accidents, promoting transportation safety, and assisting victims of transportation accidents and their families. Resources Press Releases Speeches/Testimony Databases...

Mar 5, 2006 ... The Columbia Accident Investigation Board released Volume I of its final report on Aug. 26, 2003. The report is posted here in three ...

... 22-25 VI. Measures to Prevent or Minimize Casualties (or Accidents) Engineering and Maintenance ... of accidents that release dangerous materials. ...

In this report the radioactive fallout on Greece from the Chernobyl nuclear accident is described. The flow pattern to Greece of the radioactive materials released, the measurements performed on environmental samples and samples of the food chain and some...

After a brief description of the Chernobyl reactor and the accident, the activity release is assessed. Radiological effects in the immediate vicinity as well as in Europe are discussed, with particular emphasis on Switzerland. Results concerning food cont...

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...

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

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

A collection of three staff papers about the motorist is provided. The first examines accident data and concludes that removing a small fraction of drivers from the road would not dramatically reduce the total accident count. The second considers normal a...

The purpose of this report is to compare in-containment source terms developed for NUREG-1159, which used the Source Term Code Package (STCP), with those generated by MELCOR to identify significant differences. For this comparison, two short-term depressurized station blackout sequences (with a dry cavity and with a flooded cavity) and a Loss-of-Coolant Accident (LOCA) ...

The possibility of worker exposure to radioactive materials during accidents at nuclear facilities is a principal concern of the DOE. The KBERT analysis tool has been developed at Sandia National Laboratories under DOE support to address this issue by assisting in the estimation of risks posed by accidents at chemical and nuclear facilities. KBERT is an ...

The Chernobyl source term available for long-range transport was estimated by integration of radiological measurements with atmospheric dispersion modeling and by reactor core radionuclide inventory estimation in conjunction with WASH-1400 release fractions associated with specific chemical groups. The model simulations revealed that the radioactive cloud ...

From the major accident at Unit 4 of the Chernobyl nuclear power station, a plume of airborne radioactive fission products was initially carried northwesterly toward Poland, thence toward Scandinavia and into Central Europe. Reports of the levels of radioactivity in a variety of media and of external radiation levels were collected in the Department of Energy's ...

Emergency preparedness and response plans require a methodology for the assessment of core damage in the event of severe accidents. Some methodologies rely on measurement of fission product concentrations in the primary coolant system and the containment. Subsequently, these measurements are related to the amount of fission products released in the ...

This report describes the source term estimation codes, XSORs. The codes are written for three pressurized water reactors (Surry, Sequoyah, and Zion) and two boiling water reactors (Peach Bottom and Grand Gulf). The ensemble of codes has been named ``XSOR``. The purpose of XSOR codes is to estimate the source terms which would be released to the atmosphere in severe ...

In response to a request from the Task Group on Health Physics and Dosimetry of the President's Commission on the Accident at Three Mile Island (TMI), radiation doses to persons living within 80 km were estimated using the AIRDOS-EPA computer code. Hourly radionuclide release and corresponding meteorological data were supplied by the Task Group. ...

Radioactive emissions into the atmosphere from the damaged reactors of the Fukushima Dai-ichi nuclear power plant (NPP) started on March 12th, 2011. Among the various radionuclides released, iodine-131 ((131)I) and cesium isotopes ((137)Cs and (134)Cs) were transported across the Pacific toward the North American continent and reached Europe despite dispersion and washout ...

A systems model for shallow land burial of low-level waste was assembled from existing models available in the nuclear industry. The model covers waste packaging, transportation, burial, and post burial activities. Subprograms were developed for unsaturated zone seepage, aquifer transport, wind erosion, and atmospheric transport. Release via available pathways are converted to ...

A systems model for shallow land burial of low-level waste was assembled from existing models available in the nuclear industry. The model covers waste packaging, transportation, burial, and post burial activities. Subprograms were developed for unsaturated zone seepage, aquifer transport, wind erosion, and atmospheric transport. Release via available pathways are converted to ...

This report examines containment requirements for spent-fuel transport containers that are transported under normal and hypothetical accident conditions. A methodology is described that estimates the probability of rod failure and the quantity of radioactive material released from breached rods. This methodology characterizes the dynamic environment of the ...

Information is presented concerning the release of radioactivity in reactor accidents; physical processes in reactor meltdown accidents; safety design rationale for nuclear power plants; and design adequacy.

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 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 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. ...

Woods Discusses "Hindsight Bias" as a Possible Outcome Related to the Space Shuttle Columbia Accident to misinterpret the conclusions of the Columbia Accident Investigation Board (CAIB), according to an Ohio State bias. Often the first question people ask about the decision making leading up to the Columbia accident

This report addresses the potential LWR accident source term implication on accident evaluation assuming a change of the chemical form of iodine from elemental to cesium iodide. As a consequence, the escape of iodine to the environment and the risk to the...

The VICTORIA code is designed to be a module of the MELPROG severe accident analysis code. The VICTORIA code is designed to model the in-vessel phase of a severe reactor accident. The functions of VICTORIA in MELPROG are fission product release from fuel,...

Separate abstracts are included for each of the 22 papers presented concerning the mechanical effects of core accidents, analysis of hypothetical accidents, sodium-air reactions, and accident activity release. (DCC)

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...

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 ...

In the present report realistic estimations about the nuclear accident at Chernobyl and the radioactivity burdening of Greece from the radioactive releases of the accident are presented. Results of radioactivity measurements in Greece concerning the envir...

...CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Risk Management Plan § 68.195 Required...as follows: (a) New accident history information�For...release meeting the five-year accident history reporting...

Experiments were performed to measure the fraction of mercury inventory released when droplets of molten lead, doped with a known concentration of mercury, fall through a controlled environment. The temperature of molten droplets ranged from 335 C to 346 C, and the concentration of mercury in the droplets ranged from 0.2 mass % to 1.0 mass %. The ...

fractional release and mean age. Mean age = �p i. Mixing ratio = �w ... Fractional release increases in the lower stratosphere middle latitudes ...

... At Petroleum Release Sites Dennis A. Reed Teresa R. Sterner ... Lessons Learned Using Fractions To Assess Risk At Petroleum Release Sites ...

The Parametric Source Term (PST) software allows estimation of radioactivity release fractions for Level 2 Probabilistic Safety Assessments (PSAs). PST was developed at the Idaho National Engineering Laboratory (INEL) for the Nuclear Regulatory Commission`s (NRC`s) Accident Sequence Precursor (ASP) Program. PST contains a framework of ...

The N-Reactor confinement system release dose to the public in a postulated accident is reduced by washing the confinement atmosphere with fog sprays. This allows a low pressure release of confinement atmosphere containing fission products through filters...

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...

The report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark III type of containment. Ba...

Accident management strategies that have the potential to maintain containment integrity and control or mitigate the release of radioactivity following a severe accident at a boiling water reactor with a Mark II type of containment are identified and eval...

The report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark I type of containment. Base...

The Containment and Release Management project was carried out within the Reinforced Concerted Action Programme for Accident Management Support and partly financed by the European Union. In this report a prototype of an accident management support system ...

This paper discusses the three general classes of support provided by the Atmospheric Release Advisory Capability (ARAC) and describes the role played by ARAC in support of DOE during the Three Mile Island accident in March and April of 1979.

The vulnerability of a power distribution system in Bedford and Lexington, Massachusetts to power outages as a result of exposure to carbon fibers released in a commercial aviation accident in 1993 was examined. Possible crash scenarios at Logan Airport b...

The report identifies and evaluates accident management strategies that are potentially of value in maintaining containment integrity and controlling the release of radioactivity following a severe accident at a pressurized water reactor with an ice-conde...

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

Studies suggest that the risk of severe accidents during low power operation and/or shutdown conditions could be a significant fraction of the risk at full power operation. The Nuclear Regulatory Commission has begun two risk studies to evaluate the progression of severe accidents during these conditions: one for the Surry plant, a ...

Studies suggest that the risk of severe accidents during low power operation and/or shutdown conditions could be a significant fraction of the risk at full power operation. The Nuclear Regulatory Commission has begun two risk studies to evaluate the progression of severe accidents during these conditions: one for the Surry plant, a ...

This report documents an analysis of the radiological source terms for severe accidents in Light Water Reactors (LWR) using the Industry Degraded Core Rulemaking Program (IDCOR) integrated accident analysis methodology. The analytical study is an on-going effort sponsored by EPRI to investigate the sensitivity of the Modular Accident ...

This report describes the concepts of R/B, Total Fractional Release, and the Escape Factor and puts them into perspective.

Analyses have been carried out of the pressurization of the accident release mitigation structures of Soviet-designed VVER (Water-Cooled, Water-Moderated Energy Reactor) pressurized water reactors following large-break loss-of-coolant accidents. Specific VVER systems for which calculations were performed are the VVER-440 model V230, ...

1, 2003 Space Shuttle accident to the White House, Congress and the National Aeronautics and Space Administration... More August 21, 2003: ...

... Abstract : Release of Liquefied Natural Gas (LNG) from controlled containment, whether by accident, sabotage, or act of war, presents a number of ...

Mar 9, 2005 ... The DEIS examines potential environmental impacts under three scenarios: a normal launch; a launch accident with no radiological release ...

... It may be the result of an exterior accident that produces one of the ruptures listed, of which the first is the primary rupture, or the result of one ...

... because iodine can be unsafe at high doses. Radiation-induced thyroid cancer Nuclear accidents can release radioactive iodine into the environment, ...

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... 5 kilograms of tritium is about equivalent, in Curies, to the biologically active Chernobyl release. ... The Chernobyl accident: ...

... Descriptors : *RADIATION PROTECTION, *RADIATION DOSAGE, *REACTOR ACCIDENTS, *FISSION PRODUCT ACTIVITY, MATHEMATICAL ...

... for accidental release of large quantities of toxic chemicals and also recovery operations for accidents involving nuclear-powered space devices. ...

... Descriptors : *Blast waves, *Explosions, *Explosion effects, Damage, Accidents. Distribution Statement : APPROVED FOR PUBLIC RELEASE. ...

with safety (that is, with the possibility of a major accident that would release radioactivity in large amounts) has been the paramount issue for the designers and operators of...

avoided by some additional safety measure, the accident would very likely be released by another causeApplying STAMP in Accident Analysis Nancy Leveson, Mirna Daouk, Nicolas Dulac, and Karen Marais Massachusetts Institute of Technology April 7, 2003 Abstract: Accident models play a critical role in ...

The purpose of this report is to evaluate the two available models and determine the appropriate model for use in following waterborne release analyses. Additionally, this report will document the DB and BDB accidents to be used in the future study.

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

... Accession Number : ADD125916. Title : Risk to the Public from Carbon Fibers Released in Civil Aircraft Accidents. Descriptive ...

Confinement structures house many of the operating processes at the Savannah River Site (SRS). Under normal operating conditions, a confinement structure in conjunction with its associated ventilation systems prevents the release of radiological material to the environment. However, under potential accident conditions, the performance of the ventilation ...

...ACCIDENT PREVENTION PROVISIONS Hazard Assessment § 68.39 Documentation...on the release quantity and rate. (b) For alternative...on the release quantity and rate. (c) Documentation of...quantity released, release rate, and duration of...

Accident progression perspectives were gathered from the level 2 PRA analyses (the analysis of the accident after core damage has occurred involving the containment performance and the radionuclide release from the containment) described in the IPE submittals. Insights related to the containment failure modes, the ...

As part of the Oak Ridge Dose Reconstruction, a detailed assessment of {sup 131}I releases from radioactive lanthanum (RaLa) processing is being conducted. From 1944 through 1956, fuel slugs from Oak Ridge (X-10) and Hanford reactors were dissolved and processed at Oak Ridge to separate {sup 140}La for Los Alamos weapons development. Fuel cooling times were as short as several ...

As part of the Oak Ridge Dose Reconstruction, a detailed assessment of {sup 131}I releases from radioactive lanthanum (RaLa) processing is being conducted. From 1944 through 1956, fuel slugs from Oak Ridge (X-10) and Hanford reactors were dissolved and processed at Oak Ridge to separate {sup 140}La for Los Alamos weapons development. Fuel cooling times were as short as several ...

For evaluating the downwind, ground level exposure contours from carbon fiber dispersion, two fiber release scenarios were chosen. The first is the fire and explosion release in which all of the fibers are released instantaneously. This model applies to accident scenarios where an explosion follows a short-duration ...

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 ...

The Hot Fuel Examination Facility/South, located at the Idaho National Engineering Laboratory, supports the nation's nuclear energy program by providing a facility for destructive and nondestructive testing of reactor fuel and materials. Irradiated subassemblies and test devices are transferred from the adjacent Experimental Breeder Reactor II or other irradiation facilities into the hot ...