MARC - the NRPB methodology for assessing radiological consequences of accidental releases of activity

International Nuclear Information System (INIS)

Clarke, R.H.; Kelly, G.N.

1981-12-01

The National Radiological Protection Board has developed a methodology for the assessment of the public health related consequences of accidental releases of radionuclides from nuclear facilities. The methodology consists of a suite of computer programs which predict the transfer of activity from the point of release to the atmosphere through to the population. The suite of programs is entitled MARC; Methodology for Assessing Radiological Consequences. This report describes the overall framework and philosophy utilised within MARC. (author)

ACCI38 XL 2: a useful tool for dose assessment in case of accidental atmospheric releases of radionuclides

International Nuclear Information System (INIS)

Thomassin, A.; Merle-Szeremeta, A.

2002-01-01

In the scope of its assignments in the field of nuclear risks, the French Institute for Radiation protection and Nuclear Safety (IRSN) develops tools to assess the impact of nuclear facilities on their environment and surrounding populations. The code ACCI38 XL 2 is a tool dedicated to the assessment of integrated concentrations in the environment and of dosimetric consequences on man, in case of accidental atmospheric releases of radionuclides (up to 170 radionuclides). This code is widely used by IRSN for studies on accidents, mainly for the analysis of regulatory documents from nuclear operators. The aim of this communication is to present the main features of the model used in the code ACCI38 XL 2, and to give details about the code. After a general presentation of the model, a detailed description of atmospheric dispersion, transfer in the environment and radiological impact is given. Then, some information on parameters and limitations of the model and the code are presented

Control of accidental releases of hydrogen selenide in vented storage cabinets

Science.gov (United States)

Fthenakis, V. M.; Moskowitz, P. D.; Sproull, R. D.

1988-07-01

Highly toxic hydrogen selenide and hydrogen sulfide gases are used in the production of copper-indium-diselenide photovoltaic cells by reactive sputtering. In the event of an accident, these gases may be released to the atmosphere and pose hazards to public and occupational safety and health. This paper outlines an approach for designing systems for the control of these releases given the uncertainty in release conditions and lack of data on the chemical systems involved. Accidental releases of these gases in storage cabinets can be controlled by either a venturi and packed-bed scrubber and carbon adsorption bed, or containment scrubbing equipment followed by carbon adsorption. These systems can effectively reduce toxic gas emissions to levels needed to protect public health. The costs of these controls (˜0.012/Wp) are samll in comparison with current (˜6/Wp) and projected (˜I/Wp) production costs.

System to forecast health effects in order to determine necessary counter-measures in case an accidental atmospheric release

International Nuclear Information System (INIS)

Merchant, T.E.; Parmentier, N.

1985-01-01

In most accident situations involving radioactivity, the required data are the quantitative evaluation of the relevant constituents of the release and the dose factors applicable for these constituents. In the problem of an atmospheric release of radioactivity a third group of data also comes into play, the meteorological conditions at the site and time of the accident. The solution to this problem is the construction of a computer code which, by employing acquired compositions of the release as well as physical accident conditions (at the time of the incident), can be effectively run to calculate and present useful dosimetric data. To meet this need, an interactive computer program has been constructed by the Institut de Protection et de Surete Nucleaire of the Commissariat a l'Energie Atomique which calculates the gamut of dosimetric and statistical information for a region of accidental radiological concern. Application of the program is such that it outputs dosimetric information and other important data in a form independent of the site under consideration, allowing, at the same time, the computation of the same information for areas where demographics show them to be of the highest radiological concern. All this is done after requiring minimal user input

Historical Doses from Tritiated Water and Tritiated Hydrogen Gas Released to the Atmosphere from Lawrence Livermore National Laboratory (LLNL). Part 5. Accidental Releases

Energy Technology Data Exchange (ETDEWEB)

Peterson, S

2007-08-15

Over the course of fifty-three years, LLNL had six acute releases of tritiated hydrogen gas (HT) and one acute release of tritiated water vapor (HTO) that were too large relative to the annual releases to be included as part of the annual releases from normal operations detailed in Parts 3 and 4 of the Tritium Dose Reconstruction (TDR). Sandia National Laboratories/California (SNL/CA) had one such release of HT and one of HTO. Doses to the maximally exposed individual (MEI) for these accidents have been modeled using an equation derived from the time-dependent tritium model, UFOTRI, and parameter values based on expert judgment. All of these acute releases are described in this report. Doses that could not have been exceeded from the large HT releases of 1965 and 1970 were calculated to be 43 {micro}Sv (4.3 mrem) and 120 {micro}Sv (12 mrem) to an adult, respectively. Two published sets of dose predictions for the accidental HT release in 1970 are compared with the dose predictions of this TDR. The highest predicted dose was for an acute release of HTO in 1954. For this release, the dose that could not have been exceeded was estimated to have been 2 mSv (200 mrem), although, because of the high uncertainty about the predictions, the likely dose may have been as low as 360 {micro}Sv (36 mrem) or less. The estimated maximum exposures from the accidental releases were such that no adverse health effects would be expected. Appendix A lists all accidents and large routine puff releases that have occurred at LLNL and SNL/CA between 1953 and 2005. Appendix B describes the processes unique to tritium that must be modeled after an acute release, some of the time-dependent tritium models being used today, and the results of tests of these models.

The Bulgarian Emergency Response System for dose assessment in the early stage of accidental releases to the atmosphere

International Nuclear Information System (INIS)

Syrakov, D.; Veleva, B.; Prodanova, M.; Popova, T.; Kolarova, M.

2009-01-01

The Bulgarian Emergency Response System (BERS) is being developed in the Bulgarian National Institute of Meteorology and Hydrology since 1994. BERS is based on numerical weather forecast meteorological information and a numerical long-range dispersion model accounting for the transport, dispersion, chemical and radioactive transformations of pollutants. In the present paper, the further development of this system for a mixture of radioactive gaseous and aerosol pollutants is described. The basic module for the BERS, the numerical dispersion model EMAP, is upgraded with a 'dose calculation block'. Two scenarios for hypothetical accidental atmospheric releases from two NPPs, one in Western, and the other in Eastern Europe, are numerically simulated. The effective doses from external irradiation, from air submersion and ground shinning, effective dose from inhalation and absorbed dose by thyroid gland formed by 37 different radionuclides, significant for the early stage of a nuclear accident, are calculated as dose fields for both case studies and discussed

Maxine: A spreadsheet for estimating dose from chronic atmospheric radioactive releases

Energy Technology Data Exchange (ETDEWEB)

Jannik, Tim [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bell, Evaleigh [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-07-24

MAXINE is an EXCEL© spreadsheet, which is used to estimate dose to individuals for routine and accidental atmospheric releases of radioactive materials. MAXINE does not contain an atmospheric dispersion model, but rather doses are estimated using air and ground concentrations as input. Minimal input is required to run the program and site specific parameters are used when possible. Complete code description, verification of models, and user’s manual have been included.

Comparison of numerical models for calculating dispersion from accidental releases of pollutants

Energy Technology Data Exchange (ETDEWEB)

Pepper, D W [Savannah River Lab., Aiken, SC; Cooper, R E; Baker, A J

1982-01-01

A modular, data-based system approach has been developed to facilitate computational simulation of multi-dimensional pollutant dispersion in atmospheric, steam, estuary, and groundwater applications. This system is used to assess effects of accidental releases of pollutants to the environment. Model sophistication ranges from simple statistical to complex three-dimensional numerical methods. The system used specifies desired degree of model sophistication from a terminal. The model used depends on the particular type of problem being solved, and on a basis of merit related to computer cost. The results of prediction for several model problems are presented.

Atmospheric Release Advisory Capability (ARAC)

International Nuclear Information System (INIS)

Dickerson, M.H.

1975-01-01

The chief purpose of ARAC data acquisition program is to provide site officials, who are responsible for ensuring maximum health protection for the endangered site personnel and public, with estimates of the effects of atmospheric releases of hazardous material as rapidly and accurately as possible. ARAC is in the initial stages of being implemented and is therefore susceptible to changes before it reaches its final form. However the concept of ARAC is fully developed and was successfully demonstrated during a feasibility study conducted in June 1974, as a joint effort between the Savannah River Laboratory (SRL) and Lawrence Livermore Laboratory (LLL). Additional tests between SRL and LLL are scheduled for December 1975. While the immediate goal is the application of ARAC to assist a limited number of ERDA sites, the system is designed with sufficient flexibility to permit expanding the service to a large number of sites. Success in ARAC application should provide nuclear facilities with a means to handle better the urgent questions concerning the potential accidental hazards from atmospheric releases in addition to providing the sites with a capability to assess the effort of their normal operations

Radioactive releases into the environment under accidental conditions

International Nuclear Information System (INIS)

Beninson, D.

1976-01-01

Although accidents involving the release of radioactive materials and the unplanned exposure of people can occur at any stage of the nuclear fuel cycle, most attention has been focused on reactor accidents. Although no power reactor accidents involving exposure of the public have yet occured, it should be recognized that the probability of such accidental releases cannot be reduced to zero. Since the inventory of radioactive materials in power reactors is very large, it is usual to postulate, for safety assessments, that a release of fission products takes place in spite of all protective measures. This postulated release is of importance for reactor siting and for preparing emergency plans. (HP) [de

National Atmospheric Release Advisory Center (NARAC) Capabilities for Homeland Security

Energy Technology Data Exchange (ETDEWEB)

Sugiyama, G; Nasstrom, J; Baskett, R; Simpson, M

2010-03-08

The Department of Energy's National Atmospheric Release Advisory Center (NARAC) provides critical information during hazardous airborne releases as part of an integrated national preparedness and response strategy. Located at Lawrence Livermore National Laboratory, NARAC provides 24/7 tools and expert services to map the spread of hazardous material accidentally or intentionally released into the atmosphere. NARAC graphical products show affected areas and populations, potential casualties, and health effect or protective action guideline levels. LLNL experts produce quality-assured analyses based on field data to assist decision makers and responders. NARAC staff and collaborators conduct research and development into new science, tools, capabilities, and technologies in strategically important areas related to airborne transport and fate modeling and emergency response. This paper provides a brief overview of some of NARAC's activities, capabilities, and research and development.

Dispersion modeling of accidental releases of toxic gases - utility for the fire brigades.

Science.gov (United States)

Stenzel, S.; Baumann-Stanzer, K.

2009-09-01

Several air dispersion models are available for prediction and simulation of the hazard areas associated with accidental releases of toxic gases. The most model packages (commercial or free of charge) include a chemical database, an intuitive graphical user interface (GUI) and automated graphical output for effective presentation of results. The models are designed especially for analyzing different accidental toxic release scenarios ("worst-case scenarios”), preparing emergency response plans and optimal countermeasures as well as for real-time risk assessment and management. The research project RETOMOD (reference scenarios calculations for toxic gas releases - model systems and their utility for the fire brigade) was conducted by the Central Institute for Meteorology and Geodynamics (ZAMG) in cooperation with the Viennese fire brigade, OMV Refining & Marketing GmbH and Synex Ries & Greßlehner GmbH. RETOMOD was funded by the KIRAS safety research program of the Austrian Ministry of Transport, Innovation and Technology (www.kiras.at). The main tasks of this project were 1. Sensitivity study and optimization of the meteorological input for modeling of the hazard areas (human exposure) during the accidental toxic releases. 2. Comparison of several model packages (based on reference scenarios) in order to estimate the utility for the fire brigades. For the purpose of our study the following models were tested and compared: ALOHA (Areal Location of Hazardous atmosphere, EPA), MEMPLEX (Keudel av-Technik GmbH), Trace (Safer System), Breeze (Trinity Consulting), SAM (Engineering office Lohmeyer). A set of reference scenarios for Chlorine, Ammoniac, Butane and Petrol were proceed, with the models above, in order to predict and estimate the human exposure during the event. Furthermore, the application of the observation-based analysis and forecasting system INCA, developed in the Central Institute for Meteorology and Geodynamics (ZAMG) in case of toxic release was

Dispersion modeling of accidental releases of toxic gases - Comparison of the models and their utility for the fire brigades.

Science.gov (United States)

Stenzel, S.; Baumann-Stanzer, K.

2009-04-01

Dispersion modeling of accidental releases of toxic gases - Comparison of the models and their utility for the fire brigades. Sirma Stenzel, Kathrin Baumann-Stanzer In the case of accidental release of hazardous gases in the atmosphere, the emergency responders need a reliable and fast tool to assess the possible consequences and apply the optimal countermeasures. For hazard prediction and simulation of the hazard zones a number of air dispersion models are available. The most model packages (commercial or free of charge) include a chemical database, an intuitive graphical user interface (GUI) and automated graphical output for display the results, they are easy to use and can operate fast and effective during stress situations. The models are designed especially for analyzing different accidental toxic release scenarios ("worst-case scenarios"), preparing emergency response plans and optimal countermeasures as well as for real-time risk assessment and management. There are also possibilities for model direct coupling to automatic meteorological stations, in order to avoid uncertainties in the model output due to insufficient or incorrect meteorological data. Another key problem in coping with accidental toxic release is the relative width spectrum of regulations and values, like IDLH, ERPG, AEGL, MAK etc. and the different criteria for their application. Since the particulate emergency responders and organizations require for their purposes unequal regulations and values, it is quite difficult to predict the individual hazard areas. There are a quite number of research studies and investigations coping with the problem, anyway the end decision is up to the authorities. The research project RETOMOD (reference scenarios calculations for toxic gas releases - model systems and their utility for the fire brigade) was conducted by the Central Institute for Meteorology and Geodynamics (ZAMG) in cooperation with the Vienna fire brigade, OMV Refining & Marketing GmbH and

Analysis of tritium releases to the atmosphere by a CTR

International Nuclear Information System (INIS)

Renne, D.S.; Sandusky, W.F.; Dana, M.T.

1975-08-01

Removal by atmospheric processes of routinely and accidentally released tritium from a controlled thermonuclear reactor (CTR) was investigated. Based on previous studies, the assumed form of the tritium for this analysis was HTO or tritiated water vapor. Assuming a CTR operation in Morris, Illinois, surface water and ground-level air concentration values of tritium were computed for three space (or time) scales: local (50 Km of a plant), regional (up to 1000 Km of the plant), and global

Computer programs at SRL to evaluate environmental effects SRP operations and postulated accidental releases

International Nuclear Information System (INIS)

Cooper, R.E.

1975-09-01

Savannah River Plant operations unavoidably result in the release of some chemical and radioactive effluents to the environs. The most environmentally significant releases are gaseous effluents to the atmosphere; computer codes dealing with these atmospheric releases are discussed in this report. There is a wide variety of effluents, both chemical and radioactive, to be considered, and each must be correlated with meteorological dispersion data as a function of time to estimate the environmental effects. In addition, large inventories of toxic and radioactive materials in some facilities represent a potential for accidental releases. Accidents are postulated for these facilities, and the environmental effects of resulting releases are again evaluated by correlating with meteorological dispersion data. In accordance with AEC Regulatory Guide 23, a 2-year meteorological data base is used in performing all analyses. Due to the diversity of possible releases and the large meteorological data base, the environmental analyses are necessarily performed with the aid of a large computer facility. Several computer programs have been written to facilitate these analyses according to the type of analysis desired. The computer programs described in this report are basically of three categories: probability distributions of estimated concentrations or doses as a function of distance from a point of origin, estimates of average concentrations or doses over a specified time period such as annual averages, and some miscellaneous programs in support of the first two categories to optimize the use of the computing facility. A complete documentation of each program is included with a program listing and sample input-output

PAVAN, Atmospheric Dispersion of Radioactive Releases from Nuclear Power Plants

International Nuclear Information System (INIS)

2001-01-01

1 - Description of program or function: PAVAN estimates down-wind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Options can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. 2 - Method of solution: Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases or evaluated releases from free-standing stacks. The X/Q calculations are based on the theory that material released to the atmosphere will be normally distributed (Gaussian) about the plume centerline. A straight-line trajectory is assumed between the point of release and all distances for which X/Q values are calculated. 3 - Restrictions on the complexity of the problem: - The code cannot handle multiple emission sources

Methodology for estimating accidental radioactive releases in nuclear waste management

International Nuclear Information System (INIS)

Levy, H.B.

1979-01-01

Estimation of the risks of accidental radioactive releases is necessary in assessing the safety of any nuclear waste management system. The case of a radioactive waste form enclosed in a barrier system is considered. Two test calculations were carried out

Review of decontamination and clean-up techniques for use in the UK following accidental releases of radioactivity to the environment

International Nuclear Information System (INIS)

Brown, J.; Cooper, J.R.; Jones, J.A.; Flaws, L.; McGeary, R.; Spooner, J.

1996-10-01

This review examines decontamination and clean-up methodologies that may be applied following an accidental release of radionuclides to the atmosphere in the UK. An accidental release of radionuclides to the environment could cause contamination of land and property, and may necessitate movement of the resident population to reduce their exposure. Decontamination procedures may reduce the level of contamination and, in determining whether to implement such procedures in an affected area, it is necessary to weigh the effectiveness of the techniques against the associated economic costs and other disadvantages. The report gives a review of available methods of decontamination and clean-up in terms of the effectiveness of the various methods to remove activity from building or land surfaces and dose saved. It also considers associated disadvantages, costs, clean-up rates for land and buildings, waste disposal implications, and personnel and resource requirements. On the basis of these factors, the techniques are prioritised and overall strategies for decontamination following releases of both fission products and alpha emitters are presented. (author)

Method and apparatus for controlling accidental releases of tritium

International Nuclear Information System (INIS)

Galloway, T.R.

1980-01-01

An improvement in a tritium control system based on a catalytic oxidation reactor is provided wherein accidental releases of tritium into room air are controlled by flooding the catalytic oxidation reactor with hydrogen when the tritium concentration in the room air exceeds a specified limit. The sudden flooding with hydrogen heats the catalyst to a high temperature within seconds, thereby greatly increasing the catalytic oxidation rate of tritium to tritiated water vapor. Thus, the catalyst is heated only when needed. In addition to the heating effect, the hydrogen flow also swamps the tritium and further reduces the tritium release

Method and apparatus for controlling accidental releases of tritium

Science.gov (United States)

Galloway, Terry R. [Berkeley, CA

1980-04-01

An improvement in a tritium control system based on a catalytic oxidation reactor wherein accidental releases of tritium into room air are controlled by flooding the catalytic oxidation reactor with hydrogen when the tritium concentration in the room air exceeds a specified limit. The sudden flooding with hydrogen heats the catalyst to a high temperature within seconds, thereby greatly increasing the catalytic oxidation rate of tritium to tritiated water vapor. Thus, the catalyst is heated only when needed. In addition to the heating effect, the hydrogen flow also swamps the tritium and further reduces the tritium release.

Accidental releases of radionuclides: a preliminary study of the consequences of land contamination

International Nuclear Information System (INIS)

Simmonds, J.R.; Haywood, S.M.; Linsley, G.S.

1982-10-01

The long term consequences of land contamination from accidental releases of activity from thermal reactors are examined. The radiological consequences are assessed using an analysis of the exposure of individuals and the population to ground deposits of the radionuclides released. The contribution of the different nuclides in the release by their various exposure routes to the irradiation of man are calculated as a function of time after release and the most radiologically important are identified. A preliminary assessment is made of off-site economic and social consequences of accidental releases by estimating the areas of land which would be affected by the introduction of countermeasures to control individual radiation exposure due to external irradiation from ground deposits (relocation of populations), and the intake of radionuclides contained in locally produced foodstuffs (restrictions on food production). The areas where administrative controls would be necessary decline in size with time after the release; estimates are made of this time-dependent behaviour using dynamic environmental transfer models. Finally, the collective doses saved by the introduction of countermeasures are estimated using population and agricultural distribution data for a rural location in the United Kingdom. (author)

Study of applying the Atmospheric Release Advisory Capability to nuclear power plants

International Nuclear Information System (INIS)

Orphan, R.C.

1978-06-01

Each utility licensee for a nuclear power reactor is required to minimize the adverse effects from an accidental radionuclide release into the atmosphere. In the past the ability to forecast quantitatively the extent of the hazard from such a release has been limited. Now powerful atmospheric modeling techniques are available to assist nuclear reactor site officials with greatly improved assessments. Lawrence Livermore Laboratory (LLL) has developed a prototype system called the Atmospheric Release Advisory Capability (ARAC) which is designed to integrate the modeling with advanced sensors, data handling techniques, and weather data in order to provide timely, usable advisories to the site officials. The purpose of this project is to examine the ways and means of adapting ARAC for application to many nuclear power reactors widely dispersed across the nation. The project will emphasize the management aspects, including government-industry relationships, technology transfer, organizational structure, staffing, implementing procedures, and costs. Benefits and costs for several alternative systems will be compared. The results will be reviewed and evaluated by the management and staff of the ARAC project at LLL and also by selected staff members of the sponsoring government agency

UFOING: A program for assessing the off-site consequences from ingestion of accidentally released radionuclides

International Nuclear Information System (INIS)

Steinhauer, C.

1988-12-01

The program UFOING estimates foodchain-related consequences following accidental releases of radionuclides to the atmosphere. It was developed as a stand-alone supplement to the accident consequence assessment program system UFOMOD to allow faster and more detailed investigations of the consequences arising from the foodchain pathways than possible with the version of UFOING which is implemented in UFOMOD. For assumed releases at different times of the year, age dependent individual doses, collective doses, individual risks for fatal stochastic somatic health effects as a function of time, the total numbers of the effects, and the areas affected by foodbans together with the estimated duration of the bans are calculated. In addition, percentage contributions of radionuclides and foodstuffs to the doses and risks can be evaluated. In the first part of this report, an overview over the program is given. The other parts contain a user's guide, a program guide, and descriptions of the data employed and of the version of UFOING which is implemented in UFOMOD. (orig.) [de

A 'Puff' dispersion model for routine and accidental releases

International Nuclear Information System (INIS)

Grsic, Z.; Rajkovic, B.; Milutinovic, P.

1999-01-01

A Puff dispersion model for accidental or routine releases is presented. This model was used as a constitutive part of an automatic meteorological station.All measured quantities are continuously displayed on PC monitor in a digital and graphical form, they are averaging every 10 minutes and sending to the civil information center of Belgrade. In the paper simulation of a pollutant plume dispersion from The oil refinery 'Pancevo', on April 18 th 1999 is presented. (author)

Simulated atmospheric disperison of radioactive material released in an urban area

International Nuclear Information System (INIS)

Akins, R.E.; Church, H.W.; Tierney, M.S.

1977-01-01

A combination of Gaussian plume and particle-in-cell techniques is used to simulate the atmospheric transport and dispersion of a puff release of radioactive material. The release is caused by an accident that is assumed to occur during the shipment of the radioactive material through central New York City. The simulation provides estimates of volumetric and surface concentrations of the dispersed material that are used to predict radiation doses incurred by the City's population in the event of an accidental release. In the simulation, the release point is arbitrary and the material is assumed to be either a gas or fine particles. The Gaussian plume model follows cloud concentrations from the release time until times when transport over distances up to 500 m has been achieved. The released cloud may stabilize at street level or above the mean buildings height; at a street intersection or in the middle of the block. The possibility of the formation of multiple clouds, owing to circumstances of wind flow direction and street geometry, is allowed

The atmospheric release advisory capability (ARAC): A federal emergency response capability

International Nuclear Information System (INIS)

Dickerson, M.H.; Sullivan, T.J.

1988-03-01

The Atmospheric Release Capability (ARAC) is a Department of Energy (DOE)-sponsored emergency-response service set up to provide real-time prediction of the dose levels and the extent of surface contamination resulting from a broad range of possible occurrences (accidents, spills, extortion threats involving nuclear material, reentry of nuclear-powered satellites, and atmospheric nuclear tests) that could involve the release of airborne radioactive material. During the past decade, ARAC has responded to more than 150 real-time situations, including exercises. The most notable responses include the Three Mile Island accident in Pennsylvania, the Titan II missile accident in Arkansas, the reentry of the USSR's COSMOS-954 into the atmosphere over Canada, the accidental release of uranium hexafluoride from the Sequoyah Facility accident in Oklahoma, and, most recently, the Chernobyl reactor accident in the Soviet Union. ARAC currently supports the emergency-preparedness plans at 50 Department of Defense (DOD) and DOE sites within the US and also responds to accidents that happen elsewhere. Our ARAC center serves as the focal point for data acquisition, data analysis and assessments during a response, using a computer-based communication network to acquire real-time weather data from the accident site and the surrounding region, as well as pertinent accident information. Its three-dimensional computer models for atmospheric dispersion, MATHEW and ADPIC, digest all this information and produce the predictions used in accident assessment. 9 refs., 6 figs., 1 tab

Distributed emergency response system to model dispersion and deposition of atmospheric releases

International Nuclear Information System (INIS)

Taylor, S.S.

1985-04-01

Aging hardware and software and increasing commitments by the Departments of Energy and Defense have led us to develop a new, expanded system to replace the existing Atmospheric Release Advisory Capability (ARAC) system. This distributed, computer-based, emergency response system is used by state and federal agencies to assess the environmental health hazards resulting from an accidental release of radioactive material into the atmosphere. Like its predecessor, the expanded system uses local meteorology (e.g., wind speed and wind direction), as well as terrain information, to simulate the transport and dispersion of the airborne material. The system also calculates deposition and dose and displays them graphically over base maps of the local geography for use by on-site authorities. This paper discusses the limitations of the existing ARAC system. It also discusses the components and functionality of the new system, the technical difficulties encountered and resolved in its design and implementation, and the software methodologies and tools employed in its development

The use of consequence modelling in assessing accidental releases of activity

International Nuclear Information System (INIS)

Clarke, R.H.; Hemming, C.R.; Kelly, G.N.

1982-01-01

The radiological consequences of an accidental release can be expressed as the number of health effects in the exposed population and its descendents, and the economic and social implications that may result from restrictions placed on the consumption of foodstuffs, or on the occupation of domestic and commercial premises. For any given release of activity there will be a probability distribution of consequences which will depend on the meteorological characteristics and demographic data particular to the release location. The characteristics of this distribution should be important in reaching judgements on the acceptability of a given site or design. The relative importance of the different endpoints is analysed and the influence of the release location on the resulting distribution is considered. (author)

Development of a code to simulate dispersion of atmospheric released tritium gas in the environmental media and to evaluate doses. TRIDOSE

International Nuclear Information System (INIS)

Murata, Mikio; Noguchi, Hiroshi; Yokoyama, Sumi

2000-11-01

A computer code (TRIDOSE) was developed to assess the environmental impact of atmospheric released tritium gas (T 2 ) from nuclear fusion related facilities. The TRIDOSE simulates dispersion of T 2 and resultant HTO in the atmosphere, land, plant, water and foods in the environment, and evaluates contamination concentrations in the media and exposure doses. A part of the mathematical models in TRIDOSE were verified by comparison of the calculation with the results of the short range (400 m) dispersion experiment of HT gas performed in Canada postulating a short-time (30 minutes) accidental release. (author)

Accidental Continuous Releases from Coal Processing in Semi-Confined Environment

Directory of Open Access Journals (Sweden)

Bruno Fabiano

2013-09-01

Full Text Available Notwithstanding the enforcement of ATEX EU Directives (94/9/EC of 23 March 1994 and safety management system application, explosions in the coal sector still claim lives and cause huge economic losses. Even a consolidated activity like coke dry distillation allows the opportunity of preventing explosion risk connected to fugitive emissions of coke oven gas. Considering accidental releases under semi-confined conditions, a simplified mathematical approach to the maximum allowed gaseous build-up is developed on the basis of the intrinsic hazards of the released compound. The results will help identifying and assessing low rate release consequences therefore to set-up appropriate prevention and control measures. The developed methodology was tested at the real-scale and validated by numerical computational fluid dynamics (CFD simulations showing the effectiveness of the methodology to evaluate and mitigate the risk connected to confined hazardous releases.

Evaluation and mitigation of accidental releases of radioactivity

International Nuclear Information System (INIS)

Bruessermann, K.

1982-12-01

One result of the workshop was, that even in the case of severe accident sequences in modern nuclear power plants (other facilities were not discussed), there will be enough time to take active measures in order to lower the emissions and to diminish the consequences inside and outside of the plant. On the whole, new evidence from Harrisburg show that previously estimated accidental emissions, especially of radiologically relevant nuclides, have been rather conservative and that much lower emissions are possible, if the above measures are considered. Under accident conditions, models to predict radiation exposure must be applied under the event of a short-term release. (orig./DG) [de

Development of a code to simulate dispersion of atmospheric released tritium gas in the environmental media and to evaluate doses. TRIDOSE

Energy Technology Data Exchange (ETDEWEB)

Murata, Mikio [Nuclear Engineering Co., Ltd., Hitachi, Ibaraki (Japan); Noguchi, Hiroshi; Yokoyama, Sumi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2000-11-01

A computer code (TRIDOSE) was developed to assess the environmental impact of atmospheric released tritium gas (T{sub 2}) from nuclear fusion related facilities. The TRIDOSE simulates dispersion of T{sub 2} and resultant HTO in the atmosphere, land, plant, water and foods in the environment, and evaluates contamination concentrations in the media and exposure doses. A part of the mathematical models in TRIDOSE were verified by comparison of the calculation with the results of the short range (400 m) dispersion experiment of HT gas performed in Canada postulating a short-time (30 minutes) accidental release. (author)

Dose mortality relationships: implications for hypothetical accidental releases from FBRs

International Nuclear Information System (INIS)

Kelly, G.N.

1979-01-01

A summary is given of the findings detailed in the most recent of a series of radiological studies of a liquid metal-cooled fast breeder reactor (Kelly, G.N. Simmonds, J.R. Smith, H. and Stather, J.W., The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: sensitivity to the dose-effect relationships adopted for early biological effects, Harwell, National Radiological Protection Board, NRPB-R87. London, HMSO (1979)). The results have indicated those areas where effort might be most profitably directed to improve the reliability of the predicted consequences. The composition of the released activity has been shown to have a marked influence on the sensitivity of the predicted consequences, and application of simple supportive medical treatment has a potential for reducing the predicted consequences by factors of up to an order of magnitude, depending on the composition of the release. (UK)

Dose assessment under incidental and accidental conditions

International Nuclear Information System (INIS)

Huebschmann, W.G.

1988-01-01

Dose assessment for the licesing process of a nuclear power plant covers the routine release of radioactive substances into the atmosphere as well as releases due to incidents. Source terms for these incidents are evaluated by the detailed incident analysis of the plant. The types of incidents to be covered are determined in the FRG by the ''Stoerfall-Leitlinien'' of the Ministry of the Interior. The calculation of dose equivalents in the environment of the plant differs from the calculation of doses due to routine releases, as incidents are single events occuring at undeterminate time, and the results must be conservative. Some details are being described. During the operation of the plant it is essential to measure not only the radioactivity release rates but also the necessary meteorological parameters for the instantaneous determination of the atmospheric dispersion in case of incidental or accidental releases of radioactivity. This instantaneous assessment assists in taking measurements of ground contamination and in deciding about countermeasures for the protection of plant personnell and population. (author) [pt

Fact Sheet: Clean Air Act Section 112(r): Accidental Release Prevention / Risk Management Plan Rule

Science.gov (United States)

EPA is required to publish regulations and guidance for chemical accident prevention at facilities that pose the greatest risk of harm from accidental releases of regulated flammable and toxic substances above threshold quantities.

Toxic vapor concentrations in the control room following a postulated accidental release

International Nuclear Information System (INIS)

Wing, J.

1979-05-01

An acceptable method is presented for calculating the vapor concentrations in a control room as a function of time after a postulated accidental release. Included are the mathematical formulas for computing the rates of vaporization and evaporation of liquid spills, the vapor dispersion in air, and the control room air exchange. A list of toxic chemicals and their physical properties is also given

Intermediate range atmospheric transport and technology assessments: nuclear pollutants

International Nuclear Information System (INIS)

Rohwer, P.S.; Hoffman, F.O.; Miller, C.W.

1981-01-01

Mathematical models have been used to assess potential impacts of radioactivity releases during all phases of our country's development of nuclear power. Experience to date has shown that in terms of potential dose to man, the most significant releases of radioactivity from nuclear fuel cycle facilities are those to the atmosphere. Our ability to predict atmospheric dispersion will, therefore, ultimately affect our capability to understand and assess the significance of both routine and accidental discharges of radionuclides. Assessment of potential radiological exposures from postulated routine and accidental releases of radionuclides from the fast-breeder reactor will require the use of atmospheric dispersion models, and the design, siting, and licensing of breeder reactor fuel cycle facilities will be influenced by the predictions made by these models

CRRIS, Health Risk Assessment from Atmospheric Releases of Radionuclides

International Nuclear Information System (INIS)

1999-01-01

. ANEMOS employs a Gaussian plume atmospheric dispersion model. RETADD-II is based on long-range trajectory estimates using upper-air wind data. ANEMOS, RETADD, TERRA, MLSOIL and ANDROS solve differential equations that describe decay and ingrowth. PRIMUS and ANDROS can be characterized as bookkeeping rather than computational programs. 3 - Restrictions on the complexity of the problem: ANEMOS is not to be used for short-term or accidental releases. It is appropriate only for chronic releases. It models only one source per run. Multiple ANEMOS results may be combined using SUMIT. MLSOIL does not allow upward transport of radionuclides. MLSOIL will truncate radionuclide chains of length greater than 20. All sample cases in this package are to be considered demonstration assessments. No special significance should be attached to the choices of parameters and options for these jobs

Simulation of pulsed accidental energy release in a reactor core

International Nuclear Information System (INIS)

Ryshanskii, V.A.; Ivanov, A.G.; Uskov, A.A.

1995-01-01

At the present time the strength of the load-bearing members of VVER and fast reactors during a hypothetical accident is ordinarily investigated in model experiments [1]. A power burst during an accident is simulated by a nonnuclear exothermal reaction in water, which simulates the coolant and fills the model. The problem is to make the correct choice of the simulator of the accidental energy burst as an effective (i.e., sufficiently high working capacity) source of dangerous loads, corresponding to the conditions of an accident. What factors and parameters determine the energy release? The answers to these questions are contradictory

Real-time computing of the environmental consequences of an atmospheric accidental release of radioactive material: user's point of view

International Nuclear Information System (INIS)

Boeri, G.; Caracciolo, R.; Dickerson, M.

1985-07-01

All calculations of the consequences of an atmospheric release must start with atmospheric dispersion calculations. Time factors make external and inhalation dose estimates of immediate concern closely followed by ground contamination of land, pastures and onch agricultural crops. In general, the difficulties in modeling the source term and atmospheric transport and diffusion account for most of the error in calculating the dose to man. Thus, sophisticated treatment of the dose part of the calculating is not usually justified, though the relative distribution of dose in individual organs may be needed for correct decision marking. This paper emphasizes the atmospheric transport and diffusion part of the dose estimate and relates how this calculation can be used to estimate dose. 12 refs

Nuclear power: Accidental releases - principles of public health action

International Nuclear Information System (INIS)

1984-01-01

This report is based on the collective knowledge and experience of the members of a Working Group, convened by WHO in collaboration with the Government of Belgium in Brussels on 23-27 November 1981, to discuss and appraise the different actions that might be taken following accidental radioactive releases from nuclear plants. It does not provide detailed technical data, but broadly surveys the rational basis for decision-making, indicating the present position as assessed by members of the Working Group. Four major disciplines (radiological protection, health physics, environmental science and technology, and human biology) and three main professional categories (physicians, engineers and physicists) were represented, providing a comprehensive multidisciplinary approach to the topic. The purpose of this report is to give guidance to national authorities on how to develop the capacity to take action in a nuclear emergency

Forecasting consequences of accidental release: how reliable are current assessment models

International Nuclear Information System (INIS)

Rohwer, P.S.; Hoffman, F.O.; Miller, C.W.

1983-01-01

This paper focuses on uncertainties in model output used to assess accidents. We begin by reviewing the historical development of assessment models and the associated interest in uncertainties as these evolutionary processes occurred in the United States. This is followed by a description of the sources of uncertainties in assessment calculations. Types of models appropriate for assessment of accidents are identified. A summary of results from our analysis of uncertainty is provided in results obtained with current methodology for assessing routine and accidental radionuclide releases to the environment. We conclude with discussion of preferred procedures and suggested future directions to improve the state-of-the-art of radiological assessments

Estimation of the environmental or radiological impact in the event of accidental release of radionuclides in a DCLL fusion reactor; Estimacion del impacto radiologico ambiental en caso de liberacion accidental de radionucleidos en un reactor de fusion DCLL

Energy Technology Data Exchange (ETDEWEB)

Palermo, I.; Gomez Ros, J. M.; Sanz, J.; Mota, F.

2013-07-01

Tritium production and activation in the LiPb products can pose a radiological risk in the event of accidental release in a fusion reactor. Within the research programme Consolider TECNO{sub F}US (CSD2008-079) fusion technology has developed a design for a reactor with regenerative wrap with dual refrigeration (DCLL). The purpose of this communication is to present estimates of the radiological impact derived from an accidental release of radionuclides from the circuit of LiPb provinients. (Author)

Summary of accidental releases of radioactivity detected off the Nevada Test Site, 1963--1986

International Nuclear Information System (INIS)

Patzer, R.G.; Phillips, W.G.; Grossman, R.F.; Black, S.C.; Costa, C.F.

1988-08-01

Of the more than 450 underground nuclear explosives tests conducted at the Nevada Test Site from August 1963 (signing of the Limited Test Ban Treaty) through the end of 1986, only 23 accidentally released radioactivity that was detectable beyond the boundary of the NTS. Of these 23, 4 were detectable off the NTS only by aircraft while the remainder were detectable by ground monitoring instruments. Since the Baneberry venting of December 1970, only two tests released radioactivity that was detectable off the NTS, and this was a seepage of radioactive noble gases. None of these releases from underground tests designed for complete containment caused exposure of the population living in the area that exceeded standards recommended by national and international radiation protection agencies. This report summarizes the releases from each of the tests, describes the monitoring that was conducted, and lists the location of the maximum exposure

A comparison of alternative methods of calculating complementary cumulative distribution functions of health effects following an atmospheric radioactive release

International Nuclear Information System (INIS)

Ponting, A.C.; Nair, S.

1984-04-01

A concept extensively used in studying the consequences of accidental atmospheric radioactive releases is that of the Complementary Cumulative Distribution Function, CCDF. Various methods of calculating CCDFs have been developed with particular applications in putting degraded core accidents in perspective and in identifying release sequences leading to high risks. This note compares three methods with specific reference to their accuracy and computational efficiency. For two of the methods (that used in the US Reactor Safety Study code CRAC2 and extended version of that method), the effects of varying the sector width and considering site-specific population distributions have been determined. For the third method it is only necessary to consider the effects of site-specific population distributions. (author)

Individual dose due to radioactivity accidental release from fusion reactor

Energy Technology Data Exchange (ETDEWEB)

Nie, Baojie [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China); Ni, Muyi, E-mail: muyi.ni@fds.org.cn [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); Wei, Shiping [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China)

2017-04-05

Highlights: • Conservative early dose of different unit fusion radioactivity release were assessed. • Data of accident level in INES for fusion reactor were proposed. • Method of environmental restoration time after fusion accident was proposed. • The maximum possible accident level for ITER like fusion reactor is 6. • We need 34–52 years to live after the fusion hypothetical accident. - Abstract: As an important index shaping the design of fusion safety system, evaluation of public radiation consequences have risen as a hot topic on the way to develop fusion energy. In this work, the comprehensive public early dose was evaluated due to unit gram tritium (HT/HTO), activated dust, activated corrosion products (ACPs) and activated gases accidental release from ITER like fusion reactor. Meanwhile, considering that we cannot completely eliminate the occurrence likelihood of multi-failure of vacuum vessel and tokamak building, we conservatively evaluated the public radiation consequences and environment restoration after the worst hypothetical accident preliminarily. The comparison results show early dose of different unit radioactivity release under different conditions. After further performing the radiation consequences, we find it possible that the hypothetical accident for ITER like fusion reactor would result in a level 6 accident according to INES, not appear level 7 like Chernobyl or Fukushima accidents. And from the point of environment restoration, we need at least 69 years for case 1 (1 kg HTO and 1000 kg dust release) and 34–52 years for case 2 (1 kg HTO and 10kg–100 kg dust release) to wait the contaminated zone drop below the general public safety limit (1mSv per year) before it is suitable for human habitation.

Illustration of probabilistic approach in consequence assessment of accidental radioactive releases

International Nuclear Information System (INIS)

Pecha, P.; Hofman, R.; Kuca, P.

2009-01-01

We are describing a certain application of uncertainty analysis of environmental model HARP applied on atmospheric and deposition sub-model. Simulation of uncertainties propagation through the model is basic inevitable task bringing data for advanced techniques of probabilistic consequence assessment and further improvement of reliability of model predictions based on statistical procedures of assimilation with measured data. The activities are investigated in the institute IITA AV CR within the grant project supported by GACR (2007-2009). The problem is solved in close cooperation with section of information systems in institute NRPI. The subject of investigation concerns evaluation of consequences of radioactivity propagation after an accidental radioactivity release from nuclear facility.Transport of activity is studied from initial atmospheric propagation, deposition of radionuclides on terrain and spreading through food chains towards human body .Subsequent deposition processes of admixtures and food chain activity transport are modeled. In the final step a hazard estimation based on doses on population is integrated into the software system HARP. Extension to probabilistic approach has increased the complexity substantially, but offers much more informative background for modem methods of estimation accounting for inherent stochastic nature of the problem. Example of probabilistic assessment illustrated here is based on uncertainty analysis of input parameters of SGPM model. Predicted background field of Cs-137 deposition are labelled with index p. as P X SGPM . Final goal is estimation of a certain unknown true background vector χ true , which accounts also for deficiencies of the SGPM formulation in itself insisting in insufficient description of reality. We must have on mind, that even if we know true values of all input parameters θ m true (m= 1 ,..., M) of SGPM model, the χ true still remain uncertain. One possibility how to approach reality insists

Illustration of probabilistic approach in consequence assessment of accidental radioactive releases

International Nuclear Information System (INIS)

Pecha, P.; Hofman, R.; Kuca, P.

2008-01-01

We are describing a certain application of uncertainty analysis of environmental model HARP applied on atmospheric and deposition sub-model. Simulation of uncertainties propagation through the model is basic inevitable task bringing data for advanced techniques of probabilistic consequence assessment and further improvement of reliability of model predictions based on statistical procedures of assimilation with measured data. The activities are investigated in the institute IITA AV CR within the grant project supported by GACR (2007-2009). The problem is solved in close cooperation with section of information systems in institute NRPI. The subject of investigation concerns evaluation of consequences of radioactivity propagation after an accidental radioactivity release from nuclear facility.Transport of activity is studied from initial atmospheric propagation, deposition of radionuclides on terrain and spreading through food chains towards human body .Subsequent deposition processes of admixtures and food chain activity transport are modeled. In the final step a hazard estimation based on doses on population is integrated into the software system HARP. Extension to probabilistic approach has increased the complexity substantially, but offers much more informative background for modem methods of estimation accounting for inherent stochastic nature of the problem. Example of probabilistic assessment illustrated here is based on uncertainty analysis of input parameters of SGPM model. Predicted background field of Cs-137 deposition are labelled with index p. as P X SGPM . Final goal is estimation of a certain unknown true background vector χ true , which accounts also for deficiencies of the SGPM formulation in itself insisting in insufficient description of reality. We must have on mind, that even if we know true values of all input parameters θ m true (m= 1 ,..., M) of SGPM model, the χ true still remain uncertain. One possibility how to approach reality insists

The radiological impact on the Greater London population of postulated accidental releases from the Sizewell PWR

CERN Document Server

Kelly, G N; Charles, D; Hemming, C R

1983-01-01

This report contains an assessment of the radiological impact on the Greater London population of postulated accidental releases from the Sizewell PWR. Three of the degraded core accident releases postulated by the CEGB are analysed. The consequences, conditional upon each release, are evaluated in terms of the health impact on the exposed population and the impact of countermeasures taken to limit the exposure. Consideration is given to the risk to the Greater London population as a whole and to individuals within it. The consequences are evaluated using the NRPB code MARC (Methodology for Assessing Radiological Consequences). The results presented in this report are all conditional upon the occurrence of each release. In assessing the significance of the results, due account must be taken of the frequency with which such releases may be predicted to occur.

Comprehensive default methodology for the analysis of exposures to mixtures of chemicals accidentally released to the atmosphere

International Nuclear Information System (INIS)

Craig, D.K.; Baskett, R.L.; Powell, T.J.; Davis, J.S.; Dukes, L.L.; Hansen, D.J.; Petrocchi, A.J.; Sutherland, P.J.

1997-01-01

Safety analysis of Department of Energy (DOE) facilities requires consideration of potential exposures to mixtures of chemicals released to the atmosphere. Exposure to chemical mixtures may lead to additive, synergistic, or antagonistic health effects. In the past, the consequences of each chemical have been analyzed separately. This approach may not adequately protect the health of persons exposed to mixtures. However, considerable time would be required to evaluate all possible mixtures. The objective of this paper is to present reasonable default methodology developed by the EFCOG Safety Analysis Working Group Nonradiological Hazardous Material Subgroup (NHMS) for use in safety analysis within the DOE Complex

Effectiveness of cleanup criteria relative to an accidental nuclear release

International Nuclear Information System (INIS)

Chen, S.Y.; Yuan, Y.C.

1988-01-01

In the event of an accidental nuclear release, the associated long-term radiological risks would result primarily from ground contamination pathways. Cleanup of the contaminated ground surfaces is a necessary step toward reducing the radiological risk to the general population. Ideally, the radiological risk decreases as the level of cleanup effort increases; however, as the cleanup criterion (i.e., the required contaminant concentration after cleanup) becomes more stringent, the cleanup effort may become prohibitively costly. This study examines several factors that are important in determining the effectiveness of the cleanup criteria for selected radionuclides: (a) annual individual dose commitment (mrem/yr), (b) total population environmental dose commitment (person-rem), and (c) total area (km 2 ) requiring cleanup following an accident. To effectively protect the general population, the benefits of cleanup should be weighed against the potentially large increase in cleanup area (and the associated costs) as the cleanup criterion becomes more stringent. The effectiveness of cleanup will vary, depending largely on site-specific parameters such as population density and agricultural productivity as well as on the amount and type of radionuclide released. Determination of an optimum cleanup criterion should account for all factors, including a comprehensive cost/benefit analysis

Atmospheric release advisory capability

International Nuclear Information System (INIS)

Sullivan, T.J.

1981-01-01

The ARAC system (Atmospheric Release Advisory Capability) is described. The system is a collection of people, computers, computer models, topographic data and meteorological input data that together permits a calculation of, in a quasi-predictive sense, where effluent from an accident will migrate through the atmosphere, where it will be deposited on the ground, and what instantaneous and integrated dose an exposed individual would receive

Preliminary investigations of the significance of the ingestion pathway following accidental releases with actinides

International Nuclear Information System (INIS)

Steinhauer, C.

1985-10-01

Preliminary accident consequence assessments have been performed with the computer code UFOMOD to study the significance of the ingestion pathway in accidental releases with actinides. The investigation was based on the release category K1 of the 'Risk Oriented Analysis of the SNR 300', in which a higher fraction of actinides is released than in the worst release category for an LWR. The analysis was carried out using the currently implemented food chain transport model WASH-1400/BSU and data from the dynamic model from the MARC methodology. To study the influence of the time of the accident on the food chain-related results, releases in January and July were considered by means of the MARC data. In this report the differences are presented between both food chain transport models for transuranium elements and those which are observed in the potential doses due to ingestion, the areas affected by food-bans and the late health effects when using both models and taking the influence of the season into account. (orig./HP) [de

Modelling for radiological and radioecological consequences of an accidental radionuclide release at Sea

International Nuclear Information System (INIS)

Paschoa, A.S.

1997-01-01

Full text: Scenarios concerning accidental releases of radionuclides into water bodies can be found in the open literature, mostly in connection with nuclear power plants located either onshore or inland. However, meager attention has been given to nuclear reactors used as energy sources for propulsion at sea, which are also subject to accidents. Such potential accidents may involve the loss of part of the reactor core to the surrounding water body. In addition of the initial instantaneous releases, one can estimate delayed source terms based on the rate at which radionuclides are dissolved or leached from the solidified material, like part of the core or structural materials in contact with water. Most of such solidified material might be a mixture of uranium, zirconium, iron, calcium, silica, fission and activation products, and transuranium elements as oxides, forming a glassy type solid. Transport models were used to calculate radionuclide concentrations in water resulting from short and delayed source terms. Oceanographic data used in the calculations were taken either from the open literature or from unclassified reports of the Brazilian Navy, being, however, as generic as possible. Time-dependent concentration functions for radionuclides in aquatic food following an accidental release reflect the net result of intake and elimination processes. However, to avoid the complexities of multiple parameters involved in such processes, the model accounts only for trophic transfer of radionuclides, and yet avoids the necessity of analyzing the details of each transfer step used to determine fish, crustacea, molluscs and seaweed accumulation. Swimming and other aquatic sports are not included in the model used for dose calculations because of theirs relatively low importance in comparison with the pathways concerning ingestion of aquatic food

Contaminative influence of beef due to the inhalation of air and the ingestion of soil of cattle in an accidental release of radioactive materials

International Nuclear Information System (INIS)

Hwang, W. T.; Kim, E. H.; Seo, K. S.; Jung, H. J.; Lee, S. M.; Hang, M. H.

2004-01-01

The contaminative influence of beef due to the inhalation of air and the ingestion of soil of cattle, both of which are dealt with as minor contaminative pathways in most radioecological models but may not be neglected, was comprehensively investigated with the improvement of the Korean dynamic food chain model DYNACON. As the results, it was found that both pathways can not be neglected at all in the contamination of beef in the case of an accidental release during the non-grazing period of cattle. The ingestion of soil was more influential in the contamination of beef than the inhalation of air over most time following an release. If precipitation is encountered during an accidental release, contaminative influence due to the ingestion of soil was far greater compared with the cases of no precipitation. This fact was more distinct for a long-lived radionuclide 137 Cs than a short-lived radionuclide 131 I (elemental iodine). Compared with the results for milk performed prior to this study, the contaminative pathways due to the inhalation of air and the ingestion of soil were more important in beef because of longer biological half-lives. In the meantime, in the case of an accidental release during the grazing period of cattle, radioactive contamination due to the ingestion of pasture was dominant irrespective of the existence of precipitation during an accidental release. It means that contaminative influence due to the inhalation of air and the ingestion of soil is negligible like the cases of milk

Forecasting the consequences of accidental releases of radionuclides in the atmosphere from ensemble dispersion modelling

International Nuclear Information System (INIS)

Galmarini, S.; Bianconi, R.; Bellasio, R.; Graziani, G.

2001-01-01

The RTMOD system is presented as a tool for the intercomparison of long-range dispersion models as well as a system for support of decision making. RTMOD is an internet-based procedure that collects the results of more than 20 models used around the world to predict the transport and deposition of radioactive releases in the atmosphere. It allows the real-time acquisition of model results and their intercomparison. Taking advantage of the availability of several model results, the system can also be used as a tool to support decision making in case of emergency. The new concept of ensemble dispersion modelling is introduced which is the basis for the decision-making application of RTMOD. New statistical parameters are presented that allow gathering the results of several models to produce a single dispersion forecast. The devised parameters are presented and tested on the results of RTMOD exercises

Partitioning of perfluorooctanesulfonate and perfluorohexanesulfonate in the aquatic environment after an accidental release of aqueous film forming foam at Schiphol Amsterdam Airport

NARCIS (Netherlands)

Kwadijk, C.J.A.F.; Kotterman, M.J.J.; Koelmans, A.A.

2014-01-01

In the summer of 2008, an accidental release of Aqueous Film Forming Foam (AFFF) took place at Schiphol Amsterdam Airport (The Netherlands). After the release, water, fish and sediment samples were collected and analyzed for perfluoroalkyl sulfonates (PFSA). In situ perfluorooctane sulfonate (PFOS)

The hazard to man of accidental releases of tritium

International Nuclear Information System (INIS)

Brearley, I.R.

1985-03-01

Some aspects of the atmospheric dispersion of tritium are discussed, followed by consideration of the dosimetric pathways. In order to assess the significance of a tritium release the doses from various pathways are estimated and compared with the doses estimated from a similar release of iodine-131. The major hazard from tritium is the ingestion of contaminated food products. For similar releases of tritium and I 131 the ingestion hazard can be comparable if the release occurs near and before the end of the harvest season. However, in the tritium release case the agricultural season influences the consequences markedly and, at other times during the year, the ingestion hazard from tritium may be approximately 20 times less. The dose from inhalation of tritium is sensitive to its chemical form and for similar releases of tritiated water and tritium gas then the dose from tritiated water is approximately 10 4 greater than the dose from tritium gas. For similar releases of tritiated water and iodine-131 then a comparison of the inhalation shows that the dose from the iodine is approximately 300 times greater. (author)

International conference and workshop on modeling and mitigating the consequences of accidental releases of hazardous materials

International Nuclear Information System (INIS)

Anon.

1995-01-01

This conference was held September 26--29, 1995 in New Orleans, Louisiana. The purpose of this conference was to provide a multidisciplinary forum for exchange of state-of-the-art information on the consequences of accidental releases of hazardous materials. Attention is focused on air dispersion of vapors. Individual papers have been processed separately for inclusion in the appropriate data bases

Assessment of Cesium, Iodine, Strontium and Ruthenium isotopes behaviour in urban areas, after contamination from accidental release

International Nuclear Information System (INIS)

Vetere, Maria Ines de Carvalho

2002-01-01

The exposures of urban populations to the radiation derived from the deposition, after accidental atmospheric releases, of 137 Cs, 134 Cs, 129 I, 131 I, 133 I, 89 Sr, 103 Ru and 106 Ru were assessed, using the integrated system for the evaluation of environmental radiological impact in emergency situations, developed by the Instituto de Radioprotecao e Dosimetria (IRD)/Comissao Nacional de Energia Nuclear (CNEN). These radionuclide are fission products likely to be emitted in the occurrence of severe nuclear reactor accidents. Their environmental behaviour in urban areas, due to their deposition in soil, in urban surfaces and in vegetable-garden food products, such as leafy and non-leafy vegetables, were analyzed, and dose assessments at the short, medium and long terms were performed, with an without the application of protective measures for reduction of doses. Simulations of unitary initial deposition for each radionuclide and of two different potential accidents involving water reactors (PWR), with different source terms and distinct deposition for each radionuclide, were performed. Results were analyzed on the basis of relative relevance of radionuclides and pathways for the exposure of members of the public, as a function of age and time after the release. It was also performed an assessment of the effectiveness of protective measures as a function of the moment of their implementation. (author)

Estimation of the environmental impact of emissions from the La Reina NEC, by atmospheric dispersion modeling

International Nuclear Information System (INIS)

Bustamante C, Paula M.; Ortiz R, Marcela A.

1996-01-01

Based on a dispersion model, an accidental release of radioactive material to the atmosphere was simulated. To evaluate the consequences of the accidental release it was used the P C COSYMA program (KfK and NRPB). The atmospheric dispersion model was MUSEMET, a segmented Gaussian plume model which requires information on meteorological conditions for a period of one year. This study was carried out to determine the plume's behavior and path, and to define protective actions. The meteorological analysis shows an airflow from the WSW and a channeling flow from the S E at night, due to topographical influences. (author)

Dynamic evaluation of environmental impact due to tritium accidental release from the fusion reactor.

Science.gov (United States)

Nie, Baojie; Ni, Muyi; Jiang, Jieqiong; Wu, Yican

2015-10-01

As one of the key safety issues of fusion reactors, tritium environmental impact of fusion accidents has attracted great attention. In this work, the dynamic tritium concentrations in the air and human body were evaluated on the time scale based on accidental release scenarios under the extreme environmental conditions. The radiation dose through various exposure pathways was assessed to find out the potential relationships among them. Based on this work, the limits of HT and HTO release amount for arbitrary accidents were proposed for the fusion reactor according to dose limit of ITER. The dynamic results aim to give practical guidance for establishment of fusion emergency standard and design of fusion tritium system. Copyright © 2015 Elsevier Ltd. All rights reserved.

Impacts of accidental radioactive releases to the hydrosphere from floating and land-based nuclear power plants

International Nuclear Information System (INIS)

Vollmer, R.H.

1978-01-01

To assess the impacts of accidental radioactive releases to the hydrosphere from floating and land-based nuclear power plants, the Liquid Pathway Generic Study was initiated. The objective of this study was to compare the risks associated with releases through the liquid pathway from accidents that may reasonably be expected and those that are very improbable. Consequences were estimated in terms of radiation dose to man from drinking water ingestion, shell-fish and fish flesh consumption, and direct exposure (swimming, beach) as well as long-term effects, such as genetic effects or aquatic species degradation. (author)

Dynamic evaluation of environmental impact due to tritium accidental release from the fusion reactor

International Nuclear Information System (INIS)

Nie, Baojie; Ni, Muyi; Jiang, Jieqiong; Wu, Yican

2015-01-01

As one of the key safety issues of fusion reactors, tritium environmental impact of fusion accidents has attracted great attention. In this work, the dynamic tritium concentrations in the air and human body were evaluated on the time scale based on accidental release scenarios under the extreme environmental conditions. The radiation dose through various exposure pathways was assessed to find out the potential relationships among them. Based on this work, the limits of HT and HTO release amount for arbitrary accidents were proposed for the fusion reactor according to dose limit of ITER. The dynamic results aim to give practical guidance for establishment of fusion emergency standard and design of fusion tritium system. - Highlights: • Dynamic tritium concentration in the air and human body evaluated on the time scale. • Different intake forms and relevant radiation dose assessed to find out the potential relationships. • HT and HTO release amount limits for arbitrary accidents proposed for the fusion reactor according to dose limit

Atmospheric Release Advisory Capability

International Nuclear Information System (INIS)

Dickerson, M.H.; Gudiksen, P.H.; Sullivan, T.J.

1983-02-01

The Atmospheric Release Advisory Capability (ARAC) project is a Department of Energy (DOE) sponsored real-time emergency response service available for use by both federal and state agencies in case of a potential or actual atmospheric release of nuclear material. The project, initiated in 1972, is currently evolving from the research and development phase to full operation. Plans are underway to expand the existing capability to continuous operation by 1984 and to establish a National ARAC Center (NARAC) by 1988. This report describes the ARAC system, its utilization during the past two years, and plans for its expansion during the next five to six years. An integral part of this expansion is due to a very important and crucial effort sponsored by the Defense Nuclear Agency to extend the ARAC service to approximately 45 Department of Defense (DOD) sites throughout the continental US over the next three years

Performance evaluation of of caesium, iodine, strontium and ruthenium isotopes in urban areas after contamination by accidental release

International Nuclear Information System (INIS)

Vetere, Maria Ines de Carvalho

2002-03-01

The exposures of urban populations to the radiation derived from the deposition, after accidental atmospheric releases, of I37 Cs, 134 Cs, 129 I, 131 I, 133 I, 89 Sr, l03 Ru and 106 Ru were assessed, using the integrated system for the evaluation of environmental radiological impact in emergency situations (SIEM), developed by the Instituto de Radioprotecao e Dosimetria (IRD) / Comissao Nacional de Energia Nuclear (CNEN). These radionuclides are fission products likely to be emitted in the occurrence of severe nuclear reactor accidents. Their environmental behaviour in urban areas, due to their deposition in soil, in urban surfaces and in vegetable-garden food products, such as leafy and non-leafy vegetables, were analyzed, and dose assessments at the short, medium and long terms were performed, with and without the application of protective measures for reduction of doses. Simulations of unitary initial deposition for each radionuclide and of two different potential accidents involving pressurized water reactors (PWR), with different source terms and distinct deposition for each radionuclide, were performed. Results were analyzed on the basis of the relative relevance of radionuclides and pathways for the exposure of members of the public, as a function of age and time after the release. It was also performed an assessment of the effectiveness of protective measures as a function of the moment of their implementation. (author)

Development of management tools for accidental radiological contamination of the French coastal areas - Development of management tools for accidental radiological contamination in the French marine coastal areas

Energy Technology Data Exchange (ETDEWEB)

Duffa, C.; Charmasson, S. [IRSN/PRP-ENV/SESURE/LERCM - Antenne de Radioecologie Marine, Centre Ifremer, Zone portuaire de Bregaillon, 13507 La Seyne sur Mer (France); Bailly du Bois, P.; Fievet, B. [IRSN/PRP-ENV/SERIS/LRC (France); Couvez, C.; Renaud, P. [IRSN/PRP-ENV/SESURE/DIR (France); Didier, D. [IRSN/PRP-CRI/SESUC/BMTA (France)

2014-07-01

The Fukushima nuclear accident led to the most important accidental release of artificial radionuclides into the sea. This accident has underlined the importance of being able to adequately reproduce the fate of radioactive releases and to estimate their consequences for the marine environment. For its Crisis Centre, the French Institute for Radioprotection and Nuclear Safety (IRSN) has operational tools, in order to help experts and decision makers in case of any atmospheric accidental release and terrestrial environment contamination. The on-going project aims to develop tools to manage any marine contamination of the French coastal areas. We should be able to evaluate and anticipate the marine post-accidental situation: contaminated areas localization and contamination levels, and possible consequences. Many sites has be considered as potential source terms into the sea: the Coastal Nuclear Power Plants, the La Hague reprocessing Plant, the Brest and Toulon Military Harbours as home-ports of nuclear powered vessels, and different river mouths (Rhone River, Gironde, Loire, Seine) that could be contaminated by upstream accidental release. To achieve this goal, two complementary approaches are developed: Marine sheets and a dedicated modelling tool (STERNE). - Marine sheets aim to summarize marine environment characteristics for the different sites, identify potential stakes for human protection such as aquaculture areas, beaches, or industrial water intakes, and ecological stakes. Whenever possible, a local climatology (main currents depending on meteorological or tide conditions) that could be a support to first environmental measurement strategy is proposed. A list of available local contacts for any operational management is also provided. - The modelling tool, STERNE (Simulation du Transport et du transfert d'Elements Radioactifs dans l'environNEment marin), must predict radionuclide dispersion and contamination of water, marine species and sediments

The environmental impact of radioactive releases from accidents in nuclear power reactors

International Nuclear Information System (INIS)

Beattie, J.R.; Griffiths, R.F.; Kaiser, G.D.; Kinchin, G.H.

1978-01-01

A survey of accidental releases of radioactivity from thermal and fast reactors is presented. Following a general discussion on the hazards involved, the nature of the environmental impact of radioactive releases is examined. This includes a brief review of the natural radiation background, the effect on human health of various levels of radiation and radioactivity, permissible and reference levels, and the type of hazards from both passing clouds of airbourne radioactive material and from ground deposited material. The problem of atmospheric dispersion and methods of calculations of radioactive materials in the atmosphere are examined in order for the consequences of accidental release to be analysed. National accidents and their environmental consequences are then examined. Finally there is a review of the risks to which man is always exposed because of his environment. Common and collective risks are also considered. Conclusions are reached as to the acceptibility or otherwise of the environmental impact of reactor accidents. (U.K.)

Modelling of the tritium dispersion from postulated accidental release of nuclear power plants

International Nuclear Information System (INIS)

Soares, Abner Duarte; Simoes Filho, Francisco Fernando Lamego; Cunha, Tatiana Santos da; Aguiar, Andre Silva de; Lapa, Celso Marcelo Franklin

2011-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models to simulation of tritium dispersion caused by an accident in a Candu reactor located in the ongoing Angra 3 site. The Candu reactor is one that uses heavy water (D 2 O) as moderator and coolant of the core. It was postulated, then, the LOCA accident (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 P Bq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m 3 ) during the first 14 days after the accident. (author)

Puff-plume atmospheric deposition model for use at SRP in emergency-response situations

International Nuclear Information System (INIS)

Garrett, A.J.; Murphy, C.E. Jr.

1981-05-01

An atmospheric transport and diffusion model developed for real-time calculation of the location and concentration of toxic or radioactive materials during an accidental release was improved by including deposition calculations

Modeling the wind-fields of accidental releases with an operational regional forecast model

International Nuclear Information System (INIS)

Albritton, J.R.; Lee, R.L.; Sugiyama, G.

1995-01-01

The Atmospheric Release Advisory Capability (ARAC) is an operational emergency preparedness and response organization supported primarily by the Departments of Energy and Defense. ARAC can provide real-time assessments of atmospheric releases of radioactive materials at any location in the world. ARAC uses robust three-dimensional atmospheric transport and dispersion models, extensive geophysical and dose-factor databases, meteorological data-acquisition systems, and an experienced staff. Although it was originally conceived and developed as an emergency response and assessment service for nuclear accidents, the ARAC system has been adapted to also simulate non-radiological hazardous releases. For example, in 1991 ARAC responded to three major events: the oil fires in Kuwait, the eruption of Mt. Pinatubo in the Philippines, and the herbicide spill into the upper Sacramento River in California. ARAC's operational simulation system, includes two three-dimensional finite-difference models: a diagnostic wind-field scheme, and a Lagrangian particle-in-cell transport and dispersion scheme. The meteorological component of ARAC's real-time response system employs models using real-time data from all available stations near the accident site to generate a wind-field for input to the transport and dispersion model. Here we report on simulation studies of past and potential release sites to show that even in the absence of local meteorological observational data, readily available gridded analysis and forecast data and a prognostic model, the Navy Operational Regional Atmospheric Prediction System, applied at an appropriate grid resolution can successfully simulate complex local flows

Assessment of the Public Health impact from the accidental release of UF6 at the Sequoyah Fuels Corporation Facility at Gore, Oklahoma (Docket No. 40-8027). Volume 2

International Nuclear Information System (INIS)

1986-03-01

Following the accidental release of UF 6 from the Sequoyah Fuels Facility on January 4, 1986, an Ad Hoc Interagency Public Health Assessment Task Force was established. The Task Force consists of technical staff members from various agencies who have prepared this assessment of the public health impact associated with the accidental release. Volume 2 of the report contains Appendices which provide more detailed information used in the assessment and support the discussion in Volume 1

Methodology for prediction and estimation of consequences of possible atmospheric releases of hazardous matter: 'Kursk' submarine study

Directory of Open Access Journals (Sweden)

A. Baklanov

2003-01-01

Full Text Available There are objects with some periods of higher than normal levels of risk of accidental atmospheric releases (nuclear, chemical, biological, etc.. Such accidents or events may occur due to natural hazards, human errors, terror acts, and during transportation of waste or various operations at high risk. A methodology for risk assessment is suggested and it includes two approaches: 1 probabilistic analysis of possible atmospheric transport patterns using long-term trajectory and dispersion modelling, and 2 forecast and evaluation of possible contamination and consequences for the environment and population using operational dispersion modelling. The first approach could be applied during the preparation stage, and the second - during the operation stage. The suggested methodology is applied on an example of the most important phases (lifting, transportation, and decommissioning of the ``Kursk" nuclear submarine operation. It is found that the temporal variability of several probabilistic indicators (fast transport probability fields, maximum reaching distance, maximum possible impact zone, and average integral concentration of 137Cs showed that the fall of 2001 was the most appropriate time for the beginning of the operation. These indicators allowed to identify the hypothetically impacted geographical regions and territories. In cases of atmospheric transport toward the most populated areas, the forecasts of possible consequences during phases of the high and medium potential risk levels based on a unit hypothetical release (e.g. 1 Bq are performed. The analysis showed that the possible deposition fractions of 10-11 (Bq/m2 over the Kola Peninsula, and 10-12 - 10-13 (Bq/m2 for the remote areas of the Scandinavia and Northwest Russia could be observed. The suggested methodology may be used successfully for any potentially dangerous object involving risk of atmospheric release of hazardous materials of nuclear, chemical or biological nature.

Methodology for prediction and estimation of consequences of possible atmospheric releases of hazardous matter: "Kursk"? submarine study

Science.gov (United States)

Baklanov, A.; Mahura, A.; Sørensen, J. H.

2003-03-01

There are objects with some periods of higher than normal levels of risk of accidental atmospheric releases (nuclear, chemical, biological, etc.). Such accidents or events may occur due to natural hazards, human errors, terror acts, and during transportation of waste or various operations at high risk. A methodology for risk assessment is suggested and it includes two approaches: 1) probabilistic analysis of possible atmospheric transport patterns using long-term trajectory and dispersion modelling, and 2) forecast and evaluation of possible contamination and consequences for the environment and population using operational dispersion modelling. The first approach could be applied during the preparation stage, and the second - during the operation stage. The suggested methodology is applied on an example of the most important phases (lifting, transportation, and decommissioning) of the "Kursk" nuclear submarine operation. It is found that the temporal variability of several probabilistic indicators (fast transport probability fields, maximum reaching distance, maximum possible impact zone, and average integral concentration of 137Cs) showed that the fall of 2001 was the most appropriate time for the beginning of the operation. These indicators allowed to identify the hypothetically impacted geographical regions and territories. In cases of atmospheric transport toward the most populated areas, the forecasts of possible consequences during phases of the high and medium potential risk levels based on a unit hypothetical release are performed. The analysis showed that the possible deposition fractions of 1011 over the Kola Peninsula, and 10-12 - 10-13 for the remote areas of the Scandinavia and Northwest Russia could be observed. The suggested methodology may be used successfully for any potentially dangerous object involving risk of atmospheric release of hazardous materials of nuclear, chemical or biological nature.

Methodology for prediction and estimation of consequences of possible atmospheric releases of hazardous matter: "Kursk" submarine study

Science.gov (United States)

Baklanov, A.; Mahura, A.; Sørensen, J. H.

2003-06-01

There are objects with some periods of higher than normal levels of risk of accidental atmospheric releases (nuclear, chemical, biological, etc.). Such accidents or events may occur due to natural hazards, human errors, terror acts, and during transportation of waste or various operations at high risk. A methodology for risk assessment is suggested and it includes two approaches: 1) probabilistic analysis of possible atmospheric transport patterns using long-term trajectory and dispersion modelling, and 2) forecast and evaluation of possible contamination and consequences for the environment and population using operational dispersion modelling. The first approach could be applied during the preparation stage, and the second - during the operation stage. The suggested methodology is applied on an example of the most important phases (lifting, transportation, and decommissioning) of the ``Kursk" nuclear submarine operation. It is found that the temporal variability of several probabilistic indicators (fast transport probability fields, maximum reaching distance, maximum possible impact zone, and average integral concentration of 137Cs) showed that the fall of 2001 was the most appropriate time for the beginning of the operation. These indicators allowed to identify the hypothetically impacted geographical regions and territories. In cases of atmospheric transport toward the most populated areas, the forecasts of possible consequences during phases of the high and medium potential risk levels based on a unit hypothetical release (e.g. 1 Bq) are performed. The analysis showed that the possible deposition fractions of 10-11 (Bq/m2) over the Kola Peninsula, and 10-12 - 10-13 (Bq/m2) for the remote areas of the Scandinavia and Northwest Russia could be observed. The suggested methodology may be used successfully for any potentially dangerous object involving risk of atmospheric release of hazardous materials of nuclear, chemical or biological nature.

Radionuclide dispersion and hydrodynamics of Ilha Grande Bay (Angra dos Reis, RJ) simulated from hypothetical accidental releases of liquid wastes

International Nuclear Information System (INIS)

Simoes Filho, Fernando Lamego; Lapa, Celso Marcelo Franklin; Aguiar, Andre Silva; Soares, Abner Duarte

2011-01-01

This study has the aim to assess the impact of accidental release of radionuclides postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamic circulation and transport for the simulation of tritium dispersion caused by an accidental release in Ilha Grande Bay from the site of the future third plant in two circulation scenarios. The main difference between the scenarios is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1 x 10 9 to 5 x 10 5 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m³). (author)

SRNL EMERGENCY RESPONSE CAPABILITY FOR ATMOSPHERIC CONTAMINANT RELEASES

International Nuclear Information System (INIS)

Koffman, L; Chuck Hunter, C; Robert Buckley, R; Robert Addis, R

2006-01-01

Emergency response to an atmospheric release of chemical or radiological contamination is enhanced when plume predictions, field measurements, and real-time weather information are integrated into a geospatial framework. The Weather Information and Display (WIND) System at Savannah River National Laboratory (SRNL) utilizes such an integrated framework. The rapid availability of predictions from a suite of atmospheric transport models within this geospatial framework has proven to be of great value to decision makers during an emergency involving an atmospheric contaminant release

Environmental and radiological impact of accidental tritium release

Energy Technology Data Exchange (ETDEWEB)

Guetat, Ph. [CEA Valduc, 21 - Is-sur-Tille (France); Patryl, L. [CEA Bruyeres-le-Chatel, 91 (France)

2008-07-15

Within the IAEA program EMRAS, an exercise has been performed by 7 countries to evaluate the consequences of an acute atmospheric release of tritium (10 g). This study aimed at giving practical technical information to decision-makers. Three scenarios with different meteorological conditions were modeled. The objective of this paper is to give the main information about transfer and impact, evaluate uncertainties in models/assessments and so help to set countermeasures. From the results of this exercise, reference activity values for countermeasures can be discussed. All pathways and chemical forms (HTO-HT-OBT) are considered. (authors)

An application of cost-effectiveness analysis to restrict the damage caused by an accidental release of radioactive material to the environment

International Nuclear Information System (INIS)

Frittelli, L.; Tamburrano, A.

1980-01-01

When an accidental release of radioactive material occurs health effects in the exposed population can be mitigated by remedial actions applied to individuals or their environment. A cost-effectiveness analysis is performed by comparing the cost of remedial action with the monetary value of the collective dose avoided. (H.K.)

Application of the HGSYSTEM/UF6 model to simulate atmospheric dispersion of UF6 releases from uranium enrichment plants

International Nuclear Information System (INIS)

Goode, W.D. Jr.; Bloom, S.G.; Keith, K.D. Jr.

1995-01-01

Uranium hexafluoride is a dense, reactive gas used in Gaseous Diffusion Plants (GDPs) to make uranium enriched in the 235 U isotope. Large quantities of UF 6 exist at the GDPs in the form of in-process gas and as a solid in storage cylinders; smaller amounts exist as hot liquid during transfer operations. If liquid UF 6 is released to the environment, it immediately flashes to a solid and a dense gas that reacts rapidly with water vapor in the air to form solid particles of uranyl fluoride and hydrogen fluoride gas. Preliminary analyses were done on various accidental release scenarios to determine which scenarios must be considered in the safety analyses for the GDPS. These scenarios included gas releases due to failure of process equipment and liquid/gas releases resulting from a breach of transfer piping from a cylinder. A major goal of the calculations was to estimate the response time for mitigating actions in order to limit potential off-site consequences of these postulated releases. The HGSYSTEM/UF 6 code was used to assess the consequences of these release scenarios. Inputs were developed from release calculations which included two-phase, choked flow followed by expansion to atmospheric pressure. Adjustments were made to account for variable release rates and multiple release points. Superpositioning of outputs and adjustments for exposure time were required to evaluate consequences based on health effects due to exposures to uranium and HF at a specific location

An adaptive Bayesian inference algorithm to estimate the parameters of a hazardous atmospheric release

Science.gov (United States)

Rajaona, Harizo; Septier, François; Armand, Patrick; Delignon, Yves; Olry, Christophe; Albergel, Armand; Moussafir, Jacques

2015-12-01

In the eventuality of an accidental or intentional atmospheric release, the reconstruction of the source term using measurements from a set of sensors is an important and challenging inverse problem. A rapid and accurate estimation of the source allows faster and more efficient action for first-response teams, in addition to providing better damage assessment. This paper presents a Bayesian probabilistic approach to estimate the location and the temporal emission profile of a pointwise source. The release rate is evaluated analytically by using a Gaussian assumption on its prior distribution, and is enhanced with a positivity constraint to improve the estimation. The source location is obtained by the means of an advanced iterative Monte-Carlo technique called Adaptive Multiple Importance Sampling (AMIS), which uses a recycling process at each iteration to accelerate its convergence. The proposed methodology is tested using synthetic and real concentration data in the framework of the Fusion Field Trials 2007 (FFT-07) experiment. The quality of the obtained results is comparable to those coming from the Markov Chain Monte Carlo (MCMC) algorithm, a popular Bayesian method used for source estimation. Moreover, the adaptive processing of the AMIS provides a better sampling efficiency by reusing all the generated samples.

Development of scheme for predicting atmospheric dispersion of radionuclides during nuclear emergency by using atmospheric dynamic model

Energy Technology Data Exchange (ETDEWEB)

Nagai, Haruyasu; Chino, Masamichi; Yamazawa, Hiromi (Japan Atomic Energy Research Inst., Tokyo (Japan))

1999-07-01

The meteorological forecast models are critically important for the accuracy of predicting the atmospheric dispersion of radionuclides discharged into atmosphere during nuclear emergencies. Thus, this paper describes a new scheme for predicting environmental impacts due to accidental release of radionuclides by using an atmospheric dynamic model PHYSIC. The advantages of introducing PHYSIC are, (1) three-dimensional local meteorological forecasts can be conducted, (2) synoptic meteorological changes can be considered by inputting grid data of synoptic forecasts from Japan Meteorological Agency to PHYSIC as initial and boundary conditions, (3) forecasts can be improved by nudging method using local meteorological observations, and (4) atmospheric dispersion model can consider the variation of the mixed layer. (author)

Development of scheme for predicting atmospheric dispersion of radionuclides during nuclear emergency by using atmospheric dynamic model

International Nuclear Information System (INIS)

Nagai, Haruyasu; Chino, Masamichi; Yamazawa, Hiromi

1999-01-01

The meteorological forecast models are critically important for the accuracy of predicting the atmospheric dispersion of radionuclides discharged into atmosphere during nuclear emergencies. Thus, this paper describes a new scheme for predicting environmental impacts due to accidental release of radionuclides by using an atmospheric dynamic model PHYSIC. The advantages of introducing PHYSIC are, (1) three-dimensional local meteorological forecasts can be conducted, (2) synoptic meteorological changes can be considered by inputting grid data of synoptic forecasts from Japan Meteorological Agency to PHYSIC as initial and boundary conditions, (3) forecasts can be improved by nudging method using local meteorological observations, and (4) atmospheric dispersion model can consider the variation of the mixed layer. (author)

Parametric study of the Ignalina reactor building capability as barrier against accidental releases of radioactivity

International Nuclear Information System (INIS)

Blomquist, R.; Johansson, Kjell; Nilsson, Lars.

1993-01-01

The results of a parametric study are offered to the Ignalina plant management staff and to the Lithuanian and Swedish nuclear inspectorates as a basis for a decision whether there is mutual interest in a project for the purpose of strengthening the Ignalina reactor buildings inherent capabilities to provide a barrier against accidental releases of radioactivity. Practical measures to consider are: * establish natural convection of warm air from the steam drums to the tall stack of 150 m height. * reduce the resulting draught of air through the reactor hall floor between the fuel channel shield blocks into the steam drum compartments. * apply filtration to the stack air flow. 18 refs

A CASE STUDY OF CHLORINE TRANSPORT AND FATE FOLLOWING A LARGE ACCIDENTAL RELEASE

Energy Technology Data Exchange (ETDEWEB)

Buckley, R.; Hunter, C.; Werth, D.; Whiteside, M.; Chen, K.; Mazzola, C.

2012-08-01

A train derailment that occurred in Graniteville, South Carolina during the early morning hours of 06 January, 2005 resulted in the prompt release of approximately 60 tons of chlorine to the environment. Comprehensive modeling of the transport and fate of this release was performed including the characterization of the initial three-phased chlorine release, a detailed determination of the local atmospheric conditions acting to generate, disperse, and deplete the chlorine vapor cloud, the establishment of physical exchange mechanisms between the airborne vapor and local surface waters, and local aquatic dilution and mixing.

The Atmospheric Release Advisory Capability Site Workstation System

International Nuclear Information System (INIS)

Foster, K.T.; Sumikawa, D.A.; Foster, C.S.; Baskett, R.L.

1993-01-01

The Atmospheric Release Advisory Capability (ARAC) is a centralized emergency response service that assesses the consequences that may result from an atmospheric release of toxic material. ARAC was developed by the Lawrence Livermore National Laboratory (LLNL) for the Departments of Energy (DOE) and Defense (DOD) and responds principally to radiological accidents. ARAC provides radiological health and safety guidance to decision makers in the form of computer-generated estimates of the effects of an actual, or potential release of radioactive material into the atmosphere. Upon receipt of the release scenario, the ARAC assessment staff extracts meteorological, topographic, and geographic data from resident world-wide databases for use in complex, three-dimensional transport and diffusion models. These dispersion models generate air concentration (or dose) and ground deposition contour plots showing estimates of the contamination patterns produced as the toxic material is carried by the prevailing winds. To facilitate the ARAC response to a release from specific DOE and DOD sites and to provide these sites with a local emergency response tool, a remote Site Workstation System (SWS) is being placed at various ARAC-supported facilities across the country.. This SWS replaces the existing antiquated ARAC Site System now installed at many of these sites. The new system gives users access to complex atmospheric dispersion models that may be run either by the ARAC staff at LLNL, or (in a later phase of the system) by site personnel using the computational resources of the SWS. Supporting this primary function are a variety of SWS-resident supplemental capabilities that include meteorological data acquisition, manipulation of release-specific databases, computer-based communications, and the use of a simpler Gaussian trajectory puff model that is based on Environmental Protection Agency's INPUFF code

An overview of computer models for pollutant transfer through the atmosphere, with special consideration for radioisotopes

International Nuclear Information System (INIS)

Zivanovic, M.; Djukanovic, J.; Davidovic, M.; Cekerevac, D.; Stankovic, S.

2011-01-01

Modern society is intrinsically connected with usage and production of radioisotopes, both for military and civilian applications. During the march of 2007, there were 443 active nuclear plants, unknown quantity of nuclear weapons and a huge number of industrial, medical and other facilities that possess and use radioisotopes for various purposes. With the widespread usage of radioisotopes, there comes a danger of accidental or planed release into the biosphere. This paper gives an overview of the models that can be used for prognosis or reconstruction of radioisotope transfer through the atmosphere in case of accidental or planned release [sr

Program report: FY 1976, Atmospheric and Geophysical Sciences Division, Physics Department

International Nuclear Information System (INIS)

Knox, J.B.; Orphan, R.C.

1976-01-01

The Atmospheric Release Advisory Capability (ARAC), with its central facility located at LLL, is meeting the long-term need for rapid and accurate regional dose-to-man estimates of nuclear material released as a result of accidents, operations, or terrorism acts. During the past two years, ARAC has been used in four potential WARMSPOT events and for one accidental release. Continuing research, in terms of new modeling techniques, simulation of regional tracer experiments, and other verification activities, support this capability. Emergency response is currently being upgraded to evaluate the consequences of atmospheric releases at selected nuclear facilities and for potential acts of nuclear terrorism anywhere in the Northern Hemisphere. Regional modeling was also applied in monitoring SO 2 -sulfate concentrations in the northeastern USA

Final Report: Safety of Plasma Components and Aerosol Transport During Hard Disruptions and Accidental Energy Release in Fusion Reactor

Energy Technology Data Exchange (ETDEWEB)

Bourham, Mohamed A.; Gilligan, John G.

1999-08-14

Safety considerations in large future fusion reactors like ITER are important before licensing the reactor. Several scenarios are considered hazardous, which include safety of plasma-facing components during hard disruptions, high heat fluxes and thermal stresses during normal operation, accidental energy release, and aerosol formation and transport. Disruption events, in large tokamaks like ITER, are expected to produce local heat fluxes on plasma-facing components, which may exceed 100 GW/m{sup 2} over a period of about 0.1 ms. As a result, the surface temperature dramatically increases, which results in surface melting and vaporization, and produces thermal stresses and surface erosion. Plasma-facing components safety issues extends to cover a wide range of possible scenarios, including disruption severity and the impact of plasma-facing components on disruption parameters, accidental energy release and short/long term LOCA's, and formation of airborne particles by convective current transport during a LOVA (water/air ingress disruption) accident scenario. Study, and evaluation of, disruption-induced aerosol generation and mobilization is essential to characterize database on particulate formation and distribution for large future fusion tokamak reactor like ITER. In order to provide database relevant to ITER, the SIRENS electrothermal plasma facility at NCSU has been modified to closely simulate heat fluxes expected in ITER.

Estimation of radiological consequences from accidental iodine releases at nuclear power plants

International Nuclear Information System (INIS)

Drozdovitch, V.V.

2001-01-01

The radiological consequences of a beyond design-basis accident at an NPP for a VVER-1000 reactor are evaluated. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Inhalation and ingestion thyroid doses to different population sub-groups have been calculated. Using modern knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways. Thyroid doses and risk was estimated for populations living at different distances from the NPP. The comparative analysis of exposure pathways and radiological danger of the radionuclides in release during early and intermediate stage of accident has conducted. (author)

Development of dose assessment code for accidental releases of activation products

International Nuclear Information System (INIS)

Noguchi, H.; Yokoyama, S.

2000-01-01

It is expected that activation products will be important radionuclides as well as tritium in the assessment of the public doses necessary for licensing of a future fusion reactor. In order to calculate the public doses due to the activation products released in cases of accidents, a code named ACUTAP (dose assessment code for ACUTe Activation Product releases) has been developed. Major characteristics of the code are as follows: (1) the transfer model reflects specific behavior of the activation products in the environment, (2) the doses are assessed based on ICRP dose models, (3) it is possible to calculate individual doses using annual meteorological data statistically according to the guide of the Nuclear Safety Commission of Japan, and (4) the code can calculate collective doses as well as individual doses. Individual doses are calculated for the following pathways: internal exposure by inhalation of activation products in a plume and those resuspended from the ground, external exposure from a plume (cloudshine), and external exposure from activation products deposited on the ground (groundshine). The inhalation in a plume and cloudshine pathways are included in the model for calculating collective doses. In addition to parent nuclides released from the facilities, progeny nuclides produced during the atmospheric dispersion are considered in calculating inhalation doses, and those during the deposition period in calculating groundshine doses. External doses from the cloudshine are calculated for 18 energy groups instead of individual energy of emitted gamma rays in order to save the computation time. Atmospheric concentrations are calculated using a Gaussian plume model with atmospheric dispersion parameters prescribed in the guide of the Nuclear Safety Commission of Japan. Data sets of parameters necessary for the dose assessment, such as internal dos coefficients, external dose rate conversion factors and half lives, are prepared for about 100 radionuclides

Operators guide: Atmospheric Release Advisory Capability (ARAC) site facility

International Nuclear Information System (INIS)

Lawver, B.S.

1977-01-01

In this report capabilities and services are described for the Atmospheric Release Advisory Capability (ARAC). The ARAC site system and its operating procedures and interactions with the ARAC central facility located at LLL is outlined. ARAC is designed to help officials at designated ERDA sites and other locations in estimating the effects of atmospheric releases of radionuclides or other hazardous materials by issuing real-time advisories to guide them in their planning

Operators guide: Atmospheric Release Advisory Capability (ARAC) site facility

International Nuclear Information System (INIS)

Cassaro, E.; Lomonaco, L.

1979-01-01

The Atmospheric Release Advisory Capability (ARAC) is designed to help officials at designated DOE sites and other locations in estimating the effects of atmospheric releases of radionuclides or other hazardous materials by issuing real-time advisories to guide them in their planning. This report outlines the capabilities and sources of ARAC, and in more detail describes an ARAC Site Facility, its operating procedures and interactions with the ARAC Central Facility (ACF) located at LLL

Report of the consultant's meeting on monitoring accidentally released radionuclides in the environment

International Nuclear Information System (INIS)

2001-01-01

At an earlier Research Co-ordination Meeting (12-16 August 1991, VIC, Vienna) for the IAEA Programme on 'Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples', it was recognized that a network of analytical laboratories with specially qualified scientists is needed which will provide a timely coordinated response to any future requests for assistance from Member States. The experience gained from the International Chernobyl Project revealed that there is a need for such a closely linked group when the Member State lacks sufficient technical resource to independently perform an assessment of environmental contamination following an accidental release of radioactivity. The existence of such a network of laboratories would help to assure responsible government representatives and the general public that the Agency has additional available resources including specialized experts to perform assessments on which to base required actions for many accident scenarios and their radiological consequences. The purpose of the present Consultants' Meeting is to discuss the organization and scope of the proposed network of analytical laboratories. The Consultants should discuss the matrices and nuclides of interest at various time frames of an accidental release of radioactivity. It is also intended that the Consultants should discuss the laboratories from their experience which would have the specialized expertise needed, in both terrestrial and aquatic sample collection and analysis. Finally, it is intended that the Consultants should discuss whether it would be desirable for the Agency to produce a technical document based on the achievements of the Agency programme on 'Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples'. A Guide Book was considered essential by the participants of this Co-ordinated Research Programme because it would be a succinct form and on a common

Final Report: Safety of Plasma-Facing Components and Aerosol Transport During Hard Disruptions and Accidental Energy Release in Fusion Reactor

International Nuclear Information System (INIS)

Bourham, Mohamed A.; Gilligan, John G.

1999-01-01

Safety considerations in large future fusion reactors like ITER are important before licensing the reactor. Several scenarios are considered hazardous, which include safety of plasma-facing components during hard disruptions, high heat fluxes and thermal stresses during normal operation, accidental energy release, and aerosol formation and transport. Disruption events, in large tokamaks like ITER, are expected to produce local heat fluxes on plasma-facing components, which may exceed 100 GW/m 2 over a period of about 0.1 ms. As a result, the surface temperature dramatically increases, which results in surface melting and vaporization, and produces thermal stresses and surface erosion. Plasma-facing components safety issues extends to cover a wide range of possible scenarios, including disruption severity and the impact of plasma-facing components on disruption parameters, accidental energy release and short/long term LOCA's, and formation of airborne particles by convective current transport during a LOVA (water/air ingress disruption) accident scenario. Study, and evaluation of, disruption-induced aerosol generation and mobilization is essential to characterize database on particulate formation and distribution for large future fusion tokamak reactor like ITER. In order to provide database relevant to ITER, the SIRENS electrothermal plasma facility at NCSU has been modified to closely simulate heat fluxes expected in ITER

HGSYSTEMUF6, Simulating Dispersion Due to Atmospheric Release of Uranium Hexafluoride (UF6)

International Nuclear Information System (INIS)

Hanna, G; Chang, J.C.; Zhang, J.X.; Bloom, S.G.; Goode, W.D. Jr; Lombardi, D.A.; Yambert, M.W.

2001-01-01

1 - Description of program or function: HGSYSTEMUF6 is a suite of models designed for use in estimating consequences associated with accidental, atmospheric release of Uranium Hexafluoride (UF 6 ) and its reaction products, namely Hydrogen Fluoride (HF), and other non-reactive contaminants which are either negatively, neutrally, or positively buoyant. It is based on HGSYSTEM Version 3.0 of Shell Research LTD., and contains specific algorithms for the treatment of UF 6 chemistry and thermodynamics. HGSYSTEMUF6 contains algorithms for the treatment of dense gases, dry and wet deposition, effects due to the presence of buildings (canyon and wake), plume lift-off, and the effects of complex terrain. The models components of the suite include (1) AEROPLUME/RK, used to model near-field dispersion from pressurized two-phase jet releases of UF6 and its reaction products, (2) HEGADAS/UF6 for simulating dense, ground based release of UF 6 , (3) PGPLUME for simulation of passive, neutrally buoyant plumes (4) UF6Mixer for modeling warm, potentially reactive, ground-level releases of UF 6 from buildings, and (5) WAKE, used to model elevated and ground-level releases into building wake cavities of non-reactive plumes that are either neutrally or positively buoyant. 2 - Methods: The atmospheric release and transport of UF 6 is a complicated process involving the interaction between dispersion, chemical and thermodynamic processes. This process is characterized by four separate stages (flash, sublimation, chemical reaction entrainment and passive dispersion) in which one or more of these processes dominate. The various models contained in the suite are applicable to one or more of these stages. For example, for modeling reactive, multiphase releases of UF 6 , the AEROPLUME/RK component employs a process-splitting scheme which numerically integrates the differential equations governing dispersion, UF 6 chemistry, and thermodynamics. This algorithm is based on the assumption that

The influence of the physico-chemical form of the aerosol on the radiological consequences of notional accidental releases of radioactivity from a fast breeder reactor

International Nuclear Information System (INIS)

Kelly, G.N.; Jones, J.A.; Simmonds, J.R.

1979-01-01

The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR (Liquid Metal-cooled Fast Breeder Reactor) were assessed in a study published by the National Radiological Protection Board (NRPB) in 1977. In that study representative values were in general adopted for each of the important parameters while recognising that in reality they could vary considerably. The present study is concerned with the sensitivity of the predicted consequences to the physico-chemical form of the released aerosol. Of particular interest is the importance of a mixed sodium-transuranium element aerosol which may be formed in accidental releases of activity from sodium cooled FBRs. Two significant findings emerge from the study. First the predicted consequences in general are relatively insensitive to the range of physico-chemical forms analysed. For generic assessments therefore it is sufficient to assume the properties of the aerosol adopted in the initial study (1 μm AMAD and each element in the oxide form); the exception concerns the estimation of the incidence of early morbidity, and to a lesser extent early mortality, but only for a limited range of release composition. The second finding is that the radiological consequences are not, contrary to what might have been expected, significantly increased for the release of a mixed sodium-element aerosol

Optimal selection of the time of hazardous operations, and prediction of consequences of atmospheric releases of harmful matter: the 'Kursk' submarine study

International Nuclear Information System (INIS)

Baklanov, A.; Havskov Sorensen, J.; Mahura, A.

2003-01-01

Full text: There are objects and events with higher than normal risks of accidental atmospheric releases (nuclear, chemical, biological, etc.) during certain periods. Such accidents or events may occur due to natural hazards, human errors, terror acts, and may take place during transportation of waste or during various operations at high risk. A methodology for risk assessment is presented including two approaches: 1) probabilistic analysis of possible atmospheric transport patterns using long-term trajectory and dispersion modelling, and 2) forecast and evaluation of possible contamination and consequences for the environment and population using operational dispersion modelling. The first approach can be applied during the preparation stage, and the second during the operation stage. The methodology is applied on an example of the most important phases (lifting, transportation, and decommissioning) of the 'Kursk' nuclear submarine operation. It is found that the temporal variability of several probabilistic indicators (fast transport probability fields, maximum reaching distance, maximum possible impact zone, and average integral concentration of 137 Cs) show that the fall of 2001 was the most appropriate time for the beginning of the operation. These indicators allow identifying the hypothetically impacted geographical regions and territories. In cases of atmospheric transport toward the most populated areas, forecasts of possible consequences during phases of high and medium risks are performed based on a unit hypothetical release, e.g. 1 Bq. The analysis shows possible deposition fractions of 10 -11 Bq/m 2 over the Kola Peninsula, and 10 -12 -10 -13 Bq/m 2 for the remote areas of Scandinavia and Northwest Russia. The methodology may be applied to any potentially dangerous object involving a risk of atmospheric release of hazardous materials of nuclear, chemical or biological nature. In the present paper, the methodology is applied to the handling of the

Probabilistic consequence assessment of hydrogen sulphide releases from a heavy water plant

International Nuclear Information System (INIS)

Baynes, C.J.

1986-05-01

This report provides a summary of work carried out on behalf of the Atomic Energy Control Board, concerned with the consequences of accidental releases to the atmosphere of hydrogen sulphide (H 2 S) at a heavy water plant. In this study, assessments of consequences are made in terms of the probabilities of a range of possible outcomes, i.e., numbers of fatalities, given a certain release scenario. The report describes the major features of a computer model which was developed to calculate the consequences and their associated probabilities, and the major input data used in applying the model to a consequence assessment of the Bruce heavy water plant (HWP) in Ontario. The results of the sensitivity analyses of the model are summarized. Finally, the results of the consequence assessments of 43 accidental release scenarios at the Bruce HWP are summarized, together with a number of conclusions which were drawn from these results regarding the predicted consequences and the factors which influence them

Wind field forecast for accidental release of radiative materials

International Nuclear Information System (INIS)

Kang Ling; Chen Jiayi; Cai Xuhui

2003-01-01

A meso-scale wind field forecast model was designed for emergency environmental assessment in case of accidental release of radiative materials from a nuclear power station. Actual practice of the model showed that it runs fast, has wind field prediction function, and the result given is accurate. With meteorological data collected from weather stations, and pre-treated by a wind field diagnostic model, the initial wind fields at different times were inputted as initial values and assimilation fields for the forecasting model. The model, in turn, worked out to forecast meso-scale wind field of 24 hours in a horizontal domain of 205 km x 205 km. And then, the diagnostic model was employed again with the forecasting data to obtain more detail information of disturbed wind field by local terrain in a smaller domain of 20.5 km x 20.5 km, of which the nuclear power station is at the center. Using observation data in January, April, July and October of 1996 over the area of Hangzhou Bay, wind fields in these 4 months were simulated by different assimilation time and number of the weather stations for a sensitive test. Results indicated that the method used here has increased accuracy of the forecasted wind fields. And incorporating diagnostic method with the wind field forecast model has greatly increased efficiency of the wind field forecast for the smaller domain. This model and scheme have been used in Environmental Consequence Assessment System of Nuclear Accident in Qinshan Area

Atmospheric dispersion of radionuclides released by a nuclear plant

International Nuclear Information System (INIS)

Barboza, A.A.

1989-01-01

A numerical model has been developed to simulate the atmospheric dispersion of radionuclides released by a nuclear plant operating under normal conditions. The model, based on gaussian plume representation, accouts for and evaluates several factors which affect the concentraction of effluents in the atmosphere, such as: ressuspension, deposition, radioactive decay, energy and type of the radiation emitted, among others. The concentraction of effluents in the atmosphere is calculated for a uniform mesh of points around the plant, allowing the equivalent doses to be then evaluated. Simulations of the atmosphere dispersion of radioactive plumes of Cs 137 and Ar 41 have been performed assuming a constant rate of release, as expected from the normal operation of a nuclear plant. Finally, this work analyzes the equivalent doses at ground level due to the dispersion of Cs 137 and Ar 41 , accumulated over one year and determines the isodose curves for a hypothetical site. (author) [pt

Joint release rate estimation and measurement-by-measurement model correction for atmospheric radionuclide emission in nuclear accidents: An application to wind tunnel experiments.

Science.gov (United States)

Li, Xinpeng; Li, Hong; Liu, Yun; Xiong, Wei; Fang, Sheng

2018-03-05

The release rate of atmospheric radionuclide emissions is a critical factor in the emergency response to nuclear accidents. However, there are unavoidable biases in radionuclide transport models, leading to inaccurate estimates. In this study, a method that simultaneously corrects these biases and estimates the release rate is developed. Our approach provides a more complete measurement-by-measurement correction of the biases with a coefficient matrix that considers both deterministic and stochastic deviations. This matrix and the release rate are jointly solved by the alternating minimization algorithm. The proposed method is generic because it does not rely on specific features of transport models or scenarios. It is validated against wind tunnel experiments that simulate accidental releases in a heterogonous and densely built nuclear power plant site. The sensitivities to the position, number, and quality of measurements and extendibility of the method are also investigated. The results demonstrate that this method effectively corrects the model biases, and therefore outperforms Tikhonov's method in both release rate estimation and model prediction. The proposed approach is robust to uncertainties and extendible with various center estimators, thus providing a flexible framework for robust source inversion in real accidents, even if large uncertainties exist in multiple factors. Copyright © 2017 Elsevier B.V. All rights reserved.

Accidental Release of Chlorine from a Storage Facility and an On-Site Emergency Mock Drill: A Case Study

Directory of Open Access Journals (Sweden)

Ambalathumpara Raman Soman

2015-01-01

Full Text Available In the current industrial scenario there is a serious need for formulating strategies to handle hazardous substances in the safest way. Manufacture, storage, and use of hazardous substances pose a serious risk to industry, people, and the environment. Accidental release of toxic chemicals can lead to emergencies. An emergency response plan (ERP is inevitable to minimize the adverse effects of such releases. The on-site emergency plan is an integral component of any process safety and risk management system. This paper deals with an on-site emergency response plan for a chlorine manufacturing industry. It was developed on the basis of a previous study on chlorine release and a full scale mock drill has been conducted for testing the plan. Results indicated that properly trained personnel can effectively handle each level of incidents occurring in the process plant. As an extensive guideline to the district level government authorities for off-site emergency planning, risk zone has also been estimated with reference to a chlorine exposure threshold of 3 ppm.

The European Community dimension to the problem of accidental radioactive releases to the environment

International Nuclear Information System (INIS)

Bennett, E.

1989-01-01

The European Community has to comply with the provisions of the Euratom Treaty, 1957. As well as providing the conditions necessary for the growth of nuclear industries it lays down the task to establish uniform Safety Standards to protect the health of workers and of the general public. This includes emergency planning in case of nuclear accidents. As a result the Community followed the guide, published in 1982 by the International Commission on Radiological Protection, on the radiological protection criteria for controlling doses to the public in the event of accidental releases of radioactive materials. However when the Chernobyl accident occured the Community and International arrangements proved to be inadequate to respond to the consequent widespread contamination over Europe. Measures have been taken since then to improve the preparedness of the Community. They include better exchange of information, control of contaminated foodstuffs and better information to the public. (U.K.)

Results of atmospheric diffusion experiments, vol.3

International Nuclear Information System (INIS)

Kakuta, Michio; Hayashi, Takashi; Adachi, Takashi.

1988-02-01

An extensive study on 'Emergency monitoring and prediction code system' has been carried in JAERI since 1980. Six series of field experiments on atmospheric diffusion were conducted to develop and verify the prediction models for environmental concentration distribution following accidental release of radioactivity. Results of field experiments (Inland complex terrain, surface and elevated point sources) conducted in 15 - 19th October 1984 (TSUKUBA84) and in 6 - 10th November 1985 (TSUKUBA85) are contained in this volume. (author)

Assessment of radioactive material released from a fuel fabrication plant under accidental conditions

International Nuclear Information System (INIS)

1981-01-01

This report evaluates the amounts of fissile material released both inside and outside a mixed oxide fuel fabrication plant (MOFFP) for light water reactors. The first section begins with a descriptive study of fissile material containment systems, and the methods available for quantifying accident occurrence probabilities. In addition to accidents common to all industrial facilities, other much rarer accidents were considered, such as aircraft crashes. The minimum occurrence probability limit for consideration in this study was set at 10 -6 per annum. The second part of this report attempts to assess the consequences of the accidents considered (i.e. with occurrence probabilities exceeding 10 -6 per annum) by determining maximum values for such accidents. Acts of sabotage and other accidents of this type are beyond the scope of this study and were not taken into consideration. The most serious potential accident would be a fire involving all of the glove boxes in the PuO 2 powder calcination and preparation cell, which could release 76.5 mg of PuO 2 powder into the atmosphere; the occurrence probability of such an accident, however, is slight (less than 10 -5 per annum). The second possibility, is a specially nuclear hazard that would release fission products into the atmosphere. The occurrence probability of such an accident is currently evaluated at 10 -3 per annum

Measured tritium in groundwater related to atmospheric releases from the Marcoule nuclear site

International Nuclear Information System (INIS)

Levy, F.; Clech, A.; Crochet, P.

1996-01-01

Tritium is released into the atmosphere during normal operation from the industrial facilities operated by COGEMA at Marcoule; over a 1 5-year period covered by this study (1979-1994) the quantities ranged from 4940 to 520 TBq·yr -1 . Atmospheric release in rainy weather results in tritium migration into the ground water by a series of mechanisms associated with the water cycle. COGEMA monitors the ground water by means of bore holes. Atmospheric monitoring is also routinely performed; data on the tritium activity concentration in the air and rainwater are available for the same time period. A simplified observation suggests a relation between the atmospheric tritium release and the ground water radioactivity. In 1994, the activity ranged from 100 to 200 Bq·l -1 in the boreholes located 1 km and 2 km downwind from the point of release, diminishing with the distance to less than 20 Bq·l -1 at about 3 km. The authors attempted to model two types of transfers: atmospheric transfer from the release chimney to the borehole, and transfer in the alluvial ground water. The aquifer comprises the alluvial deposits forming the Codolet plain extending to the south of Marcoule, downwind from the point of atmospheric tritium release. The hydrogeology of the entire Marcoule site has been described in previous studies by the French bureau of geological and mineralogical research (BRGM) and ANTEA. (author)

Development of emergency response tools for accidental radiological contamination of French coastal areas

International Nuclear Information System (INIS)

Duffa, Céline; Bailly du Bois, Pascal; Caillaud, Matthieu; Charmasson, Sabine; Couvez, Céline; Didier, Damien; Dumas, Franck; Fievet, Bruno; Morillon, Mehdi; Renaud, Philippe

2016-01-01

The Fukushima nuclear accident resulted in the largest ever accidental release of artificial radionuclides in coastal waters. This accident has shown the importance of marine assessment capabilities for emergency response and the need to develop tools for adequately predicting the evolution and potential impact of radioactive releases to the marine environment. The French Institute for Radiological Protection and Nuclear Safety (IRSN) equips its emergency response centre with operational tools to assist experts and decision makers in the event of accidental atmospheric releases and contamination of the terrestrial environment. The on-going project aims to develop tools for the management of marine contamination events in French coastal areas. This should allow us to evaluate and anticipate post-accident conditions, including potential contamination sites, contamination levels and potential consequences. In order to achieve this goal, two complementary tools are developed: site-specific marine data sheets and a dedicated simulation tool (STERNE, Simulation du Transport et du transfert d’Eléments Radioactifs dans l'environNEment marin). Marine data sheets are used to summarize the marine environment characteristics of the various sites considered, and to identify vulnerable areas requiring implementation of population protection measures, such as aquaculture areas, beaches or industrial water intakes, as well as areas of major ecological interest. Local climatological data (dominant sea currents as a function of meteorological or tidal conditions) serving as the basis for an initial environmental sampling strategy is provided whenever possible, along with a list of possible local contacts for operational management purposes. The STERNE simulation tool is designed to predict radionuclide dispersion and contamination in seawater and marine species by incorporating spatio-temporal data. 3D hydrodynamic forecasts are used as input data. Direct discharge points or

Implementation of the Clean Air Act, Title III, Section 112(r) Prevention of Accidental Release Rule requirements at U.S. DOE Oak Ridge Reservation facilities

International Nuclear Information System (INIS)

Humphreys, M.P.

1997-01-01

Title III, Section 112(r) of the Clean Air Act (CAA) Amendments of 1990 requires the Environmental Protection Agency (EPA) to promulgate regulations to prevent accidental releases of regulated substances and to reduce the severity of those releases that do occur. The final EPA rule for Risk Management Programs under Section 112(r)(7) of the CAA, promulgated June 20, 1996, applies to all stationary sources with processes that contain more than a threshold quantity of any of 139 regulated substances listed under 40 CFR 68.130. All affected sources will be required to prepare a risk management plan which must be submitted to EPA and be made available to state and local governments and to the public. This paper will provide details of initiatives underway at US Department of Energy (DOE) Oak Ridge Reservation (ORR) Facilities for implementation of the Prevention of Accidental Release Rule. The ORR encompasses three DOE Facilities: the Y-12 Plant, Oak Ridge National Laboratory (ORNL), and the K-25 Site. The Y-12 Plant manufactures component parts for the national nuclear weapons program; the ORNL is responsible for research and development activities including nuclear engineering, engineering technologies, and the environmental sciences; and the K-25 Site conducts a variety of research and development activities and is the home of a mixed waste incinerator. ORR activities underway and soon to be undertaken toward implementation of the Prevention of Accidental Release Rule include: compilation of inventories of regulated substances at all processes at each of the three ORR Facilities for determination of affected processes and facilities; plans for inventory reduction to levels below threshold quantities, where necessary and feasible; determination of the overlap of processes subject to the OSHA PSM Standard and determination of parallel requirements; preparation of Risk Management Plans and Programs for affected processes and facilities including detailed requirements

Report of the first research co-ordination meeting on the co-ordinated research programme: Development and selection of analytical techniques for measuring accidentally released radionuclides in environment

International Nuclear Information System (INIS)

2001-01-01

The participants at the second Research Co-ordination Meeting (Vienna, 12-16 August 1991) of the CRP on 'Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples', recommended that a new CRP be established. The current CRP on 'Development and Selection of Analytical Techniques and Procedures for Measuring Accidentally Released Radionuclides in Environment' was established based on this recommendation. The objectives of this CRP are to conduct research and development on applicable methodologies for response to accidental releases, and to improve and maintain the capabilities of the network of laboratories and provide training of individuals within member states. Thus, the CRP serves as a vehicle to maintain contact within the network of laboratories, while developing and transferring analytical techniques and procedures for measuring accidentally released radioactivity. The purpose of the Research Co-ordination Meeting is to discuss the proposed research programs, the status to date and the work planned for the duration of the CRP. The meeting also provides the opportunity for the CRP participants to exchange ideas and possibly develop collaborations in their research. The members of the CRP also need to discuss issues related to the previous CRP on Rapid methods. These include: the preparation of the final report of the previous CRP, the preparation of an addendum to TRS-295 and the ultimate revision or updating of TRS-295. Finally, it is intended that the members of the CRP should discuss the mandate and scope of work of the network of analytical laboratories and the steps needed to firmly establish this network

Time-integrated thyroid dose for accidental releases from Pakistan Research Reactor-1

International Nuclear Information System (INIS)

Raza, S Shoaib; Iqbal, M; Salahuddin, A; Avila, R; Pervez, S

2004-01-01

The two-hourly time-integrated thyroid dose due to radio-iodines released to the atmosphere through the exhaust stack of Pakistan Research Reactor-1 (PARR-1), under accident conditions, has been calculated. A computer program, PAKRAD (which was developed under an IAEA research grant, PAK/RCA/8990), was used for the dose calculations. The sensitivity of the dose results to different exhaust flow rates and atmospheric stability classes was studied. The effect of assuming a constant activity concentration (as a function of time) within the containment air volume and an exponentially decreasing air concentration on the time-integrated dose was also studied for various flow rates (1000-50,000 m 3 h -1 ). The comparison indicated that the results were insensitive to the containment air exhaust rates up to or below 2000 m 3 h -1 , when the prediction with the constant activity concentration assumption was compared to an exponentially decreasing activity concentration model. The results also indicated that the plume touchdown distance increases with increasing atmospheric stability. (note)

Liquid pathway generic study. Impacts of accidental radioactive releases to the hydrosphere from floating and land-based nuclear power plants

International Nuclear Information System (INIS)

1978-02-01

The staff concludes that for representative sites, there are differences in the impacts of accidental radioactive releases to the hydrosphere between floating nuclear plants (FNPs) and land-based plants (LBPs) of the ice-condenser type. The consequences of releases from design basis accidents are found to be lower for an FNP than for an LBP. For core-melt events which we consider to be of very low probability, the staff results indicate that the expected liquid pathway consequences are higher at an FNP than at an LBP, and that interdiction at the site is not likely for an FNP. The staff considers this combination of differences in release magnitude and interdiction potential to be significant. An assessment of the overall significance of the total risk associated with potential releases to liquid and airborne pathways will be considered in a forthcoming environmental impact statement for the FNP. This environmental impact statement will include a consideration of the environmental, social, and economic impacts of the operation of the FNP, as well as a value-impact analysis of alternatives which may avoid or mitigate radiological impacts to the environment

Modelling of tritium dispersion from postulated accidental release of nuclear power plants

International Nuclear Information System (INIS)

Soares, Abner Duarte

2010-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. This exercise was accomplished with the aid of a code system (SisBAHIA) developed in the Rio de Janeiro Federal University (COPPE/UFRJ). The CANDU reactor is one that uses heavy water (D 2 O) as moderator and coolant of the core. It was postulated, then, the LOCA (Loss of Coolant Accident) accident in the emergency cooling system of the nucleus (without fusion), where was lost 66 m 3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped and operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m 3 ) during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10 9 to 5x10 5 Bq/m 3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value ( 3 ). (author)

Evaluation of radioxenon releases in Australia using atmospheric dispersion modelling tools

International Nuclear Information System (INIS)

Tinker, Rick; Orr, Blake; Grzechnik, Marcus; Hoffmann, Emmy; Saey, Paul; Solomon, Stephen

2010-01-01

The origin of a series of atmospheric radioxenon events detected at the Comprehensive Test Ban Treaty Organisation (CTBTO) International Monitoring System site in Melbourne, Australia, between November 2008 and February 2009 was investigated. Backward tracking analyses indicated that the events were consistent with releases associated with hot commission testing of the Australian Nuclear Science Technology Organisation (ANSTO) radiopharmaceutical production facility in Sydney, Australia. Forward dispersion analyses were used to estimate release magnitudes and transport times. The estimated 133 Xe release magnitude of the largest event (between 0.2 and 34 TBq over a 2 d window), was in close agreement with the stack emission releases estimated by the facility for this time period (between 0.5 and 2 TBq). Modelling of irradiation conditions and theoretical radioxenon emission rates were undertaken and provided further evidence that the Melbourne detections originated from this radiopharmaceutical production facility. These findings do not have public health implications. This is the first comprehensive study of atmospheric radioxenon measurements and releases in Australia.

Air concentration and ground deposition following radioactive airborne releases

International Nuclear Information System (INIS)

Brofferio, C.; Cagnetti, P.; Ferrara, V.

1985-01-01

The fundamental aim of this report is to provide the mathematical and physical operational basis for the evaluation of air concentration and ground deposition, following radioactive airborne releases from a nuclear power plant, both during normal operations and in accidental conditions. As far as accidental releases are concerned, the basical assumptions on meteorological and diffusive situation are considered from a safety point of view: namely those pessimistic but realistically representative situation are taken into account which lead to maximum air concentration and ground deposition values, even if characterized by low recurrence probability. Those elements are the inputs for many environmental transfer models of maximum consequence evaluations up to man. As far as routine releases are concerned, it is shown, together with the usual models based on long term averaged meteorological conditions, also models studied to estimate atmospheric diffusion and deposition in low wind situations and in fog conditions, being those latter very frequent in the Po valley. Finally, the main operations and modalities of collecting and elaborating meteorological data for for radioprotection evaluations are also shown. It is to be pointed out that the methods and the models developed and considered in this work are of a more general validity, and can be also used for applications concerning non-radioactive releases, as it is the case when dealing with conventional power plants

Probabilistic consequence assessment of hydrogen sulphide releases from a heavy water plant

International Nuclear Information System (INIS)

1983-06-01

This report is the second in a series concerned with the evaluation of the consequences to the public of an accidental release of hydrogen sulphide (H 2 S) to the atmosphere following a pipe or pressure envelope failure, or some other process upset, at a heavy water plant. It consists of documentation of the code GASPROB, which has been developed to provide consequence probabilities for a range of postulated releases. The code includes mathematical simulations of initial gas behaviour upon release to the atmosphere, such as gravitational settling of a cold release and the rise of jets and flares, subsequent atmospheric dispersion under a range of weather conditions, and the toxic effects on the exposed population. The code makes use of the site-specific dispersion climatology, topography and population distribution, as well as the probabilistic lethal dose data for the released gas. Output for a given postulated release can be provided in terms of the concentration of the gas at ground level around the point of release, projected numbers of fatalities within specified areas and the projected total fatalities regardless of location. This report includes a general description of GASPROB, and specifics of the code structure, the function of each subroutine, input and output data, and the permanent data files established. Three appendices to the report contain a complete code listing, detailed subroutine descriptions and a sample output

NRC's rulemaking to require materials licensees to be financially responsible for cleanup of accidental releases

International Nuclear Information System (INIS)

Seeman, M.J.

1987-01-01

On June 7, 1985, the US Nuclear Regulatory Commission (NRC) published an advance notice of proposed rulemaking (ANPRM) in the Federal Register to address funding for cleanup of accidents and unexpected decontamination by certain materials licensees. The NRC asked for public comment to help them determine whether to amend its regulations to require certain materials and fuel cycle licensees to demonstrate that they possess adequate financial means to pay for cleanup of accidental releases of radioactive materials. If licensees lack adequate financial resources and funds are to available for prompt cleanup, the consequences could be potentially significant for the public, the licencee and the federal government. The purpose of this paper is to explain the purpose and scope of the Commission's proposed regulatory action, as well as describing several accidents that made the Commission consider this action. Additionally, the paper will address other regulatory precedents. Finally, the paper will conclude by generally characterizing the public comments and items of concern raised by commenters

An overview of organically bound tritium experiments in plants following a short atmospheric HTO exposure.

Science.gov (United States)

Galeriu, D; Melintescu, A; Strack, S; Atarashi-Andoh, M; Kim, S B

2013-04-01

The need for a less conservative, but reliable risk assessment of accidental tritium releases is emphasized in the present debate on the nuclear energy future. The development of a standard conceptual model for accidental tritium releases must be based on the process level analysis and the appropriate experimental database. Tritium transfer from atmosphere to plants and the subsequent conversion into organically bound tritium (OBT) strongly depends on the plant characteristics, seasons, and meteorological conditions, which have a large variability. The present study presents an overview of the relevant experimental data for the short term exposure, including the unpublished information, also. Plenty of experimental data is provided for wheat, rice, and soybean and some for potato, bean, cherry tomato, radish, cabbage, and tangerine as well. Tritiated water (HTO) uptake by plants during the daytime and nighttime has an important role in further OBT synthesis. OBT formation in crops depends on the development stage, length, and condition of exposure. OBT translocation to the edible plant parts differs between the crops analyzed. OBT formation during the nighttime is comparable with that during the daytime. The present study is a preliminary step for the development of a robust model of crop contamination after an HTO accidental release. Copyright © 2012 Elsevier Ltd. All rights reserved.

International Comprehensive Ocean-Atmosphere Data Set (ICOADS) with Enhanced Trimming, Release 3

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This dataset contains the latest official release of International Comprehensive Ocean-Atmosphere Data Set (ICOADS) with Enhanced Trimming, provided in a common...

Nuclear power: Accidental releases - practical guidance for public health action

International Nuclear Information System (INIS)

1987-01-01

The disaster at Chernobyl, USSR, has caused a major crisis of confidence in nuclear safety, and highlighted the need for comprehensive contingency planning for - and emergency response to - such accidents. This report gives practical guidance on how the authorities should deal with an accident in any type of nuclear installation, whether it involves accidental releases to the air or into water. It is based on principles developed in a previous WHO report published in 1984. It summarizes the range of accidents for which plans need to be made to protect the public, the measures to be taken and the levels of dose at which they should be applied. It indicates how to measure the levels of exposure and what are the most likely routes of exposure. It then outlines the problems faced by public health authorities and medical practitioners, and the administrative arrangements that will have to be made. The example used is of a standard pressurized light water reactor of the type currently used for electricity generation, but many of the features will be common to other nuclear installations as well. This report is addressed to those organizations and individuals responsible for public health in the event of a nuclear accident. It will also be of use to those medical practitioners who are not administratively responsible in an accident, but who may need to be aware of the consequences and of the action to be taken in the aftermath of an accident. Coordination is vital between the public health administration and the organizations with direct responsibilities in the event of an accident, and this report is essential reading for them all. 29 refs, 2 figs, 7 tabs

Analysis of an LPG accidental release

Energy Technology Data Exchange (ETDEWEB)

Demichela, M.; Piccinini, N.; Poggio, A.

2004-03-01

An industrial LPG storage accident due to the release of propane from a tanker is described in this paper and the sequence of events that led to the collapse of a storage tank is examined using simulation software. A model taking both released flows into account as a radiant thermal contribution in the presence of flames is presented. The progression of the accident is assessed through digitalization and processing of the film of the fireball produced by about 500 L of LPG, whose diameter was calculated as approximately 50 m. (author)

Calculation of Doses Due to Accidentally Released Plutonium From An LMFBR

Energy Technology Data Exchange (ETDEWEB)

Fish, B.R.

2001-08-07

Experimental data and analytical models that should be considered in assessing the transport properties of plutonium aerosols following a hypothetical reactor accident have been examined. Behaviors of released airborne materials within the reactor containment systems, as well as in the atmosphere near the reactor site boundaries, have been semiquantitatively predicted from experimental data and analytical models. The fundamental chemistry of plutonium as it may be applied in biological systems has been used to prepare models related to the intake and metabolism of plutonium dioxide, the fuel material of interest. Attempts have been made to calculate the possible doses from plutonium aerosols for a typical analyzed release in order to evaluate the magnitude of the internal exposure hazards that might exist in the vicinity of the reactor after a hypothetical LMFBR (Liquid-Metal Fast Breeder Reactor) accident. Intake of plutonium (using data for {sup 239}Pu as an example) and its distribution in the body were treated parametrically without regard to the details of transport pathways in the environment. To the extent possible, dose-response data and models have been reviewed, and an assessment of their adequacy has been made so that recommended or preferred practices could be developed.

Mesoscale atmospheric modeling of accidental toxic and radioactive releases for emergency response at SRS

International Nuclear Information System (INIS)

O'Steen, B.L.; Fast, J.D.

1992-01-01

In August of 1991, the Environmental Transport Group (ETG) began the development of an advanced Emergency Response (ER) system based upon the Colorado State University Regional Atmospheric Modeling System 1 (RAMS). This model simulates the three-dimensional, time-dependent, flow field and thermodynamic structure of the planetary boundary layer (PBL). A companion Lagrangian Particle Dispersion Model 2 (LPDM) simulates contaminant transport based on the flow and turbulence fields generated by RAMS. The current report describes progress to date on this project in the areas of data development, data assimilation, and operational (real-time) procedures. In particular, a diagnostic capability for simulating contaminant transport is demonstrated

Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants

International Nuclear Information System (INIS)

Aguiar, Andre Silva de; Simoes Filho, Francisco Fernando Lamego; Lapa, Celso Marcelo Franklin; Alvim, Antonio Carlos Marques; Soares, Abner Duarte

2013-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA - Loss of Coolant Accident -, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m 3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m 3 ), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10 9 to 5x10 5 Bq/m 3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value ( 3 ). (author)

Assessment of the public health impact from the accidental release of UF6 at the Sequoyah Fuels Corporation Facility at Gore, Oklahoma (Docket No. 40-8027, License No. SUB-1010). Main report. Volume 1

International Nuclear Information System (INIS)

1986-03-01

Following the accidental release of UF 6 from the Sequoyah Fuels Facility on January 4, 1986, an Ad Hoc Interagency Public Health Assessment Task Force was established. The Task Force consists of technical staff members from various agencies who have prepared this assessment of the public health impact associated with the accidental release. The assessment consists of two volumes and is based on data from the accident available as of February 14, 1986. Volume 1 of the report describes the effects from the intake of uranium and fluoride and summarizes the findings and recommendations of the Task Force. Volume 2 of the report contains Appendices which provide more detailed information used in the assessment and support the discussion in Volume 1. 57 refs., 26 figs., 12 tabs

The release code package REVOLS/RENONS for fission product release from a liquid sodium pool into an inert gas atmosphere

International Nuclear Information System (INIS)

Starflinger, J.; Scholtyssek, W.; Unger, H.

1994-12-01

For aerosol source term considerations in the field of nuclear safety, the investigation of the release of volatile and non-volatile species from liquid surfaces into a gas atmosphere is important. In case of a hypothetical liquid metal fast breeder reactor accident with tank failure, primary coolant sodium with suspended or solved fuel particles and fission products may be released into the containment. The computer code package REVOLS/RENONS, based on a theoretical mechanistic model with a modular structure, has been developed for the prediction of sodium release as well as volatile and non-volatile radionuclide release from a liquid pool surface into the inert gas atmosphere of the inner containment. Hereby the release of sodium and volatile fission products, like cesium and sodium iodide, is calculated using a theoretical model in a mass transfer coefficient formulation. This model has been transposed into the code version REVOLS.MOD1.1, which is discussed here. It enables parameter analysis under highly variable user-defined boundary conditions. Whereas the evaporative release of the volatile components is governed by diffusive and convective transport processes, the release of the non-volatile ones may be governed by mechanical processes which lead to droplet entrainment from the wavy pool surface under conditions of natural or forced convection into the atmosphere. The mechanistic model calculates the liquid entrainment rate of the non-volatile species, like the fission product strontium oxide and the fuel (uranium dioxide) from a liquid pool surface into a parallel gas flow. The mechanistic model has been transposed into the computer code package REVOLS/RENONS, which is discussed here. Hereby the module REVOLS (RElease of VOLatile Species) calculates the evaporative release of the volatile species, while the module RENONS (RElease of NON-Volatile Species) computes the entrainment release of the non-volatile radionuclides. (orig./HP) [de

The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: sensitivity of the incidence of early effects to the duration

International Nuclear Information System (INIS)

Hemming, C.R.; Hallam, J.; Kelly, G.N.

1979-12-01

The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR were assessed in a study published in 1977 (NRPB-R53). In that study representative values were in general adopted for each of the important parameters while recognising that in reality they could vary considerably. In this study the sensitivity of the predicted incidence of early effects to the release duration, in so far as it affects the crosswind spread of the activity, is investigated. Two situations are considered; a short release in which the crosswind distribution of the activity is assumed to be Gaussian and a more prolonged release (as modelled in the initial study) in which the crosswind distribution of activity is assumed uniform over a 30 0 sector. For the particular conditions and population distributions considered, the incidence of early effects is greater for the short compared with the more prolonged release. The size of the increase depends upon the radionuclide composition, the magnitude of the release, the distribution of the exposed population, and the prevailing meteorological conditions, but in general the increase is not large. This relatively limited sensitivity indicates that the results obtained in the initial study can be assumed, to a good approximation, to be applicable irrespective of the release duration. (author)

The choice of individual dose criterion at which to restrict agricultural produce following an unplanned release of radioactive material to atmosphere

CERN Document Server

Dionian, J

1985-01-01

In the event of an accidental release of radioactive material to atmosphere, the introduction of emergency countermeasures will be based on the need to limit the risk to individuals. However, it has been suggested that a form of cost-benefit analysis may be used as an input to decisions on the withdrawal of countermeasures, although it is recognised that these decisions may be influenced by factors other than those directly related to radiological protection. In this study, a method based on cost-benefit analysis is illustrated for assessing the optimum level of individual dose at which restrictions on agricultural production may be considered. This requires monetary values to be assigned to both the lost food production and to the health detriment, expressed as the collective effective dose equivalent commitment. It has been assumed in this analysis that food-supply restrictions are both introduced and withdrawn at the same projected level of annual individual dose. The effect on the optimum dose level of th...

National atmospheric release advisory center (NARAC) tools and services for emergency management

International Nuclear Information System (INIS)

Nasstrom, J.

2003-01-01

Full text: This paper describes recent scientific and technological advances in the National Atmospheric Release Advisory Center (NARAC) that aid emergency management. The U.S. Department of Energy's NARAC system provides tools and services that help map the probable spread of hazardous material accidentally or intentionally released into the atmosphere. Located at Lawrence Livermore National Laboratory, NARAC is a national support and resource center for planning, real-time assessment and detailed studies of incidents involving a wide variety of hazards, including nuclear, radiological, chemical, or biological emissions. In recent years, the DOE National Nuclear Security Agency (NNSA) Office of Emergency Response and Chemical and Biological National Security Program (CBNP) have supported major upgrades and modernization of NARAC that have advanced the accuracy and utility of NARAC products for emergency planning and management. A new NARAC central modeling system, which became operational in the year 2000, has provided a higher-resolution suite of diagnostic and prognostic meteorological models, and a Lagrangian particle dispersion model, for producing predictions of air concentration, ground deposition, and dose. The 3-D meteorological data assimilation model, ADAPT, and Lagrangian particle dispersion model, LODI, allow the simulation of mean wind advection, turbulent diffusion, radioactive decay and production, bio-agent degradation, first-order chemical reactions, wet deposition, gravitational settling, dry deposition, and buoyant/momentum plume rise. The functions performed by this system have been fully automated to minimized response time for emergencies. An in-house version of the Naval Research Laboratory's COAMPS numerical weather prediction model is used to provide mesoscale forecasts. The final plume predictions are plotted with key geographical information (including estimates of the counts of affected population), and with applicable U

Manual of dose evaluation from atmospheric releases

Energy Technology Data Exchange (ETDEWEB)

Shirvaikar, V V; Abrol, V [Health Physics Division, Bhabha Atomic Research Centre, Bombay (India)

1978-07-01

The problem of dose evaluation from atmospheric releases is reduced to simple arithmetic by giving tables of concentrations and time integrated concentrations for instantaneous plumes and long time (1 year), sector averaged plumes for distances upto 10 km, effective release heights of upto 200 m and the six Pasquill stability classes. Correction factors for decay, depletion due to deposition and rainout are also given. Inhalation doses, immersion doses and contamination levels can be obtained from these by using multiplicative factors tabulated for various isotopes of significance. Tables of external gamma doses from plume are given separately for various gamma energies. Tables are also given to evaluate external beta and gamma dose rates from contaminated surfaces. The manual also discusses the basic diffusion model relevant to the problem. (author)

Comparison of the MARC and CRAC2 programs for assessing the radiological consequences of accidental releases of radioactive material

CERN Document Server

Hemming, C R; Charles, D; Ostmeyer, R M

1983-01-01

This report describes a comparison of the MARC (Methodology for Assessing Radiological Consequences) and CRAC2 (Calculation of Reactor Accident Consequences, version 2) computer programs for assessing the radiological consequences of accidental releases of radioactive material. A qualitative comparison has been made of the features of the constituent sub-models of the two codes, and potentially the most important differences identified. The influence of these differences has been investigated quantitatively by comparison of the predictions of the two codes in a wide variety of circumstances. Both intermediate quantities and endpoints used as a measure of risk have been compared in order to separate the variables more clearly. The results indicate that, in general, the predictions of MARC and CRAC2 are in good agreement.

Evidence Theory Based Uncertainty Quantification in Radiological Risk due to Accidental Release of Radioactivity from a Nuclear Power Plant

International Nuclear Information System (INIS)

Ingale, S. V.; Datta, D.

2010-01-01

Consequence of the accidental release of radioactivity from a nuclear power plant is assessed in terms of exposure or dose to the members of the public. Assessment of risk is routed through this dose computation. Dose computation basically depends on the basic dose assessment model and exposure pathways. One of the exposure pathways is the ingestion of contaminated food. The aim of the present paper is to compute the uncertainty associated with the risk to the members of the public due to the ingestion of contaminated food. The governing parameters of the ingestion dose assessment model being imprecise, we have approached evidence theory to compute the bound of the risk. The uncertainty is addressed by the belief and plausibility fuzzy measures.

Impact of Industrial Releases on Inshas Area

International Nuclear Information System (INIS)

El-Messiry, A.M.; Aly, M.M.

1999-01-01

Two Egyptian research reactors are located within the nuclear research center at Inshas area, 30 km north east of Cairo. This area are crowded by different industrial plants. The releases from them has a hazardous and economical effects on the research center workers and the surrounding inhabitancy. In the present work we study these effects. A meteorological regional specific data is considered all over the year, including a wind rose characterization. The study considered both normal operating conditions and an accidental releases. The results shows that there are a considerable risk due to normal releases in some areas downwind direction of the major releases, and a highly risk in areas subjected to major exposure. Regional maps of emission distribution, economical damage , pollutant concentration are obtained. The study helps to identify solutions to problems of atmospheric protection. It can be used as a decision support for the environmental, economic, and innovation planning at the national levels taking into consideration the national pollution standards and variety of existing emission sources

Transfer of accidentally released radionuclides in agricultural systems (TARRAS)

International Nuclear Information System (INIS)

Cancio, D.; Maubert, Colle; Rauret, G.; Grandison, A.S.

1993-01-01

The aim of this project is to contribute to the reliability of radiological assessment methods and establish a scientific base for the design of post-accident countermeasures. Three main aspects are considered in this project: A simulated accidental source term is used and the behaviour of aerosol deposits containing Sr, Cs and Ag isotopes are followed in some European soil-crop systems; the modification of radionuclide transfer rates through the food chain by well established food processing techniques is studied for Sr, Cs, Co and Ru; the project includes a study on the specific mediterranean diet and transfer data that are compared with currently used generic parameters. Seven contributions of the project for the reporting period are presented. (R.P.) 11 figs., 12 tabs

Visits to Australia by nuclear powered or armed vessels: contingency planning for the accidental release of ionizing radiation

International Nuclear Information System (INIS)

1989-01-01

The report refers to the adequacy of current contingency planning by the Australian Federal and Senate authorities to deal with the accidental release of ionizating radiation from visiting nuclear powered or armed vessels in Australian waters and ports. Much of the material was obtained in response to questions put in writing by the Senate Standing Committee to the Department of Defence, ANSTO and others. In addition, the report contains relevant information from Commonwealth documents as well as the Committee findings and recommendations. Issues considered include: types of visiting nuclear powered vessels, accident likelihood and consequences, differences between naval and land-based reactors, safety records. The persons or organizations who made submissions or appeared in all public hearings are listed in the appendixes, along with all visits to Australian ports by nuclear powered warships from 1976 to 1988

Game theory of pre-emptive vaccination before bioterrorism or accidental release of smallpox.

Science.gov (United States)

Molina, Chai; Earn, David J D

2015-06-06

Smallpox was eradicated in the 1970s, but new outbreaks could be seeded by bioterrorism or accidental release. Substantial vaccine-induced morbidity and mortality make pre-emptive mass vaccination controversial, and if vaccination is voluntary, then there is a conflict between self- and group interests. This conflict can be framed as a tragedy of the commons, in which herd immunity plays the role of the commons, and free-riding (i.e. not vaccinating pre-emptively) is analogous to exploiting the commons. This game has been analysed previously for a particular post-outbreak vaccination scenario. We consider several post-outbreak vaccination scenarios and compare the expected increase in mortality that results from voluntary versus imposed vaccination. Below a threshold level of post-outbreak vaccination effort, expected mortality is independent of the level of response effort. A lag between an outbreak starting and a response being initiated increases the post-outbreak vaccination effort necessary to reduce mortality. For some post-outbreak vaccination scenarios, even modest response lags make it impractical to reduce mortality by increasing post-outbreak vaccination effort. In such situations, if decreasing the response lag is impossible, the only practical way to reduce mortality is to make the vaccine safer (greater post-outbreak vaccination effort leads only to fewer people vaccinating pre-emptively). © 2015 The Author(s) Published by the Royal Society. All rights reserved.

Release mitigation spray safety systems for chemical demilitarization applications.

Energy Technology Data Exchange (ETDEWEB)

Leonard, Jonathan; Tezak, Matthew Stephen; Brockmann, John E.; Servantes, Brandon; Sanchez, Andres L.; Tucker, Mark David; Allen, Ashley N.; Wilson, Mollye C.; Lucero, Daniel A.; Betty, Rita G.

2010-06-01

Sandia National Laboratories has conducted proof-of-concept experiments demonstrating effective knockdown and neutralization of aerosolized CBW simulants using charged DF-200 decontaminant sprays. DF-200 is an aqueous decontaminant, developed by Sandia National Laboratories, and procured and fielded by the US Military. Of significance is the potential application of this fundamental technology to numerous applications including mitigation and neutralization of releases arising during chemical demilitarization operations. A release mitigation spray safety system will remove airborne contaminants from an accidental release during operations, to protect personnel and limit contamination. Sandia National Laboratories recently (November, 2008) secured funding from the US Army's Program Manager for Non-Stockpile Chemical Materials Agency (PMNSCMA) to investigate use of mitigation spray systems for chemical demilitarization applications. For non-stockpile processes, mitigation spray systems co-located with the current Explosive Destruction System (EDS) will provide security both as an operational protective measure and in the event of an accidental release. Additionally, 'tented' mitigation spray systems for native or foreign remediation and recovery operations will contain accidental releases arising from removal of underground, unstable CBW munitions. A mitigation spray system for highly controlled stockpile operations will provide defense from accidental spills or leaks during routine procedures.

Atmospheric Dispersion Modeling of the February 2014 Waste Isolation Pilot Plant Release

Energy Technology Data Exchange (ETDEWEB)

Nasstrom, John [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Piggott, Tom [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Simpson, Matthew [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lobaugh, Megan [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Tai, Lydia [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pobanz, Brenda [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Yu, Kristen [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-07-22

This report presents the results of a simulation of the atmospheric dispersion and deposition of radioactivity released from the Waste Isolation Pilot Plant (WIPP) site in New Mexico in February 2014. These simulations were made by the National Atmospheric Release Advisory Center (NARAC) at Lawrence Livermore National Laboratory (LLNL), and supersede NARAC simulation results published in a previous WIPP report (WIPP, 2014). The results presented in this report use additional, more detailed data from WIPP on the specific radionuclides released, radioactivity release amounts and release times. Compared to the previous NARAC simulations, the new simulation results in this report are based on more detailed modeling of the winds, turbulence, and particle dry deposition. In addition, the initial plume rise from the exhaust vent was considered in the new simulations, but not in the previous NARAC simulations. The new model results show some small differences compared to previous results, but do not change the conclusions in the WIPP (2014) report. Presented are the data and assumptions used in these model simulations, as well as the model-predicted dose and deposition on and near the WIPP site. A comparison of predicted and measured radionuclide-specific air concentrations is also presented.

Real-time modeling of complex atmospheric releases in urban areas

International Nuclear Information System (INIS)

Baskett, R.L.; Ellis, J.S.; Sullivan, T.J.

1994-08-01

If a nuclear installation in or near an urban area has a venting, fire, or explosion, airborne radioactivity becomes the major concern. Dispersion models are the immediate tool for estimating the dose and contamination. Responses in urban areas depend on knowledge of the amount of the release, representative meteorological data, and the ability of the dispersion model to simulate the complex flows as modified by terrain or local wind conditions. A centralized dispersion modeling system can produce realistic assessments of radiological accidents anywhere in a country within several minutes if it is computer-automated. The system requires source-term, terrain, mapping and dose-factor databases, real-time meteorological data acquisition, three-dimensional atmospheric transport and dispersion models, and experienced staff. Experience with past responses in urban areas by the Atmospheric Release Advisory Capability (ARAC) program at Lawrence Livermore National Laboratory illustrate the challenges for three-dimensional dispersion models

Real-time modelling of complex atmospheric releases in urban areas

International Nuclear Information System (INIS)

Baskett, R.L.; Ellis, J.S.; Sullivan, T.J.

2000-01-01

If a nuclear installation in or near an urban area has a venting, fire, or explosion, airborne radioactivity becomes the major concern. Dispersion models are the immediate tool for estimating the dose and contamination. Responses in urban areas depend on knowledge of the amount of the release, representative meteorological data, and the ability of the dispersion model to simulate the complex flows as modified by terrain or local wind conditions. A centralised dispersion modelling system can produce realistic assessments of radiological accidents anywhere in a country within several minutes if it is computer-automated. The system requires source-term, terrain, mapping and dose-factor databases, real-time meteorological data acquisition, three-dimensional atmospheric transport and dispersion models, and experienced staff. Experience with past responses in urban areas by the Atmospheric Release Advisory Capability (ARAC) program at Lawrence Livermore National Laboratory illustrate the challenges for three-dimensional dispersion models. (author)

Long-range transport of radioisotopes in the atmosphere and the calculation of collective dose

International Nuclear Information System (INIS)

Apsimon, H.M.; Goddard, A.J.H.; Wrigley, J.

1980-01-01

In estimating the long range (up to 1000 km) transport and dispersal of atmospheric pollutants, the meteorological conditions at the source become less relevant as the distance from the source increases, making it difficult to extrapolate to larger distances using short range modelling techniques. The MESOS model has therefore been developed to take into account the temporal and spatial changes in the atmospheric boundary layer along the trajectory of a pollutant release, including the effects of diurnal cycle and lateral dispersion in the synoptic scale windfield. The model is described together with the associated data base incorporating a year's meteorological data from synoptic stations and ships across Western Europe. A simulation of dispersal following the Windscale release of 1957 is compared with measurements. The use of the model is further illustrated by application to a hypothetical site both for routine continuous releases and short term accidental releases. This work has been carried out within the framework of a research contract between the EURATOM-CEA Association and Imperial College. (H.K.)

Determination of the safety zones of Angra dos Reis Nuclear Power Plant, according to the model of radion diffusion in the atmosphere

International Nuclear Information System (INIS)

Santina, M.D.

1978-01-01

The safety distance for Angra dos Reis Nuclear Power Plant are calculated, based on the model of the maximum credible accident for PWR power reactors and on the calculation of the dose due to hypothetical accidental release of radioactivity, using the model of radiation dispersion in the atmosphere. The safety distances for the Angra dos Reis reactors are also calculated using the model of the nine accident categories of the Rasmussen Report. The values of probability associated to each type of accident are used with the respective fractions of radiation release to the atmosphere. The soil contamination is also calculated for all the accidents considered and for several conditions of atmospheric stability, according to the model developed by Chamberlain. The program ACRA-II is used for calculation of the diffusion of radiation in the atmosphere, and the doses associated to it [pt

ARANO - a computer program for the assessment of radiological consequences of atmospheric radioactive releases

International Nuclear Information System (INIS)

Savolainen, I.; Vuori, S.

1980-09-01

A short description of the calculation possibilities, methods and of the structure of the computer code system ARANO is given, in addition to the input quide. The code can be employed in the calculation of environmental radiological consequences caused by radioactive materials released to atmosphere. Results can be individual doses for different organs at given distances from the release point, collective doses, numbers of persons exceeding given dose limits, numbers of casualties, areas polluted by deposited activity and losses of investments or production due to radioactive contamination. Both a case with a single release and atmospheric dispersion situation and a group of radioactive release and dispersions with discrete probability distributions can be considered. If the radioactive releases or the dispersion conditions are described by probability distributions, the program assesses the magnitudes of the specified effects in all combinations of the release and dispersion situations and then calculates the expectation values and the cumulative probability distributions of the effects. The vertical mixing in the atmosphere is described with a Ksub(Z)-model. In the lateral direction the plume is assumed to be Gaussian, and the release duration can be taken into account in the σsub(y)-values. External gamma dose from the release plume is calculated on the basis of a data file which has been created by 3-dimensional integration. Dose due to inhalation and due to gamma radiation from the contaminated ground are calculated by using appropriate dose conversion factors, which are collected into two mutually alternative block data subprograms. (author)

Impact of methane flow through deformable lake sediments on atmospheric release

Science.gov (United States)

Scandella, B.; Juanes, R.

2010-12-01

Methane is a potent greenhouse gas that is generated geothermally and biologically in lake and ocean sediments. Free gas bubbles may escape oxidative traps and contribute more to the atmospheric source than dissolved methane, but the details of the methane release depend on the interactions between the multiple fluid phases and the deformable porous medium. We present a model and supporting laboratory experiments of methane release through “breathing” dynamic flow conduits that open in response to drops in the hydrostatic load on lake sediments, which has been validated against a high-resolution record of free gas flux and hydrostatic pressure in Upper Mystic Lake, MA. In contrast to previous linear elastic fracture mechanics analysis of gassy sediments, the evolution of gas transport in a deformable compliant sediment is presented within the framework of multiphase poroplasticity. Experiments address how strongly the mode and rate of gas flow, captured by our model, impacts the size of bubbles released into the water column. A bubble's size in turn determines how efficiently it transports methane to the atmosphere, and integrating this effect will be critical to improving estimates of the atmospheric methane source from lakes. Cross-sectional schematic of lake sediments showing two venting sites: one open at left and one closed at right. The vertical release of gas bubbles (red) at the open venting site creates a local pressure drop, which drives both bubble formation from the methane-rich pore water (higher concentrations shaded darker red) and lateral advection of dissolved methane (purple arrows). Even as bubbles in the open site escape, those at the closed site remain trapped.

Savannah River Site radioiodine atmospheric releases and offsite maximum doses

International Nuclear Information System (INIS)

Marter, W.L.

1990-01-01

Radioisotopes of iodine have been released to the atmosphere from the Savannah River Site since 1955. The releases, mostly from the 200-F and 200-H Chemical Separations areas, consist of the isotopes, I-129 and 1-131. Small amounts of 1-131 and 1-133 have also been released from reactor facilities and the Savannah River Laboratory. This reference memorandum was issued to summarize our current knowledge of releases of radioiodines and resultant maximum offsite doses. This memorandum supplements the reference memorandum by providing more detailed supporting technical information. Doses reported in this memorandum from consumption of the milk containing the highest I-131 concentration following the 1961 1-131 release incident are about 1% higher than reported in the reference memorandum. This is the result of using unrounded 1-131 concentrations of I-131 in milk in this memo. It is emphasized here that this technical report does not constitute a dose reconstruction in the same sense as the dose reconstruction effort currently underway at Hanford. This report uses existing published data for radioiodine releases and existing transport and dosimetry models

The choice of individual dose criterion at which to restrict agricultural produce following an unplanned release of radioactive material to atmosphere

International Nuclear Information System (INIS)

Dionian, J.; Simmonds, J.R.

1985-06-01

In the event of an accidental release of radioactive material to atmosphere, the introduction of emergency countermeasures will be based on the need to limit the risk to individuals. However, it has been suggested that a form of cost-benefit analysis may be used as an input to decisions on the withdrawal of countermeasures, although it is recognised that these decisions may be influenced by factors other than those directly related to radiological protection. In this study, a method based on cost-benefit analysis is illustrated for assessing the optimum level of individual dose at which restrictions on agricultural production may be considered. This requires monetary values to be assigned to both the lost food production and to the health detriment, expressed as the collective effective dose equivalent commitment. It has been assumed in this analysis that food-supply restrictions are both introduced and withdrawn at the same projected level of annual individual dose. The effect on the optimum dose level of the following parameters is examined: the type of produce restricted; the size of the release; the site and direction of the release; the weather conditions; and the cost assigned to unit collective dose. It is shown that the optimum dose criterion, based on the effective dose equivalent received by an individual from a years intake of food, varies over practically the whole range of individual dose considered, i.e., 0.1 to 50 mSv. However, it is concluded that 5 mSv would represent the optimum dose criterion in a substantial number of cases. (author)

Risk assessment, risk management and risk-based monitoring following a reported accidental release of poliovirus in Belgium, September to November 2014.

Science.gov (United States)

Duizer, Erwin; Rutjes, Saskia; de Roda Husman, Ana Maria; Schijven, Jack

2016-01-01

On 6 September 2014, the accidental release of 10(13) infectious wild poliovirus type 3 (WPV3) particles by a vaccine production plant in Belgium was reported. WPV3 was released into the sewage system and discharged directly to a wastewater treatment plant (WWTP) and subsequently into rivers that flowed to the Western Scheldt and the North Sea. No poliovirus was detected in samples from the WWTP, surface waters, mussels or sewage from the Netherlands. Quantitative microbial risk assessment (QMRA) showed that the infection risks resulting from swimming in Belgium waters were above 50% for several days and that the infection risk by consuming shellfish harvested in the eastern part of the Western Scheldt warranted a shellfish cooking advice. We conclude that the reported release of WPV3 has neither resulted in detectable levels of poliovirus in any of the samples nor in poliovirus circulation in the Netherlands. This QMRA showed that relevant data on water flows were not readily available and that prior assumptions on dilution factors were overestimated. A QMRA should have been performed by all vaccine production facilities before starting up large-scale culture of WPV to be able to implement effective interventions when an accident happens.

Emergency response capability for pollutant releases to streams and rivers

International Nuclear Information System (INIS)

Buckner, M.R.; Hayes, D.W.; Watts, J.R.

1975-01-01

Stream-river models have been developed which provide an accurate prediction of normal and accidental pollutant releases to streams and rivers. Stream parameters are being developed for the Savannah River Plant streams and the Savannah River to allow quick response in case of an accidental release of radioactive material. These data are stored on permanent disk storage for quick access via the JOSHUA operating system. This system provides an efficient and flexible emergency response capability for pollutant releases to streams and rivers

The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: sensitivity to the dose-effect relationships adopted for early biological effects

International Nuclear Information System (INIS)

Kelly, G.N.; Simmonds, J.R.; Smith, H.; Stather, J.W.

1979-07-01

This study considered the sensitivity to the dose-response relationships adopted for the estimation of early biological effects from notional accidental releases of radioactivity from fast breeder reactors. Two distinct aspects were considered: the sensitivity of the predicted consequences to variation in the dose-mortality relationships for irradiation of the bone marrow and the lung; and the influence of simple supportive medical treatment in reducing the incidence of early deaths in the exposed population. The numbers of early effects estimated in the initial study were relatively insensitive to variation in the dose-mortality relationships within the bounds proposed. The few exceptions concerned releases of particular nuclide composition, and the variation in the predicted consequences could be around an order of magnitude; the absolute numbers of effects however were in general small when the sensitivity was most pronounced. The reduction in the incidence of early deaths when using simple supportive treatment varied markedly with the nuclide composition of the release. Areas of uncertainty were identified where further research and investigation might most profitably be directed with a view to improving the reliability of the dose-effect relationships adopted and hence of the predicted consequences of the release considered. (author)

Results for SEAFP-subtask A 10: Assessments of individual and collective doses to the public for routine and accidental releases of tritium and activation products

International Nuclear Information System (INIS)

Raskob, W.

1995-04-01

Dose calculations have been performed for accidental releases of tritium and activation products. Unit releases of 1 GBq per nuclide have been investigated for 31 fusion relevant nuclides. Additionally, unit releases of 1g of tritium and several activated materials have been studied. Under normal operation conditions, dose calculations have been performed for real source terms of tritium and activated materials. The individual dose values at the fence of the site (1 km) as well as the collective dose to the public (from 1 km to 100 km) have been obtained. As site specific parameters are still missing, different so called ''worst case'' release conditions have been applied. To have a first guess of the influence of the release duration on the dose to the Most Exposed Individual (MEI) in the vicinity of a reactor, different release durations, ranging from 1 hour up to 168 hours have been investigated, too. Finally, dose calculations have been performed for mobilisation source terms which take account of deposition and retention in the plant. This has been done for several RPM and APM source terms. The dose values of these final source terms seem to be less than every criteria to start emergency actions, however, some problems e.g. the behaviour of tritium in the plant, remain unsolved. (orig.)

Simulation of atmospheric dispersion of radionuclides using an Eulerian-Lagrangian modelling system.

Science.gov (United States)

Basit, Abdul; Espinosa, Francisco; Avila, Ruben; Raza, S; Irfan, N

2008-12-01

In this paper we present an atmospheric dispersion scenario for a proposed nuclear power plant in Pakistan involving the hypothetical accidental release of radionuclides. For this, a concept involving a Lagrangian stochastic particle model (LSPM) coupled with an Eulerian regional atmospheric modelling system (RAMS) is used. The atmospheric turbulent dispersion of radionuclides (represented by non-buoyant particles/neutral traces) in the LSPM is modelled by applying non-homogeneous turbulence conditions. The mean wind velocities governed by the topography of the region and the surface fluxes of momentum and heat are calculated by the RAMS code. A moving least squares (MLS) technique is introduced to calculate the concentration of radionuclides at ground level. The numerically calculated vertical profiles of wind velocity and temperature are compared with observed data. The results obtained demonstrate that in regions of complex terrain it is not sufficient to model the atmospheric dispersion of particles using a straight-line Gaussian plume model, and that by utilising a Lagrangian stochastic particle model and regional atmospheric modelling system a much more realistic estimation of the dispersion in such a hypothetical scenario was ascertained. The particle dispersion results for a 12 h ground release show that a triangular area of about 400 km(2) situated in the north-west quadrant of release is under radiological threat. The particle distribution shows that the use of a Gaussian plume model (GPM) in such situations will yield quite misleading results.

The current status of ARAC [Atmospheric Release Advisory Capability] and its application to the Chernobyl event

International Nuclear Information System (INIS)

Gudiksen, P.H.; Sullivan, T.J.; Harvey, T.F.

1986-10-01

The Atmospheric Release Advisory Capability (ARAC) project, developed by the Lawrence Livermore National Laboratory (LLNL), provides real-time dose assessments and estimates of the extent of surface contamination that may result from an atmospheric release of radioactivity. It utilizes advanced computer-based data communication and processing systems to acquire the meteorological and source term information needed by the three-dimensional atmospheric dispersion models to derive the consequence assessments. The ARAC responded to the recent Chernobyl reactor accident in the Soviet Union by estimating the source term and the radiation dose distribution due to exposure to the radioactive cloud over Europe and the Northern Hemisphere. This analysis revealed that approximately 50% of the estimated core inventories of I-131 and Cs-137 were released. The estimated committed effective dose equivalent due to inhalation of radioactivty during cloud passage is of the order of 10 mrem within parts of Scandinavia and eastern Europe, while most of the populations within central Europe were exposed to levels ranging from 1 to 10 mrem. The amount of Cs-137 released by the Chernobyl accident far exceeds that released by previous reactor accidents, but is only about 6% of the Cs-137 produced by the atmospheric weapon testing programs. 9 refs., 4 figs., 2 tabs

Accidental release of iodine 131 by the IRE of the Fleurus site: return on experience by the Belgian safety authority

International Nuclear Information System (INIS)

Vandecasteele, C.M.; Sonck, M.; Degueldre, D.

2010-01-01

After a presentation of the activities of the IRE, the Belgian National Institute of Radio-elements, i.e. the production of radionuclides used in nuclear medicine, this report describes the process and chemical reaction which caused an accidental release of iodine 131. It analyzes the causes of this incident, and how the incident has been managed by the Belgian safety authority. It discusses the first assessment of radiological consequences, describes how the incident has been managed at the federal level, and how population and media have been informed. It discusses the actual radiological consequences through measurements performed on grass and vegetables (graphs and maps indicate contamination levels and contaminated areas), and through the assessment of exposure of adults and children by different ways. Lessons learned are then discussed

Commitment of involved actors in the preparation of accidental and post-accident situations: European experiments

International Nuclear Information System (INIS)

Schneider, Th.

2010-01-01

The author briefly describes some approaches developed within the EURANOS European research programme between 2004 and 2009 which aims at promoting the building up of a European network (NERIS) for the management of nuclear accidental and post-accident situations. Notably, he comments the experiment which took place in the Montbeliard district where two types of radiological events have been modelled and simulated: an accident in the Fessenheim nuclear power plant with two scenarios of release, and a transportation accident with a release of radioactive caesium 137. He also evokes the Norwegian experience and some other actions in Finland, Great-Britain, Spain and Slovakia where reflections on the management of accidental and post-accident situations or crisis exercises have been organized

MODELS SELECTED FOR CALCULATION OF DOSES, HEALTH EFFECTS AND ECONOMIC COSTS DUE TO ACCIDENTAL RADIONUCLIDE RELEASES FROM NUCLEAR POWER PLANTS

Energy Technology Data Exchange (ETDEWEB)

Strenge, D L; Baker, D A; Droppo, J G; McPherson, R B; Napier, B A; Nieves, L A; Soldat, J K

1980-05-01

Models are described for use in site-specific environmental consequence analysis of nuclear reactor accidents of Classes 3 through 9. The models presented relate radioactivity released to resulting doses, health effects, and costs of remedial actions. Specific models are presented for the major exposure pathways of airborne releases, waterborne releases and direct irradiation from activity within the facility buildings, such as the containment. Time-dependent atmospheric dispersion parameters, crop production parameters and other variable parameters are used in the models. The environmental effects are analyzed for several accident start times during the year.

Use of hydraulic and aerial mock up to study atmospheric pollution

International Nuclear Information System (INIS)

Facy, L.; Perrin De Brichambaut, C.; Doury, A.; Le Quinio, R.

1962-01-01

Fundamental studies on turbulent atmospheric diffusion of finely divided particles, cannot remain on a purely theoretical basis. Further experimental studies must be considered. - In full scale, from accidental and induced releases. - On a reduced scale, in aerodynamic wind tunnels or hydraulic water tunnels. A first set of studies on reduced scale models has been worked out according to a contract between French 'Meteorologie Nationale' and French 'Commissariat a l'Energie Atomique' and with the Collaboration of Saint-Cyr 'Institut Aerotechnique'. Essentially two kinds of results have been obtained: - The mathematical model of SUTTON for the turbulent diffusion in the atmosphere, deduced from the SUTTON theory, generally used by us, has been correctly verified, qualitatively and quantitatively whenever experiments were consistent with the theory conditions. - The quantitative assays of photographic and cinematographic visualization have given precise details on the phenomena inaccessible to calculations, due to the influence of obstacles and release conditions. - Generally, it can be asserted, that the atmospheric pollution studies are worked out by mock up experimentations and that, in some cases these experiments never can be replaced by mathematically pure models. (authors) [fr

Atmospheric effects of heat release at large power plants

International Nuclear Information System (INIS)

Kikuchi, Yukio

1979-01-01

In power plants, the thermal efficiency of generating electricity is generally 1/3, the rest 2/3 being carried away by cooling water. To release the heat, there are three alternative methods; i.e. cooling water released into sea, cooling water released into a cooling pond, and cooling of such water with a cooling tower. In the third method, cooling towers are stacks of 10m -- 80m bore, and warm cooling water flowing on the side wall is cooled with atmospheric air. The resultant heated air is discharged as plume from their top. Upon condensation, it becomes visible and then leads to the formation of clouds. In this manner, the weather around the sites of power plants is affected, such as reduction of insolation reaching ground and increase in precipitation. The following matters are described: cooling towers; phenomena and prediction methods of visible plume, cloud formation, increase of precipitation and deposition of drifting waterdrops; and effects of the group of power plants. (J.P.N.)

Social evaluation of intentional, truly accidental, and negligently accidental helpers and harmers by 10-month-old infants.

Science.gov (United States)

Woo, Brandon M; Steckler, Conor M; Le, Doan T; Hamlin, J Kiley

2017-11-01

Whereas adults largely base their evaluations of others' actions on others' intentions, a host of research in developmental psychology suggests that younger children privilege outcome over intention, leading them to condemn accidental harm. To date, this question has been examined only with children capable of language production. In the current studies, we utilized a non-linguistic puppet show paradigm to examine the evaluation of intentional and accidental acts of helping or harming in 10-month-old infants. In Experiment 1 (n=64), infants preferred intentional over accidental helpers but accidental over intentional harmers, suggestive that by this age infants incorporate information about others' intentions into their social evaluations. In Experiment 2 (n=64), infants did not distinguish "negligently" accidental from intentional helpers or harmers, suggestive that infants may find negligent accidents somewhat intentional. In Experiment 3 (n=64), we found that infants preferred truly accidental over negligently accidental harmers, but did not reliably distinguish negligently accidental from truly accidental helpers, consistent with past work with adults and children suggestive that humans are particularly sensitive to negligently accidental harm. Together, these results imply that infants engage in intention-based social evaluation of those who help and harm accidentally, so long as those accidents do not stem from negligence. Copyright © 2017 Elsevier B.V. All rights reserved.

Dose Assessment Model for Chronic Atmospheric Releases of Tritium

International Nuclear Information System (INIS)

Shen Huifang; Yao Rentai

2010-01-01

An improved dose assessment model for chronic atmospheric releases of tritium was proposed. The proposed model explicitly considered two chemical forms of tritium.It was based on conservative assumption of transfer of tritiated water (HTO) from air to concentration of HTO and organic beam tritium (OBT) in vegetable and animal products.The concentration of tritium in plant products was calculated based on considering dividedly leafy plant and not leafy plant, meanwhile the concentration contribution of tritium in the different plants from the tritium in soil was taken into account.Calculating the concentration of HTO in animal products, average water fraction of animal products and the average weighted tritium concentration of ingested water based on the fraction of water supplied by each source were considered,including skin absorption, inhalation, drinking water and food.Calculating the annual doses, the ingestion doses were considered, at the same time the contribution of inhalation and skin absorption to the dose was considered. Concentrations in foodstuffs and dose of annual adult calculated with the specific activity model, NEWTRI model and the model proposed by the paper were compared. The results indicate that the model proposed by the paper can predict accurately tritium doses through the food chain from chronic atmospheric releases. (authors)

Locating the Source of Atmospheric Contamination Based on Data From the Kori Field Tracer Experiment

Directory of Open Access Journals (Sweden)

Piotr Kopka

2015-01-01

Full Text Available Accidental releases of hazardous material into the atmosphere pose high risks to human health and the environment. Thus it would be valuable to develop an emergency reaction system which can recognize the probable location of the source based only on concentrations of the released substance as reported by a network of sensors. We apply a methodology combining Bayesian inference with Sequential Monte Carlo (SMC methods to the problem of locating the source of an atmospheric contaminant. The input data for this algorithm are the concentrations of a given substance gathered continuously in time. We employ this algorithm to locating a contamination source using data from a field tracer experiment covering the Kori nuclear site and conducted in May 2001. We use the second-order Closure Integrated PUFF Model (SCIPUFF of atmospheric dispersion as the forward model to predict concentrations at the sensors' locations. We demonstrate that the source of continuous contamination may be successfully located even in the very complicated, hilly terrain surrounding the Kori nuclear site. (original abstract

Estimation of radiological consequences from accidental iodine releases at nuclear power plants

International Nuclear Information System (INIS)

Drozdovich, V.V.

2000-01-01

To evaluate the radiological consequences of a beyond design-basis accident at an NPP for a WWER-1000 reactor, a preliminary investigation was conducted. The scenario of the hypothetical accident was a fast loss of coolant as a result of a rupture in the primary circuit pipeline with diameter of 850 mm and minimum radiation consequences when containment integrity is preserved. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Using modem knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways: (a) extemal exposure from radionuclides in air; (b) extemal exposure from radionuclides deposited on the ground surface; (c) internal exposures from inhalation of radionuclides in air; and (d) internal exposure from ingestion of radionuclides with contaminated foodstuffs. Risk was estimated for populations living at different distances from the source. Preliminary results show that the methodology and models can be applied to the evaluation of radiological danger of an accident at an NPP. Experience from the Chernobyl accident has shown that the damage from a radiation accident can be vast. Expenditures on advanced simulations of the different accident scenarios are worth the cost because they allow radiation protection of populations for these low probability cases, but nevertheless possible accidents at an NPP. (authors)

Automated data system for emergency meteorological response

International Nuclear Information System (INIS)

Kern, C.D.

1975-01-01

The Savannah River Plant (SRP) releases small amounts of radioactive nuclides to the atmosphere as a consequence of the production of radioisotopes. The potential for larger accidental releases to the atmosphere also exists, although the probability for most accidents is low. To provide for emergency meteorological response to accidental releases and to conduct research on the transport and diffusion of radioactive nuclides in the routine releases, a series of high-quality meteorological sensors have been located on towers in and about SRP. These towers are equipped with instrumentation to detect and record temperature and wind turbulence. Signals from the meterological sensors are brought by land-line to the SRL Weather Center-Analysis Laboratory (WC-AL). At the WC-AL, a Weather Information and Display (WIND) system has been installed. The WIND system consists of a minicomputer with graphical displays in the WC-AL and also in the emergency operating center (EOC) of SRP. In addition, data are available to the system from standard weat []er teletype services, which provide both routine surface weather observations and routine upper air wind and temperature observations for the southeastern United States. Should there be an accidental release to the atmosphere, available recorded data and computer codes would allow the calculation and display of the location, time, and downwind concentration of the atmospheric release. These data are made available to decision makers in near real-time to permit rapid decisive action to limit the consequences of such accidental releases. (auth)

Decreased atmospheric sulfur deposition across the southeastern U.S.: When will watersheds release stored sulfate?

Science.gov (United States)

Rice, Karen C.; Scanlon, Todd M.; Lynch, Jason A.; Cosby, Bernard J.

2014-01-01

Emissions of sulfur dioxide (SO2) to the atmosphere lead to atmospheric deposition of sulfate (SO42-), which is the dominant strong acid anion causing acidification of surface waters and soils in the eastern United States (U.S.). Since passage of the Clean Air Act and its Amendments, atmospheric deposition of SO2 in this region has declined by over 80%, but few corresponding decreases in stream-water SO42- concentrations have been observed in unglaciated watersheds. We calculated SO42- mass balances for 27 forested, unglaciated watersheds from Pennsylvania to Georgia, by using total atmospheric deposition (wet plus dry) as input. Many of these watersheds still retain SO42-, unlike their counterparts in the northeastern U.S. and southern Canada. Our analysis showed that many of these watersheds should convert from retaining to releasing SO42- over the next two decades. The specific years when the watersheds crossover from retaining to releasing SO42- correspond to a general geographical pattern of later net watershed release from north to south. The single most important variable that explained the crossover year was the runoff ratio, defined as the ratio of annual mean stream discharge to precipitation. Percent clay content and mean soil depth were secondary factors in predicting crossover year. The conversion of watersheds from net SO42- retention to release anticipates more widespread reductions in stream-water SO42- concentrations in this region.

Atmospheric Release Advisory capability (ARAC) response to the Three Mile Island accident

International Nuclear Information System (INIS)

Dickerson, M.H.; Gudiksen, P.H.

1979-10-01

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

Accidental release of chlorine in Chicago: Coupling of an exposure model with a Computational Fluid Dynamics model

Science.gov (United States)

Sanchez, E. Y.; Colman Lerner, J. E.; Porta, A.; Jacovkis, P. M.

2013-01-01

The adverse health effects of the release of hazardous substances into the atmosphere continue being a matter of concern, especially in densely populated urban regions. Emergency responders need to have estimates of these adverse health effects in the local population to aid planning, emergency response, and recovery efforts. For this purpose, models that predict the transport and dispersion of hazardous materials are as necessary as those that estimate the adverse health effects in the population. In this paper, we present the results obtained by coupling a Computational Fluid Dynamics model, FLACS (FLame ACceleration Simulator), with an exposure model, DDC (Damage Differential Coupling). This coupled model system is applied to a scenario of hypothetical release of chlorine with obstacles, such as buildings, and the results show how it is capable of predicting the atmospheric dispersion of hazardous chemicals, and the adverse health effects in the exposed population, to support decision makers both in charge of emergency planning and in charge of real-time response. The results obtained show how knowing the influence of obstacles in the trajectory of the toxic cloud and in the diffusion of the pollutants transported, and obtaining dynamic information of the potentially affected population and of associated symptoms, contribute to improve the planning of the protection and response measures.

Atmospheric Release Advisory Capability (ARAC): development and plans for implementation

International Nuclear Information System (INIS)

Dickerson, M.H.; Orphan, R.C.

1975-01-01

The Atmospheric Release Advisory Capability (ARAC) is an ERDA-sponsored service planned for nuclear facilities which require a means of real-time prediction of the extent of health hazards that may result from a release of radionuclides or other toxic materials. Since 1973 when the ARAC concept was initiated, a joint feasibility study has been conducted by Lawrence Livermore Laboratory and Savannah River Laboratory, and a prototype component of the system has been built and placed in operation. During the next three years plans are to implement the ARAC service for certain ERDA nuclear facilities. A brief description is presented of the ARAC concept, and progress to date is reported. (U.S.)

Radiological impact of atmospheric releases from a coal-fired power station

International Nuclear Information System (INIS)

Aigueperse, J.; Chalabreysse, J.; Coulon, R.; Grauby, A.; Uzzan, G.

1982-01-01

As the first stage of a study carried out under contract with the Commission of the European Communities for the comparative assessment of the risks to which the individuals of a regional population are exposed, the paper seeks to evaluate atmospheric releases from a coal-fired thermal power station. The station is of traditional design with an installed capacity of 415MW(e) and uses only lignite-type coal produced from a coal basin situated nearby. Gaseous effluents are released from four stacks. The area close to the station is rural in nature: there are a number of small farms, fairly abundant natural vegetation and some fairly well-populated zones with various industries. The main feature of the weather conditions is the strong prevailing winds in the optimum direction. A radiation measurement campaign involving the main 238 U and 232 Th daughter products was carried out focussing on: (1) the coal burnt in the power station; (2) the solid residues resulting from combustion (fly ash, wet ash); (3) gaseous effluents by means of direct sampling from the two release stacks. The information obtained on the releases has made it possible, with the help of dispersion and transfer models, to evaluate the atmospheric concentration of the different radionuclide released as well as their deposition and presence in the biotope in the plant vicinity. The effective dose equivalents received by persons living in the zone of maximum exposure and consuming food produced in that zone were assessed at approximately 7x10 -5 Sv.a -1 at the end of the plant's operating period. Finally, the main radionuclides were measured at a number of points near the plant with the aim of verifying the model evaluations for a particular situation. (author)

Radiological impact of atmospheric releases from a coal-fired power station

Energy Technology Data Exchange (ETDEWEB)

Aigueperse, J; Chalabreysse, J; Coulon, R; Grauby, A [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Protection; Uzzan, G [Association EURATOM-CEA, Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Protection

1982-01-01

As the first stage of a study carried out under contract with the Commission of the European Communities for the comparative assessment of the risks to which the individuals of a regional population are exposed, the paper seeks to evaluate atmospheric releases from a coal-fired thermal power station. The station is of traditional design with an installed capacity of 415MW(e) and uses only lignite-type coal produced from a coal basin situated nearby. Gaseous effluents are released from four stacks. The area close to the station is rural in nature: there are a number of small farms, fairly abundant natural vegetation and some fairly well-populated zones with various industries. The main feature of the weather conditions is the strong prevailing winds in the optimum direction. A radiation measurement campaign involving the main /sup 238/U and /sup 232/Th daughter products was carried out focussing on: (1) the coal burnt in the power station; (2) the solid residues resulting from combustion (fly ash, wet ash); (3) gaseous effluents by means of direct sampling from the two release stacks. The information obtained on the releases has made it possible, with the help of dispersion and transfer models, to evaluate the atmospheric concentration of the different radionuclide released as well as their deposition and presence in the biotope in the plant vicinity. The effective dose equivalents received by persons living in the zone of maximum exposure and consuming food produced in that zone were assessed at approximately 7x10/sup -5/Sv.a/sup -1/ at the end of the plant's operating period. Finally, the main radionuclides were measured at a number of points near the plant with the aim of verifying the model evaluations for a particular situation.

REDUCING AMMONIA CONCENTRATIONS IN ATMOSPHERE AFTER ITS UNPLANNED RELEASE

Directory of Open Access Journals (Sweden)

L. V. Amelina

2017-08-01

Full Text Available Purpose. The aim of this work is development of numerical model, which allows to calculate the efficiency of neutralizer supply for reduction of air pollution in case of unplanned ammonia emission at the territory of ammonia pump station. The numerical model should allow fast calculating, taking into account the meteorological parameters and buildings situated near the source of toxic chemical emission and equipment for neutralizer supply. Methodology. The developed model is based on the equation for potential flow and equation of pollutant dispersion. To simulate the chemical interaction between ammonia and neutralizer the stoichiometry equation is used. Equation of potential flow is used to compute flow pattern among buildings. To solve the equation for potential flow the Samarskii implicit difference scheme is used. The implicit change-triangle difference scheme is used to solve equation of mass transfer. While for the numerical integration the authors use the rectangular difference grid. Method of porosity technique («markers method» is applied to create the form of comprehensive computational region. Emission of ammonia is modeled using Delta function for point source. Findings. Developed numerical model belongs to the class of «diagnostic models». This model takes into account the main physical factors affecting the process of dispersion of ammonia and neutralizer in the atmosphere, as well as the influence of buildings on admixture dispersion. On the basis of the developed numerical models the authors carried out a computational experiment to estimate the efficiency of neutralizer supply for reduction of air pollution in case of unplanned ammonia release at ammonia pump station. Originality. Developed numerical model allows calculating the flow pattern among buildings and estimating the efficiency of neutralizer supply for reduction of air pollution in the case unplanned ammonia release. Practical value. Model allows performing fast

The use of nonlinear regression analysis for integrating pollutant concentration measurements with atmospheric dispersion modeling for source term estimation

International Nuclear Information System (INIS)

Edwards, L.L.; Freis, R.P.; Peters, L.G.; Gudiksen, P.H.; Pitovranov, S.E.

1993-01-01

The accuracy associated with assessing the environmental consequences of an accidental release of radioactivity is highly dependent on the knowledge of the source term characteristics, which are generally poorly known. The development of an automated numerical technique that integrates the radiological measurements with atmospheric dispersion modeling for more accurate source term estimation is reported. Often, this process of parameter estimation is performed by an emergency response assessor, who takes an intelligent first guess at the model parameters, then, comparing the model results with whatever measurements are available, makes an intuitive, informed next guess of the model parameters. This process may be repeated any number of times until the assessor feels that the model results are reasonable in terms of the measured observations. A new approach, based on a nonlinear least-squares regression scheme coupled with the existing Atmospheric Release Advisory Capability three-dimensional atmospheric dispersion models, is to supplement the assessor's intuition with automated mathematical methods that do not significantly increase the response time of the existing predictive models. The viability of the approach is evaluated by estimation of the known SF 6 tracer release rates associated with the Mesoscale Atmospheric Transport Studies tracer experiments conducted at the Savannah River Laboratory during 1983. These 19 experiments resulted in 14 successful, separate tracer releases with sampling of the tracer plumes along the cross-plume arc situated ∼30 km from the release site

LNG containment release: Comparison of NFPA-59A and 49-CFR-193

International Nuclear Information System (INIS)

West, H.H.; Pfenning, D.B.

1994-01-01

Due to the potential wide area impact of an unplanned LNG (Liquefied Natural Gas) release, the National Fire Protection Association (NFPA) and later the US Department of Transportation issued standards and regulations which included specific methodologies for analyzing the consequence of an accidental LNG release. The concept of a ''design spill'' was defined in order to evaluate the consequences of an accidental LNG release, with particular attention to the influence of safety protective measures. In addition to specifying the magnitude of the unplanned release, the design spill also specified some of the parameters for estimation of the downwind LNG vapor dispersion and the extent of the radiant heat from an LNG pool fire. Since the NFPA-59A and 49-CFR-193 standards were the first in-depth regulation to address consequence analysis estimation for petroleum components, it is particularly important to consider their details in light of the recently proposed EPA 40-CFR-68 regulations [Risk Management for Chemical Accidental Release Prevention] which specifically address consequence analysis as a part of process safety management

Harmonization of French and German calculation procedures for atmospheric dispersion following accidental releases from nuclear power plants

International Nuclear Information System (INIS)

Crabol, B.; Romeo, E.; Nester, K.

1992-01-01

In case of an accident in a nuclear power plant near the French-German border different schemes for dispersion calculations in both countries will currently be applied. An intercomparison of these schemes initiated from the German-French Commission for the safety of nuclear installations (DFK) revealed in some meteorological situations large differences in the resulting concentrations for radionuclides. An ad hoc working group was installed by the DFK with the mandate to analyse the reasons for the different model results and also to consider new theoretical concepts. The working group has agreed to apply a Gaussian puff model for emergency response calculations. The results of the model based on turbulence parameterization via similarity approach or spectral theory - have been compared with tracer experiments for different emission heights and atmospheric stability regimes. As a reference the old modelling approaches have been included in the study. The simulations with the similarity approach and the spectral theory show a slightly better agreement to the measured concentration data than the schemes used in the past. Instead of diffusion categories both new approaches allow a continuous characterization of the atmospheric dispersion conditions. Because the spectral approach incorporates the sampling time of the meteorological data as an adjustable parameter thereby offering the possibility to adjust the dispersion model to different emission scenarios this turbulence parameterization scheme will be foreseen as the basis for a joint French-German puff model

Screening models for releases of radionuclides to atmosphere, surface water, and ground -- Work sheets

International Nuclear Information System (INIS)

1996-01-01

Three levels of screening for the atmospheric transport pathways and two levels for surface water are presented. The ground has only one screening level. Level 1 is the simplest approach and incorporates a high degree of conservatism. The estimate of the effective dose for this level assumes a concentration based upon the radionuclide concentration at the point of emission to the environment, i.e., at the stack for atmospheric emissions, at the end of the effluent pipe for liquid effluent releases, and at a well because of the buried radioactive material. Levels 2 and 3 are presented for atmospheric releases, and Level 2 for surface water releases only and are more detailed and correspondingly less conservative. Level 2 screening accounts for dispersion in the atmosphere and in surface waters and combines all recognized pathways into the screening factor. For the atmospheric pathway, Level 3 screening includes more definitive pathways analysis. Should the user be found in compliance on the basis of Level 1 screening, no further calculations are required. If the user fails Level 1, the user proceeds to the next level and checks for compliance. This process is repeated until the user passes screening (is in compliance) or no further screening levels exist. If the user fails the final level, professional assistance should be obtained in environmental radiological assessment. Work sheets are designed to lead the user through screening in a step-by-step manner until compliance is demonstrated or it is determined that more sophisticated methods or expertise are needed. Flow diagrams are provided as a guide to identify key steps in the screening process

Atmospheric Release Advisory Capability (ARAC) response to the Three Mile Island accident

International Nuclear Information System (INIS)

Dickerson, M.H.; Gudiksen, P.H.

1980-01-01

A discussion is presented of 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. 6 refs

ARAC: a centralized computer assisted emergency planning, response, and assessment system for atmospheric releases of toxic material

International Nuclear Information System (INIS)

Dickerson, M.H.; Knox, J.B.

1986-10-01

The Atmospheric Release Advisory Capability (ARAC) is an emergency planning, response, and assessment service, developed by the US Departments of Energy and Defense, and focused, thus far, on atmospheric releases of nuclear material. For the past 14 years ARAC has responded to over 150 accidents, potential accidents, and major exercises. The most notable accident responses are the COSMOS 954 reentry, the Three Mile Island (TMI-2) accident and subsequent purge of 85 Kr from the containment vessel, the recent UF 6 accident at the Kerr-McGee Plant, Gore, Oklahoma, and the Chernobyl nuclear reactor accident in the Soviet Union. Based on experience in the area of emergency response, developed during the past 14 years, this paper describes the cost effectiveness and other advantages of a centralized emergency planning, response, and assessment service for atmospheric releases of nuclear material

ARAC: a centralized computer-assisted emergency planning, response, and assessment system for atmospheric releases of toxic material

International Nuclear Information System (INIS)

Dickerson, M.H.; Knox, J.B.

1987-01-01

The Atmospheric Release Advisory Capability (ARAC) is an emergency planning, response, and assessment service, developed by the US Departments of Energy and Defense, and focused, thus far, on atmospheric releases of nuclear material. For the past 14 years ARAC has responded to over 150 accidents, potential accidents, and major exercises. The most notable accident responses are the COSMOS 954 reentry, the Three Mile Island (TMI-2) accident and subsequent purge of 85 Kr from the containment vessel, the recent UF 6 accident at the Kerr-McGee Plant, Gore, Oklahoma, and the Chernobyl nuclear reactor accident in the Soviet Union. Based on experience in the area of emergency response, developed during the past 14 years, this paper describes the cost effectiveness and other advantages of a centralized emergency planning, response, and assessment service for atmospheric releases of nuclear material

Model to estimate the local radiation doses to man from the atmospheric release of radionuclides (LWBR development program)

International Nuclear Information System (INIS)

Rider, J.L.; Beal, S.K.

1977-04-01

A model was developed to estimate the radiation dose commitments received by people in the vicinity of a facility that releases radionuclides into the atmosphere. This model considers dose commitments resulting from immersion in the plume, ingestion of contaminated food, inhalation of gaseous and suspended radioactivity, and exposure to ground deposits. The dose commitments from each of these pathways is explicitly considered for each radionuclide released into the atmosphere and for each daughter of each released nuclide. Using the release rate of only the parent radionuclide, the air and ground concentrations of each daughter are calculated for each position of interest. This is considered to be a significant improvement over other models in which the concentrations of daughter radionuclides must be approximated by separate releases

OLDES - an on-line dose evaluation system that can be integrated into the remote monitoring system of nuclear power stations for additional monitoring and prognostic assessment in case of major accidental activity release

International Nuclear Information System (INIS)

Witt, H. de; Brenk, H.D.; Kruschel, K.P.; Knaup, A.G.

1986-01-01

Remote monitoring systems are an inherent part of the environmental surveillance installations of most commercial LWR power plants in the FRG. The systems are designed to cover routine and accident situations. They provide meteorological data, gross effluent dose rates, and dose measurements at approximately 25 locations in the vicinity of the plant in time steps of 10 minutes. Based on such a network, an attempt has been made to develop an on-line dose evaluation system (OLDES) as a tool to aid decision making processes in case of major accidental releases. On-line, here means that the software package directly includes the measurements at the monitoring stations in order to adjust the dose computations to the measurements in time steps of 10 minutes. In this way the system yields the best possible bases, both for actual diagnosis of radiation exposure, and for dose projections. The software package uses a Gaussian puff trajectory model to simulate atmospheric dispersion and deposition of radionuclides. It includes 'cloud- and ground-shine irradiation' and allows for changing weather conditions without exceeding the limits of real time calculation. Preliminary tests of the software package revealed reasonable semioperational performance. (orig.)

Model description and evaluation of model performance: DOSDIM model

International Nuclear Information System (INIS)

Lewyckyj, N.; Zeevaert, T.

1996-01-01

DOSDIM was developed to assess the impact to man from routine and accidental atmospheric releases. It is a compartmental, deterministic, radiological model. For an accidental release, dynamic transfer are used in opposition to a routine release for which equilibrium transfer factors are used. Parameters values were chosen to be conservative. Transfer between compartments are described by first-order differential equations. 2 figs

The present status and recent applications of the accidental tritium assessment code UFOTRI

International Nuclear Information System (INIS)

Raskob, W.

1999-01-01

The computer program UFOTRI can be used for assessing the impact of accidental released tritium in the two chemical forms tritiated water vapour and tritium gas. By applying UFOTRI to potential European sites for ITER, it could be demonstrated that the main goal, the nonevacuation criteria, is fulfilled for the present release limits. Contributions in international studies together with the re-evaluation of experimental data showed that the plant sub-model as well as the soil sub-model are areas for further improvement. (author)

Improved Meteorological Input for Atmospheric Release Decision support Systems and an Integrated LES Modeling System for Atmospheric Dispersion of Toxic Agents: Homeland Security Applications

Energy Technology Data Exchange (ETDEWEB)

Arnold, E; Simpson, M; Larsen, S; Gash, J; Aluzzi, F; Lundquist, J; Sugiyama, G

2010-04-26

When hazardous material is accidently or intentionally released into the atmosphere, emergency response organizations look to decision support systems (DSSs) to translate contaminant information provided by atmospheric models into effective decisions to protect the public and emergency responders and to mitigate subsequent consequences. The Department of Homeland Security (DHS)-led Interagency Modeling and Atmospheric Assessment Center (IMAAC) is one of the primary DSSs utilized by emergency management organizations. IMAAC is responsible for providing 'a single piont for the coordination and dissemination of Federal dispersion modeling and hazard prediction products that represent the Federal position' during actual or potential incidents under the National Response Plan. The Department of Energy's (DOE) National Atmospheric Release Advisory Center (NARAC), locatec at the Lawrence Livermore National Laboratory (LLNL), serves as the primary operations center of the IMAAC. A key component of atmospheric release decision support systems is meteorological information - models and data of winds, turbulence, and other atmospheric boundary-layer parameters. The accuracy of contaminant predictions is strongly dependent on the quality of this information. Therefore, the effectiveness of DSSs can be enhanced by improving the meteorological options available to drive atmospheric transport and fate models. The overall goal of this project was to develop and evaluate new meteorological modeling capabilities for DSSs based on the use of NASA Earth-science data sets in order to enhance the atmospheric-hazard information provided to emergency managers and responders. The final report describes the LLNL contributions to this multi-institutional effort. LLNL developed an approach to utilize NCAR meteorological predictions using NASA MODIS data for the New York City (NYC) region and demonstrated the potential impact of the use of different data sources and data

Atmospheric Dispersion of Various Types of Iodine in UAE in February and August

Energy Technology Data Exchange (ETDEWEB)

Kim, Sungyeop; Beeley, Philip A. [Khalifa Univ. of Science, Abu Dhabi (United Arab Emirates); Kim, Sungyeop; Chang, Soonheung; Lee, Kunjai [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2013-05-15

The distribution ratio of these three types of iodine being released to the atmosphere under accident scenario is still not clearly reported because of its complex kinetics of chemical and physical process in the accidental condition. In this research, the dispersion behaviors of three kinds of iodine in the atmosphere have been considered in the UAE environment in winter and summer situations. Higher ground level concentration on the same downwind distance from the source appears in summer because of lower wind speed than that of winter. More lateral spreading of vertical downwind direction in summer has been confirmed because of less stable air than that of winter. Higher ground level concentrations have been appeared in order of particle type, organic gas type and elemental gas type of I-131 with given assumptions.

XOQDOQ, Meteorological Evaluation of Atmospheric Nuclear Power Plant Effluents

International Nuclear Information System (INIS)

Sagendorf, J.F.; Goll, J.T.; Sandusky, W.F.; Eyberger, L.R.

1990-01-01

1 - Description of program or function: XOQDOQ was designed for meteorological evaluation of continuous and anticipated intermittent releases from commercial nuclear power reactors. It calculates annual relative effluent concentrations and average relative deposition values at locations specified by the user and at various standard radial distances and segments for downwind sectors. It also calculates these values at the specified locations for anticipated intermittent (e.g. containment or purge) releases, which occur during routine operation. The program computes an effective plume height that accounts for physical release height, aerodynamic down-wash, plume rise, and terrain features. The user may optionally select additional plume dispersion due to building wakes, plume depletion via dry deposition, and plume radioactive decay, or specify adjustments to represent non-straight line trajectories (recirculation or stagnation). 2 - Method of solution: XOQDOQ is based on the principle that diffusion of material released to the atmosphere can be described by a Gaussian distribution within the plume with transport described by a straight-line trajectory. The horizontal and vertical dispersion coefficients are empirically determined, largely from observations at or near ground level. The program implements the assumptions outlined in Section C of NRC Regulatory Guide 1.111. Long-term average values of relative effluent concentration are calculated by assuming a long-term continuous release with effluent distributed evenly across a 22-1/2 degree sector. 3 - Restrictions on the complexity of the problem - Maxima of: 30 receptor locations/receptor type, 14 wind-speed classes, 10 distances of site-specific recirculation correction factors, 8 receptor types, 7 atmospheric stability categories, 5 separate release points. XOQDOQ cannot handle multiple emission sources or plume depletion via wet deposition, or evaluate the meteorological aspects of the consequences of

Blast from pressurized carbon dioxide released into a vented atmospheric chamber

Science.gov (United States)

Hansen, P. M.; Gaathaug, A. V.; Bjerketvedt, D.; Vaagsaether, K.

2018-03-01

This study describes the blast from pressurized carbon dioxide (CO2) released from a high-pressure reservoir into an openly vented atmospheric chamber. Small-scale experiments with pure vapor and liquid/vapor mixtures were conducted and compared with simulations. A motivation was to investigate the effects of vent size and liquid content on the peak overpressure and impulse response in the atmospheric chamber. The comparison of vapor-phase CO2 test results with simulations showed good agreement. This numerical code described single-phase gas dynamics inside a closed chamber, but did not model any phase transitions. Hence, the simulations described a vapor-only test into an unvented chamber. Nevertheless, the simulations reproduced the incident shock wave, the shock reflections, and the jet release inside the atmospheric chamber. The rapid phase transition did not contribute to the initial shock strength in the current test geometry. The evaporation rate was too low to contribute to the measured peak overpressure that was in the range of 15-20 kPa. The simulation results produced a calculated peak overpressure of 12 kPa. The liquid tests showed a significantly higher impulse compared to tests with pure vapor. Reducing the vent opening from 0.1 to 0.01 m2 resulted in a slightly higher impulse calculated at 100 ms. The influence of the vent area on the calculated impulse was significant in the vapor-phase tests, but not so clear in the liquid/vapor mixture tests.

Dutch distribution zones of stable iodine tablets based on atmospheric dispersion modelling of accidental releases from nuclear power plants.

NARCIS (Netherlands)

Kok-Palma, Y.S.; Leenders, M.; Meulenbelt, J.

2010-01-01

Rapid administration of stable iodine is essential for the saturation and subsequent protection of the thyroid gland against the potential harm caused by radioiodines. This paper proposes the Dutch risk analysis that uses an atmospheric dispersion model to calculate the size of the zones around

User guide programmer's reference. NUDOS: A computer programme for assessing the consequences of airborne releases of radionuclides

International Nuclear Information System (INIS)

Grupa, J.

1996-10-01

NUDOS is a computer program that can be used to evaluate the consequences of airborne releases of radioactive materials. The consequences evaluated are individual dose and associated radiological risk, collective dose and the contamination of land. The code is capable of dealing with both routine and accidental releases. For accidental releases both deterministic and probabilistic calculations can be performed and the impact and effectiveness of emergency actions can be evaluated. (orig.)

Models selected for calculation of doses, health effects and economic costs due to accidental radionuclide releases from nuclear power plants. Technical report

International Nuclear Information System (INIS)

Strenge, D.L.; Acharya, S.; Baker, D.A.; Droppo, J.G.; McPherson, R.B.

1980-05-01

Models are described for use in site-specific environmental consequence analysis of nuclear reactor accidents of Classes 3 through 9. The models presented relate radioactivity released to resulting doses, health effects, and costs of remedial actions. Specific models are presented for the major exposure pathways of airborne releases, waterborne releases and direct irradiation from activity within the facility buildings, such as the containment. Time-dependent atmospheric dispersion parameters, crop production parameters, and other variable parameters are used in the models. The environmental effects are analyzed for several accident start times during the year. Several remedial actions are considered

Correlation between hydrogen release and degradation of limestone concrete exposed to hot liquid sodium in inert atmosphere

International Nuclear Information System (INIS)

Parida, F.C.; Das, S.K.; Sharma, A.K.; Ramesh, S.S.; Somayajulu, P.A.; Kannan, S.E.

2005-01-01

Full text of publication follows: Concrete is used as a structural material in a Fast Breeder Reactor (FBR) plant for the construction of its foundation, containment, radiation shield and equipment support structures. An accidental leakage of hot sodium on these civil structures can bring about thermo-chemical reactions, with concrete producing hydrogen gas and causing structural degradation. The concrete damage and hydrogen generation take place concurrently due to conduction of heat from sodium into the concrete and migration of steam / moisture in counter current direction towards sodium. In a series of experiments conducted with limestone concrete for two different types of design corresponding to composition and geometry, were exposed to liquid sodium (∼2 kg) at initial temperatures varying from 180 deg. C to 500 deg. C in an inerted test vessel (Capacity = 203 L). Immersion heater was employed to heat the sodium pool on the concrete cavity during the test period in some test runs. On-line continuous measurement of pressure, temperature, hydrogen gas and oxygen gas was carried out. Pre- and post- test nondestructive testing such as colour photography, spatial profiling of ultrasonic pulse velocity and measurement of dimensions were also conducted. Solid samples were collected from sodium debris by manual core drilling machine and from concrete block by hand held electric drilling machine. These samples were subjected to chemical analysis for the determination of free and bound water along with unburnt and burnt sodium. The hydrogen generation parameters such as average and peak release rate as well as release efficiency are derived from measured test variables. These test variables include temperature, pressure and hydrogen concentration in the argon atmosphere contained in the test vessel. The concrete degradation parameters encompass percentage reduction in ultrasonic pulse velocity, depth of physical and chemical dehydration and sodium penetration. These

An analytical model for radioactive pollutant release simulation in the atmospheric boundary layer

International Nuclear Information System (INIS)

Weymar, Guilherme J.; Vilhena, Marco T.; Bodmann, Bardo E.J.; Buske, Daniela; Quadros, Regis

2013-01-01

Simulations of emission of radioactive substances in the atmosphere from the Brazilian nuclear power plant Angra 1 are a necessary tool for control and elaboration of emergency plans as a preventive action for possible accidents. In the present work we present an analytical solution for radioactive pollutant dispersion in the atmosphere, solving the time-dependent three-dimensional advection-diffusion equation. The experiment here used as a reference in the simulations consisted of the controlled releases of radioactive tritiated water vapor from the meteorological tower close to the power plant at Itaorna Beach. The wind profile was determined using experimental meteorological data and the micrometeorological parameters were calculated from empirical equations obtained in the literature. We report on a novel analytical formulation for the concentration of products of a radioactive chain released in the atmospheric boundary layer and solve the set of coupled equations for each chain radionuclide by the GILTT solution, assuming the decay of all progenitors radionuclide for each equation as source term. Further we report on numerical simulations, as an explicit but fictitious example and consider three radionuclides in the radioactive chain of Uranium 235. (author)

An analytical model for radioactive pollutant release simulation in the atmospheric boundary layer

Energy Technology Data Exchange (ETDEWEB)

Weymar, Guilherme J.; Vilhena, Marco T.; Bodmann, Bardo E.J., E-mail: guicefetrs@gmail.com, E-mail: mtmbvilhena@gmail.com, E-mail: bejbodmann@gmail.com [Universidade Federal do Rio Grande do Sul (UFRGS), Porto Alegre, RS (Brazil). Programa de Pos-Graduacao em Engenharia Mecanica; Buske, Daniela; Quadros, Regis, E-mail: danielabuske@gmail.com, E-mail: quadros99@gmail.com [Universidade Federal de Pelotas (UFPel), Capao do Leao, RS (Brazil). Programa de Pos-Graduacao em Modelagem Matematica

2013-07-01

Simulations of emission of radioactive substances in the atmosphere from the Brazilian nuclear power plant Angra 1 are a necessary tool for control and elaboration of emergency plans as a preventive action for possible accidents. In the present work we present an analytical solution for radioactive pollutant dispersion in the atmosphere, solving the time-dependent three-dimensional advection-diffusion equation. The experiment here used as a reference in the simulations consisted of the controlled releases of radioactive tritiated water vapor from the meteorological tower close to the power plant at Itaorna Beach. The wind profile was determined using experimental meteorological data and the micrometeorological parameters were calculated from empirical equations obtained in the literature. We report on a novel analytical formulation for the concentration of products of a radioactive chain released in the atmospheric boundary layer and solve the set of coupled equations for each chain radionuclide by the GILTT solution, assuming the decay of all progenitors radionuclide for each equation as source term. Further we report on numerical simulations, as an explicit but fictitious example and consider three radionuclides in the radioactive chain of Uranium 235. (author)

Atmospheric dispersion and deposition of 131I released from the Hanford Site

International Nuclear Information System (INIS)

Ramsdell, J.V. Jr.; Simonen, C.A.; Burk, K.W.; Stage, S.A.

1996-01-01

Approximately 2.6 x 10 4 TBq (700,000 Ci) of 131 I were released to the air from reactor fuel processing plants on the Hanford Site in southcentral Washington State from December 1944 through December 1949. The Hanford Environmental Dose Reconstruction Project developed a suite of codes to estimate the doses that might have resulted from these releases. The Regional Atmospheric Transport Code for Hanford Emission Tracking (RATCHET) computer code is part of this suite. The RATCHET code implements a Lagrangian-trajectory, Gaussian-puff dispersion model that uses hourly meterological and release rate data to estimate daily time-integrated air concentrations and surface contamination for use, in dose estimates. In this model, iodine is treated as a mixture of three species (inorganic gases, organic gases, and particles). Model deposition parameters are functions of the mixture and meterological conditions. A resistance model is used to calculate dry deposition velocities. Equilibrium between concentrations in the precipitation and the air near the ground is assumed in calculating wet deposition of gases, and irreversible washout of the particles is assumed. RATCHET explicitly treats the uncertainties in model parameters and meteorological conditions. Uncertainties in 131 I release rates and partitioning among the nominal species are treated by varying model input. The results of 100 model runs for December 1944 through December 1949 indicate that monthly average air concentrations and deposition have uncertainties ranging from a factor of two near the center of the time-integrated plume to more than an order of magnitude near the edge. These results indicate that ∼10% of the 131 I released to the atmosphere decayed during transit in the study area, ∼56% was deposited within the study area, and the remaining 34% was transported out of the study area while still in the air

MAXDOSE-SR: A routine release atmospheric dose model used at SRS

International Nuclear Information System (INIS)

Simpkins, A.A.

2000-01-01

MAXDOSE-SR is a PC version of the dosimetry code MAXIGASP, which was used to calculate doses to the maximally exposed offsite individual for routine atmospheric releases of radioactive material at the Savannah River Site (SRS). Complete code description, verification of models, and user's manual have been included in this report. Minimal input is required to run the program, and site specific parameters are used when possible

Comparison of gridded versus observation data to initialize ARAC dispersion models for the Algeciras, Spain steel mill CS-137 release

International Nuclear Information System (INIS)

Aluzzi, F J; Pace, J C; Pobanz, B M; Vogt, P J

1999-01-01

On May 30, 1998 scrap metal containing radioactive Cesium-137 (Cs-137) was accidentally melted in a furnace at the Acerinox steel mill in Algeciras, Spain. Cs-137 was released from the mill's smokestack, and spread across the western Mediterranean Sea to France and Italy and beyond. The first indication of the release was radiation levels up to 1000 times background reported by Swiss, French, and Italian authorities during the following two weeks. Initially no elevated radiation levels were detected over Spain. A release of hazardous material to the atmosphere is the type of situation the Atmospheric Release Advisory Capability (ARAC) emergency response organization was designed to address. The amount and exact time of the release were unknown, though the incident was thought to have taken place during the last week in May. Using air concentration measurements supplied by colleagues of ARAC in Spain, France, Switzerland, Italy, Sweden, Russia and the European Union, ARAC meteorologists estimated the magnitude and timing of the release (Vogt, 1999). Correctly locating the downwind footprint is the most important goal of emergency response modeling. In this study, we compare predicted results for the Algeciras event based on four wind data sources: (1) US Navy Operational Global Atmospheric Prediction System (NOGAPS) data alone, (2) surface and upper air observations alone, (3) NOGAPS data together with surface and upper air observations, and (4) forecasts from ARAC's in-house execution of the U.S. Navy Operational Regional Atmospheric Prediction System (NORAPS) (without surface or upper air observations). We compare the resulting dispersion predictions from ARAC's diagnostic dispersion modeling system to the measurements supplied by our European colleagues to determine which data source produced the best results

Sensitivity study of the Continuous Release Dispersion Model (CRDM) for radioactive pollutants

International Nuclear Information System (INIS)

Camacho, F.

1987-08-01

The Continuous Release Dispersion Model (CRDM) is used to calculate spatial distribution of pollutants and their radiation doses in the event of accidental releases of radioactive material from Nuclear Generation Stations. A sensitivity analysis of the CRDM was carried out to develop a method for quantifying the expected output uncertainty due to inaccuracies and uncertainties in the input values. A simulation approach was used to explore the behaviour of the sensitivity functions. It was found that the most sensitive variable is wind speed, the least sensitive is the ambient temperature, and that largest values of normalized concentrations are likely to occur for small values of wind speed and highly stable atmospheric conditions. It was also shown that an error between 10% and 25% should be expected in the output values for a 1% overall error in the input values, and this factor could be much larger in certain situations

A model for short and medium range dispersion of radionuclides released to the atmosphere

International Nuclear Information System (INIS)

Clarke, R.H.

1979-09-01

A Working Group was established to give practical guidance on the estimation of the dispersion of radioactive releases to the atmosphere. The dispersion is estimated in the short and medium range, that is from about 100 m to a few tens of kilometres from the source, and is based upon a Gaussian plume model. A scheme is presented for categorising atmospheric conditions and values of the associated dispersion parameters are given. Typical results are presented for releases in specific meteorological conditions and a scheme is included to allow for durations of release of up to 24 hours. Consideration has also been given to predicting longer term average concentrations, typically annual averages, and results are presented which facilitate site specific calculations. The results of the models are extended to 100 km from the source, but the increasing uncertainty with which results may be predicted beyond a few tens of kilometres from the source is emphasised. Three technical appendices provide some of the rationale behind the decisions made in adopting the various models in the proposed dispersion scheme. (author)

Gas and aerosol radionuclide transfers in complex environments: experimental studies of atmospheric dispersion and interfaces exchanges

International Nuclear Information System (INIS)

Maro, Denis

2011-01-01

In situations of chronic or accidental releases, the atmosphere is the main pathway of radioactive releases from nuclear facilities to the environment and, consequently, to humans. It is therefore necessary to have sufficient information on this pathway to accurately assess the radiological impact on man and his environment. Institute for Radioprotection and Nuclear Safety develops its own tools of dispersion and atmospheric transfer for its expertise, under normal operation conditions of a facility, but especially in crisis or post-accident. These tools must have a national and international recognition in particular through scientific validation against benchmark experiments performed internationally, nationally or within the IRSN. The Radioecology Laboratory of Cherbourg-Octeville provides, and will increasingly make, a significant contribution to the scientific influence of the Institute in this field. The work presented in this report has contributed to the development or improvement of experimental techniques in the fields of atmospheric dispersion of radionuclides and transfer at interfaces, in complex environments (complex topography, urban area). These experimental techniques, applied during field campaigns, have allowed to acquire new data in order to get a better understanding of radionuclide transfers in the form of gases and aerosols. (author)

Atmospheric plume progression as a function of time and distance from the release point for radioactive isotopes.

Science.gov (United States)

Eslinger, Paul W; Bowyer, Ted W; Cameron, Ian M; Hayes, James C; Miley, Harry S

2015-10-01

The radionuclide network of the International Monitoring System comprises up to 80 stations around the world that have aerosol and xenon monitoring systems designed to detect releases of radioactive materials to the atmosphere from nuclear explosions. A rule of thumb description of plume concentration and duration versus time and distance from the release point is useful when designing and deploying new sample collection systems. This paper uses plume development from atmospheric transport modeling to provide a power-law rule describing atmospheric dilution factors as a function of distance from the release point. Consider the plume center-line concentration seen by a ground-level sampler as a function of time based on a short-duration ground-level release of a nondepositing radioactive tracer. The concentration C (Bq m(-3)) near the ground varies with distance from the source with the relationship C=R×A(D,C) ×e (-λ(-1.552+0.0405×D)) × 5.37×10(-8) × D(-2.35) where R is the release magnitude (Bq), D is the separation distance (km) from the ground level release to the measurement location, λ is the decay constant (h(-1)) for the radionuclide of interest and AD,C is an attenuation factor that depends on the length of the sample collection period. This relationship is based on the median concentration for 10 release locations with different geographic characteristics and 365 days of releases at each location, and it has an R(2) of 0.99 for 32 distances from 100 to 3000 km. In addition, 90 percent of the modeled plumes fall within approximately one order of magnitude of this curve for all distances. Copyright © 2015 Elsevier Ltd. All rights reserved.

Modelling and assessment of accidental oil release from damaged subsea pipelines.

Science.gov (United States)

Li, Xinhong; Chen, Guoming; Zhu, Hongwei

2017-10-15

This paper develops a 3D, transient, mathematical model to estimate the oil release rate and simulate the oil dispersion behavior. The Euler-Euler method is used to estimate the subsea oil release rate, while the Eulerian-Lagrangian method is employed to track the migration trajectory of oil droplets. This model accounts for the quantitative effect of backpressure and hole size on oil release rate, and the influence of oil release rate, oil density, current speed, water depth and leakage position on oil migration is also investigated in this paper. Eventually, the results, e.g. transient release rate of oil, the rise time of oil and dispersion distance are determined by above-mentioned model, and the oil release and dispersion behavior under different scenarios is revealed. Essentially, the assessment results could provide a useful guidance for detection of leakage positon and placement of oil containment boom. Copyright © 2017 Elsevier Ltd. All rights reserved.

Analysis of explosion-induced releases of toxic materials at an environmental restoration project

International Nuclear Information System (INIS)

Bloom, S.G.; Moon, W.H. Jr.

1993-01-01

Prior to 1988, a variety of materials were buried on the US DOE Oak Ridge Reservation. Records of the disposal operations are incomplete and toxic materials may have been placed adjacent to potential explosives. One of the safety concerns in conducting an environmental restoration project at the burial sites, is the possibility of an explosion which could release toxic materials to the atmosphere. A safety analysis examined the consequences of such releases by first postulating an upper bound for the strength of an explosive. A correlation, developed by Steindler and Seefeldt of Argonne National Laboratory, was then used to estimate the amount and particle-size distribution of the material that could become airborne from the explosion. The estimated amount of airborne material was the source term in an atmospheric dispersion model which was used to calculate infinite-time, concentration-time integrals and 5-minute, time- weighted average concentrations at locations down-wind from the explosion. The dispersion model includes particle deposition as a function of particle-size distribution class. The concentration-time integrals and average concentrations were compared to published guidelines to assess the consequences of an accidental explosion

Improvement of long-distance atmospheric transfer models Post-Chernobyl action

International Nuclear Information System (INIS)

Sinnaeve, J.

1991-01-01

The Chernobyl accident, although a tragedy in human terms, provided a valuable opportunity to examine our ability to model the dispersion and deposition of pollutants released into the atmosphere as they are transported over long distances by the wind. Models of long-range pollutant transport have a variety of uses in the context of accidental releases of radioactivity: in the early stages after or during an incident, they would assist in providing an indication of when and where contamination might be expected to appear in subsequent days and what its severity would be for a postulated (or known) release magnitude. As measurements of contamination become available, models can play a further role in emergency response: if the characteristics of the release, particularly the amounts of various radionuclides, are not known, they could be used to work back from measurements to properties of the release. They also provide a tool for an intelligent interpolation or extrapolation from the measurements to estimates of contamination levels in areas having no data. On a longer time-scale after an accident, they could assist in forming a total view of the situation and in assessing how important various phenomena were in determining the final contamination patterns

AEROS: a real-time emergency response system for atmospheric releases of toxic material

International Nuclear Information System (INIS)

Nasstrom, J.S.; Greenly, G.D.

1986-01-01

The Atmospheric Release Advisory Capability (ARAC) at the Lawrence Livermore National Laboratory has developed a sophisticated computer-based real-time emergency response system for radiotoxic releases into the atmosphere. The ARAC Emergency Response Operating System (AEROS) has a centralized computer facility linked to remote site computers, meteorological towers, and meteorological data sources. The system supports certain fixed sites, but has the ability to respond to accidents at arbitrary locations. Product quality and response time are optimized by using complex three-dimensional dispersion models; extensive on-line data bases; automated data processing; and an efficient user interface, employing graphical computer displays and computer-displayed forms. Upon notification, the system automatically initiates a response to an emergency and proceeds through preliminary calculations, automatically processing accident information, meteorological data, and model parameters. The model calculations incorporate mass-consistent three-dimensional wind fields, terrain effects, and particle-in-cell diffusion. Model products are color images of dose or deposition contours overlaid on a base map

Modelling of the tritium dispersion from postulated accidental release of nuclear power plants; Modelagem da dispersao de tritio a partir de liberacoes acidentais postuladas de centrais nucleares

Energy Technology Data Exchange (ETDEWEB)

Soares, Abner Duarte; Simoes Filho, Francisco Fernando Lamego; Cunha, Tatiana Santos da [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Aguiar, Andre Silva de; Lapa, Celso Marcelo Franklin, E-mail: asoares@cnen.gov.b, E-mail: flamego@ien.gov.b, E-mail: lapa@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2011-07-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models to simulation of tritium dispersion caused by an accident in a Candu reactor located in the ongoing Angra 3 site. The Candu reactor is one that uses heavy water (D{sub 2}O) as moderator and coolant of the core. It was postulated, then, the LOCA accident (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 P Bq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m{sup 3}) during the first 14 days after the accident. (author)

Presentation and interpretation of field experiments of gaseous UF6 releases in the atmosphere

International Nuclear Information System (INIS)

Crabol, B.; Boulaud, D.; Deville-Cavelin, G.

1992-01-01

An experimental programme concerning the behaviour of UF 6 released in gaseous phase in the atmosphere has been conducted in the years 1986-1989 by the french Atomic Energy Commission and Eurodif. Three field tests have been performed on the CEA/CESTA experimental site. These experiments permitted to get informations about the kinetics of the hydrolysis reaction of the UF 6 , the behaviour of the hydrolysis products in the atmosphere and the granulometry of the solid particles

Presentation and interpretation of field experiments of gaseous UF6 releases in the atmosphere

Energy Technology Data Exchange (ETDEWEB)

Crabol, B.; Boulaud, D.; Deville-Cavelin, G. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Dept. de Protection de l`Environnement et des Installations; Geisse, C.; Iacona, L. [EURODIF, 26 - Pierrelatte (France)

1992-12-31

An experimental programme concerning the behaviour of UF{sub 6} released in gaseous phase in the atmosphere has been conducted in the years 1986-1989 by the french Atomic Energy Commission and Eurodif. Three field tests have been performed on the CEA/CESTA experimental site. These experiments permitted to get informations about the kinetics of the hydrolysis reaction of the UF{sub 6}, the behaviour of the hydrolysis products in the atmosphere and the granulometry of the solid particles.

User Guide ECOREA-RICE (version 1.0). Program for assessing the transfer of radionuclides released accidentally onto flooded rice-fields

International Nuclear Information System (INIS)

Keum, Dong Kwon; Lee, Han Soo; Choi, Hei Hu; Kang, Hee Seok; Lee, Chang Woo

2004-05-01

The computer code ECOREA-RICE is a dynamic compartment model that is specially designed for estimating the transfer of radionuclides deposited onto flooded rice-fields after an accidental release. The model consists of six independent compartments including rice-body, grain, surface water, root-zone soil, fixed soil and deep soil, and takes into account the transfer processes including radioactive decay, percolation, leaching, shoot-base absorption, root-uptake, weathering, translocation, fixation in soil by adsorption and desorption, and soil-mixing by plowing. The rate of the change of radioactivity in compartments is expressed by a set of the first order ordinary differential equations, which are solved by the fourth order Runge-Kutta algorithm. Input to the program includes the deposition date, transplanting date, ear emergence date, harvest date, soil data, the biomass data of rice-plant, and rate constants associated with transfer processes. Output includes the list of input data, the activity of radionuclides in compartment, the rate constant, and the transfer factor of rice-body and grain with time

Acute Renal Failure following Accidental Potassium Bromate ...

African Journals Online (AJOL)

Accidental poisoning is common in children. Potassium bromate is a commonly used additive and raising agent in many edibles particularly bread, a staple food worldwide, yet its accidental poisoning has hitherto, not been documented in Nigeria. We report an unusual case of acute renal failure following accidental ...

Signos Vitales de los CDC–Prevención de muertes por accidentes cerebrovasculares (Preventing Stroke Deaths)

Centers for Disease Control (CDC) Podcasts

2017-09-06

Este podcast se basa en la edición de septiembre del 2017 del informe Signos Vitales de los CDC. Cada año, más de 140 000 personas mueren y muchos sobrevivientes quedan con discapacidades. El ochenta por ciento de los accidentes cerebrovasculares son prevenibles. Conozca los signos de un accidente cerebrovascular y sepa cómo prevenirlo.  Created: 9/6/2017 by Centers for Disease Control and Prevention (CDC).   Date Released: 9/6/2017.

Introduction to CRRIS: a computerized radiological risk investigation system for assessing atmospheric releases of radionuclides

International Nuclear Information System (INIS)

Baes, C.F. III; Miller, C.W.; Kocher, D.C.; Sjoreen, A.L.; Murphy, B.D.

1985-08-01

The CRRIS is a Computerized Radiological Risk Investigation System consisting of eight fully integrated computer codes which calculate environmental transport of atmospheric releases of radionuclides and resulting doses and health risks to individuals or populations. Each code may also be used alone for various assessment applications. Radionuclides are handled by the CRRIS either in terms of the released radionuclides or the exposure radionuclides which consist of both the released nuclides and decay products that grow in during environmental transport. The CRRIS is not designed to simulate short-term effects. 51 refs

Sugarcane vinasse CO2 gasification and release of ash-forming matters in CO2 and N2 atmospheres.

Science.gov (United States)

Dirbeba, Meheretu Jaleta; Brink, Anders; DeMartini, Nikolai; Lindberg, Daniel; Hupa, Mikko

2016-10-01

Gasification of sugarcane vinasse in CO2 and the release of ash-forming matters in CO2 and N2 atmospheres were investigated using a differential scanning calorimetry and thermogravimetric analyzer (DSC-TGA) at temperatures between 600 and 800°C. The results showed that pyrolysis is the main mechanism for the release of the organics from vinasse. Release of ash-forming matters in the vinasse is the main cause for vinasse char weight losses in the TGA above 700°C. The losses are higher in N2 than in CO2, and increase considerably with temperature. CO2 gasification also consumes the carbon in the vinasse chars while suppressing alkali release. Alkali release was also significant due to volatilization of KCl and reduction of alkali sulfate and carbonate by carbon. The DSC measured thermal events during heating up in N2 atmosphere that correspond to predicted melting temperatures of alkali salts in the char. Copyright © 2016 Elsevier Ltd. All rights reserved.

HARAD, Decay Isotope Concentration from Atmospheric Noble-Gas Release

International Nuclear Information System (INIS)

Moore, R.E.

1986-01-01

1 - Description of problem or function: HARAD calculates concentrations of radioactive daughters in air following the atmospheric release of a parent radionuclide for a variety of release heights and meteorological conditions. It can be applied most profitably to the assessment of doses to man from the noble gases such as Rn-222, Rn-220, and Xe and Kr isotopes. These gases can produce significant quantities of short-lived particulate daughters in an airborne plume, which are the major contributors to dose. The simultaneous processes of radioactive decay, buildup and environmental loss due to wet and dry deposition on ground surfaces are calculated for a daughter chain in an airborne plume as it is dispersed downwind from a point of release of a parent. 2 - Method of solution: The code evaluates the analytic solution to the set of coupled first order differential equations describing time variation of the concentration of a chain of radionuclides. The analytic solutions assume that the coefficient describing the fractional rate of dry deposition is constant with time. To account for the variation the time coordinate is automatically divided into intervals and a set of average values are used. 3 - Restrictions on the complexity of the problem: - The maximum length of decay chain is 10 nuclides; calculations can be made at a maximum of 24 downwind distances

Model-Data Fusion and Adaptive Sensing for Large Scale Systems: Applications to Atmospheric Release Incidents

Science.gov (United States)

Madankan, Reza

All across the world, toxic material clouds are emitted from sources, such as industrial plants, vehicular traffic, and volcanic eruptions can contain chemical, biological or radiological material. With the growing fear of natural, accidental or deliberate release of toxic agents, there is tremendous interest in precise source characterization and generating accurate hazard maps of toxic material dispersion for appropriate disaster management. In this dissertation, an end-to-end framework has been developed for probabilistic source characterization and forecasting of atmospheric release incidents. The proposed methodology consists of three major components which are combined together to perform the task of source characterization and forecasting. These components include Uncertainty Quantification, Optimal Information Collection, and Data Assimilation. Precise approximation of prior statistics is crucial to ensure performance of the source characterization process. In this work, an efficient quadrature based method has been utilized for quantification of uncertainty in plume dispersion models that are subject to uncertain source parameters. In addition, a fast and accurate approach is utilized for the approximation of probabilistic hazard maps, based on combination of polynomial chaos theory and the method of quadrature points. Besides precise quantification of uncertainty, having useful measurement data is also highly important to warranty accurate source parameter estimation. The performance of source characterization is highly affected by applied sensor orientation for data observation. Hence, a general framework has been developed for the optimal allocation of data observation sensors, to improve performance of the source characterization process. The key goal of this framework is to optimally locate a set of mobile sensors such that measurement of textit{better} data is guaranteed. This is achieved by maximizing the mutual information between model predictions

Doses due to tritium releases by NET - data base and relevant parameters on biological tritium behaviour

International Nuclear Information System (INIS)

Diabate, S.; Strack, S.

1990-12-01

This study gives an overview on the current knowledge about the behaviour of tritium in plants and in food chains in order to evaluate the ingestion pathway modelling of existing computer codes for dose estimations. The tritium uptake and retention by plants standing at the beginning of the food chains is described. The different chemical forms of tritium, which may be released into the atmosphere (HT, HTO and tritiated organics), and incorporation of tritium into organic material of plants are considered. Uptake and metabolism of tritiated compounds in animals and man are reviewed with particular respect to organically bound tritium and its significance for dose estimations. Some basic remarks on tritium toxicity are also included. Furthermore, a choice of computer codes for dose estimations due to chronic or accidental tritium releases has been compared with respect to the ingestion pathway. (orig.) [de

Evaluating the Effect of Nuclear Power Plant Buildings on the Atmospheric Dispersion Behavior of Released Radioactive Materials

International Nuclear Information System (INIS)

Nassar, N.N.; Tawfik, F.S.; Agamy, S.A.; Nagla, T.F.

2017-01-01

One of the most important principles in air pollution is to minimize the release of pollutants to the atmosphere, deposition on the ground and promote sufficient dilution of released pollutants within the atmosphere. Building down wash describes the effect that wind flowing over or around buildings create a cavity of reticulating winds in the are a near the buildings. These cavities cause increased vertical dispersion of plumes emitted from stacks on or near the buildings . Often it leads to elevated concentrations downwind of affected stacks. The aim of this work is to evaluate the effect of the building down wash phenomena on the atmospheric dispersion behavior of released radioactive materials from NPP. In this study, a hypothetical scenario is presented involving a point source with varying stack parameters and rectangular shaped buildings (Mille stone Nuclear Power Plant) using meteorological parameters of a chosen day. The concentrations of assumed released radionuclides, taking into consideration the building down wash effect and without are calculated using the AERMOD Model taking into consideration the effect of the type of atmospheric stability class. Also the analysis includes the model predictions for the highest 1-hour cavity concentration. The results show that the size of the cavity zone is not affected by the type of stability class, but is affected by the stack location and buildings shape. On other hand, the distance at which the plume touches the ground is affected by the type of stability class, the stack location and buildings shape. So, strategies for locating buildings need to be considered to maximize dispersion when planning for constructing several reactors and accessory buildings at a nuclear site

Isopleths of surface concentration and surface exposure rate due to a radioactive cloud released from a stack

International Nuclear Information System (INIS)

Kobayashi, Hideo; Yabuta, Hajimu; Katagiri, Hiroshi; Obata, Kazuichi; Kokubu, Morinobu

1982-03-01

Various calculations are made to estimate the distributions of concentration and γ-exposure rate due to a radioactive cloud released from a point source to the atmosphere. In this report, the isopleths of concentration and γ-exposure rate which were calculated are given in graphs to enable rapid prediction of the influence of released radioactive material in the emergency situation. Recently there are facilities which are equipped with a system to display the calculation results on CRT; but such practice is rather rare. By placing the calculated isopleths of reduction scale 1/25000 or 1/50000 on the usual map, any facilities without the CRT system can readily estimate the influence of an accidental release. The graphs of isopleths are given with the release height (11 values of 0 to 200 m at about 20 m intervals) and the atmospheric stability (6 classes) as parameters. Calculations of γ-exposure rates were made using the computer code GAMPUL developed by T. Hayashi and T. Shiraishi. In the calculation of radioactive concentrations and γ-exposure rates, the vertical diffusion depths, σsub(z), exceeding 1000 m are taken to be 1000 m according to the Meteorological Guide for the Safety Analysis of Power Reactor (J.AEC). The comparison between with and without this limitation in σsub(z) is made in the case of downwind axial surface distributions. (author)

SPEEDI: a computer code system for the real-time prediction of radiation dose to the public due to an accidental release

International Nuclear Information System (INIS)

Imai, Kazuhiko; Chino, Masamichi; Ishikawa, Hirohiko

1985-10-01

SPEEDI, a computer code system for prediction of environmental doses from radioactive materials accidentally released from a nuclear plant has been developed to assist the organizations responsible for an emergency planning. For realistic simulation, have been developed a model which statistically predicts the basic wind data and then calculates the three-dimensional mass consistent wind field by interpolating these predicted data, and a model for calculation of the diffusion of released materials using a combined model of random-walk and PICK methods. These calculation in the system is carried out in conversational mode with a computer so that we may use the system with ease in an emergency. SPEEDI has also versatile files, which make it easy to control the complicated flows of calculation. In order to attain a short computation time, a large-scale computer with performance of 25 MIPS and a vector processor of maximum 250 MFLOPS are used for calculation of the models so that quick responses have been made. Simplified models are also prepared for calculation in a minicomputer widely used by local governments and research institutes, although the precision of calculation as same with the above models can not be expected to obtain. The present report outlines the structure and functions of SPEEDI, methods for prediction of the wind field and the models for calculation of the concentration of released materials in air and on the ground, and the doses to the public. Some of the diffusion models have been compared with the field experiments which had been carried out as a part of the SPEEDI development program. The report also discusses the reliability of the diffusion models on the basis of the compared results, and shows that they can reasonably simulate the diffusion in the internal boundary layer which commonly occurs near the coastal region. (J.P.N.)

Savannah River Site Ingestion Pathway Methodology Manual for Airborne Radioactive Releases

Energy Technology Data Exchange (ETDEWEB)

Vincent, A.W. III

2001-01-03

This manual documents a recommended methodology for determining the ingestion pathway consequences of hypothetical accidental airborne radiological releases from facilities at the Savannah River Site. Both particulate and tritiated radioactive contaminants are addressed. Other approaches should be applied for evaluation of routine releases.

Atmospheric dispersion simulations of volcanic gas from Miyake Island by SPEEDI

International Nuclear Information System (INIS)

Nagai, Haruyasu; Furuno, Akiko; Terada, Hiroaki; Umeyama, Nobuaki; Yamazawa, Hiromi; Chino, Masamichi

2001-03-01

Japan Atomic Energy Research Institute is advancing the study for prediction of material circulation in the environment to cope with environmental pollution, based on SPEEDI (System for Prediction of Environmental Emergency Dose Information) and WSPEEDI (Worldwide version of SPEEDI), which are originally developed aiming at real-time prediction of atmospheric dispersion of radioactive substances accidentally released from nuclear facility. As a part of this study, dispersion simulation of volcanic gas erupted from Miyake Island is put into practice. After the stench incident at the west Kanto District on 28 August 2000 caused by volcanic gas from Miyake Island, the following simulations dealing with atmospheric dispersion of volcanic gas from Miyake Island have been carried out. (1) Retrospective simulation to analyze examine the mechanism of the transport of high concentration volcanic gas to the west Kanto District on 28 August and to estimate the release amount of volcanic gas. (2) Retrospective simulation to analyze the mechanism of the transport of volcanic gas to Tokai and Kansai districts in a case of stench incident on 13 September. (3) Automated real-time simulation from the acquisition of meteorological data to the output of figures for operational prediction of the transport of volcanic gas to Tokai and Kanto districts. This report describes the details of these studies. (author)

Region study of the impact of an accidental radioactive pollution on the corn of winter

International Nuclear Information System (INIS)

Delboe, A.; Mercat-Rommens, C.

2005-01-01

The goal of this study is to evaluate the sensitivity of corn of winter with respect to an accidental release of radioactivity. We want to know if a uniform and specific deposit would involve the same contamination on the scale of the whole territory. the study was based on the equations of the A.S.T.R.A.L. model which makes it possible to evaluate the transfer of the radionuclides in the terrestrial food chain following an accidental atmospheric emission. The parameter of A.S.T.R.A.L. on which the study concentrated is the factor of transfer of the radioactivity of the air to the grain. This factor depends on the parameters of captation and translocation, since harvest is contaminated when the radionuclides deposited on the leaves are assimilated and transported towards the grain. Methodology thus consisted in regionalizing these two parameters. for that, software S.T.I.C.S. (multidisciplinary simulator for standard cultures) developed by the I.N.R.A. of Avignon was used. This model proposes a daily follow-up of the foliar index, as well as the dates of occurrence of the agronomic stages of corn. These variables were correlated with captation and translocation. The outputs of the simulations carried out on 12 climates and 2 varieties made it possible to express the parameters of captation and translocation according to the typology of A.S.T.R.A.L., i e according to the time deposit-harvest. Then, these values were compared with bibliographical data and with data issued from I.R.S.N. programs R.E.S.S.A.C. and R.A.D.E.M.I.C.. (authors)

Ruthenium release modelling in air and steam atmospheres under severe accident conditions using the MAAP4 code

International Nuclear Information System (INIS)

Beuzet, Emilie; Lamy, Jean-Sylvestre; Perron, Hadrien; Simoni, Eric; Ducros, Gérard

2012-01-01

Highlights: ► We developed a new modelling of fuel oxidation and ruthenium release in the EDF version of the MAAP4 code. ► We validated this model against some VERCORS experiments. ► Ruthenium release prediction quantitatively and qualitatively well reproduced under air and steam atmospheres. - Abstract: In a nuclear power plant (NPP), a severe accident is a low probability sequence that can lead to core fusion and fission product (FP) release to the environment (source term). For instance during a loss-of-coolant accident, water vaporization and core uncovery can occur due to decay heat. These phenomena enhance core degradation and, subsequently, molten materials can relocate to the lower head of the vessel. Heat exchange between the debris and the vessel may cause its rupture and air ingress. After lower head failure, steam and air entering in the vessel can lead to degradation and oxidation of materials that are still intact in the core. Indeed, Zircaloy-4 cladding oxidation is very exothermic and fuel interaction with the cladding material can decrease its melting temperature by several hundred of Kelvin. FP release can thus be increased, noticeably that of ruthenium under oxidizing conditions. Ruthenium is of particular interest because of its high radio-toxicity due to 103 Ru and 106 Ru isotopes and its ability to form highly volatile compounds, even at room temperature, such as gaseous ruthenium tetra-oxide (RuO 4 ). It is consequently of great need to understand phenomena governing steam and air oxidation of the fuel and ruthenium release as prerequisites for the source term issues. A review of existing data on these phenomena shows relatively good understanding. In terms of oxygen affinity, the fuel is oxidized before ruthenium, from UO 2 to UO 2+x . Its oxidation is a rate-controlling surface exchange reaction with the atmosphere, so that the stoichiometric deviation and oxygen partial pressure increase. High temperatures combined with the presence

Atmospheric dilution factors for radioactive releases from Inshas research reactor, Egypt

International Nuclear Information System (INIS)

Abdel Aal, M.M.; Aly, A.I.M.; Tawfik, F.S.

1994-01-01

In the frame of assessing the suitability of Inshas site for constructing a new research reactor 20 MW, the meteorological condition are analyzed to determine the most affected population sectors. The atmospheric stability classes are estimated by a developed computer program in which the meteorological data for one year are used as input data. The results indicate that stability class F (moderately stable) is predominant one. The dilution factor is calculated using the computer code XOQDOQ for meteorological evaluation of routine effluent releases at nuclear power stations, which implements regulatory Guide 1.111 for both normal and desert conditions and for ground and elevated releases. The concentration isopleths are plotted and the most affected sector is the southern one with higher values for desert condition than the corresponding normal condition at same distance from the source. 4 fig., 3 tab

Radiative accidental matter

Energy Technology Data Exchange (ETDEWEB)

Sierra, D. Aristizabal [IFPA, Dép. AGO, Université de Liège,Bât B5, Sart Tilman B-4000 Liège 1 (Belgium); Universidad Técnica Federico Santa María - Departamento de Física,Casilla 110-V, Avda. España 1680, Valparaíso (Chile); Simoes, C.; Wegman, D. [IFPA, Dép. AGO, Université de Liège,Bât B5, Sart Tilman B-4000 Liège 1 (Belgium)

2016-07-25

Accidental matter models are scenarios where the beyond-the-standard model physics preserves all the standard model accidental and approximate symmetries up to a cutoff scale related with lepton number violation. We study such scenarios assuming that the new physics plays an active role in neutrino mass generation, and show that this unavoidably leads to radiatively induced neutrino masses. We systematically classify all possible models and determine their viability by studying electroweak precision data, big bang nucleosynthesis and electroweak perturbativity, finding that the latter places the most stringent constraints on the mass spectra. These results allow the identification of minimal radiative accidental matter models for which perturbativity is lost at high scales. We calculate radiative charged-lepton flavor violating processes in these setups, and show that μ→eγ has a rate well within MEG sensitivity provided the lepton-number violating scale is at or below 5×10{sup 5} GeV, a value (naturally) assured by the radiative suppression mechanism. Sizeable τ→μγ branching fractions within SuperKEKB sensitivity are possible for lower lepton-number breaking scales. We thus point out that these scenarios can be tested not only in direct searches but also in lepton flavor-violating experiments.

Probabilistic siting analysis of nuclear power plants emphasizing atmospheric dispersion of radioactive releases and radiation-induced health effects

International Nuclear Information System (INIS)

Savolainen, Ilkka

1980-01-01

A presentation is made of probabilistic evaluation schemes for nuclear power plant siting. Effects on health attributable to ionizing radiation are reviewed, for the purpose of assessment of the numbers of the most important health effect cases in light-water reactor accidents. The atmospheric dispersion of radioactive releases from nuclear power plants is discussed, and there is presented an environmental consequence assessment model in which the radioactive releases and atmospheric dispersion of the releases are treated by the application of probabilistic methods. In the model, the environmental effects arising from exposure to radiation are expressed as cumulative probability distributions and expectation values. The probabilistic environmental consequence assessment model has been applied to nuclear power plant site evaluation, including risk-benefit and cost-benefit analyses, and the comparison of various alternative sites. (author)

A radioecological risk assessment tool for post-accidental situations. Application in the Toulon marine area (South of France)

International Nuclear Information System (INIS)

Duffa, Celine; Thebault, Herve

2010-01-01

To estimate any post-accidental consequences in the environment and to propose adapted management plans, data concerning both radionuclides spatial dispersion and environmental sensitivity to this contamination are necessary. IRSN develops integrated tools to support experts and decision makers in post-accident situation concerning this area. This management tool aims to combine radionuclides dispersion modelling and radioecological sensitivity local maps to outline vulnerable areas front of a known release. An example of application to a maritime environment is given: the naval base of Toulon. Calculation of radionuclides dispersion is based on the existing MARS 3D hydrodynamic model. The radioecological sensitivity of the marine environment is based on the ecosystem intrinsic characteristics and the socio-economical resources. Mapping radionuclides dispersion results and sensitivity of defined zones of the studies area, we show that the Little Bay and the western part of Toulon marine area are the most vulnerable in case of accidental release occuring in the harbour. (orig.)

Forecasting accidental marine pollution drift: the French operational plan

International Nuclear Information System (INIS)

Daniel, P.; Poitevin, J.; Tiercelin, C.; Marchand, M.

1998-01-01

In case of accidental marine pollution, Cedre and Meteo-France, within the framework of their own public service missions, provide assistance to the French authorities in charge of pollution response. Meteo-France has developed a numerical marine oil pollution transport model, named MOTHY, designed to simulate the transport of oil in three dimensions. A hydrodynamic ocean model is linked to an oil spill model including current shear, vertical movements and fate of the oil. The use of a global atmospheric model for atmospheric forcing enables world-wide application of the model. This oil spill response system has been operational since February 1994. In case of marine pollution, Meteo-France send meteorological forecasts and oil spill drift forecasts to Cedre. In return, by its experimentations and interventions on actual pollution, Cedre is contributing to the improvement and validation of the model. New developments, exercises and training are conducted jointly. This paper summarizes the key features of MOTHY and presents some examples of model applications. (author)

Presentation and interpretation of field experiments of gaseous UF{sub 6} releases in the atmosphere

Energy Technology Data Exchange (ETDEWEB)

Crabol, B.; Boulaud, D.; Deville-Cavelin, G. [CEA/Inst. de Protection et de Surete Nucleaire, Dept. de Protection de l' Environnement et des Installations, Fontenay-aux-Roses (France); Geisse, C.; Iacona, L. [EURODIF/Production, Site de Tricastin, Pierrelatte Cedex (France)

1992-07-01

An experimental programme concerning the behaviour of UF{sub 6} released in gaseous phase in the atmosphere has been conducted in the years 1986-1989 by the French Atomic Energy Commission and EURODIF. Three field tests have been performed on the CEA/CESTA experimental site. These experiments permitted to get information about the kinetics of the hydrolysis reaction of the UF{sub 6}, the behaviour of the hydrolysis products in the atmosphere and the granulometry of the solid particles. (author)

[THREE CASES OF ACCIDENTAL AUTO-INJECTION OF ADRENALINE].

Science.gov (United States)

Yanagida, Noriyuki; Iikura, Katsuhito; Ogura, Kiyotake; Wang, Ling-jen; Asaumi, Tomoyuki; Sato, Sakura; Ebisawa, Motohiro

2015-12-01

Reports on accidental auto-injection of adrenaline are few. We encountered three cases of accidental injection of adrenaline. In this study, we have examined and reported the clinical courses and symptoms of our cases. CASE 1 involved a female physician in her 50s who had attended an explanatory meeting on auto-injection of adrenaline. She mistook EpiPen® to be the EpiPen trainer and accidentally injected herself with 0.3 mg EpiPen®. Her systolic/diastolic pressure peaked at 7 min to reach 144/78 mmHg and decreased to 120/77 mmHg at 14 min. Except for palpitation after 7 min, the only subjective symptom was local pain at the injection site. CASE 2 was noted in a 6-year-old boy. He accidentally pierced his right forefinger with 0.15 mg EpiPen®, and after 20 min, his right forefinger was swollen. The swelling improved 80 min after the accidental injection. CASE 3 was noted in a 4-year-old girl. She accidentally injected herself with 0.15 mg EpiPen®. Her systolic/diastolic pressure peaked at 23 min to reach 123/70 mmHg and decreased to 96/86 mmHg at 28 min. Severe adverse effects of accidental auto-injection of adrenaline were not observed in these three cases. Our findings suggest that while handling adrenaline auto-injectors, we should keep in mind the possibility of accidental injection.

Accidental hypothermia-an update

DEFF Research Database (Denmark)

Paal, Peter; Gordon, Les; Strapazzon, Giacomo

2016-01-01

BACKGROUND: This paper provides an up-to-date review of the management and outcome of accidental hypothermia patients with and without cardiac arrest. METHODS: The authors reviewed the relevant literature in their specialist field. Summaries were merged, discussed and approved to produce this nar......BACKGROUND: This paper provides an up-to-date review of the management and outcome of accidental hypothermia patients with and without cardiac arrest. METHODS: The authors reviewed the relevant literature in their specialist field. Summaries were merged, discussed and approved to produce...... this narrative review. RESULTS: The hospital use of minimally-invasive rewarming for non-arrested, otherwise healthy, patients with primary hypothermia and stable vital signs has the potential to substantially decrease morbidity and mortality for these patients. Extracorporeal life support (ECLS) has...... and post-resuscitation care. CONCLUSIONS: Based on new evidence, additional clinical experience and clearer management guidelines and documentation, the treatment of accidental hypothermia has been refined. ECLS has substantially improved survival and is the treatment of choice in the patient with unstable...

WRAITH, Internal and External Doses from Atmospheric Release of Isotopes

International Nuclear Information System (INIS)

1984-01-01

1 - Description of problem or function: WRAITH calculates the atmospheric transport of radioactive material to each of a number of downwind receptor points and the external and internal doses to a reference man at each of the receptor points. 2 - Method of solution: The movement of the released material through the atmosphere is calculated using a bivariate straight-line Gaussian distribution model with Pasquill values for standard deviations. The quantity of material in the released cloud is modified during its transit time to account for radioactive decay and daughter production. External doses due to exposure to the cloud can be calculated using a semi-infinite cloud approximation or a 'finite plume' three-dimensional point-kernel numerical integration technique. Internal doses due to acute inhalation are calculated using the ICRP Task Group Model and a four-segmented gastro- intestinal tract model. Translocation of the material between body compartments and retention in the body compartments are calculated using multiple exponential retention functions. Internal doses to each organ are calculated as sums of cross-organ doses with each target organ irradiated by radioactive material in a number of source organs. All doses are calculated in rads with separate values determined for high-LET and low-LET radiation. 3 - Restrictions on the complexity of the problem: - Doses to only three target organs (total body, red bone marrow, and the lungs) are considered and acute inhalation is the only pathway for material to enter the body. The dose response model is not valid for high-LET radiation other than alphas. The high-LET calculation ignores the contributions of neutrons, spontaneous fission fragments, and alpha recoil nuclei

Safety of atmospheric storage tanks during accidental explosions

OpenAIRE

Noret , E.; Prod'Homme , Gaëtan; Yalamas , Thierry; Reimeringer , Mathieu; Hanus , Jean-Luc; Duong , Duy-Hung

2012-01-01

International audience; The occurrence of a chain reaction from blast on atmospheric storage tanks in oil and chemical facilities is hard to predict. The current French practice for SEVESO facilities ignores projectiles and assumes a critical peak overpressure value observed from accident data. This method could lead to conservative or dangerous assessments. This study presents various simple mechanical models to facilitate quick effective assessment of risk analysis, the results of which are...

Selection of Hydrological Model for Waterborne Release

International Nuclear Information System (INIS)

Blanchard, A.

1999-01-01

Following a request from the States of South Carolina and Georgia, downstream radiological consequences from postulated accidental aqueous releases at the three Savannah River Site nonreactor nuclear facilities will be examined. This evaluation will aid in determining the potential impacts of liquid releases to downstream populations on the Savannah River. 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 accidents to be used in the future study

Compilation of documented computer codes applicable to environmental assessment of radioactivity releases

International Nuclear Information System (INIS)

Hoffman, F.O.; Miller, C.W.; Shaeffer, D.L.; Garten, C.T. Jr.; Shor, R.W.; Ensminger, J.T.

1977-04-01

The objective of this paper is to present a compilation of computer codes for the assessment of accidental or routine releases of radioactivity to the environment from nuclear power facilities. The capabilities of 83 computer codes in the areas of environmental transport and radiation dosimetry are summarized in tabular form. This preliminary analysis clearly indicates that the initial efforts in assessment methodology development have concentrated on atmospheric dispersion, external dosimetry, and internal dosimetry via inhalation. The incorporation of terrestrial and aquatic food chain pathways has been a more recent development and reflects the current requirements of environmental legislation and the needs of regulatory agencies. The characteristics of the conceptual models employed by these codes are reviewed. The appendixes include abstracts of the codes and indexes by author, key words, publication description, and title

Mesoscale atmospheric modeling of the July 12, 1992 tritium release from the Savannah River Site

International Nuclear Information System (INIS)

Fast, J.D.; O'Steen, B.L.; Addis, R.P.

1992-01-01

In August of 1991, the Environmental Transport Group (ETG) began the development of an advanced Emergency Response (ER) system based upon the Colorado State University Regional Atmospheric Modeling System (RAMS). This model simulates the three-dimensional, time-dependent, flow field and thermodynamic structure of the planetary boundary layer (PBL). A companion Lagrangian Particle Dispersion Model (LPDM) simulates contaminant transport based on the flow and turbulence fields generated by RAMS. This paper describes the performance of the advanced ER system in predicting transport and diffusion near the SRS when compared to meteorological and sampling data taken during the July 12, 1992 tritium release. Since PUFF/PLUME and 2DPUF are two Weather INformation and Display (WIND) System atmospheric models that were used to predict the transport and diffusion of the plume at the time of the release, the results from the advanced ER system are also compared to those produced by PUFF/PLUME and 2DPUF

Release of radionuclides following severe accident in interim storage facility. Source term determination

International Nuclear Information System (INIS)

Morandi, S.; Mariani, M.; Giacobbo, F.; Covini, R.

2006-01-01

Among the severe accidents that can cause the release of radionuclides from an interim storage facility, with a consequent relevant radiological impact on the population, there is the impact of an aircraft on the facility. In this work, a safety assessment analysis for the case of an aircraft crash into an interim storage facility is tackled. To this aim a methodology, based upon DOE, IAEA and NUREG standard procedures and upon conservative yet realistic hypothesis, has been developed in order to evaluate the total radioactivity, source term, released to the biosphere in consequence of the impact, without recurring to the use of complicated numerical codes. The procedure consists in the identification of the accidental scenarios, in the evaluation of the consequent damage to the building structures and to the waste packages and in the determination of the total release of radionuclides through the building-atmosphere interface. The methodology here developed has been applied to the case of an aircraft crash into an interim storage facility currently under design. Results show that in case of perforation followed by a fire incident the total released activity would be greater of some orders of magnitude with respect to the case of mere perforation. (author)

Model description. NUDOS: A computer program for assessing the consequences of airborne releases of radionuclides

International Nuclear Information System (INIS)

Poley, A.D.

1996-02-01

NUDOS is a computer program that can be used to evaluate the consequences of airborne releases of radioactive material. The consequences which can be evaluated are individual dose and associated radiological risk, collective dose and the contamination of land. The code is capable of dealing with both continuous (routine) and accidental releases. For accidental releases both deterministic and probabilistic calculations can be performed, and the impact and effectiveness of emergency actions can be evaluated. This report contains a description of the models contained in NUDOS92 and the recommended values for the input parameters of these models. Additionally, a short overview is given of the future model improvement planned for the next NUDOS-version. (orig.)

Determination of radiation doses caused by release into the atmosphere by nuclear power plants, based on measurement of emission and immission

International Nuclear Information System (INIS)

Ekler, B.; Deme, S.

2006-01-01

The radiation impact of nuclear facilities, and the nuclear power plants as well, can be determined by using two methods. The first one calculates the dose of critical group of population based on the release, meteorological and hydrological parameters. The second method gives an estimate of the additional dose caused by the nuclear facility from the radiological measurements in the environment. This article compares this two methods for the release in the atmosphere, and gives an estimate of the relative error. The comparison can be applied for cases when the atmospheric pollution is released from a point type source, so for the conventional power plants as well. (author)

Development of an advanced atmospheric/transport model for emergency response purposes

International Nuclear Information System (INIS)

Fast, J.D.; O'Steen, B.L.; Addis, R.P.

1991-01-01

Atmospheric transport and diffusion models have been developed for real-time calculations of the location and concentration of toxic or radioactive materials during an accidental release at the Savannah River Site (SRS). These models are based Gaussian distributions and have been incorporated into an automated menu-driven program called the WIND (Weather INformation and Display) system. The WIND system atmospheric models employ certain assumptions that allow the computations of the ground-level concentration of toxic or radioactive materials to be made quickly. Gaussian models, such as PF/PL and 2DPUF, suffer from serious limitations including the inability to represent recirculation of pollutants in complex terrain, the use of one stability class at a given time to represent turbulent mixing over heterogeneous terrain, and the use of a wind field computed at only one height in the atmosphere. These limitations arise because the fundamental conservation relations of the atmosphere have been grossly simplified. Three-dimensional coupled atmospheric-dispersion models are not limited by the over-simplifications of the Gaussian assumption and have been used in the past to predict the transport of pollutants in a variety of atmospheric circulations. The disadvantage of these models is that they require large amounts of computational time; however, technology has progressed enough so that real-time simulations of dispersion may be made. These complex models can be run in an operational mode so that routine forecasts of the wind field and particulate concentration can be made

Reconstruction of Atmospheric Tracer Releases with Optimal Resolution Features: Concentration Data Assimilation

Science.gov (United States)

Singh, Sarvesh Kumar; Turbelin, Gregory; Issartel, Jean-Pierre; Kumar, Pramod; Feiz, Amir Ali

2015-04-01

The fast growing urbanization, industrialization and military developments increase the risk towards the human environment and ecology. This is realized in several past mortality incidents, for instance, Chernobyl nuclear explosion (Ukraine), Bhopal gas leak (India), Fukushima-Daichi radionuclide release (Japan), etc. To reduce the threat and exposure to the hazardous contaminants, a fast and preliminary identification of unknown releases is required by the responsible authorities for the emergency preparedness and air quality analysis. Often, an early detection of such contaminants is pursued by a distributed sensor network. However, identifying the origin and strength of unknown releases following the sensor reported concentrations is a challenging task. This requires an optimal strategy to integrate the measured concentrations with the predictions given by the atmospheric dispersion models. This is an inverse problem. The measured concentrations are insufficient and atmospheric dispersion models suffer from inaccuracy due to the lack of process understanding, turbulence uncertainties, etc. These lead to a loss of information in the reconstruction process and thus, affect the resolution, stability and uniqueness of the retrieved source. An additional well known issue is the numerical artifact arisen at the measurement locations due to the strong concentration gradient and dissipative nature of the concentration. Thus, assimilation techniques are desired which can lead to an optimal retrieval of the unknown releases. In general, this is facilitated within the Bayesian inference and optimization framework with a suitable choice of a priori information, regularization constraints, measurement and background error statistics. An inversion technique is introduced here for an optimal reconstruction of unknown releases using limited concentration measurements. This is based on adjoint representation of the source-receptor relationship and utilization of a weight

Atmospheric dispersion and inverse modelling for the reconstruction of accidental sources of pollutants

International Nuclear Information System (INIS)

Winiarek, Victor

2014-01-01

Uncontrolled releases of pollutant in the atmosphere may be the consequence of various situations: accidents, for instance leaks or explosions in an industrial plant, or terrorist attacks such as biological bombs, especially in urban areas. In the event of such situations, authorities' objectives are various: predict the contaminated zones to apply first countermeasures such as evacuation of concerned population; determine the source location; assess the long-term polluted areas, for instance by deposition of persistent pollutants in the soil. To achieve these objectives, numerical models can be used to model the atmospheric dispersion of pollutants. We will first present the different processes that govern the transport of pollutants in the atmosphere, then the different numerical models that are commonly used in this context. The choice between these models mainly depends of the scale and the details one seeks to take into account. We will then present several inverse modeling methods to estimate the emission as well as statistical methods to estimate prior errors, to which the inversion is very sensitive. Several case studies are presented, using synthetic data as well as real data such as the estimation of source terms from the Fukushima accident in March 2011. From our results, we estimate the Cesium-137 emission to be between 12 and 19 PBq with a standard deviation between 15 and 65% and the Iodine-131 emission to be between 190 and 380 PBq with a standard deviation between 5 and 10%. Concerning the localization of an unknown source of pollutant, two strategies can be considered. On one hand parametric methods use a limited number of parameters to characterize the source term to be reconstructed. To do so, strong assumptions are made on the nature of the source. The inverse problem is hence to estimate these parameters. On the other hand nonparametric methods attempt to reconstruct a full emission field. Several parametric and nonparametric methods are

Atmosphere dependence of fission products release: The Vercors 4 and 5 experiments

Energy Technology Data Exchange (ETDEWEB)

Andre, B.; Ducros, G.; Tourasse, M.; Ferroud-Plattet, M.P. [CEA Centre d`Etudes de Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique; Boulaud, D. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

1996-12-31

Because of the severe consequences, in terms of radiological and biological effects, of a nuclear accident, the international reactor safety authorities initiated, 25 years ago, numerous experimental programs in order to improve the understanding and the prediction of these situations. In France, the Nuclear Protection and Safety Institute (IPSN) in collaboration with Electricite de France (EDF) co-fund the Heva-Vercors program, since 1983. The experiments are conducted in a shielded hot cell of the LAMA facility at Grenoble. The test specimen is a fuel rod section taken from a power reactor operated by EDF and includes three irradiated pellets in their original cladding. The fuel sample is re-irradiated at low power in the Siloe experimental reactor for seven days in order to recreate the short-lived fission products without inducing any in-pile release. Since the experimental sequence is performed less than 40 hours after the end of the reirradiation, direct measurement of radioactive fission products release is possible using gamma spectrometry. The measurements performed during the tests are essentially aimed at characterising the release kinetics and the total release of fission products and structural materials as a function of fuel temperature and oxidising/reducing conditions of the environment. The four last tests (Vercors 3 to Vercors 6), performed at 2600 K, allowed to measure the kinetic of high and low volatile species release, as well as the total released fraction of non volatile species and the transuranic elements. This paper is devoted to the comparison of the Vercors 4 and Vercors 5 tests. The first one has been conducted up to 2600 K under reducing conditions (hydrogen fluid), after an oxidising period at 1670 K. The second one was performed in a pure steam atmosphere after several plateaus at intermediate temperatures in oxidising conditions. The total release of volatile (Sb, Te, I, Cs) is not significantly modified and a higher release of Mo

Atmospheric surveillance self-propelling device

International Nuclear Information System (INIS)

Cartoux, Gerard.

1980-11-01

The atmospheric surveillance self-propelling device of the Saclay Nuclear Research Center can, by its conception (autonomy, rapid put into service, multiplicity of sampling and measurements), be used for all kind of measuring campains: pollution radioactive or not, routine or accidental situation, technical and logistic support and as a coordination or investigation vehicle [fr

Uncertainty analysis in an accidental situation. Radionuclide transfer in environment and assessment of human exposure by food

International Nuclear Information System (INIS)

Sy, Mouhamadou Moustapha

2016-01-01

Major nuclear accidents of Chernobyl (April, 1986) and Fukushima (March, 2011) have led to a huge environmental contamination with important amounts of radionuclides released in the atmosphere. Risk assessment, in case of nuclear emergency, is confronted to uncertainties on the transfer of radioactive substances in terrestrial ecosystems and to human population through the food chain, which could affect the reliability of decisions. The extent of the repercussions of Chernobyl and Fukushima accidents highlighted the difficulty of managing the consequences of such disasters and specifically to accommodate the different sources of uncertainty within decision-making processes. The objective of this research project is to develop a methodology to take into account uncertainties within environmental and food risk assessment models in order to improve decision support tools used for accidental situations. In this regard, different hierarchical Bayesian models aiming at capturing, within a unique modelling framework, uncertainty and variability about radioecological parameters of great important for accidental situation (dry and wet interception fractions and weathering loss parameter) were developed. Models parameters were estimated by Bayesian inference applied on databases obtained by an extended literature review. The impact on the risk assessment models of uncertainty and variability about these radioecological parameters was then assessed by stochastic simulations and sensitivity analyses applied on two case-studies: a hypothetical accident simulating a standardized deposition of radionuclides and the accident of Fukushima nuclear power plant. The works developed in this project contribute to enhance knowledge on key processes governing environmental transfer of radionuclides and to improve the parameterization of the radioecological risk assessment models with respect to the research lines outlined by the scientific community in radioecology. (author)

MISTRAL V1.1.1: assessing doses from atmospheric releases in normal and off-normal conditions

International Nuclear Information System (INIS)

David Kerouanton; Patrick Devin; Malvina Rennesson

2006-01-01

Protecting the environment and the public from radioactive and chemical hazards has always been a top priority for all companies operating in the nuclear domain. In this scope, SGN provides all the services the nuclear industry needs in environmental studies especially in relation to the impact assessment in normal operating conditions and risk assessment in off-normal conditions. In order to quantify dose impact on members of the public due to atmospheric releases, COGEMA and SGN developed MISTRAL V1.1.1 code. Dose impact depends strongly on dispersion of radionuclides in atmosphere. The main parameters involved in dispersion characterization are wind velocity and direction, rain, diffusion conditions, coordinates of the point of observation and stack elevation. MISTRAL code implements DOURY and PASQUILL Gaussian plume models which are widely used in the scientific community. These models, applicable for distances of transfer ranging from 100 m up to 30 km, are used to calculate atmospheric concentration and deposit at different distances from the point of release. MISTRAL allows the use of different dose regulations or dose coefficient databases such as: - ICRP30 and ICPR71 for internal doses (inhalation, ingestion) - Despres/Kocher database or US-EPA Federal Guidance no.12 (ICPR72 for noble gases) for external exposure (from plume or ground). The initial instant of the release can be considered as the origin of time or a date format can be specified (could be useful in a crisis context). While the context is specified, the user define the meteorological conditions of the release. In normal operating mode (routine releases), the user gives the annual meteorological scheme. The data can be recorded in the MISTRAL meteorological database. In off-normal conditions mode, MISTRAL V1.1 allows the use of successive release stages for which the user gives the duration, the meteorological conditions, that is to say stability class, wind speed and direction and rainfall

Influence of stability classification on atmospheric diffusion calculations for elevated releases over a terrain of major roughness

International Nuclear Information System (INIS)

Hu Erbang

1988-01-01

A series (22) of atmospheric tracer experiments with 100m release height have been performed at the kernforschungszentrum karlsruhe (KfK) of West Germany over a terrain of major roughness (Z 0 = 1.5 m). The concentration data of the tracers are statistically analysed in which 5 methods of stability classification are used. The results show that the normalized diffusion factors predicted by Gaussian plume dispersion model is in good agreement with the observed ones for elevated releases over a terrain of major roughness. Differnent sets of dispersion parameters could be obtained for the same series of atmospheric tracer experiments if different methods of classification are applied. The same method of stability classification should be used for the application of these dispersion parameters to evaluate the environment impact

Hydrogen Storage and Release Properties of Transition Metal-Added Magnesium Hydride Alloy Fabricated by Grinding in a Hydrogen Atmosphere

Energy Technology Data Exchange (ETDEWEB)

Kwon, Sung Nam; Song, Myoung Youp [Chonbuk National University, Jeonju (Korea, Republic of); Park, Hye Ryoung [Chonnam National University, Gwangju (Korea, Republic of)

2016-07-15

90 wt% MgH{sub 2}+5 wt% Ni+2.5 wt% Fe+2.5 wt% Ti (called MgH{sub 2}+Ni+Fe+Ti), a hydrogen storage and release material, was fabricated by grinding in a hydrogen atmosphere, and then its quantities of stored and released hydrogen as a function of time were examined. A nanocrystalline MgH{sub 2}+Ni+Fe+Ti specimen was made by grinding in a hydrogen atmosphere and subsequent hydrogen storage-release cycling. The crystallite size of Mg and the strain of the Mg crystallite after ten hydrogen storage-release cycles, which were obtained using the Williamson-Hall method, were 38.6 (±1.4) nm and 0.025 (±0.0081) %, respectively. The MgH{sub 2}+Ni+Fe+Ti sample after the process of grinding in a hydrogen atmosphere was highly reactive with hydrogen. The sample exhibited an available storage capacity of hydrogen (the amount of hydrogen stored during 60 minutes) of about 5.7 wt%. At the first cycle, the MgH2+Ni+Fe+Ti sample stored hydrogen of 5.53 wt% in 5 minutes, 5.66 wt% in 10 minutes and 5.73 wt% in 60 minutes at 573 K and 12 bar of hydrogen. The MgH{sub 2}+Ni+Fe+Ti after activation released hydrogen of 0.56 wt% in 5 minutes, 1.26 wt% in 10 minutes, 2.64 wt% in 20 minutes, 3.82 wt% in 30 minutes, and 5.03 wt% in 60 minutes.

Accidental childhood poisoning in Benin City: Still a problem ...

African Journals Online (AJOL)

Accidental poisoning (AP) is a leading cause of ill – health and deaths among. Nigerian children. Reports on AP are infrequent in Nigeria. This retrospective descriptive study examined the prevailing pattern of accidental childhood poisoning in Benin City. Accidental poisonings were identified in 226 (3.3%) of the cases ...

ACUTRI a computer code for assessing doses to the general public due to acute tritium releases

CERN Document Server

Yokoyama, S; Noguchi, H; Ryufuku, S; Sasaki, T

2002-01-01

Tritium, which is used as a fuel of a D-T burning fusion reactor, is the most important radionuclide for the safety assessment of a nuclear fusion experimental reactor such as ITER. Thus, a computer code, ACUTRI, which calculates the radiological impact of tritium released accidentally to the atmosphere, has been developed, aiming to be of use in a discussion of licensing of a fusion experimental reactor and an environmental safety evaluation method in Japan. ACUTRI calculates an individual tritium dose based on transfer models specific to tritium in the environment and ICRP dose models. In this calculation it is also possible to analyze statistically on meteorology in the same way as a conventional dose assessment method according to the meteorological guide of the Nuclear Safety Commission of Japan. A Gaussian plume model is used for calculating the atmospheric dispersion of tritium gas (HT) and/or tritiated water (HTO). The environmental pathway model in ACUTRI considers the following internal exposures: i...

Impact of atmospheric release in stable night meteorological conditions; can emergency models predict dispersion

Energy Technology Data Exchange (ETDEWEB)

Connan, O.; Hebert, D.; Solier, L.; Voiseux, C.; Lamotte, M.; Laguionie, P.; Maro, D.; Thomas, L. [IRSN/PRP-ENV/SERIS/LRC (France)

2014-07-01

Atmospheric dispersion of pollutant or radionuclides in stratified meteorological condition, i.e. especially when weather conditions are very stable, mainly at night, is still poorly understood and not well apprehended by the operational atmospheric dispersion models. However, correctly predicting the dispersion of a radioactive plume, and estimating the radiological consequences for the population, following an unplanned atmospheric release of radionuclides are crucial steps in an emergency response. To better understand dispersion in these special weather conditions, IRSN performed a series of 22 air sampling campaigns between 2010 and 2013 in the vicinity of the La Hague nuclear reprocessing plant (AREVA - NC, France), at distances between 200 m and 3000 m from the facility. Krypton-85 ({sup 85}Kr), a b-and g-emitting radionuclide, released during the reprocessing of spent nuclear fuel was used as a non-reactive tracer of radioactive plumes. Experimental campaigns were realized in stability class stable or very stable (E or F according to Pasquill classification) 18 times, and in neutral conditions (D according to Pasquill classification) 4 times. During each campaign, Krypton-85 real time measurement were made to find the plume around the plant, and then integrated samples (30 min) were collected in bag perpendicularly to the assumed wind direction axis. After measurement by gamma spectrometry, we have, when it was possible, estimate the point of impact and the width of the plume. The objective was to estimate the horizontal dispersion (width) of the plume at ground level in function of the distance and be able to calculate atmospheric transfer coefficients. In a second step, objective was to conclude on the use of common model and on their uncertainties. The results will be presented in terms of impact on the near-field. They will be compared with data obtained in previous years in neutral atmospheric conditions, and finally the results will be confronted with

Relocation impacts of a major release from SRTC

International Nuclear Information System (INIS)

Blanchard, A.; Thompson, E.A.; Thompson, J.M.

1999-01-01

The relocation impacts of an accidental release, scenario 1-RD-3 , are evaluated for the Savannah River Technology Center. The extent of the area potentially contaminated to a level that would result in doses exceeding the relocation protective action guide(PAG)is calculated. The maximum calculated distance downwind from the accident at which the relocation PAG is exceeded is also determined. The consequences of the particulate portion of the release are evaluated using the HOTSPOT model and an EXCEL spreadsheet. The consequences of the tritium release are evaluated using UFOTRI

Tension Pneumothorax following an Accidental Kerosene Poisoning ...

African Journals Online (AJOL)

Tension pneumothorax is a rare complication following an accidental kerosene poisoning. In such situation, a bed-side needle thoracocentesis is performed because of its potential of becoming fatal; hence its clinical importance. A case of 15 month old boy with tension pneumothorax following accidental kerosene ...

Environmental processes and parameters influencing the consequences of an accidental release of radioactivity weather and season

International Nuclear Information System (INIS)

Boeri, G.C.

1989-01-01

Seasonal, climatic and meteorological conditions may have a substantial influence on the physical factors involved in transport and deposition of airborne contaminants, and on the transfer and accumulation of radionuclides in terrestrial and aquatic ecosystems. As well, these environmental conditions can also have a significant influence on living habits and practices, and thus on potential radiological and economical impacts. Moreover, these conditions may affect the features and the impact of countermeasures which are adopted for the protection of the public in case of an accidental release. During a Special Session that the Committee of Radiation Protection and Public Health (CRPPH) held on the 1st-2nd September 1986 to review the radiological aspects of the Chernobyl nuclear accident, it was agreed that a consultant should prepare a report reviewing different accident consequences in a radiation protection and public health perspective, and identify the influence of such parameters as time of the year, weather and environmental conditions on the overall impact and the determination of appropriate countermeasures. A Consultant Report on this issue was prepared, by Dr. G. Boeri, and submitted to the CRPPH for review and consideration at its meeting of 22nd-24th November 1987. The CRPPH subsequently agreed that the Consultant Report should be revised and completed, taking into account comments and suggestions sent to the Secretariat and focussing especially on the effect of seasonal and weather conditions in terms of their influence on the radiological impact of an accident and on the emergency countermeasures to be taken. It was decided that the Consultant Report should be developed into an Overview Paper for a workshop on this issue to be organised by the NEA in 1988

Recent developments in the atmospheric dispersion models to be used for regulatory purposes and in risk evaluation

International Nuclear Information System (INIS)

Graziani, G.

1996-01-01

Climatological models and those most widely used for risk evaluation are generally based on the classification of atmospheric turbulence according to the Pasquill-Gifford categories, and use the Gaussian solution of the dispersion equation. One of their main limitations is that they deal only with continuous or instantaneous (puff) emission. Furthermore, a discretisation in the definition of atmospheric turbulence is performed according to the Pasquill-Gifford categories. This can generate uncertainties, since partial information on the state of the atmosphere at the time of emission can lead to the choice of one category rather than another and consequently to select wrong dispersion parameters. Some of these limits, such as the assumption of flat or slowly varying terrain, and the choice of constant atmospheric conditions during the duration of the release, are intrinsic to the schematization required by these models. Other limitations, such as the finite duration of the emissions and the continuous variation of the physical quantities describing the effect of turbulence on dispersion parameters, can be overcome. This paper describes the possible improvements which can be made in the dispersion models used in regulating emissions in the atmosphere and to calculate the associated risk. In particular the turbulence is based on the definition of some physical quantities varying with continuity which can be easily deduced from simple observations at the meteorological station at release site. It then analyses the application of this approach to a simple dispersion model, which can take into account the finite and non-zero durations of accidental emissions

The legacy of Cf-252 operations at Savannah River Technology Center: Continuous releases of radioiodine to the atmosphere

International Nuclear Information System (INIS)

Kantelo, M.V.; Crandall, B.S.

1992-01-01

The iodine isotopes I-132, 1-133, I-134, and I-135, which have half-lives ranging from 53 minutes to 21 hours, are measured in the atmospheric effluent from the Savannah River Technology Center (SRTC) at the Savannah River Site (SRS) near Aiken, South Carolina. SRS is operated by Westinghouse Savannah River Company for the US Department of Energy (DOE). The isotopes' release rates range from 10 to 300 microcuries per week compared to the rate. The resulting annual dose from all iodine isotopes is minor; it comprises 0.01 percent of the total offsite dose due to atmospheric releases from SRS in 1990. Circumstantial evidence indicates the radioiodine originates from traces of unencapsulated Cf-252. The determination that spontaneous fission of Cf-252 is the source of the radioiodine has several ramifications. Radioactive fission-product isotopes of the noble gas elements krypton and xenon must also be released. Noble gases are more volatile and mobile than iodine. Also, the released iodine isotopes decay to xenon isotopes. The noble gases decay to non-gaseous elements that are transported along with radioiodine to the terrestrial environment by deposition from the SRTC plume. Only Sr-89 is believed to accumulate sufficiently in the environment to approach detectable levels. Given similar conditions in earlier years, releases of short-lived radioiodine have occurred undetected in routine monitoring since the early 1970s. Release rates 20 years ago would have been 200 times greater than current release rates. This report documents preliminary experiments conducted by SRTC and Environmental Monitoring Section (EMS) scientists. The release process and the environmental impact of fission products from Cf-252 should be thoroughly researched

Accidental Poisoning with Otapiapia: a Local Organophasphate ...

African Journals Online (AJOL)

Children are prone to accidental poisoning. We report this fatal organophosphate poisoning of a 3-year-old Nigerian boy following accidental ingestion of a homemade cocktail of kerosene and 'Otapiapia': a local rodenticide to highlight the dangers inherent in un-regulated production, home use and storage of this ...

Factors affecting release of ethanol vapour in active modified atmosphere packaging systems for horticultural products

Directory of Open Access Journals (Sweden)

Weerawate Utto

2014-04-01

Full Text Available The active modified atmosphere packaging (active MAP system , which provides interactive postharvest control , using ethanol vapour controlled release, is one of the current interests in the development of active packaging for horticultural products. A number of published research work have discussed the relationship between the effectiveness of ethanol vapour and its concentration in the package headspace, including its effect on postharvest decay and physiological controls. This is of importance because a controlled release system should release and maintain ethanol vapour at effective concentrations during the desired storage period. A balance among the mass transfer processes of ethanol vapour in the package results in ethanol vapour accumulation in the package headspace. Key factors affecting these processes include ethanol loading, packaging material, packaged product and storage environment (temperature and relative h umidity. This article reviews their influences and discusses future work required to better understand their influences on ethanol vapour release and accumulations in active MAP.

Application of PC-CREAM in the Netherlands. Dose impact due to atmospheric releases

International Nuclear Information System (INIS)

Eleveld, H.; Twenhoefel, C.J.W.; Pruppers, M.J.M.

1999-01-01

A methodology to assess the radiological impact of routine releases, CREAM, was developed at the National Radiological Protection Board (UK). The software implementation of that methodology to the PC platform, PC-CREAM, has been compared to the Dutch regulation guidelines. The results of the PC-CREAM software and previous RIVM studies are compared for two specific reference situations and eleven naturally occurring radionuclides. The methodology in the submodels in PC-CREAM is also studied and compared to the Dutch regulation guidelines. The assessment of the radiological impact for atmospheric releases using PC-CREAM showed good agreement with the results obtained in previous RIVM studies. Some changes and additions in the methodology are proposed to be able to calculate the radiological impact using PC-CREAM in other relevant reference situations

ACUTRI: a computer code for assessing doses to the general public due to acute tritium releases

Energy Technology Data Exchange (ETDEWEB)

Yokoyama, Sumi; Noguchi, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ryufuku, Susumu; Sasaki, Toshihisa; Kurosawa, Naohiro [Visible Information Center, Inc., Tokai, Ibaraki (Japan)

2002-11-01

Tritium, which is used as a fuel of a D-T burning fusion reactor, is the most important radionuclide for the safety assessment of a nuclear fusion experimental reactor such as ITER. Thus, a computer code, ACUTRI, which calculates the radiological impact of tritium released accidentally to the atmosphere, has been developed, aiming to be of use in a discussion of licensing of a fusion experimental reactor and an environmental safety evaluation method in Japan. ACUTRI calculates an individual tritium dose based on transfer models specific to tritium in the environment and ICRP dose models. In this calculation it is also possible to analyze statistically on meteorology in the same way as a conventional dose assessment method according to the meteorological guide of the Nuclear Safety Commission of Japan. A Gaussian plume model is used for calculating the atmospheric dispersion of tritium gas (HT) and/or tritiated water (HTO). The environmental pathway model in ACUTRI considers the following internal exposures: inhalation from a primary plume (HT and/or HTO) released from the facilities and inhalation from a secondary plume (HTO) reemitted from the ground following deposition of HT and HTO. This report describes an outline of the ACUTRI code, a user guide and the results of test calculation. (author)

Characterisation of childhood and adolescence accidental fatalities ...

African Journals Online (AJOL)

Background: Accidental death in childhood and adolescence is posing a public health problem in Nigeria, as most of these deaths were not caused by the victims. There is need to research into the pattern and circumstances surrounding the death. Aim: To characterise and study accidental deaths in childhood and ...

Xenon-133 and caesium-137 releases into the atmosphere from the Fukushima Dai-ichi nuclear power plant: determination of the source term, atmospheric dispersion, and deposition

Directory of Open Access Journals (Sweden)

A. Stohl

2012-03-01

Full Text Available On 11 March 2011, an earthquake occurred about 130 km off the Pacific coast of Japan's main island Honshu, followed by a large tsunami. The resulting loss of electric power at the Fukushima Dai-ichi nuclear power plant developed into a disaster causing massive release of radioactivity into the atmosphere. In this study, we determine the emissions into the atmosphere of two isotopes, the noble gas xenon-133 (¹³³Xe and the aerosol-bound caesium-137 (¹³⁷Cs, which have very different release characteristics as well as behavior in the atmosphere. To determine radionuclide emissions as a function of height and time until 20 April, we made a first guess of release rates based on fuel inventories and documented accident events at the site. This first guess was subsequently improved by inverse modeling, which combined it with the results of an atmospheric transport model, FLEXPART, and measurement data from several dozen stations in Japan, North America and other regions. We used both atmospheric activity concentration measurements as well as, for ¹³⁷Cs, measurements of bulk deposition. Regarding ¹³³Xe, we find a total release of 15.3 (uncertainty range 12.2–18.3 EBq, which is more than twice as high as the total release from Chernobyl and likely the largest radioactive noble gas release in history. The entire noble gas inventory of reactor units 1–3 was set free into the atmosphere between 11 and 15 March 2011. In fact, our release estimate is higher than the entire estimated ¹³³Xe inventory of the Fukushima Dai-ichi nuclear power plant, which we explain with the decay of iodine-133 (half-life of 20.8 h into ¹³³Xe. There is strong evidence that the ¹³³Xe release started before the first active venting was made, possibly indicating structural damage to reactor components and/or leaks due to overpressure which would have allowed early release of noble gases. For ¹³⁷

Xenon-133 and caesium-137 releases into the atmosphere from the Fukushima Dai-ichi nuclear power plant. Determination of the source term, atmospheric dispersion, and deposition

International Nuclear Information System (INIS)

Stohl, A.; Burkhart, J.F.; Eckhardt, S.; Seibert, P.; Arnold, D.; Technical Univ. of Catalonia, Barcelona; Tapia, C.; Vargas, A.; Yasunari, T.J.

2012-01-01

On 11 March 2011, an earthquake occurred about 130 km off the Pacific coast of Japan's main island Honshu, followed by a large tsunami. The resulting loss of electric power at the Fukushima Dai-ichi nuclear power plant developed into a disaster causing massive release of radioactivity into the atmosphere. In this study, we determine the emissions into the atmosphere of two isotopes, the noble gas xenon-133 ("1"3"3Xe) and the aerosol-bound caesium-137 ("1"3"7Cs), which have very different release characteristics as well as behavior in the atmosphere. To determine radionuclide emissions as a function of height and time until 20 April, we made a first guess of release rates based on fuel inventories and documented accident events at the site. This first guess was subsequently improved by inverse modeling, which combined it with the results of an atmospheric transport model, FLEXPART, and measurement data from several dozen stations in Japan, North America and other regions. We used both atmospheric activity concentration measurements as well as, for "1"3"7Cs, measurements of bulk deposition. Regarding "1"3"3Xe, we find a total release of 15.3 (uncertainty range 12.2-18.3) EBq, which is more than twice as high as the total release from Chernobyl and likely the largest radioactive noble gas release in history. The entire noble gas inventory of reactor units 1-3 was set free into the atmosphere between 11 and 15 March 2011. In fact, our release estimate is higher than the entire estimated "1"3"3Xe inventory of the Fukushima Dai-ichi nuclear power plant, which we explain with the decay of iodine-133 (half-life of 20.8 h) into "1"3"3Xe. There is strong evidence that the "1"3"3Xe release started before the first active venting was made, possibly indicating structural damage to reactor components and/or leaks due to overpressure which would have allowed early release of noble gases. For "1"3"7Cs, the inversion results give a total emission of 36.6 (20.1-53.1) PBq, or about

Xenon-133 and caesium-137 releases into the atmosphere from the Fukushima Dai-ichi nuclear power plant. Determination of the source term, atmospheric dispersion, and deposition

Energy Technology Data Exchange (ETDEWEB)

Stohl, A.; Burkhart, J.F.; Eckhardt, S. [NILU - Norwegian Institute for Air Research, Kjeller (Norway); Seibert, P. [Univ. of Natural Resources and Life Sciences, Vienna (Austria). Inst. of Meteorology; Wotawa, G. [Central Institute for Meteorology and Geodynamics, Vienna (Austria); Arnold, D. [Univ. of Natural Resources and Life Sciences, Vienna (Austria). Inst. of Meteorology; Technical Univ. of Catalonia, Barcelona (Spain). Inst. of Energy Technologies; Tapia, C. [Technical Univ. of Catalonia, Barcelona (Spain). Dept. of Physics and Nucelar Engineering; Vargas, A. [Technical Univ. of Catalonia, Barcelona (Spain). Inst. of Energy Technologies; Yasunari, T.J. [Univs. Space Research Association, Columbia, MD (United States). Goddard Earth Sciences and Technology and Research

2012-07-01

On 11 March 2011, an earthquake occurred about 130 km off the Pacific coast of Japan's main island Honshu, followed by a large tsunami. The resulting loss of electric power at the Fukushima Dai-ichi nuclear power plant developed into a disaster causing massive release of radioactivity into the atmosphere. In this study, we determine the emissions into the atmosphere of two isotopes, the noble gas xenon-133 ({sup 133}Xe) and the aerosol-bound caesium-137 ({sup 137}Cs), which have very different release characteristics as well as behavior in the atmosphere. To determine radionuclide emissions as a function of height and time until 20 April, we made a first guess of release rates based on fuel inventories and documented accident events at the site. This first guess was subsequently improved by inverse modeling, which combined it with the results of an atmospheric transport model, FLEXPART, and measurement data from several dozen stations in Japan, North America and other regions. We used both atmospheric activity concentration measurements as well as, for {sup 137}Cs, measurements of bulk deposition. Regarding {sup 133}Xe, we find a total release of 15.3 (uncertainty range 12.2-18.3) EBq, which is more than twice as high as the total release from Chernobyl and likely the largest radioactive noble gas release in history. The entire noble gas inventory of reactor units 1-3 was set free into the atmosphere between 11 and 15 March 2011. In fact, our release estimate is higher than the entire estimated {sup 133}Xe inventory of the Fukushima Dai-ichi nuclear power plant, which we explain with the decay of iodine-133 (half-life of 20.8 h) into {sup 133}Xe. There is strong evidence that the {sup 133}Xe release started before the first active venting was made, possibly indicating structural damage to reactor components and/or leaks due to overpressure which would have allowed early release of noble gases. For {sup 137}Cs, the inversion results give a total emission of 36

About Assessment Criteria of Driver's Accidental Abilities

Science.gov (United States)

Lobanova, Yuliya I.; Glushko, Kirill V.

2016-01-01

The article points at the importance of studying the human factor as a cause of accidents of drivers, especially in loosely structured traffic situations. The description of the experiment on the measurement of driver's accidental abilities is given. Under accidental ability is meant the capability to ensure the security of driving as a behavior…

An interactive computer model for the assessment of continuous release atmospheric transfers

International Nuclear Information System (INIS)

Pages, P.; Rancillac, F.

1983-05-01

The purpose of the model is to assess air concentrations and soil deposits following a continuous release of gaseous effluents. This is usually part of the problem of assessing the consequences of normal operation of a plant. The atmospheric dispersion model used is the gaussian plume model according to DOURY's scheme. Ground reflexion, the presence of an inversion layer and removal processes (by dry or wet deposition and radioactive decay type) are taken into account. Air and ground concentrations are computed around the release point according to an arbitrary grid with spatial coordinates and accounting for annual frequencies of meteorological conditions. The methodology is presented in detail and assumptions are clearly stated. A conversational structured computer program has been set up in APL which allows to get results easily and to test their sensitivity to various assumptions concerning both input data and model parameters. As an example an application of the model with real data and results is given [fr

Assessment of particle size distribution in CO 2 accidental releases

NARCIS (Netherlands)

Hulsbosch-Dam, C.E.C.; Spruijt, M.P.N.; Necci, A.; Cozzani, V.

2012-01-01

A model was developed to calculate the particle size distribution following the release of pressurised supercritical CO 2. The model combines several sub-models for the different stages of jet break-up and specifically addresses the possible formation of solid particles, which is important for CO 2

Specialists' meeting on fission product release and transport in gas-cooled reactors. Summary report

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-07-01

The purpose of the Meeting on Fission Product Release and Transport in Gas-Cooled Reactors was to compare and discuss experimental and theoretical results of fission product behaviour in gas-cooled reactors under normal and accidental conditions and to give direction for future development. The technical part of the meeting covered operational experience and laboratory research, activity release, and behaviour of released activity.

Specialists' meeting on fission product release and transport in gas-cooled reactors. Summary report

International Nuclear Information System (INIS)

1985-01-01

The purpose of the Meeting on Fission Product Release and Transport in Gas-Cooled Reactors was to compare and discuss experimental and theoretical results of fission product behaviour in gas-cooled reactors under normal and accidental conditions and to give direction for future development. The technical part of the meeting covered operational experience and laboratory research, activity release, and behaviour of released activity

Developments in consequence modelling of accidental releases of hazardous materials

NARCIS (Netherlands)

Boot, H.

2012-01-01

The modelling of consequences of releases of hazardous materials in the Netherlands has mainly been based on the “Yellow Book”. Although there is no updated version of this official publication, new insights have been developed during the last decades. This article will give an overview of new

Muertes por enfermedades cardiacas y accidentes cerebrovasculares prevenibles - (Preventable Deaths from Heart Disease and Stroke)

Centers for Disease Control (CDC) Podcasts

2013-09-03

Este podcast se basa en la edición de septiembre del 2013 del informe Signos Vitales de los CDC. Más de 800,000 personas en los Estados Unidos mueren cada año a causa de enfermedades cardiacas y accidentes cerebrovasculares. Aprenda cómo controlar todos los principales factores de riesgo.  Created: 9/3/2013 by Centers for Disease Control and Prevention (CDC).   Date Released: 9/3/2013.

Atmospheric Rawinsonde and Pigeon Release Data Implicate Infrasound as the Long- Range Map Cue in Avian Navigation

Science.gov (United States)

Hagstrum, J. T.

2007-12-01

Pigeons ( Columba livia) and other birds released from distant familiar and unfamiliar sites generally head in the homeward (loft) direction, but often vanish from view or radio contact consistently off the exact homeward bearing. At some sites the deviation can be a significant and stable amount, while at other sites birds can appear to become completely lost and depart in random directions. These deviations or biases can change from hour to hour, day to day, and year to year, but have not, over the last ~50 years of intensive research, been related to any atmospheric factor. They are, however, still considered to reflect significant irregularities in the pigeons' "map" function. Celestial and geomagnetic "compasses" have been shown to orient avian flight, but how pigeons determine their location in order to select the correct homeward bearing remains controversial. At present the debate is primarily between workers advocating an olfactory "map" and those advocating variations in the direction and intensity of the geomagnetic field as map functions. Alternatively, infrasonic cues can travel 1000s of km in the atmosphere with little attenuation, and can be detected in the laboratory by pigeons at frequencies down to 0.05 Hz. Although infrasound has been considered as a navigational tool for homing and migratory birds, little supporting evidence of its use has been found. Infrasonic ray paths in the atmosphere are controlled primarily by temperature and secondarily by wind. Assuming birds use infrasonic cues, atmospheric conditions could cause the perplexing changes (both geographic and temporal) observed in the mean vanishing bearings (MVBs) of pigeons released from experimental sites. To test for correlations between MVBs and tropospheric conditions, release data collected by the late W.T. Keeton between 1968 and 1980 from around the Cornell University lofts in upstate NY are compared to rawinsonde data from stations near Buffalo and Albany. For example, birds

Suggested Methods for Assessment of Accidental External Exposure and Internal Contamination of Workers and their Medical Management

International Nuclear Information System (INIS)

Mahmoud, K.A.; Morsy, Samira M.; Hanna, I.R.A.; Hafez, M.B.; Mohamed, H.O.; Jahns, E.; Saied, F.I.A.

1969-01-01

Certain assumptions are given for the amount of fission products released from a research reactor after the occurrence of an accident. The size and location of radioactive cloud are assumed, and the corresponding external and internal exposures of workers are computed. A method is suggested for assessment of accidental external radiation dose based on experimental studies performed on the changes of quenching effect of plasma or sera as a.result of whole- body gamma-radiation ranging from 25-200 rems. For assessment of accidentally internally incorporated gamma emitters we suggest the standard chair whole-body counter technique which was found to detect reliably 1/100 of the maximum permissible body burden within eight minutes. It was also suggested that a separation method based on the use of absorption phenomena observed for Sephadex (gel resin) can be applied for quick determination of gross alpha activity in urine. For management of accidentally exposed workers to radiation doses of a lethal or sublethal nature, bone-marrow transplantation therapy and blood component therapy in sterile rooms is discussed in the light of experience gained from treatment of leukaemia with intensive chemotherapy. (author)

Review of uncertainty estimates associated with models for assessing the impact of breeder reactor radioactivity releases

International Nuclear Information System (INIS)

Miller, C.; Little, C.A.

1982-08-01

The purpose is to summarize estimates based on currently available data of the uncertainty associated with radiological assessment models. The models being examined herein are those recommended previously for use in breeder reactor assessments. Uncertainty estimates are presented for models of atmospheric and hydrologic transport, terrestrial and aquatic food-chain bioaccumulation, and internal and external dosimetry. Both long-term and short-term release conditions are discussed. The uncertainty estimates presented in this report indicate that, for many sites, generic models and representative parameter values may be used to calculate doses from annual average radionuclide releases when these calculated doses are on the order of one-tenth or less of a relevant dose limit. For short-term, accidental releases, especially those from breeder reactors located in sites dominated by complex terrain and/or coastal meteorology, the uncertainty in the dose calculations may be much larger than an order of magnitude. As a result, it may be necessary to incorporate site-specific information into the dose calculation under these circumstances to reduce this uncertainty. However, even using site-specific information, natural variability and the uncertainties in the dose conversion factor will likely result in an overall uncertainty of greater than an order of magnitude for predictions of dose or concentration in environmental media following shortterm releases

Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of an atmospheric dispersion model with an improved deposition scheme and oceanic dispersion model

Energy Technology Data Exchange (ETDEWEB)

Katata, G.; Chino, M.; Kobayashi, T. [Japan Atomic Energy Agency (JAEA), Ibaraki (Japan); and others

2015-07-01

Temporal variations in the amount of radionuclides released into the atmosphere during the Fukushima Daiichi Nuclear Power Station (FNPS1) accident and their atmospheric and marine dispersion are essential to evaluate the environmental impacts and resultant radiological doses to the public. In this paper, we estimate the detailed atmospheric releases during the accident using a reverse estimation method which calculates the release rates of radionuclides by comparing measurements of air concentration of a radionuclide or its dose rate in the environment with the ones calculated by atmospheric and oceanic transport, dispersion and deposition models. The atmospheric and oceanic models used are WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information) and SEA-GEARN-FDM (Finite difference oceanic dispersion model), both developed by the authors. A sophisticated deposition scheme, which deals with dry and fog-water depositions, cloud condensation nuclei (CCN) activation, and subsequent wet scavenging due to mixed-phase cloud microphysics (in-cloud scavenging) for radioactive iodine gas (I{sub 2} and CH{sub 3}I) and other particles (CsI, Cs, and Te), was incorporated into WSPEEDI-II to improve the surface deposition calculations. The results revealed that the major releases of radionuclides due to the FNPS1 accident occurred in the following periods during March 2011: the afternoon of 12 March due to the wet venting and hydrogen explosion at Unit 1, midnight of 14 March when the SRV (safety relief valve) was opened three times at Unit 2, the morning and night of 15 March, and the morning of 16 March. According to the simulation results, the highest radioactive contamination areas around FNPS1 were created from 15 to 16 March by complicated interactions among rainfall, plume movements, and the temporal variation of release rates. The simulation by WSPEEDI-II using the new source term reproduced the local and regional patterns of

Future trends in the assessment of hazards from fission product releases

Energy Technology Data Exchange (ETDEWEB)

Beattie, J. R.

1983-11-15

In comparing and selecting sites for reactors from the point of view of safety, one considers the remote possibility of an accidental release of moderately large amounts of fission products and its effects in relation to the present and future distribution of population in the neighbourhood. At present, until experience is gained of the reliability and safety of reactors, there is a tendency to site them remotely from centres of industry and population, although for economic reasons there will be a need to site large power reactors more closely to such centres in the future. With, among other objectives, the aim of adopting, in the proper course or time, less restrictive siting criteria, improvements are continually made in the intrinsic safety of reactor system and more sophisticated forms of reactor containment are devised, in order to reduce the possibility and scale of any fission product release. Changes and improvements in reactor systems could affect the nature and proportion of an accidental release of fission products if this should occur in the future. It is appropriate to consider what such a release and its radiobiological effects might be.

Atmospheric 14C changes resulting from fossil fuel CO2 release and cosmic ray flux variability

International Nuclear Information System (INIS)

Stuiver, M.; Quay, P.D.

1981-01-01

A high-precision tree-ring record of the atmospheric 14 C levels between 1820 and 1954 is presented. Good agreement is obtained between measured and model calculated 19th and 20th century atmospheric δ 14 C levels when both fossil fuel CO 2 release and predicted natural variations in 14 C production are taken into account. The best fit is obtained by using a box-diffusion model with an oceanic eddy diffusion coefficient of 3 cm 2 /s, a CO 2 atmosphere-ocean gas exchange rate of 21 moles msup(-2) yrsup(-1) and biospheric residence time of 60 years. For trees in the state of Washington the measured 1949-1951 atmospheric δ 14 C level was 20.0 +- 1.2per mille below the 1855-1864 level. Model calculations indicate that in 1950 industrial CO 2 emissions are responsible for at least 85% of the δ 14 C decline, whereas natural variability accounts for the remaining 15%. (orig.)

Siting of Nuclear Power Plants in Metropolitan Areas. Estimation of Population Doses due to Accidental Release of Fission Products

Energy Technology Data Exchange (ETDEWEB)

Bresser, H. [Technischer Ueberwachungs-Verein Rheinland E.V., Cologne (Germany); Schwarzer, W. [Institut fuer Reaktorsicherheit der Technischen Ueberwachungs-Vereine E.V., Cologne (Germany)

1967-09-15

The safety of large nuclear power plants in heavily populated areas depends entirely on engineered safeguards. An assessment of their reliability and effectiveness will have to play a major role in any safety analysis of such a plant, and this assessment will have to be made on the basis of the radiological burden to the environment - in terms of individual dose and a population dose - which can be accepted as tolerable in case of a severe accident. The calculation of the dispersion of fission products in the atmosphere, which links the radiological burden to the release of radioactivity, should be modified. The fact that distance factors, aside from a comparably small exclusion area, can no longer be taken into account suggests the introduction of the parameter ''population density'' and an extensive use of the man-rem concept. In this connection the time history of the release and the influence of variations of wind directions lose their importance. The authors have carried out calculations of the population dose, which could be received in a metropolitan area as a consequence of a severe reactor accident, using population densities, height of release above ground and generalized meteorological data as the main parameters. The results of these calculations are used as a basis for an assessment of the performance requirements of the engineered safeguards system, and the relative importance of different components of this system is discussed. (author)

Probabilistic consequence assessment of hydrogen sulphide releases from a heavy water plant

International Nuclear Information System (INIS)

1983-01-01

This report is concerned with the evaluation of the consequences to the public of an accidental release of hydrogen sulphide (H 2 S) to the atmosphere following a pipe or pressure envelope failure, or some other process upset, at a heavy water plant. It covers the first stage of a programme in which the nature of the problem was analyzed and recommendations made for the implementation of a computer model. The concepts of risk assessment and consequence assessment are discussed and a methodology proposed for combining the various elements of the problem into an overall consequence model. These elements are identified as the 'Initiating Events', 'Route to Receptor' and 'Receptor Response' and each is studied in detail in the report. Such phenomena as the blowdown of H 2 S from a rupture, the initial gas cloud behaviour, atmospheric dispersion and the toxicity of H 2 S and sulphur dioxide (SO 2 ) are addressed. Critical factors are identified and modelling requirements specified, with special reference to the Bruce heavy water plant. Finally, an overall model is recommended for implementation at the next stage of the programme, together with detailed terms of reference for the remaining work

Radiation shielding provided by residential houses in Japan in reactor accidents accompanied with atmospheric release

International Nuclear Information System (INIS)

Yamaguchi, Yasuhiro; Minami, Kentaro

1991-01-01

The present report describes the radiation shielding effect of houses in Japan against the radioactive cloud resulting from a major reactor accident accompanied with atmospheric release. The shielding factor of houses, the ratio of indoor exposure rate to outdoor one, has been studied for the semi-infinite and finite clouds which contain γ-emitting radionuclides released from a reactor facility. The shielding factor of houses against γ-rays from the radioactive cloud decreases gradually with release delay time and keeps a minimum during the period from 50 to 1000 hours after reactor shutdown while 133 Xe predominates in the cloud. Radioiodines mixed in the cloud raise slightly the shielding factor, and the factor depends little on the shape of the cloud. A set of shielding factors for the use of emergency planning was consequently proposed as 0.4 for simple ferroconcrete residential house and 0.9 for other ordinary ones. (author)

Modeling of methane bubbles released from large sea-floor area: Condition required for methane emission to the atmosphere

OpenAIRE

Yamamoto, A.; Yamanaka, Y.; Tajika, E.

2009-01-01

Massive methane release from sea-floor sediments due to decomposition of methane hydrate, and thermal decomposition of organic matter by volcanic outgassing, is a potential contributor to global warming. However, the degree of global warming has not been estimated due to uncertainty over the proportion of methane flux from the sea-floor to reach the atmosphere. Massive methane release from a large sea-floor area would result in methane-saturated seawater, thus some methane would reach the atm...

The Accidental Transgressor: Morally Relevant Theory of Mind

Science.gov (United States)

Killen, Melanie; Mulvey, Kelly Lynn; Richardson, Cameron; Jampol, Noah

2014-01-01

To test young children’s false belief theory of mind in a morally relevant context, two experiments were conducted. In Experiment 1, children (N = 162) at 3.5, 5.5, and 7.5 years of age were administered 3 tasks: prototypic moral transgression task, false belief theory of mind task (ToM), and an “accidental transgressor” task, which measured a morally relevant false belief theory of mind (MoToM). Children who did not pass false belief ToM were more likely to attribute negative intentions to an accidental transgressor than children who passed false belief ToM, and to use moral reasons when blaming the accidental transgressor. In Experiment 2, children (N = 46) who did not pass false belief ToM viewed it as more acceptable to punish the accidental transgressor than did participants who passed false belief ToM. Findings are discussed in light of research on the emergence of moral judgment and theory of mind. PMID:21377148

Atmospheric release model for the E-area low-level waste facility: Updates and modifications

International Nuclear Information System (INIS)

None, None

2017-01-01

The atmospheric release model (ARM) utilizes GoldSim® Monte Carlo simulation software (GTG, 2017) to evaluate the flux of gaseous radionuclides as they volatilize from E-Area disposal facility waste zones, diffuse into the air-filled soil pores surrounding the waste, and emanate at the land surface. This report documents the updates and modifications to the ARM for the next planned E-Area PA considering recommendations from the 2015 PA strategic planning team outlined by Butcher and Phifer.

Atmospheric release model for the E-area low-level waste facility: Updates and modifications

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-11-16

The atmospheric release model (ARM) utilizes GoldSim® Monte Carlo simulation software (GTG, 2017) to evaluate the flux of gaseous radionuclides as they volatilize from E-Area disposal facility waste zones, diffuse into the air-filled soil pores surrounding the waste, and emanate at the land surface. This report documents the updates and modifications to the ARM for the next planned E-Area PA considering recommendations from the 2015 PA strategic planning team outlined by Butcher and Phifer.

Evacuation emergency response model coupling atmospheric release advisory capability output

International Nuclear Information System (INIS)

Rosen, L.C.; Lawver, B.S.; Buckley, D.W.; Finn, S.P.; Swenson, J.B.

1983-01-01

A Federal Emergency Management Agency (FEMA) sponsored project to develop a coupled set of models between those of the Lawrence Livermore National Laboratory (LLNL) Atmospheric Release Advisory Capability (ARAC) system and candidate evacuation models is discussed herein. This report describes the ARAC system and discusses the rapid computer code developed and the coupling with ARAC output. The computer code is adapted to the use of color graphics as a means to display and convey the dynamics of an emergency evacuation. The model is applied to a specific case of an emergency evacuation of individuals surrounding the Rancho Seco Nuclear Power Plant, located approximately 25 miles southeast of Sacramento, California. The graphics available to the model user for the Rancho Seco example are displayed and noted in detail. Suggestions for future, potential improvements to the emergency evacuation model are presented

Automated emergency meteorological response system

International Nuclear Information System (INIS)

Pepper, D.W.

1980-01-01

A sophisticated emergency response system was developed to aid in the evaluation of accidental releases of hazardous materials from the Savannah River Plant to the environment. A minicomputer system collects and archives data from both onsite meteorological towers and the National Weather Service. In the event of an accidental release, the computer rapidly calculates the trajectory and dispersion of pollutants in the atmosphere. Computer codes have been developed which provide a graphic display of predicted concentration profiles downwind from the source, as functions of time and distance

Oxidation of siloxanes during biogas combustion and nanotoxicity of Si-based particles released to the atmosphere.

Science.gov (United States)

Tansel, Berrin; Surita, Sharon C

2014-01-01

Siloxanes have been detected in the biogas produced at municipal solid waste landfills and wastewater treatment plants. When oxidized, siloxanes are converted to silicon oxides. The objectives of this study were to evaluate the transformation of siloxanes and potential nanotoxicity of Si-based particles released to the atmosphere from the gas engines which utilize biogas. Data available from nanotoxicity studies were used to assess the potential health risks associated with the inhalation exposure to Si-based nanoparticles. Silicon dioxide formed from siloxanes can range from 5 nm to about 100 nm in diameter depending on the combustion temperature and particle clustering characteristics. In general, silicon dioxide particles formed during from combustion process are typically 40-70 nm in diameter and can be described as fibrous dusts and as carcinogenic, mutagenic, astmagenic or reproductive toxic (CMAR) nanoparticles. Nanoparticles deposit in the upper respiratory system, conducting airways, and the alveoli. Size ranges between 5 and 50 nm show effective deposition in the alveoli where toxic effects are higher. In this study the quantities for the SiO₂ formed and release during combustion of biogas were estimated based on biogas utilization characteristics (gas compositions, temperature). The exposure to Si-based particles and potential effects in humans were analyzed in relation to their particle size, release rates and availability in the atmosphere. The analyses showed that about 54.5 and 73 kg/yr of SiO₂ can be released during combustion of biogas containing D4 and D5 at 14.1 mg/m(3) (1 ppm) and 15.1 mg/m(3) (1ppm), respectively, per MW energy yield. Copyright © 2013 Elsevier B.V. All rights reserved.

Xenon-133 and caesium-137 releases into the atmosphere from the Fukushima Dai-ichi nuclear power plant: determination of the source term, atmospheric dispersion, and deposition

Science.gov (United States)

Stohl, A.; Seibert, P.; Wotawa, G.; Arnold, D.; Burkhart, J. F.; Eckhardt, S.; Tapia, C.; Vargas, A.; Yasunari, T. J.

2012-04-01

This presentation will show the results of a paper currently under review in ACPD and some additional new results, including more data and with an independent box modeling approach to support some of the findings of the ACPD paper. On 11 March 2011, an earthquake occurred about 130 km off the Pacific coast of Japan's main island Honshu, followed by a large tsunami. The resulting loss of electric power at the Fukushima Dai-ichi nuclear power plant (FD-NPP) developed into a disaster causing massive release of radioactivity into the atmosphere. In this study, we determine the emissions of two isotopes, the noble gas xenon-133 (133Xe) and the aerosol-bound caesium-137 (137Cs), which have very different release characteristics as well as behavior in the atmosphere. To determine radionuclide emissions as a function of height and time until 20 April, we made a first guess of release rates based on fuel inventories and documented accident events at the site. This first guess was subsequently improved by inverse modeling, which combined the first guess with the results of an atmospheric transport model, FLEXPART, and measurement data from several dozen stations in Japan, North America and other regions. We used both atmospheric activity concentration measurements as well as, for 137Cs, measurements of bulk deposition. Regarding 133Xe, we find a total release of 16.7 (uncertainty range 13.4-20.0) EBq, which is the largest radioactive noble gas release in history not associated with nuclear bomb testing. There is strong evidence that the first strong 133Xe release started early, before active venting was performed. The entire noble gas inventory of reactor units 1-3 was set free into the atmosphere between 11 and 15 March 2011. For 137Cs, the inversion results give a total emission of 35.8 (23.3-50.1) PBq, or about 42% of the estimated Chernobyl emission. Our results indicate that 137Cs emissions peaked on 14-15 March but were generally high from 12 until 19 March, when they

Field studies of the atmospheric processing of radionuclides released at Chernobyl

International Nuclear Information System (INIS)

Slinn, W.G.N.; Brodzinski, R.L.; Busness, K.M.

1987-01-01

This report gives a summary description of the goals and execution of field studies to characterize the radionuclides released from Chernobyl and to examine their long-range atmospheric transport and processing. Starting on April 28, 1986, an intensive planning and preparation effort was mounted over a very short time intercept and characterize the Chernobyl plume on its arrival over the western US. During the execution of these studies, they had very little firm information (beyond their own measurements and trajectory estimates) to confirm the location of the Chernobyl plume. On May 20, 1986, the studies were terminated, after extensive airborne sampling of air, cloud water, precipitation, soil, and vegetation as the plume traversed the western and central US and moved into Canada

Fate and potential environmental effects of methylenediphenyl diisocyanate and toluene diisocyanate released into the atmosphere.

Science.gov (United States)

Tury, Bernard; Pemberton, Denis; Bailey, Robert E

2003-01-01

Information from a variety of sources has been collected and summarized to facilitate an overview of the atmospheric fate and potential environmental effects of emissions of methylenediphenyl diisocyanate (MDI) or toluene diisocyanate (TDI) to the atmosphere. Atmospheric emissions of both MDI and TDI are low, both in terms of concentration and mass, because of their low volatility and the need for careful control over all aspects of their lifecycle from manufacture through disposal. Typical emission losses for TDI are 25 g/t of TDI used in slabstock foam production. MDI emission losses are lower, often less than 1 g/t of MDI used. Dispersion modeling predicts that concentrations at the fenceline or beyond are very low for typical releases. Laboratory studies show that TDI (and by analogy MDI) does not react with water in the gas phase at a significant rate. The primary degradation reaction of these aromatic diisocyanates in the atmosphere is expected to be oxidation by OH radicals with an estimated half-life of one day. Laboratory studies also show that this reaction is not expected to result in increased ground-level ozone accumulation.

Accidental and retrospective dosimetry using TL method

International Nuclear Information System (INIS)

Mesterházy, D.; Osvay, M.; Kovács, A.; Kelemen, A.

2012-01-01

Retrospective dosimetry is one of the most important tools of accidental dosimetry for dose estimation when dose measurement was not planned. In the affected area many objects can be applied as natural dosimeters. The paper discusses our recent investigations on various electronic components and common salt (NaCl) having useful thermoluminescence (TL) properties. Among materials investigated the electronic components of cell phones seem promising for retrospective dosimetry purposes, having high TL responses, proper glow curve peaks and the intensity of TL peaks vs. gamma dose received provided nearly linear response in the dose range of 10 mGy–1.5 Gy. - Highlights: ► Electronic components and common salt were investigated for accidental and retrospective dosimetry. ► SMD resistors seem promising for retrospective dosimetry purposes. ► Table salt can be used effectively for accidental dosimetry purposes, as well.

Application of dynamic modeling for assessing the impact of radioactive releases to water sewer systems

International Nuclear Information System (INIS)

Sundell-Bergman, Synnove; Avila, Rodolfo; Cruz, Idalmis de la

2008-01-01

Full text: Potential radiological emergencies due to accidental or malicious acts involving nuclear materials requires tools for emergency dose assessment to help in the planning of countermeasures. In urban areas, the municipal sewage systems will receive the wastewater from households, industries and hospitals as well as the run-off water. Investigations have shown that sewage sludge is a sensitive indicator for radionuclides released from hospitals or spread via the atmosphere and thus simulation modelling of the fate of radionuclides entering sewage treatment plants via urban drainage systems could prove useful in emergency situations. A dynamic model (LUCIA) has been developed to assess the radiological consequences of non-homogenous releases of radionuclides to the sewage plants. In the first step the focussing has been on radioactive liquid releases from hospitals and the predictions show that there is a significant probability (> 0,2) that the sewage worker doses exceed 10 μSv/y while doses to farmers or fishermen (downstream plants) are marginal. Comparison of measured and estimated concentration values for iodine-131 reveal that the predictions made by LUCIA are reasonably good and fall within a factor of 2. For the purpose of emergency preparedness, scenarios have been defined and the fate of released radionuclides has been assessed. The main features of the LUCIA model will be presented and the application of the tool for emergency preparedness will be discussed. (author)

Identification and characterization of five non-traditional-source categories: Catastrophic/accidental releases, vehicle repair facilities, recycling, pesticide application, and agricultural operations. Final report, September 1991-September 1992

International Nuclear Information System (INIS)

Sleva, S.; Pendola, J.A.; McCutcheon, J.; Jones, K.; Kersteter, S.L.

1993-03-01

The work is part of EPA's program to identify and characterize emissions sources not currently accounted for by either the existing Aerometric Information Retrieval System (AIRS) or State Implementation Plans (SIP) area source methodologies and to develop appropriate emissions estimation methodologies and emission factors for a group of these source categories. Based on the results of the identification and characterization portions of the research, five source categories were selected for methodology and emission factor development: catastrophic/accidental releases, vehicle repair facilities, recycling, pesticide application and agricultural operations. The report presents emissions estimation methodologies and emission factor data for the selected source categories. The discussions for each selected category include general background information, emissions generation activities, pollutants emitted, sources of activity and pollutant data, emissions estimation methodologies, issues to be considered and recommendations. The information used in these discussions was derived from various sources including available literature, industrial and trade association publications and contracts, experts on the category and activity, and knowledgeable federal and state personnel

Commitment of involved actors in the preparation of accidental and post-accident situations: European experiments; Engagement des parties prenantes a la preparation aux situations accidentelles et post-accidentelles: experiences Europeennes

Energy Technology Data Exchange (ETDEWEB)

Schneider, Th. [CEPN, 28 rue de la Redoute, 92260 Fontenay-aux-Roses (France)

2010-07-01

The author briefly describes some approaches developed within the EURANOS European research programme between 2004 and 2009 which aims at promoting the building up of a European network (NERIS) for the management of nuclear accidental and post-accident situations. Notably, he comments the experiment which took place in the Montbeliard district where two types of radiological events have been modelled and simulated: an accident in the Fessenheim nuclear power plant with two scenarios of release, and a transportation accident with a release of radioactive caesium 137. He also evokes the Norwegian experience and some other actions in Finland, Great-Britain, Spain and Slovakia where reflections on the management of accidental and post-accident situations or crisis exercises have been organized

Assessment of impact of a severe accident at nuclear power plant of Angra dos Reis with release of radionuclides to the atmosphere

International Nuclear Information System (INIS)

Aguiar, Andre Silva de

2015-01-01

This study had as purpose the assess the impact of a severe accident, and also analyze the dispersion of 131 I in the atmosphere, so that, through concentrating and inhaling dose of the plume, were possible to verify if the results are in accordance with the indicated data by the Plan of Emergency of the CNAAA regarding the Impact Zone and Control. This exercise was performed with the aid of an atmospheric model and a dispersion where to atmospheric modeling we used the data coupling WRF / CALMET and of dispersion, CALPUFF. The suggested accident consists of a Station Blackout at Nuclear Power of Angra (Unit 1), where through the total core involvement, will release 100% of the 131 I to the atmosphere. The value of the total activity in the nucleus to this radionuclide is 7.44 x 1017 Bq, that is relative on the sixth day of burning. This activity will be released through the chimney at a rate in Bq/s in the scenario of 12, 24, 48 and 72 hours of release. Applying the model in the proposed scenario, it is verified that the plume has concentrations of the order of 1020 Bq/m³ and dose of about 108 Sv whose value is beyond of the presented by Eletronuclear in your current emergency plan. (author)

Overview of the National Atmospheric Release Advisory Center's urban research and development activities

International Nuclear Information System (INIS)

Lundquist, J K; Sugiyama, G A; Nasstrom, J

2007-01-01

This presentation describes the tools and services provided by the National Atmospheric Release Advisory Center (NARAC) at Lawrence Livermore National Laboratory (LLNL) for modeling the impacts of airborne hazardous materials. NARAC provides atmospheric plume modeling tools and services for chemical, biological, radiological, and nuclear airborne hazards. NARAC can simulate downwind effects from a variety of scenarios, including fires, industrial and transportation accidents, radiation dispersal device explosions, hazardous material spills, sprayers, nuclear power plant accidents, and nuclear detonations. NARAC collaborates on radiological dispersion source terms and effects models with Sandia National Laboratories and the U.S. Nuclear Regulatory Commission. NARAC was designated the interim provider of capabilities for the Department of Homeland Security's Interagency Modeling and Atmospheric Assessment Center by the Homeland Security Council in April 2004. The NARAC suite of software tools include simple stand-alone, local-scale plume modeling tools for end-user's computers, and Web- and Internet-based software to access advanced modeling tools and expert analyses from the national center at LLNL. Initial automated, 3-D predictions of plume exposure limits and protective action guidelines for emergency responders and managers are available from the center in 5-10 minutes. These can be followed immediately by quality-assured, refined analyses by 24 x 7 on-duty or on-call NARAC staff. NARAC continues to refine calculations using updated on-scene information, including measurements, until all airborne releases have stopped and the hazardous threats are mapped and impacts assessed. Model predictions include the 3-D spatial and time-varying effects of weather, land use, and terrain, on scales from the local to regional to global. Real-time meteorological data and forecasts are provided by redundant communications links to the U.S. National Oceanic and Atmospheric

A statistical model for deriving probability distributions of contamination for accidental releases

International Nuclear Information System (INIS)

ApSimon, H.M.; Davison, A.C.

1986-01-01

Results generated from a detailed long-range transport model, MESOS, simulating dispersal of a large number of hypothetical releases of radionuclides in a variety of meteorological situations over Western Europe have been used to derive a simpler statistical model, MESOSTAT. This model may be used to generate probability distributions of different levels of contamination at a receptor point 100-1000 km or so from the source (for example, across a frontier in another country) without considering individual release and dispersal scenarios. The model is embodied in a series of equations involving parameters which are determined from such factors as distance between source and receptor, nuclide decay and deposition characteristics, release duration, and geostrophic windrose at the source. Suitable geostrophic windrose data have been derived for source locations covering Western Europe. Special attention has been paid to the relatively improbable extreme values of contamination at the top end of the distribution. The MESOSTAT model and its development are described, with illustrations of its use and comparison with the original more detailed modelling techniques. (author)

Development of computer-based function to estimate radioactive source term by coupling atmospheric model with monitoring data

International Nuclear Information System (INIS)

Akiko, Furuno; Hideyuki, Kitabata

2003-01-01

Full text: The importance of computer-based decision support systems for local and regional scale accidents has been recognized by many countries with the experiences of accidental atmospheric releases of radionuclides at Chernobyl in 1986 in the former Soviet Union. The recent increase of nuclear power plants in the Asian region also necessitates an emergency response system for Japan to predict the long-range atmospheric dispersion of radionuclides due to overseas accident. On the basis of these backgrounds, WSPEEDI (Worldwide version of System for Prediction of Environmental Emergency Dose Information) at Japan Atomic Energy Research Institute is developed to forecast long-range atmospheric dispersions of radionuclides during nuclear emergency. Although the source condition is critical parameter for accurate prediction, it is rarely that the condition can be acquired in the early stage of overseas accident. Thus, we have been developing a computer-based function to estimate radioactive source term, e.g. the release point, time and amount, as a part of WSPEEDI. This function consists of atmospheric transport simulations and statistical analysis for the prediction and monitoring of air dose rates. Atmospheric transport simulations are carried out for the matrix of possible release points in Eastern Asia and possible release times. The simulation results of air dose rates are compared with monitoring data and the best fitted release condition is defined as source term. This paper describes the source term estimation method and the application to Eastern Asia. The latest version of WSPEEDI accommodates following two models: an atmospheric meteorological model MM5 and a particle random walk model GEARN. MM5 is a non-hydrostatic meteorological model developed by the Pennsylvania State University and the National Center for Atmospheric Research (NCAR). MM5 physically calculates more than 40 meteorological parameters with high resolution in time and space based an

Dose assessment for Greifswald and Cadarache

International Nuclear Information System (INIS)

Raskob, W.

1996-07-01

Probabilistic dose assessments for accidental atmospheric releases of tritium and activation products as well as releases under normal operation conditions were performed for the sites of Greifswald, Germany, and Cadarache, France. Additionally, aquatic releases were considered for both sites. No country specific rules were applied and the input parameters were adapted as far as possible to those used within former ITER studies to have a better comparison to site independent dose assessments performed in the frame of ITER. The main goal was to complete the generic data base with site specific values. The agreement between the results from the ITER study on atmospheric releases and the two sites are rather good for tritium, whereas the ITER reference dose values for the activation product releases are often lower, than the maximum doses for Greifswald and Cadarache. However, the percentile values fit better to the deterministic approach of ITER. Within all scenarios, the consequences of aquatic releases are in nearly all cases smaller than those from comparable releases to the atmosphere (HTO and steel). This rule is only broken once in case of accidental releases of activated steel from Cadarache. However, the uncertainties associated with the aquatic assessments are rather high and a better data base is needed to obtain more realistic and thus more reliable dose values. (orig.) [de

Probabilistic consequence model of accidenal or intentional chemical releases.

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.-S.; Samsa, M. E.; Folga, S. M.; Hartmann, H. M.

2008-06-02

In this work, general methodologies for evaluating the impacts of large-scale toxic chemical releases are proposed. The potential numbers of injuries and fatalities, the numbers of hospital beds, and the geographical areas rendered unusable during and some time after the occurrence and passage of a toxic plume are estimated on a probabilistic basis. To arrive at these estimates, historical accidental release data, maximum stored volumes, and meteorological data were used as inputs into the SLAB accidental chemical release model. Toxic gas footprints from the model were overlaid onto detailed population and hospital distribution data for a given region to estimate potential impacts. Output results are in the form of a generic statistical distribution of injuries and fatalities associated with specific toxic chemicals and regions of the United States. In addition, indoor hazards were estimated, so the model can provide contingency plans for either shelter-in-place or evacuation when an accident occurs. The stochastic distributions of injuries and fatalities are being used in a U.S. Department of Homeland Security-sponsored decision support system as source terms for a Monte Carlo simulation that evaluates potential measures for mitigating terrorist threats. This information can also be used to support the formulation of evacuation plans and to estimate damage and cleanup costs.

Utilization of the atmospheric release advisory capability (ARAC) services during and after the Three Mile Island accident

International Nuclear Information System (INIS)

Knox, J.B.; Dickerson, M.H.; Greenly, G.D.; Gudiksen, P.H.; Sullivan, T.J.

1980-01-01

At 0820 PST on 28 March 1979, the Department of Energy's Emergency Operations Center advised the Atmospheric Release Advisory Capability (ARAC) that the Three Mile Island nuclear power plant in Harrisburg, Pennsylvania, had experienced an accident some four hours earlier, resulting in the atmospheric release of xenon-133 and krypton-88. This report describes ARAC's response to the Three Mile Island accident, including the role ARAC played throughout the 20 days that real-time assessments were made available to the Department of Energy on-scene commander. It also describes the follow-up population-dose calculations performed for the President's Commission on Three Mile Island. At the request of the Nuclear Regulatory Commission, a questionnaire addressing the usefulness of ARAC products during the accident was sent to ARAC-product users. A summary of the findings from this questionnaire, along with recommendations for improving ARAC service, is also presented. The accident at Mississauga, Ontario, Canada, is discussed in the context of a well-planned emergency response by local and Federal officials

Plant air quality following accidental radioactive releases

International Nuclear Information System (INIS)

Slawson, P.R.; Hitchman, G.J.

1987-01-01

Radionuclides exhausted to the atmosphere through vent stacks may contaminate the immediate building structure and/or nearby adjacent buildings resulting in hazardous contaminants entering the intake air. The objective of the work reported here was to obtain an overview of the analytical and experimental tools available to evaluate the transport and diffusion of vented effluents, and the nature of flows about structures, in order to predict the concentrations adjacent to an subsequently inside the immediate and nearby structures. A scaling analysis established the requirements for physical modelling of flows about structures in wind and/or water tunnels. Subsequently, a series of test model studies were conducted in a water tunnel in the Mechanical Engineering Department of the University of Waterloo. The expected result that increased stack height and structure separation have on reducing recirculation and interference is clearly illustrated. Interference was still significant on the downstream structure when the vent stack height was increased to its maximum of one model cube height above the cube. A literature survey was conducted to establish the nature and mathematical modelling of flows about structures. Also, mathematical modelling of the concentration field from roof-top vent effluents and subsequently the models for predicting concentrations within structures was investigated. No specific data on concentrations within structures were found. There is a strong need for well documented test on the concentration fields about model structures, with which more generic models may be developed. Very little data is available on multiple structures. It is recommended that physical model studies be conducted, that simulate realistic exhaust and intake air vents with measurement of both the inside and the outside concentration fields. (59 refs., 21 figs., 2 tabs.)

Statistical atmospheric inversion of local gas emissions by coupling the tracer release technique and local-scale transport modelling: a test case with controlled methane emissions

Directory of Open Access Journals (Sweden)

S. Ars

2017-12-01

Full Text Available This study presents a new concept for estimating the pollutant emission rates of a site and its main facilities using a series of atmospheric measurements across the pollutant plumes. This concept combines the tracer release method, local-scale atmospheric transport modelling and a statistical atmospheric inversion approach. The conversion between the controlled emission and the measured atmospheric concentrations of the released tracer across the plume places valuable constraints on the atmospheric transport. This is used to optimise the configuration of the transport model parameters and the model uncertainty statistics in the inversion system. The emission rates of all sources are then inverted to optimise the match between the concentrations simulated with the transport model and the pollutants' measured atmospheric concentrations, accounting for the transport model uncertainty. In principle, by using atmospheric transport modelling, this concept does not strongly rely on the good colocation between the tracer and pollutant sources and can be used to monitor multiple sources within a single site, unlike the classical tracer release technique. The statistical inversion framework and the use of the tracer data for the configuration of the transport and inversion modelling systems should ensure that the transport modelling errors are correctly handled in the source estimation. The potential of this new concept is evaluated with a relatively simple practical implementation based on a Gaussian plume model and a series of inversions of controlled methane point sources using acetylene as a tracer gas. The experimental conditions are chosen so that they are suitable for the use of a Gaussian plume model to simulate the atmospheric transport. In these experiments, different configurations of methane and acetylene point source locations are tested to assess the efficiency of the method in comparison to the classic tracer release technique in coping

Statistical atmospheric inversion of local gas emissions by coupling the tracer release technique and local-scale transport modelling: a test case with controlled methane emissions

Science.gov (United States)

Ars, Sébastien; Broquet, Grégoire; Yver Kwok, Camille; Roustan, Yelva; Wu, Lin; Arzoumanian, Emmanuel; Bousquet, Philippe

2017-12-01

This study presents a new concept for estimating the pollutant emission rates of a site and its main facilities using a series of atmospheric measurements across the pollutant plumes. This concept combines the tracer release method, local-scale atmospheric transport modelling and a statistical atmospheric inversion approach. The conversion between the controlled emission and the measured atmospheric concentrations of the released tracer across the plume places valuable constraints on the atmospheric transport. This is used to optimise the configuration of the transport model parameters and the model uncertainty statistics in the inversion system. The emission rates of all sources are then inverted to optimise the match between the concentrations simulated with the transport model and the pollutants' measured atmospheric concentrations, accounting for the transport model uncertainty. In principle, by using atmospheric transport modelling, this concept does not strongly rely on the good colocation between the tracer and pollutant sources and can be used to monitor multiple sources within a single site, unlike the classical tracer release technique. The statistical inversion framework and the use of the tracer data for the configuration of the transport and inversion modelling systems should ensure that the transport modelling errors are correctly handled in the source estimation. The potential of this new concept is evaluated with a relatively simple practical implementation based on a Gaussian plume model and a series of inversions of controlled methane point sources using acetylene as a tracer gas. The experimental conditions are chosen so that they are suitable for the use of a Gaussian plume model to simulate the atmospheric transport. In these experiments, different configurations of methane and acetylene point source locations are tested to assess the efficiency of the method in comparison to the classic tracer release technique in coping with the distances

Response to a radioactive materials release having a transboundary impact

International Nuclear Information System (INIS)

1989-01-01

Compared with an accidental release of radioactive material which is confined to the accident State, a transboundary release has added dimensions which were not fully anticipated in publications dealing with response to accidents at nuclear facilities. The new aspects to the problem may be summarized as follows: (1) A transboundary release of radioactive material, as distinct from a release which affects only the accident State, has international repercussions in the following ways: Potentially at least, the difficulties associated with a transboundary release may be magnified in those States that have no nuclear facilities of their own and may, therefore, have foreseen no need for resources to assess and deal with radioactive contamination of their food supplies, their water and their environment appropriately. International trade, in food commodities particularly, may be severely affected. Issues of compensation may arise for which the dispute settlement mechanisms are weak or non-existent. (2) Many Member States are in such geographic locations that they could be affected by a transboundary release occurring in any of their surrounding neighbour States. Planning for and responding to such an event is necessarily more difficult than planning for an accidental release from a single, identified nuclear facility. (3) Deposits of radioactive material from a distant source are apt to be highly unpredictable. Depending on weather conditions, they may be localized in a random fashion or widespread. Because of the international dimension of the problem and its essentially unpredictable character it is recommended here that planning for such events should be carried at the national or federal government level rather than at provincial government level. 14 refs

Últimos perfiles del accidente de trabajo en misión

OpenAIRE

Poquet Catalá, Raquel

2017-01-01

En este trabajo se analiza desde un punto de vista de la doctrina judicial y jurisprudencial la construcción doctrinal del accidente de trabajo en misión como derivación del accidente de trabajo in itinere y como configuración propia del accidente de trabajo en sí. Así, se procede a la delimitación respecto del accidente in itinere, se realiza un análisis de los requisitos configuradores del mismo, tanto genéricos como específicos, así como la aplicabilidad de la presunción iuris tantum de la...

Assessment of atmospherically-released radionuclides using the computerized radiological risk investigation system

International Nuclear Information System (INIS)

Nelson, C.B.; Sjoreen, A.L.; Miller, C.W.; Baes, C.F. III.

1986-01-01

For radionuclides, the standards are in terms of an annual dose, and the regulations require assurance that no member of the general public receives a dose in excess of that standard. Thus, spatial variations in the population around an emission source must be considered. Furthermore, for most chemical pollutants the standards are written in terms of an air concentration while for radionuclides other pathways of exposure, e.g., uptake of the airborne emissions by terrestrial food chains must also be considered. The remainder of this paper discusses the computer codes that make up the CRRIS and how they are used to perform an assessment of the health impacts on man of radionuclides released to the atmosphere

Experience with effluent release from the Omaha V. A. Hospital TRIGA reactor

Energy Technology Data Exchange (ETDEWEB)

Blotcky, A J [Veterans Administration Hospital (United States)

1974-07-01

The effluent release from experiments is controlled by limiting the size of each sample irradiated so that if it was accidentally completely volatized into the closed room, the radioactive concentration would not exceed the permitted limits. The possible releases of Ar-41 and N-16 from the reactor are also considered. The experimentally determined levels of radiation around the Omaha facility are shown. From the data and calculations it was concluded that the levels of effluent release from the Omaha TRIGA are very small.

Experience with effluent release from the Omaha V. A. Hospital TRIGA reactor

International Nuclear Information System (INIS)

Blotcky, A.J.

1974-01-01

The effluent release from experiments is controlled by limiting the size of each sample irradiated so that if it was accidentally completely volatized into the closed room, the radioactive concentration would not exceed the permitted limits. The possible releases of Ar-41 and N-16 from the reactor are also considered. The experimentally determined levels of radiation around the Omaha facility are shown. From the data and calculations it was concluded that the levels of effluent release from the Omaha TRIGA are very small

Emulation and Sobol' sensitivity analysis of an atmospheric dispersion model applied to the Fukushima nuclear accident

Science.gov (United States)

Girard, Sylvain; Mallet, Vivien; Korsakissok, Irène; Mathieu, Anne

2016-04-01

Simulations of the atmospheric dispersion of radionuclides involve large uncertainties originating from the limited knowledge of meteorological input data, composition, amount and timing of emissions, and some model parameters. The estimation of these uncertainties is an essential complement to modeling for decision making in case of an accidental release. We have studied the relative influence of a set of uncertain inputs on several outputs from the Eulerian model Polyphemus/Polair3D on the Fukushima case. We chose to use the variance-based sensitivity analysis method of Sobol'. This method requires a large number of model evaluations which was not achievable directly due to the high computational cost of Polyphemus/Polair3D. To circumvent this issue, we built a mathematical approximation of the model using Gaussian process emulation. We observed that aggregated outputs are mainly driven by the amount of emitted radionuclides, while local outputs are mostly sensitive to wind perturbations. The release height is notably influential, but only in the vicinity of the source. Finally, averaging either spatially or temporally tends to cancel out interactions between uncertain inputs.

Contaminative Influence of Beef Due to the Inhalation of Air and the Ingestion of Soil of Livestock from an Acute Release of Radioactive Materials

International Nuclear Information System (INIS)

Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Jeong, Hyo Jeon; Han, Moon Hee

2004-01-01

The contaminative influence of beef due to the inhalation of air and the ingestion of soil of livestock, both of which are dealt with as minor contaminative pathways in most radioecological models but may not be neglected, was comprehensively investigated with the improvement of the Korean food chain model DYNACON. As the results, it was found that both pathways can not be neglected at all in the contamination of beef in the case of an accidental release during the non-grazing period of livestock. The ingestion of soil was more influential in the contamination of beef than the inhalation of air over most time following an release. If precipitation is encountered during an accidental release, contaminative influence due to the ingestion of soil was far greater compared with the cases of no precipitation. This fact was more distinct for a long-lived radionuclide 137 Cs than a short-lived radionuclide '1 31 I (elemental iodine). Compared with the results for milk performed prior to this study, the contaminative pathways due to the inhalation of air and the ingestion of soil were more important in beef because of longer biological half-lives. On the other hand, in the case of an accidental release during the grazing period of livestock, radioactive contamination due to the ingestion of pasture was dominant irrespective of the existence of precipitation during an accidental release. It means that contaminative influence due to the inhalation of air and the ingestion of soil is negligible, like the cases of milk.

Allegheny County Fatal Accidental Overdoses

Data.gov (United States)

Allegheny County / City of Pittsburgh / Western PA Regional Data Center — Fatal accidental overdose incidents in Allegheny County, denoting age, gender, race, drugs present, zip code of incident and zip code of residence. Zip code of...

Understanding drug-related mortality in released prisoners: a review of national coronial records

Directory of Open Access Journals (Sweden)

Andrews Jessica Y

2012-04-01

Full Text Available Abstract Background The prisoner population is characterised by a high burden of disease and social disadvantage, and ex-prisoners are at increased risk of death following release. Much of the excess mortality can be attributed to an increased risk of unnatural death, particularly from drug overdose; however, relatively few studies have investigated the circumstances surrounding drug-related deaths among released prisoners. This study aimed to explore and compare the circumstances of death for those who died from accidental drug-related causes to those who died from all other reportable causes. Methods A nationwide search of the Australian National Coroners Information System (NCIS was conducted to identify reportable deaths among ex-prisoners from 2000 to 2007. Using a structured coding form, NCIS records for these cases were interrogated to explore causes and circumstances of death. Results Coronial records for 388 deceased ex-prisoners were identified. Almost half of these deaths were a result of accidental drug-related causes (45%. The majority of accidental drug-related deaths occurred in a home environment, and poly-substance use at or around the time of death was common, recorded in 72% of drug-related deaths. Ex-prisoners who died of accidental drug-related causes were on average younger and less likely to be Indigenous, born in Australia, married, or living alone at or around the time of death, compared with those who died from all other reportable causes. Evidence of mental illness or self-harm was less common among accidental drug-related deaths, whereas evidence of previous drug overdose, injecting drug use, history of heroin use and history of drug withdrawal in the previous six months were more common. Conclusions Drug-related deaths are common among ex-prisoners and often occur in a home (vs. public setting. They are often associated with use of multiple substances at or around the time of death, risky drug-use patterns, and even

Regionalized study of the impact of an accidental radioactive pollution on a permanent meadow

International Nuclear Information System (INIS)

Durand, V.; Mercat-Rommens, C.

2006-01-01

The objective of this study consists in evaluating the sensitivity of the first part of the die grass-milk with respect to an accidental radioactive discharge. We want to know if a single uniform deposit would involve a contamination of the grazing grass identical on the scale of the own territory. The study was based on the A.S.T.R.A.L. model, a computer code developed by the I.R.S.N. which makes it possible to evaluate the transfer of the radionuclides in the terrestrial food chain following an accidental atmospheric emission. The way of transfer of A.S.T.R.A.L. on which the study focused is the transfer of the deposit to milk, via the grazing grass ingestion. The sensitivity of this way of transfer relies on several parameters: captation, yield, cows food rates and dates of setting to grass. Methodology thus consisted in regionalizing these parameters. The software S.T.I.C.S. developed by the I.N.R.A. of Avignon was then used. This model proposes a daily follow-up of the leaf area index which has been correlated with captation and with the production of fresh biomass (yield). (authors)

Overview of the National Atmospheric Release Advisory Center's Urban Research and Development Activities

Science.gov (United States)

Lundquist, J. K.; Sugiyama, G.; Nasstrom, J.

2007-12-01

This presentation describes the tools and services provided by the National Atmospheric Release Advisory Center (NARAC) at Lawrence Livermore National Laboratory (LLNL) for modeling the impacts of airborne hazardous materials. NARAC provides atmospheric plume modeling tools and services for chemical, biological, radiological, and nuclear airborne hazards. NARAC can simulate downwind effects from a variety of scenarios, including fires, industrial and transportation accidents, radiation dispersal device explosions, hazardous material spills, sprayers, nuclear power plant accidents, and nuclear detonations. NARAC collaborates on radiological dispersion source terms and effects models with Sandia National Laboratories and the U.S. Nuclear Regulatory Commission. NARAC was designated the interim provider of capabilities for the Department of Homeland Security's Interagency Modeling and Atmospheric Assessment Center by the Homeland Security Council in April 2004. The NARAC suite of software tools include simple stand-alone, local-scale plume modeling tools for end-user's computers, and Web- and Internet-based software to access advanced modeling tools and expert analyses from the national center at LLNL. Initial automated, 3-D predictions of plume exposure limits and protective action guidelines for emergency responders and managers are available from the center in 5-10 minutes. These can be followed immediately by quality-assured, refined analyses by 24 x 7 on-duty or on-call NARAC staff. NARAC continues to refine calculations using updated on-scene information, including measurements, until all airborne releases have stopped and the hazardous threats are mapped and impacts assessed. Model predictions include the 3-D spatial and time-varying effects of weather, land use, and terrain, on scales from the local to regional to global. Real-time meteorological data and forecasts are provided by redundant communications links to the U.S. National Oceanic and Atmospheric

Local scale atmospheric diffusion at a coastal site in the presence of breeze effect (phase III: data elaboration and model development). Volume 1

International Nuclear Information System (INIS)

Cagnetti, P.; Ferrara, V.; Pellegrini, A.

1985-01-01

The aim of this contract is the characterization, from the thermal and anemological point of view, of the lower layers of the atmosphere at a coastal site, affected by breeze circulation. Data are utilized to set up diffusion models for accidental releases of airborne materials, both of short and prolonged duration. Five inland meteorological campaigns, starting from Jan. 82 (Jan., Apr., Jul., Oct. 1982, Jan. 1983), have been carried out; an appropriate extension of the contract allowed the execution of two more campaigns in the open sea (Apr., Jul. 1983), utilizing the oceanographic ship ''Bannock'' kindly supplied by CNR. The analysis of the data showed the development of a well defined IBL during on-shore flow only in Spring and Summer, while an inversion layer was detectable aloft independently of the season (provided that an anticyclonic situation was present). According to those relevant features a simple diffusion model has been developed for short duration releases at local scale. Finally, the analysis and elaboration of the data, collected on site by a meteorological automatic station, allowed the extension of the model to prolonged releases

Post accidental small breaks analysis

International Nuclear Information System (INIS)

Depond, G.; Gandrille, J.

1980-04-01

EDF ordered to FRAMATOME by 1977 to complete post accidental long term studies on 'First Contrat-Programme' reactors, in order to demonstrate the safety criteria long term compliance, to get information on NSSS behaviour and to improve the post accidental procedures. Convenient analytical models were needed and EDF and FRAMATOME respectively developped the AXEL and FRARELAP codes. The main results of these studies is that for the smallest breaks, it is possible to manually undertake cooling and pressure reducing actions by dumping the steam generators secondary side in order to meet the RHR operating specifications and perform long term cooling through this system. A specific small breaks procedure was written on this basis. The EDF and FRAMATOME codes are continuously improved; the results of a French set of separate effects experiments will be incorporated as well as integral system verification

HABIT, Toxic and Radioactive Release Hazards in Reactor Control Room

International Nuclear Information System (INIS)

Stage, S.A.

2005-01-01

1 - Description of program or function: HABIT is a package of computer codes designed to be used for the evaluation of control room habitability in the event of an accidental release of toxic chemicals or radioactive materials. 2 - Methods: Given information about the design of a nuclear power plant, a scenario for the release of toxic or radionuclides, and information about the air flows and protection systems of the control room, HABIT can be used to estimate the chemical exposure or radiological dose to control room personnel

The release of lindane from contaminated building materials

OpenAIRE

Volchek, Konstantin; Thouin, Geneviève; Kuang, Wenxing; Li, Ken; Tezel, F. Handan; Brown, Carl E.

2014-01-01

The release of the organochlorine pesticide lindane (γ-hexachlorocyclohexane) from several types of contaminated building materials was studied to assess inhalation hazard and decontamination requirements in response to accidental and/or intentional spills. The materials included glass, polypropylene carpet, latex-painted drywall, ceramic tiles, vinyl floor tiles, and gypsum ceiling tiles. For each surface concentration, an equilibrium concentration was determined in the vapour phase of the s...

Causes of accidental childhood deaths in China in 2010

DEFF Research Database (Denmark)

Chan, Kit Yee; Yu, Xin-Wei; Lu, Jia-Peng

2015-01-01

-4 years in China, of which 31 633 (10.1%) were accidental. Accidental deaths contributed 7240 (4.0%) of all deaths in neonatal period, 8838 (10.5%) among all post-neonatal infant deaths, and 15 554 (31.7%) among children with 1-4 years of age. Among four tested models, the most predictive was used...

Doctor Ward's Accidental Terrarium.

Science.gov (United States)

Hershey, David R.

1996-01-01

Presents the story of the accidental invention of the Wardian case, or terrarium, by Nathaniel Bagshaw Ward. Advocates the use of this story in teaching precollege biology as an illustration of how a chance event can lead to a major scientific advancement and as an example of the common occurrence of multiple discovery in botany. Contains 34…

TRADOS - an air trajectory dose model for long range transport of radioactive release to the atmosphere

International Nuclear Information System (INIS)

Rossi, J.; Valkama, I.

1985-01-01

A model for estimating radiation doses resulting from long range atmospheric transport of released radionuclides in accidents is precented. The model (TRADOS) is able to treat changing diffusion conditions. For example the plume can be exposed to temporary rain, changes in turbulence and mixing depth. This can result in considerable changes in individual doses. The method is applied to an example trajectory and the doses caused by a serious reactor accident are calculated

Numerical methods of estimating the dispersion of radionuclides in atmosphere

International Nuclear Information System (INIS)

Vladu, Mihaela; Ghitulescu, Alina; Popescu, Gheorghe; Piciorea, Iuliana

2007-01-01

depending on the source configuration and meteorological conditions. In case of accidental situations, it would be necessary to examine the local atmospheric conditions and the range of impact around a nuclear power plant. In case that wind direction, at emission height, is not available by metering, it must be calculated on the basis of wind speed measured at 10 m height from the ground. The spatial and temporal dispersion of radioactive substances released from a nuclear facility is established through three methods of wind speed evaluation (transport) and through atmosphere turbulence movement (diffusion). The transportation process determines the direction followed by radioactive plumage and the time necessary for the transport up to a given location. (authors)

A guide to TIRION 4 - a computer code for calculating the consequences of releasing radioactive material to the atmosphere

International Nuclear Information System (INIS)

Fryer, L.S.

1978-12-01

TIRION 4 is the most recent program in a series designed to calculate the consequences of releasing radioactive material to the atmosphere. A brief description of the models used in the program and full details of the various control cards necessary to run TIRION 4 are given. (author)

Observaciones sobre accidentes de trabajo y enfermedades profesionales

Directory of Open Access Journals (Sweden)

Guillermo Sarmiento López

1948-03-01

Full Text Available En los tiempos antiguos no existía ley ni disposición alguna de carácter social que favoreciera a los trabajadores incapacitados por enfermedad o por accidente, por tanto, eran tratados como esclavos o considerados como animales. Los accidentes de trabajo y las enfermedades profesionales eran casi desconocidas antes de la introducción de la maquinaria en la industria, por lo cual no existía el derecho a indemnización por concepto de daños que sufriera el trabajador en el desempeño de sus labores. Solamente se conocen los edictos de Rotari (año 645 de la éra cristiana lanzados en Italia con el fin de reparar los accidentes de los obreros de la construcción y después, en la época del Renacimiento, algunas publicaciones que hablan de ciertas enfermedades de los trabajadores (Ellemborg 1473, Paracelso 1493-1541. Ya en la edad media la industria comenzó a tomar cierta importancia y dada la escasez de brazos, se vio obligado el patrón por fuerza de las circunstancias a prestar ayuda económica a los trabajadores incapacitados por una u otra causa. Los accidentes sucedidos en las industrias no se consideraban como de trabajo, por no conocerse el peligro que envolvía el empleo de la maqumana. En el siglo XVII y a principios del XVIII un médico italiano, Ramazzini habla del perjuicio que ocasionan ciertos trabajos en el organismo del individuo, produciendo alteraciones anatómicas y funcionales. Solamente a fines del siglo XVIII y a principios del XIX con la producción en masa, con el aumento del número de obreros y con la falta de protección, empezaron los accidentes de trabajo a hacerse notorios.

Population dose estimation from a hypothetical release of 2.4 x 106 curies of noble gases and 1 x 104 curies of 131I at the Three Mile Island Nuclear Station, Unit 2

International Nuclear Information System (INIS)

Berger, C.D.; Lane, B.H.; Cotter, S.J.; Miller, C.W.; Glandon, S.R.

1981-09-01

Beginning on March 28, 1979, a sequence of events occurred at the Three Mile Island Nuclear Station Unit 2 (TMINS-2) nuclear power reactor which resulted in the accidental release of approximately 2.4 x 10 6 Ci of noble gases and 13 to 15 Ci 131 I. A comprehensive study of this incident has been reported by the President's Commission on the Accident at Three Mile Island. As part of this study, the Technical Assessment Task Group for the Commission addressed a series of alternative event scenarios, including the potential for a higher release of 131 I. As a continuation of this task, this report presents the estimated collective dose to the population within 50 miles of TMINS-2 from a hypothetical release of 2.4 x 10 6 Ci of noble gases and 1 x 10 4 Ci 131 I by the methodology of atmospheric dispersion modeling and population dose estimation through the inhalation, ingestion and immersion exposure pathways

Accidentes de trabajo fatales y violencia interpersonal en Brasil, 2000-2010

Directory of Open Access Journals (Sweden)

Vilma Sousa Santana

2013-01-01

Full Text Available En el presente estudio se estima la mortalidad proporcional por accidentes de trabajo provocados por violencia interpersonal en Brasil, entre 2000 y 2010. Se analizaron los datos del Sistema de Información sobre Mortalidad, basados en los informes estadísti- cos de defunción del Ministerio de Salud de Brasil, los cuales incluyen un campo para el registro de accidentes de trabajo que debe ser completado en toda defunción por causas externas. Se identificaron 1.368.732 casos de defunciones por causas externas, 31.576 (2,3% por accidentes de trabajo y solo 226 (0,02% por accidentes de trabajo con violen- cia interpersonal. Cerca del 80% de los informes estadísticos de defunción no tenían el campo “accidente de trabajo” completado. La mayor cantidad de casos ocurrió entre hom- bres (94,3% de 25-34 años, con nivel de escolaridad medio, ubicados en la región sudeste y noreste, que trabajan principalmente en la producción de bienes y servicios industriales y la actividad agropecuaria. La mayoría de los casos fueron causados por armas de fuego, seguidos por armas blancas, con un aumento relativo de estos últimos en el período estu- diado. Los resultados sugieren un gran subregistro de diagnósticos que reconocen la rela- ción con el trabajo. Se hace necesaria una mejor capacitación en el llenado de los informes estadísticos, así como estudios que cuantifiquen el subregistro de accidentes de trabajo y accidentes de trabajo con violencia interpersonal.

Effects of building structures on radiation doses from routine releases of radionuclides to the atmosphere

International Nuclear Information System (INIS)

Kocher, D.C.

1978-01-01

Realistic assessments of radiation doses to the population from routine releases of radionuclides to the atmosphere require consideration of man's largely indoor environment. The effect of a building structure on radiation doses is described quantitatively by a dose reduction factor, which is the ratio of the dose to a reference individual inside a structure to the corresponding dose with no structure present. We have implemented models to estimate dose reduction factors for internal dose from inhaled radionuclides and for external photon dose from airborne and surface-deposited radionuclides. The models are particularly useful in radiological assessment applications, since dose reduction factors may readily be estimated for arbitrary mixtures and concentrations of radionuclides in the atmosphere and on the ground. The model for inhalation dose reduction factors accounts for radioactive decay, air ventilation into and out of the structure, and deposition of radionuclides on inside surfaces of the structure. External dose reduction factors are estimated using the point-kernel integration method including consideration of buildup in air and the walls of the building. The potential importance of deposition of radionuclides on inside surfaces of a structure on both inhalation and external dose reduction factors has been demonstrated. Model formulation and the assumptions used in the calculations are discussed. Results of model-parameter sensitivity studies and estimates of dose reduction factors for radionuclides occurring in routine releases from an LWR fuel reprocessing plant are presented. (author)

The stability of CaS in circulating fluidized bed boiler residue and the possible release of H2S gas to the atmosphere

International Nuclear Information System (INIS)

Mattisson, T.; Lyngfelt, A.

1995-01-01

During the combustion of coal, SO 2 is released to the atmosphere. Because of environmental concerns with acid rain, the capture of SO 2 is an important issue. In fluidized bed combustion SO 2 is captured in-situ by limestone or dolomite to form CaSO 4 . This product is stable and can be disposed of or reused as gypsum. In order to capture the sulphur as CaSO 4 oxidizing conditions are necessary. In a fluidized bed boiler (FBB) CaS may form in regions with reducing conditions, and FBB ashes sampled under irregular operating conditions may contain as much as 50 % of the captured sulphur as CaS. The stability of CaS in a landfill environment is thus very important. It is possible that the sulphide decomposes in the presence of moisture or runoff leachate with the subsequent release of H 2 S gas. This re-release of captured sulphur could have a substantial effect on the overall sulphur capture efficiency, with more sulphur released to the atmosphere than previously thought. In this study the stability of CaS in bed ashes from a 12 MW circulating FBB combusting coal has been investigated, with focus on the release of H 2 S gas. (orig.)

Non-Darwinian evolution for the source detection of atmospheric releases

Science.gov (United States)

Cervone, Guido; Franzese, Pasquale

2011-08-01

A non-Darwinian evolutionary algorithm is presented as search engine to identify the characteristics of a source of atmospheric pollutants, given a set of concentration measurements. The algorithm drives iteratively a forward dispersion model from tentative sources toward the real source. The solutions of non-Darwinian evolution processes are not generated through pseudo-random operators, unlike traditional evolutionary algorithms, but through a reasoning process based on machine learning rule generation and instantiation. The new algorithm is tested with both a synthetic case and with the Prairie Grass field experiment. To further test the capabilities of the algorithm to work in real-world scenarios, the source identification of all Prairie Grass releases was performed with a decreasing number of sensor measurements, and a relationship is found between the precision of the solution, the number of sensors available, and the levels of concentration measured by the sensors. The proposed methodology can be used for a variety of optimization problems, and is particularly suited for problems where the operations needed for evaluating new candidate solutions are computationally expensive.

Insect wings as retrospective/accidental/forensic dosimeters: An optically stimulated luminescence investigation

International Nuclear Information System (INIS)

Kazakis, Nikolaos A.; Tsetine, Anastasia Th.; Kitis, George; Tsirliganis, Nestor C.

2016-01-01

Estimation of the radiation released during nuclear accidents or radiological terrorist events is imperative for the prediction of health effects following such an exposure. In addition, in several cases there is a need to identify the prior presence of radioactive materials at buildings or sites (nuclear forensics). To this direction, several materials have been the research object of numerous studies the last decade in an attempt to identify potentially new retrospective/accidental/forensic dosimeters. However, the studies targeting biological materials are limited and their majority is mainly focused on the luminescence behavior of human biological material. Consequently, the use of such materials in retrospective dosimetry presumes the exposure of humans in the radiation field. The present work constitutes the first attempt to seek non-human biological materials, which can be found in nature in abundance or in/on other living organisms. To this end, the present work investigates the basic optically stimulated luminescence behavior of insect wings, which exhibit several advantages compared to other materials. Insects are ubiquitous, have a short life expectancy and exhibit a low decomposition rate after their death. Findings of the present study are encouraging towards the potential use of insects' wings at retrospective/accidental/forensic dosimetry, since they exhibit linear OSL response over a wide dose range and imperceptible loss of signal several days after their irradiation when they are kept in dark. On the other hand, the calculated lower detection limit is not low enough to allow their use as emergency dosimeters when individuals are exposed to non-lethal doses. In addition, wings exhibit strong optical fading when they are exposed to daylight and thus special care should be taken during the sampling procedure in order to use the wings as accidental/forensic dosimeters, by seeking (dead) insects in dark places, such as behind furniture, equipment or in

Mobility of accidentally released radiocesium in a 'soil-water' system: looking at Fukushima from Chernobyl perspective - Mobility and bioavailability of radiocesium of accidental origin: looking at Fukushima from Chernobyl perspective

Energy Technology Data Exchange (ETDEWEB)

Konoplev, Alexei; Nanba, Kenji; Takase, Tsugiko; Zheleznyak, Mark [Institute of Environmental Radioactivity, Fukushima University, 1 Kanayagawa, Fukushima 960-1296 (Japan); Onda, Yuichi; Wakiyama, Yoshifumi [Center for Research in Isotopes and Environmental Dynamics, University of Tsukuba, Tsukuba 305-8572 (Japan); Yoshimura, Kazuya [Sector of Fukushima Research and Development, Japan Atomic Energy Agency, Tokyo 100-8577 (Japan)

2014-07-01

Mobility and bioavailability of radiocesium of accidental origin is governed by the ratio of radiocesium chemical forms in fallout and site-specific environmental characteristics determining the rates of leaching, fixation/remobilization, as well as sorption-desorption of the mobile fraction (its solid-liquid distribution). When the Chernobyl accident occurred, fuel particles were released which determined the two main features of the Chernobyl-origin radiocesium behavior: a) the initial mobility and availability of radiocesium in the near field was lower that for similar conditions in case of the global fallout, the Kyshtym accident and application of isotopes in the form of solutions; b) deposition of fuel particles on the underlying surface, primarily in the near field, led to strong dependence of the radiocesium initial mobility on the distance to the damaged reactor. In the case of the Fukushima accident there are no grounds to anticipate a dependence of the initial mobility of deposited radiocesium on the distance to the nuclear power plant, i.e. the initial chemical forms of radiocesium can probably be taken to be identical on all parts of the trail. A conceptual model was proposed for the key transformation processes of radiocesium speciation in soil and water bodies. The model includes the processes of radiocesium leaching from deposited particles, sorption-desorption by the ion-exchange mechanism, fixation and remobilization. The uncertainty associated with estimates and predictions of radionuclides behavior in the natural environmental media can be significantly reduced through the use of the exchangeable distribution coefficient K{sub dex} instead of the total K{sub dtot}. A method for parameterization of the wash-off coefficients using hydrological characteristics of the run-off has been proposed, which enables the experimental characteristics obtained in Chernobyl to be used for prediction purposes on Fukushima territories. A model has been proposed

Dose-to-man studies

International Nuclear Information System (INIS)

Anon.

1976-01-01

Dose-to-Man Studies focused on developing computer data handling and computer modules which permit easy, rapid assessment of the dose to southeastern United States populations from routine or accidental releases of radionuclides to atmospheric and stream systems

Resuspension parameters for TRAC dispersion model

International Nuclear Information System (INIS)

Langer, G.

1987-01-01

Resuspension factors for the wind erosion of soil contaminated with plutonium are necessary to run the Rocky Flats Plant Terrain Responsive Atmospheric Code (TRAC). The model predicts the dispersion and resulting population dose due to accidental plutonium releases

Expedition surveys of the sea water and atmospheric air radioactive contamination in the Russian Far Eastern coastal areas and in the North- Western Pacific in connection with accident at the 'Fukushima-1' NPP

Energy Technology Data Exchange (ETDEWEB)

Nikitin, Aleksandr; Shershakov, Viacheslav; Artemev, Georgii [Research and Production Association ' Typhoon' (RPA ' Typhoon' ), Obninsk, Kaluga Region (Russian Federation); Ramzaev, Valery [Ramzaev Saint-Petersburg Research Institute of Radiation Hygiene, Saint-Petersburg (Russian Federation); Osokin, Vladimir [V.G.Khlopin Radium institute, Saint-Petersburg (Russian Federation); Sevastianov, Aleksandr [Far Eastern Regional Hydrometeorological Research Institute, Vladivostok (Russian Federation)

2014-07-01

of these measurements are presented and discussed in the paper).Laboratory radionuclide analysis of the sea water samples included more precise definition of gamma-emitters content and radiochemical determination of {sup 90}Sr, {sup 239,240}Pu and tritium. The data received allowed to conclude that the levels of contamination by radioactive products of accidental releases and discharges at 'Fukushima-1' NPP observed in investigated water areas near the Russian Federation coast of the Sea of Japan and of the Kurile-Kamchatka region of the Pacific ocean have no hazard. However, these expedition surveys indicated that wide region of the North-Western Pacific water area, located in zone of the Kuroshio current at a distance from 400 to 800 km to the east from the 'Fukushima-1' NPP, contaminated by radioactive products of accidental releases and discharges. Here the {sup 137}Cs concentration in sea water reached 30 Bq/m{sup 3} in April-May, 2011, which approximately 20 times exceed pre-accidental level. The results of 2011-2012 surveys allows to conclude that distinct penetration take place of the 'Fukushima-1' accidental products in a deep water layers, till 200 m depth at least. Correct estimation of current and potential consequences of the 'Fukushima-1' accident for the Far-Eastern water areas requires in future more detailed studies of transport with marine currents (with Kuroshio current especially) of products of accidental releases and discharges at 'Fukushima-1' NPP. (authors)

PABLM, Doses from Radioactive Releases to Atmosphere and Food Chain

International Nuclear Information System (INIS)

Napier, B.A.; Kennedy, W.E. Jr.; Soldat, J.K.

1983-01-01

1 - Description of problem or function: PABLM calculates internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides after the releases have ended. Radioactive decay is considered during the release, after deposition, and during holdup of food after harvest. The radiation dose models consider exposure to radionuclides deposited on the ground or crops from contaminated air or irrigation water, radionuclides in contaminated drinking water, aquatic foods raised in contaminated water, and radionuclides in bodies of water and sediments where people might fish, boat, or swim. For vegetation, the radiation dose model considers both direct deposition and uptake through roots. Doses may be calculated for either a maximum-exposed individual or for a population group. The program is designed to calculate accumulated radiation doses from the chronic ingestion of food products that contain radionuclides and doses from the external exposure to radionuclides in the environment. A first-year committed dose is calculated as well as an integrated dose for a selected number of years. 2 - Method of solution: A chain decay scheme including branching for transitions to and from isomeric states is used for radioactive decay. The equations for calculating internal radiation doses are derived from those given by the International Commission on Radio- logical Protection (ICRP) for body burdens and the maximum possible concentration (MPC) for each radionuclide. These doses are calculated as a function of radionuclide concentration in food products, ingestion rates, and a radionuclide-specific dose- commitment factor. Radiation doses from external exposure to contaminated water and soil are calculated using the basic assumption

Fluxes of Ethanol Between the Atmosphere and Oceanic Surface Waters; Implications for the Fate of Biofuel Ethanol Released into the Environment

Science.gov (United States)

Avery, G. B., Jr.; Shimizu, M. S.; Willey, J. D.; Mead, R. N.; Skrabal, S. A.; Kieber, R. J.; Lathrop, T. E.; Felix, J. D. D.

2017-12-01

The use of ethanol as a transportation fuel has increased significantly during the past decade in the US. Some ethanol escapes the combustion process in internal combustion engines resulting in its release to the atmosphere. Ethanol can be oxidized photochemically to acetaldehyde and then converted to peroxyacetyl nitrate contributing to air pollution. Therefore it is important to determine the fate ethanol released to the atmosphere. Because of its high water solubility the oceans may act as a sink for ethanol depending on its state of saturation with respect to the gas phase. The purpose of the current study was to determine the relative saturation of oceanic surface waters by making simultaneous measurements of gas phase and surface water concentrations. Data were obtained from four separate cruises ranging from estuarine to open ocean locations in the coast of North Carolina, USA. The majority of estuarine sites were under saturated in ethanol with respect to the gas phase (11-50% saturated) representing a potential sink. Coastal surface waters tended to be supersaturated (135 - 317%) representing a net flux of ethanol to the atmosphere. Open ocean samples were generally at saturation or slightly below saturation (76-99%) indicating equilibrium between the gas and aqueous phases. The results of this study underscore to variable role the oceans play in mitigating the increases in atmospheric ethanol from increased biofuel usage and their impact on air quality.

Consideration for modelling studies of migration of accidentally released radionuclides in a river watershed

International Nuclear Information System (INIS)

Matsunaga, Takeshi; Tsuduki, Katsunori; Yanase, Nobuyuki; Hanzawa, Yukiko; Ueno, Takashi

2004-01-01

Concerning radionuclides that might be released in an event of an accident from a nuclear facility, much attention has been paid to the migration pathways including the atmospheric deposition and subsequent inflow to surface water bodies since the Chernobyl nuclear accident in 1986. In European countries, computer-coded systems for predicting the migration including those pathways and providing scientific supports for decision makers to manage the contamination have been developed. This report is a summary of presentations and discussion made at the occasion of the visit of Dr. Monte in order to have directions related to the current subject of research, development of a mathematical model of the behavior of radionuclides in a river watershed. Those presentations and discussions were made at JAERI and also at prominent universities and institutes of Japan involved in this study field. As a result of these discussions, distinct advantages and key issues in use of a mathematical model for prediction of the migration of radionuclides in a river watershed have been identified and analyzed. It was confirmed that the use of mathematical modeling has distinct advantages. Re-arrangement of the existing experimental knowledge on the environment in an ordered way according to a theory (a mathematical model) will lead to a new angle to consider a problem in that environment, despite several gaps in the data array. A model to assess the radionuclide behaviour in contaminated aquatic ecosystems is a basis of decision analysis tools for helping decision-makers to select the most appropriate intervention strategies for the ecosystems. Practical use of a mathematical model and continuous effort in its validation were recognized as crucial. (author)

Demonstration of the astral post accidental code

International Nuclear Information System (INIS)

Calmon, P.; Mourlon, C.

2003-01-01

. The results proposed by ASTRAL can in turn be saved in its database, on the user's request, in order to be processed by other tools such as Geographical Information Systems, which enable spatial analysis and map production. Such maps are very helpful in crisis situations to decision makers since by answering to questions of a 'where?' type, at a given time, they complete the information delivered by ASTRAL, which answers to questions of a 'when?' type, at a given site. This is why a link to ASTRAL has been constructed in CARTINFO, an IRSN tool dedicated to mapping results for its Crisis Technical Center. Thus the CONRAD, ASTRAL and CARTINFO softwares constitute a chain for IRSN's Crisis Technical Center, calculating transfers through the environment and consequences of an atmospheric accidental radionuclide release. The development of this version started in 1999 and has been subject to a quality assurance program. The identified customers and users have been associated in a control committee expressing needs, validating choices and checking the good progress of the project. The programming is currently being validated by test scenarios that check the equations, parameters, functionalities and navigation through the screens. The technology and architecture chosen for the second version of ASTRAL are different from the previous ones. It now uses an internet technology and is of a three-third type, the software requiring an Oracle database, a Microsoft web server and a consultation station. These choices offer important advantages: the spreading and maintenance of the tool are very easy. In fact, once the server and the database have been installed an a network, the users only need a web browser to run the code. The initial installation and the updating are thus no more to be made an every user station, but only on the server and/or the database; the code may be installed on a portable computer, which hosts the database, the internet server and the web browser. This

Reporting a sudden death due to accidental gasoline inhalation.

Science.gov (United States)

Martínez, María Antonia; Ballesteros, Salomé; Alcaraz, Rafael

2012-02-10

The investigation of uncertain fatalities requires accurate determination of the cause of death, with assessment of all factors that may have contributed to it. Gasoline is a complex and highly variable mixture of aliphatic and aromatic hydrocarbons that can lead to cardiac arrhythmias due to sensitization of the myocardium to catecholamines or acts as a simple asphyxiant if the vapors displace sufficient oxygen from the breathing atmosphere. This work describes a sudden occupational fatality involving gasoline. The importance of this petroleum distillate detection and its quantitative toxicological significance is discussed using a validated analytical method. A 51 year-old Caucasian healthy man without significant medical history was supervising the repairs of the telephone lines in a manhole near to a gas station. He died suddenly after inhaling gasoline vapors from an accidental leak. Extensive blistering and peeling of skin were observed on the skin of the face, neck, anterior chest, upper and lower extremities, and back. The internal examination showed a strong odor of gasoline, specially detected in the respiratory tract. The toxicological screening and quantitation of gasoline was performed by means of gas chromatography with flame ionization detector and confirmation was performed using gas chromatography-mass spectrometry. Disposition of gasoline in different tissues was as follows: heart blood, 35.7 mg/L; urine, not detected; vitreous humor, 1.9 mg/L; liver, 194.7 mg/kg; lung, 147.6 mg/kg; and gastric content, 116,6 mg/L (2.7 mg total). Based upon the toxicological data along with the autopsy findings, the cause of death was determined to be gasoline poisoning and the manner of death was accidental. We would like to alert on the importance of testing for gasoline, and in general for volatile hydrocarbons, in work-related sudden deaths involving inhalation of hydrocarbon vapors and/or exhaust fumes. Copyright © 2011 Elsevier Ireland Ltd. All rights

Effects of indoor residence on radiation doses from routine releases of radionuclides to the atmosphere

International Nuclear Information System (INIS)

Kocher, D.C.

1980-01-01

Dose reduction factors from indoor residence during routine releases of radionuclides to the atmosphere were studied using models that are suitable for application to arbitrary source terms. Dose reduction factors for internal exposure to inhaled radionuclides account for air ventilation and deposition on inside building surfaces. Estimated internal dose reduction factors are approx. 0.2 to 0.8 for particulates and 0.07 to 0.4 for radioiodine. Dose reduction factors for external photon exposure from airborne and surface-deposited sources are based on the point-kernel integration method. Values for source terms from a fuel reprocessing plant and a hypothetical reactor accident are within a factor of 2 of the value 0.5 adopted by the US Nuclear Regulatory Commission (NRC) for population dose assessments. For the release at Three Mile Island nuclear station, however, the external dose reduction factor may be an order of magnitude less than the value adopted by the NRC

HTO and OBT activity concentrations in soil at the historical atmospheric HT release site (Chalk River Laboratories)

International Nuclear Information System (INIS)

Kim, S.B.; Bredlaw, M.; Korolevych, V.Y.

2012-01-01

Tritium is routinely released by the Chalk River Laboratories (CRL) nuclear facilities. Three International HT release experiments have been conducted at the CRL site in the past. The site has not been disturbed since the last historical atmospheric testing in 1994 and presents an opportunity to assess the retention of tritium in soil. This study is devoted to the measurement of HTO and OBT activity concentration profiles in the subsurface 25 cm of soil. In terms of soil HTO, there is no evidence from the past HT release experiments that HTO was retained. The HTO activity concentration in the soil pore water appears similar to concentrations found in background areas in Ontario. In contrast, OBT activity concentrations in soil at the same site were significantly higher than HTO activity concentrations in soil. Elevated OBT appears to reside in the top layer of the soil (0–5 cm). In addition, OBT activity concentrations in the top soil layer did not fluctuate much with season, again, quite in contrast with soil HTO. This result suggests that OBT activity concentrations retained the signature of the historical tritium releases. Highlights: ► At the historical HT release site, HTO and OBT activity concentrations in soil depths were investigated. ► Most organically bound tritium exists in the top layer of the soil. ► The results indicated that OBT activity concentrations can be reflective of historical tritium releases into the environment.

Compliance of the Vaalputs national radioactive waste disposal facility to a frequency-magnitude release criterion as required for licensing

International Nuclear Information System (INIS)

Adrian, H.W.W.; Gerber, H.H.; Kruger, J.; Weygand, J.

1986-01-01

Accidental releases of radioactivity from the Vaalputs nuclear waste repository have been quantified and release frequencies have been attached to a number of accident scenarios of human or natural origin. These have then been compared to a frequency-magnitude release criterion according to South African licensing requirements. It was shown that the criterion was applicable in three release bands. In two of these the criterion was met by some orders of magnitude. In the third band the permitted release frequency was a factor 55 below the limit in spite of pessimistic release assumptions

Local scale atmospheric diffusion at a coastal site in the presence of breeze effect (Phase I and II: data collection at a coastal site and off shore)

International Nuclear Information System (INIS)

Cagnetti, P.; Ferrara, V.; Pellegrini, A.

1985-01-01

The aim of this contract is the characterization, from the thermal and anemological point of view of the lower layers of the atmosphere at a coastal site, affected by breeze circulation. Data are utilized to set up diffusion models for accidental releases of airborne materials, both of short and prolonged duration. Five inland meteorological campaigns, starting from Jan. 82 (Jan., Apr., Jul., Oct. 1982, Jan. 1983), have been carried out; an appropriate extension of the contract allowed the execution of two more campaigns in the open sea (Apr., Jul. 1983), utilizing the oceanographic ship ''Bannock'' kindly supplied by CNR. The analysis of the data showed the development of a well defined IBL during on-shore flow only in Spring and Summer, while an inversion layer was detectable aloft independently of the season (provided that an anticyclonic situation was present). According to those relevant features a simple diffusion model has been developed for short duration releases at local scale. Finally, the analysis and elaboration of the data, collected on site by a meteorological automatic station, allowed the extension of the model to prolonged releases

The contribution of the CSNI Principal Working Group on Confinement of Accidental Radioactive Releases to the technical consensus and spreading of knowledge on severe accidents

International Nuclear Information System (INIS)

De Boeck, B.; Royen, J.

1999-01-01

The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) is an international committee made up of scientists and engineers. It was set up 1973 to develop and co-ordinate the activities of the NEA concerning the technical aspects of the design, construction and operation of nuclear installations insofar as they affect the safety of such installations. The Committee's purpose is to foster international cooperation in nuclear safety amongst the Member countries. Five Principal Working Groups (PWG) operate under the leadership of CSNI. PWG4 is named 'Confinement of Accidental Radioactive Releases' and its main activities are State of the Art Reports, International Standard Problem exercises, Specialist Meetings and Technical Opinion Papers. Together with other groups of experts involved in severe accident work, PWG4 has strongly contributed to the understanding of phenomena and the development of the knowledge base in that area, to the resolution of technical issues, and to the dissemination of the results. Taking examples from the products of the work of PWG4, the paper shows how this working group fosters international co-operation in the area of severe accidents and their management, and contributes to the development of a technical consensus. (author)

A real-time PUFF-model for accidental releases in complex terrain

International Nuclear Information System (INIS)

Thykier-Nielsen, S.; Mikkelsen, T.; Larsen, S.E.; Troen, I.; Baas, A.F. de; Kamada, R.; Skupniewicz, C.; Schacher, G.

1990-01-01

LINCOM-RIMPUFF, a combined flow/puff model, was developed at Riso National Laboratory for the Vandenberg AFB Meteorology and Plume Dispersion Handbook and is suitable as is for real time response to emergency spills and vents of gases and radionuclides. LINCOM is a linear, diagnostic, spectral, potential flow model which extends the Jackson-Hunt theory of non-hydrostatic, adiabatic wind flow over hills to the mesoscale domain. It is embedded in a weighted objective analysis (WOA) of real-time Vandenberg tower winds and may be used in ultra-high speed lookup table mode. The mesoscale dispersion model RIMPUFF is a flexible Gaussian puff model equipped with computer-time effective features for terrain and stability-dependent dispersion parameterization, plume rise formulas, inversion and ground-level reflection capabilities and wet/dry (source) depletion. It can treat plume bifurcation in complex terrain by using a puff-splitting scheme. It allows the flow-model to compute the larger scale wind field, reserving turbulent diffusion calculations for the sub-grid scale. In diagnostic mode toxic exposure are well assessed via the release of a single initial puff. With optimization, processing time for RIMPUFF should be on the order of 2 CPU minutes or less on a PC-system. In prognostic mode with shifting winds, multiple puff releases may become necessary, thereby lengthening processing time

Experimental study of the consequences of accidental sodium release in the form of peroxide aerosols on the tomato and the lettuce

International Nuclear Information System (INIS)

Camus, H.; Delmas, J.; Grauby, A.; Disdier, R.

1977-01-01

Industrial development of sodium cooled breeder reactors have lead to the study of consequences of accidents occuring in the cooling circuit. The effects on crops when aerosols are released in the atmosphere can be determined after a certain amount of molten sodium (stable element 23 Na) is brought into contact with the open air. Experiments are performed in a 'Phytotron' equipment on lettuces and tomatoes in dry atmosphere at two different moments during the growing process. The aerosol studied has a high content of sodium peroxide and the ground deposit varied between 17 and 450 mg/m 2 sodium equivalent. (Concentration at distances of 800 m and 1500 m calculated for a theoretical fire involving 10 tons of sodium). Necrosis, visible only with a microscope, were reported when deposits in sodium equivalent were under 300 mg/m 2 . Leaves were destroyed if necrosis were numerous (deposit above 300 mg/m 2 ). Tomatoes, and fruits in particular, were found to be more resistant than lettuces. Sodium embedded in dead cells does not migrate in the plant and does not disturb the plants physiological equilibrium. New sprouts have normal sodium percentage. The consequences are essentially burns of which the extent is more or less high depending on the deposits and the kind of species involved [fr

ARAC update: 1979

International Nuclear Information System (INIS)

Dickerson, M.H.; Knox, J.B.; Orphan, R.C.

1979-01-01

The Atmospheric Release Advisory Capability service (ARAC), has three main functions: to provide support to designated Department of Energy facilities during an accidental atmospheric release of radionuclides; to support the DOE Emergency Response Team in the event of potential or actual releases of radionuclides; and to provide the Federal Aviation Administration with dose assessments whenever aircraft could possibly intercept a nuclear debris cloud from a Chinese atmospheric nuclear test. A computer network linking the central facility at Livermore with the Air Force Global Weather Central and the remote DOE sites allows rapid data transmission and analysis. Facilities are described, and tests and responses of the ARAC system and models from May 1974 to April 24, 1979 are outlined

On the requirements to establish a European radiological preparedness for malicious airborne dispersion scenarios

DEFF Research Database (Denmark)

Andersson, Kasper Grann; Astrup, Poul; Roos, Per

2011-01-01

European computerised decision support systems are currently targeted for large accidental atmospheric contaminant releases from nuclear installations. To make these systems applicable also for malicious dispersion events, such as ‘dirty bomb’ blasts, a series of modifications and extensions are ...

Toxic chemical considerations for tank farm releases. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Van Keuren, J.C.

1995-11-01

This document provides a method of determining the toxicological consequences of accidental releases from Hanford Tank Farms. A determination was made of the most restrictive toxic chemicals that are expected to be present in the tanks. Concentrations were estimated based on the maximum sample data for each analyte in all the tanks in the composite. Composite evaluated were liquids and solids from single shell tanks, double shell tanks, flammable gas watch list tanks, as well as all solids, all liquids, head space gases, and 241-C-106 solids. A sum of fractions of the health effects was computed for each composite for unit releases based emergency response planning guidelines (ERPGs). Where ERPGs were not available for chemical compounds of interest, surrogate guidelines were established. The calculation method in this report can be applied to actual release scenarios by multiplying the sum of fractions by the release rate for continuous releases, or the release amount for puff releases. Risk guidelines are met if the product is less than for equal to one.

Toxic chemical considerations for tank farm releases. Revision 1

International Nuclear Information System (INIS)

Van Keuren, J.C.

1995-11-01

This document provides a method of determining the toxicological consequences of accidental releases from Hanford Tank Farms. A determination was made of the most restrictive toxic chemicals that are expected to be present in the tanks. Concentrations were estimated based on the maximum sample data for each analyte in all the tanks in the composite. Composite evaluated were liquids and solids from single shell tanks, double shell tanks, flammable gas watch list tanks, as well as all solids, all liquids, head space gases, and 241-C-106 solids. A sum of fractions of the health effects was computed for each composite for unit releases based emergency response planning guidelines (ERPGs). Where ERPGs were not available for chemical compounds of interest, surrogate guidelines were established. The calculation method in this report can be applied to actual release scenarios by multiplying the sum of fractions by the release rate for continuous releases, or the release amount for puff releases. Risk guidelines are met if the product is less than for equal to one

Radiological Emergency Preparedness after the Early Phase of an Accident : Focusing on an Air Contamination Event

International Nuclear Information System (INIS)

Jeong, Hyo Joon; Hwang, Won Tae; Kim, Eun Han; Han, Moon Hee

2010-01-01

Toxic materials in an urban area can be caused by a variety of events, such as accidental releases on industrial complexes, accidents during the transportation of hazardous materials and intentional explosions. Most governments around the world and their citizens have become increasingly worried about intentional accidents in urban area after the 911 terrorist attack in the United States of America. Even though there have been only a few attempted uses of Radiological Dispersal Devices (RDDs), accidental releases have occurred many times at commercial nuclear power plants and nuclear waste disposal sites. When an intentional release of radioactive materials occurs in an urban area, air quality for radioactive materials in the environment is of great importance to take action for countermeasures and environmental risk assessments. Atmospheric modeling is part of the decision making tasks and that it is particularly important for emergency managers as they often need to take actions quickly on very inadequate information(1). A simple model such as HOTSPOT required wind direction and source term would be enough to support the decision making in the early phase of an accident, but more sophisticated atmospheric modeling is required to adjust decontamination area and relocation etc after the early phase of an accidental event. In this study, we assume an explosion of 137 Cs using RDDs in the metropolitan area of Soul, South Korea. California Puff Model (CALPUFF) is used to calculate an atmospheric dispersion and transport for 137 Cs. Atmospheric dispersion and quantitative radiological risk analysis for 137 Cs were performed assuming an intentional explosion in the metropolitan area of Soul, South Korea after the early phase of emergency. These kinds of atmospheric modeling and risk analysis could provide a means for decision makers to take action on important issues such as the cleanup of the contaminated area and countermeasures to protect the public caused by

Accidental Durotomy in Minimally Invasive Transforaminal Lumbar Interbody Fusion: Frequency, Risk Factors, and Management

Directory of Open Access Journals (Sweden)

Jan-Helge Klingler

2015-01-01

Full Text Available Purpose. To assess the frequency, risk factors, and management of accidental durotomy in minimally invasive transforaminal lumbar interbody fusion (MIS TLIF. Methods. This single-center study retrospectively investigates 372 patients who underwent MIS TLIF and were mobilized within 24 hours after surgery. The frequency of accidental durotomies, intraoperative closure technique, body mass index, and history of previous surgery was recorded. Results. We identified 32 accidental durotomies in 514 MIS TLIF levels (6.2%. Analysis showed a statistically significant relation of accidental durotomies to overweight patients (body mass index ≥25 kg/m2; P=0.0493. Patient age older than 65 years tended to be a positive predictor for accidental durotomies (P=0.0657. Mobilizing patients on the first postoperative day, we observed no durotomy-associated complications. Conclusions. The frequency of accidental durotomies in MIS TLIF is low, with overweight being a risk factor for accidental durotomies. The minimally invasive approach seems to minimize durotomy-associated complications (CSF leakage, pseudomeningocele because of the limited dead space in the soft tissue. Patients with accidental durotomy can usually be mobilized within 24 hours after MIS TLIF without increased risk. The minimally invasive TLIF technique might thus be beneficial in the prevention of postoperative immobilization-associated complications such as venous thromboembolism. This trial is registered with DRKS00006135.

Evaluation of three atmospheric dispersion models using tracer release experiment data

International Nuclear Information System (INIS)

Daoo, V.J.; Oza, R.B.; Pandit, G.G.; Sadasivan, S.; Venkat Raj, V.

2004-01-01

Performance of three atmospheric dispersion models viz: (1) Gaussian Plume Model (GPM), (2) Equi-Distance PUFF Model (EDPUFFM) and (3) Particle Trajectory Model (PTM) is evaluated using field data collected from a tracer (SF 6 ) release experiment. The experiment was conducted within the campus of the Bhabha Atomic Research Centre (BARC), located at Trombay, Mumbai, India. The three models used are currently in operation at the BARC. The first one is a standard, well-documented empirical model while the other two models have been developed at the Bhabha Atomic Research Centre. The PTM is a numerical model while the EDPUFFM is a hybrid model combining both the numerical and analytical techniques. The procedure for evaluation is as per the recommendations of 1980 AMS (American Meteorological Society) workshop on atmospheric dispersion models performance evaluation. In addition, linear regression analysis has also been carried out. The regression analysis reveals that on an average, the EDPUFFM and the GPM predictions are higher by a factor of about 1.5 while the PTM predictions are lower by a factor of about 4. Comparison of various performance measures reveals that the performance of the EDPUFFM is marginally better than that of the GPM while the PTM performance is comparatively poor. The uncertainty factors obtained in this study, especially for higher concentration range ( > 100 ppt) are similar to those obtained in other validation study carried out elsewhere to validate the GPM predictions. However, for lower concentration range and for the conditions after the source is switched off, all the three models perform poorly in predicting the concentration. (author)

GEWEX SRB Shortwave Release 4

Science.gov (United States)

Cox, S. J.; Stackhouse, P. W., Jr.; Mikovitz, J. C.; Zhang, T.

2017-12-01

The NASA/GEWEX Surface Radiation Budget (SRB) project produces shortwave and longwave surface and top of atmosphere radiative fluxes for the 1983-near present time period. Spatial resolution is 1 degree. The new Release 4 uses the newly processed ISCCP HXS product as its primary input for cloud and radiance data. The ninefold increase in pixel number compared to the previous ISCCP DX allows finer gradations in cloud fraction in each grid box. It will also allow higher spatial resolutions (0.5 degree) in future releases. In addition to the input data improvements, several important algorithm improvements have been made since Release 3. These include recalculated atmospheric transmissivities and reflectivities yielding a less transmissive atmosphere. The calculations also include variable aerosol composition, allowing for the use of a detailed aerosol history from the Max Planck Institut Aerosol Climatology (MAC). Ocean albedo and snow/ice albedo are also improved from Release 3. Total solar irradiance is now variable, averaging 1361 Wm-2. Water vapor is taken from ISCCP's nnHIRS product. Results from GSW Release 4 are presented and analyzed. Early comparison to surface measurements show improved agreement.

Numerical investigation of the gas concentration field during accidental release in a one vent small enclosure: effect of vent configurations

OpenAIRE

MELIDEO DANIELE; BARALDI Daniele

2016-01-01

The accumulation of a flammable cloud in an enclosure due to accidental leaks is one of the potential accident scenarios related to the indoor use of hydrogen and fuel cell technologies. Indoor accident configurations involves a wide range of scales, depending on the site and the type of hydrogen technology: a hydrogen dispenser in a warehouse (for hydrogen powered forklifts), a hydrogen powered vehicle in a garage, a fuel cell or hydrogen storage in a cabinet or in a section of a container (...

Patterns and Trends in Accidental Poisoning Deaths: Pennsylvania's Experience 1979-2014.

Directory of Open Access Journals (Sweden)

Lauren C Balmert

Full Text Available The purpose of this study was to examine county and state-level accidental poisoning mortality trends in Pennsylvania from 1979 to 2014.Crude and age-adjusted death rates were formed for age group, race, sex, and county for accidental poisonings (ICD 10 codes X40-X49 from 1979 to 2014 for ages 15+ using the Mortality and Population Data System housed at the University of Pittsburgh. Rate ratios were calculated comparing rates from 1979 to 2014, overall and by sex, age group, and race. Joinpoint regression was used to detect statistically significant changes in trends of age-adjusted mortality rates.Rate ratios for accidental poisoning mortality in Pennsylvania increased more than 14-fold from 1979 to 2014. The largest rate ratios were among 35-44 year olds, females, and White adults. The highest accidental poisoning mortality rates were found in the counties of Southwestern Pennsylvania, those surrounding Philadelphia, and those in Northeast Pennsylvania near Scranton.The patterns and locations of accidental poisoning mortality by race, sex, and age group provide direction for interventions and policy makers. In particular, this study found the highest rate ratios in PA among females, whites, and the age group 35-44.

Individual housing-based socioeconomic status predicts risk of accidental falls among adults.

Science.gov (United States)

Ryu, Euijung; Juhn, Young J; Wheeler, Philip H; Hathcock, Matthew A; Wi, Chung-Il; Olson, Janet E; Cerhan, James R; Takahashi, Paul Y

2017-07-01

Accidental falls are a major public health concern among people of all ages. Little is known about whether an individual-level housing-based socioeconomic status measure is associated with the risk of accidental falls. Among 12,286 Mayo Clinic Biobank participants residing in Olmsted County, Minnesota, subjects who experienced accidental falls between the biobank enrollment and September 2014 were identified using ICD-9 codes evaluated at emergency departments. HOUSES (HOUsing-based Index of SocioEconomic Status), a socioeconomic status measure based on individual housing features, was also calculated. Cox regression models were utilized to assess the association of the HOUSES (in quartiles) with accidental fall risk. Seven hundred eleven (5.8%) participants had at least one emergency room visit due to an accidental fall during the study period. Subjects with higher HOUSES were less likely to experience falls in a dose-response manner (hazard ratio: 0.58; 95% confidence interval: 0.44-0.76 for comparing the highest to the lowest quartile). In addition, the HOUSES was positively associated with better health behaviors, social support, and functional status. The HOUSES is inversely associated with accidental fall risk requiring emergency care in a dose-response manner. The HOUSES may capture falls-related risk factors through housing features and socioeconomic status-related psychosocial factors. Copyright © 2017 Elsevier Inc. All rights reserved.

Comparison of the COMRADEX-IV and AIRDOS-EPA methodologies for estimating the radiation dose to man from radionuclide releases to the atmosphere

International Nuclear Information System (INIS)

Miller, C.W.; Hoffman, F.O.; Dunning, D.E. Jr.

1981-01-01

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 primarily to assess routine radionuclide releases from nuclear facilities. Although a number of different calculations are performed by these codes, three calculations are in common - atmospheric dispersion, estimation of internal dose from inhalation, and estimation of external dose from immersion in air containing gamma emitting radionuclides. The models used in these calculations were examined and found, in general, to be the same. Most differences in the doses calculated by the two codes are due to differences in values chosen for input parameters and not due to model differences. A sample problem is presented for illustration

Forensic Reconstructions of Radioactive Particulate Releases at the Chernobyl and the Al Tuwaitha Nuclear Facilities

International Nuclear Information System (INIS)

Chesser, R. K.; Rogers, B. E.; Philips, C. J.

2007-01-01

Evaluating dispersion of nuclear materials released by accidental, operational, or clandestine means is important to the international community. Our research team has performed forensic reconstructions of radionuclide releases at the Chernobyl Nuclear Power Plant (ChNPP) in Ukraine and the Al Tuwaitha Nuclear Facility (ATNF) near Baghdad, Iraq. Our objectives at ChNPP were to determine the influences of extant atmospheric conditions on particle size distributions and their depositions in the near-field (less than 12 km) regions surrounding the complex. We derived mathematical models of particulate fluid-flow in varying velocity and turbulence fields to fit with 3000 geographically-referenced measurements. Conformity of predicted and empirical fallout patterns was excellent, enabling accurate reconstructions of the particle size contributions, weather conditions, and release energies from the accident. The objectives at ATNF were to evaluate means of dispersion and characterization of nuclear materials within and outside of the compound. Normal facility operations, military actions, and looting of the facility could have contributed to the release of radioactivity, but would yield quite different geographic and radionuclide profiles. Detailed gamma, alpha, and beta radiation profiles were examined for 400 geographically-referenced soil samples collected from ATNF and the villages of Ishtar and Al Ryhad. Natural uranium clusters were identified in several locations clearly showing that looting of yellowcake was the primary means of dispersion. No dispersion of nuclear materials was shown to result from military operations at the site. Our programs demonstrate the precision of geographic-based forensic reconstructions and show that forecast models are robust.(author)

Maximum permissible continuous release rates of phosphorus-32 and sulphur-35 to atmosphere in a milk producing area

Energy Technology Data Exchange (ETDEWEB)

Bryant, P M

1963-01-01

A method is given for calculating, for design purposes, the maximum permissible continuous release rates of phosphorus-32 and sulphur-35 to atmosphere with respect to milk contamination. In the absence of authoritative advice from the Medical Research Council, provisional working levels for the concentration of phosphorus-32 and sulphur-35 in milk are derived, and details are given of the agricultural assumptions involved in the calculation of the relationship between the amount of the nuclide deposited on grassland and that to be found in milk. The agricultural and meteorological conditions assumed are applicable as an annual average to England and Wales. The results (in mc/day) for phosphorus-32 and sulphur-35 for a number of stack heights and distances are shown graphically; typical values, quoted in a table, include 20 mc/day of phosphorus-32 and 30 mc/day of sulfur-35 as the maximum permissible continuous release rates with respect to ground level releases at a distance of 200 metres from pastureland.

Comportamiento de los accidentes laborales

Directory of Open Access Journals (Sweden)

Miguel Gómez Vital

1999-01-01

Full Text Available Se realiza una valoración sobre la situación de la accidentalidad en centros de trabajo de la provincia de Villa Clara de 1993 a 1997. El total de accidentes registrados fue de 12 522. Últimamente han disminuido y su índice de incidencia. En el último año se redujo el promedio de días perdidos, pero el índice de gravedad alcanzó la cifra mayor. Se insiste en el cumplimiento del programa de prevención y reducción de accidentes laborales.The situation of the occupational accidents that occurred in the province of Villa Clara from 1993 to 1997 was assessed. 12 522 accidents were registered during that periods. A decrease of these accidents and of their incidence rate has been observed lately. The average of lost days was reduced during the last year, out the severity index reached the highest figure. Emphasis is made on the importance of fulfilling the program of prevention and reduction of occupational accidents.

Fission-product release during accidents

International Nuclear Information System (INIS)

Hunt, C.E.L.; Cox, D.S.

1991-09-01

One of the aims when managing a reactor accident is to minimize the release of radioactive fission products. Release is dependent not only on the temperature, but also on the partial pressure of oxygen. Strongly oxidizing atmospheres, such as those that occurred during the Chernobyl accident, released semi-volatile elements like ruthenium, which has volatile oxides. At low temperatures, UO 2 oxidization to U 3 O 8 can result in extensive breakup of the fuel, resulting in the release of non-volatile fission products as aerosols. Under less oxidizing conditions, when hydrogen accumulates from the zirconium-water reaction, the resulting low oxygen partial pressure can significantly reduce these reactions. At TMI-2, only the noble gases and volatile fission products were released in significant quantities. A knowledge of the effect of atmosphere as well as temperature on the release of fission products from damaged reactor cores is therefore a useful, if not necessary, component of information required for accident management

A descriptive study of accidental skeletal injuries and non-accidental skeletal injuries of child maltreatment.

Science.gov (United States)

Ghanem, Maha A H; Moustafa, Tarek A; Megahed, Haidy M; Salama, Naglaa; Ghitani, Sara A

2018-02-01

Lack of awareness and recognition of child maltreatment is the major reason behind underreporting. All victims often interact with the health care system for routine or emergency care. In several research works, non-accidental fractures are the second most common injury in maltreated children and it is represented up to one-third of cases. To determine the incidence of different types of accidental and non-accidental skeletal injuries among children, estimate the severity of injuries according to the modified injury severity score and to determine the degree of fractures either closed or opened (Gustiloe-Anderson open fracture classification). Moreover, identifying fractures resulting from child abuse and neglect. This aimed for early recognition of non-accidental nature of fractures in child maltreatment that can prevent further morbidity and mortality. A descriptive study was carried out on all children (109) with skeletal injuries who were admitted to both Main Alexandria and El-Hadara Orthopedic and Traumatology University Hospitals during six months. History, physical examination and investigations were done for the patients. A detailed questionnaire was taken to diagnose child abuse and neglect. Gustiloe-Anderson open fracture classification was used to estimate the degree of open fractures. Out of 109 children, twelve cases (11%) were categorized as child maltreatment. One case was physical abuse, eight cases (7.3%) were child neglect and three cases (2.8%) were labour exploitation. Road traffic accidents (RTA) was the commonest cause of skeletal injuries followed by falling from height. Regarding falls, they included 4 cases of stair falls in neglected children and another four cases of falling from height (balcony/window). The remaining 36 cases of falls were accidental. The skeletal injuries were in the form of fractures in 99 cases, dislocation in two cases, both fracture and/or dislocation in three cases, and bone deformity from brachial plexus injury

Accidental Innovation

DEFF Research Database (Denmark)

Austin, Robert D.; Devin, Lee; Sullivan, Erin E.

2012-01-01

Historical accounts of human achievement suggest that accidents can play an important role in innovation. In this paper, we seek to contribute to an understanding of how digital systems might support valuable unpredictability in innovation processes by examining how innovators who obtain value from...... they incorporate accidents into their deliberate processes and arranged surroundings. By comparing makers working in varied conditions, we identify specific factors (e.g., technologies, characteristics of technologies) that appear to support accidental innovation. We show that makers in certain specified...... conditions not only remain open to accident but also intentionally design their processes and surroundings to invite and exploit valuable accidents. Based on these findings, we offer advice for the design of digital systems to support innovation processes that can access valuable unpredictability....

The Risoe model for calculating the consequences of the release of radioactive material to the atmosphere

International Nuclear Information System (INIS)

Thykier-Nielsen, S.

1980-07-01

A brief description is given of the model used at Risoe for calculating the consequences of releases of radioactive material to the atmosphere. The model is based on the Gaussian plume model, and it provides possibilities for calculation of: doses to individuals, collective doses, contamination of the ground, probability distribution of doses, and the consequences of doses for give dose-risk relationships. The model is implemented as a computer program PLUCON2, written in ALGOL for the Burroughs B6700 computer at Risoe. A short description of PLUCON2 is given. (author)

Accidental symmetries and the effective Lagrangian of string theory

International Nuclear Information System (INIS)

Ovrut, B.A.

1989-01-01

In this paper the relationship between accidental worldsheet symmetries of the string generating functional and target space invariance groups is discussed. Accidental symmetries are used to derive the invariance groups and effective low energy Lagrangian for the bosonic string, and the heterotic string compactified to four-dimensions on Z N orbifolds. The necessity of a new type of Green-Schwarz mechanism, associated with the auxiliary vector field in the four-dimensional N = 1 supergravity multiplet, is shown using these methods

Presentation of evolutions of the CERES platform used to evaluate the consequences of the emissions of pollutants in the environment

Energy Technology Data Exchange (ETDEWEB)

Monfort, M.; Patryl, L.; Armand, P. [Commissariat a l' energie atomique et aux energies alternatives - CEA (France)

2014-07-01

The Radiological and Chemical Impact Laboratory (LIRC) of the French Atomic Energy Commission (CEA) is in charge of the development of modelling tools to evaluate the consequences on human health of releases of radionuclides or toxic chemicals in the environment, for emergency planning and for safety evaluation. In this context, the laboratory has developed the CERES application (Code d'Evaluations Rapides Environnementales et Sanitaires), in order that all impact calculations relative to CEA installations will be done using the same tools and methods. It is used to evaluate the consequences on human health of releases of isotopes in the environment, either for emergency planning or for safety evaluation. Various types of emissions can be simulated: atmospheric accidental emission, atmospheric emission during normal operation or emission in liquid media under normal operation. This application is used for emergency situations planning and for the realization of assessment calculations within a regulatory framework, for example in the safety documents relative to nuclear installations. It helps to evaluate either the consequences of accidental situations supposed to occur on installations or the impact of routine releases from single installations or nuclear sites on their near environment. A specific module is used to evaluate the dispersion and impact of tritium release and in normal situations for C-14 release. The ERASTEM module helps to estimate the release to environment in case of accidental situation on nuclear reactor. Two versions exist, one devoted to radiological impact evaluations, the other one devoted to toxic impact. This platform is used on every CEA site, either for emergency situation and impact studies on human health. Recent evolutions of these platforms follow demands expressed in CEA user's group. According to radiological version, these evolutions mainly concern the implementation of isotopes and the evaluation of atmospheric

Two standards - CSA-N288.1 and USNRC regulatory guides 1.109, 1.111 for chronic atmospheric releases from nuclear facilities - compared

International Nuclear Information System (INIS)

Peterson, S-R.

1997-05-01

Although the Canadian Standards Association's 'Guidelines for Calculating Derived Release Limits for Radioactive Material in Airborne and Liquid Effluents for Normal Operation of Nuclear Facilities', CSA-N288.1-M87 (CSA 1987) can be used to license CANDU (CANadian Deuterium Uranium) reactors sold off-shore, in practice purchasers may wish to use the United States Regulatory Guides (RG) 1.109 (United States Nuclear Regulatory Commission 1977a) and 1.111 (USNRC 1977b) to calculate doses from routine atmospheric releases to members of a critical group. When differences in dose predictions are found between the two standards, CSA-N288.1 comes under attack. This paper explains the differences between the two models. The two atmospheric dispersion models were compared for a ground level release and an elevated release such as from CANDU 6. For a ground level release, CSA's dilution factors were slightly more than half of RG's. For the elevated release, following recommendations in each guide, CSA's dilution coefficient is higher than RG's within 1000 m of the stack and only slightly lower farther away. All differences can be accounted for by different mathematical formulations and assumptions about height at which wind speed is measured. Ingestion, inhalation, immersion and external doses predicted by the two models were compared for unit release (Bq s -1 ) and for realistic source terms of a suite of 33 radionuclides commonly released from both CANDUs and Pressurized Water Reactors (PWRs). To demonstrate real differences in the models, ingestion doses for the two models were compared using the CSA diet in both models and CSA predictions were recalculated to account for decay which occurs between harvest and ingestion in RG. Once all assumptions are equalized, there is very little difference in dose predictions of the two models that cannot be explained by different parameter values. Both models have outdated dose conversion factors, and the use of improved numbers will

Night work, long work weeks, and risk of accidental injuries. A register-based study.

Science.gov (United States)

Larsen, Ann D; Hannerz, Harald; Møller, Simone V; Dyreborg, Johnny; Bonde, Jens Peter; Hansen, Johnni; Kolstad, Henrik A; Hansen, Åse Marie; Garde, Anne Helene

2017-11-01

Objectives The aims of this study were to (i) investigate the association between night work or long work weeks and the risk of accidental injuries and (ii) test if the association is affected by age, sex or socioeconomic status. Methods The study population was drawn from the Danish version of the European Labour Force Survey from 1999-2013. The current study was based on 150 438 participants (53% men and 47% women). Data on accidental injuries were obtained at individual level from national health registers. We included all 20-59-year-old employees working ≥32 hours a week at the time of the interview. We used Poisson regression to estimate the relative rates (RR) of accidental injuries as a function of night work or long work weeks (>40 hours per week) adjusted for year of interview, sex, age, socioeconomic status (SES), industry, and weekly working hours or night work. Age, sex and SES were included as two-way interactions. Results We observed 23 495 cases of accidental injuries based on 273 700 person years at risk. Exposure to night work was statistically significantly associated with accidental injuries (RR 1.11, 99% CI 1.06-1.17) compared to participants with no recent night work. No associations were found between long work weeks (>40 hours) and accidental injuries. Conclusion We found a modest increased risk of accidental injuries when reporting night work. No associations between long work weeks and risk of accidental injuries were observed. Age, sex and SES showed no trends when included as two-way interactions.

Los hombres y los accidentes de tránsito: un vistazo al riesgo, conducta de riesgo, notificación de accidentes, educación y formación profesional

Directory of Open Access Journals (Sweden)

Cintia Rodrigues

2017-05-01

Full Text Available Abstract Los accidentes de tránsito son un grave y complejo problema de salud pública. La literatura señala que los accidentes de tránsito están asociados confactores de comportamiento, seguridad de los vehículos y la precariedad del espacio urbano.Reducir el número de accidentes de tránsito es un reto para los gestores deárea. La educación en el tránsito debe considerar la vigilancia como una estrategia eficaz para cambiar el comportamiento del conductor,principalmente en relación con el exceso de velocidad y el consumo de alcohol asociado con la conducción.La ingeniería tiene un papel importante para promover un entorno seguro,en el que la convivencia de peatones, ciclistas y conductores sea posible. El escenario en que se configura los accidentes de tránsito muestra la necesidad de los profesionales de la salud reconsiderar sus prácticas con el fin de replantear la imagen de la víctima de accidentes, las formas de trabajo de prevención de accidentes, la educación en el tránsito de peatones y conductores, con el fin de promover la salud y la cultura de paz. Existe la necesidad de políticas de salud públicay estrategias que hacen posible acceso a las acciones tanto en el campo preventivo como en el campo de la rehabilitación.

Modelling of tritium dispersion from postulated accidental release of nuclear power plants; Modelagem da dispersao de tritio a partir de liberacoes acidentais postuladas de centrais nucleares

Energy Technology Data Exchange (ETDEWEB)

Soares, Abner Duarte

2010-07-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. This exercise was accomplished with the aid of a code system (SisBAHIA) developed in the Rio de Janeiro Federal University (COPPE/UFRJ). The CANDU reactor is one that uses heavy water (D{sub 2}O) as moderator and coolant of the core. It was postulated, then, the LOCA (Loss of Coolant Accident) accident in the emergency cooling system of the nucleus (without fusion), where was lost 66 m{sup 3} of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped and operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m{sup 3} ) during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10{sup 9} to 5x10{sup 5} Bq/m{sup 3} close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m{sup 3}). (author)

Overview study of LNG release prevention and control systems

Energy Technology Data Exchange (ETDEWEB)

Pelto, P.J.; Baker, E.G.; Holter, G.M.; Powers, T.B.

1982-03-01

The liquefied natural gas (LNG) industry employs a variety of release prevention and control techniques to reduce the likelihood and the consequences of accidental LNG releases. A study of the effectiveness of these release prevention and control systems is being performed. Reference descriptions for the basic types of LNG facilities were developed. Then an overview study was performed to identify areas that merit subsequent and more detailed analyses. The specific objectives were to characterize the LNG facilities of interest and their release prevention and control systems, identify possible weak links and research needs, and provide an analytical framework for subsequent detailed analyses. The LNG facilities analyzed include a reference export terminal, marine vessel, import terminal, peakshaving facility, truck tanker, and satellite facility. A reference description for these facilities, a preliminary hazards analysis (PHA), and a list of representative release scenarios are included. The reference facility descriptions outline basic process flows, plant layouts, and safety features. The PHA identifies the important release prevention operations. Representative release scenarios provide a format for discussing potential initiating events, effects of the release prevention and control systems, information needs, and potential design changes. These scenarios range from relatively frequent but low consequence releases to unlikely but large releases and are the principal basis for the next stage of analysis.

La prevención de accidentes (3

Directory of Open Access Journals (Sweden)

Chinchilla, M.

1966-04-01

Full Text Available The financial loss due to working accidents is very substantial, quite apart from the actual loss of human lives. Hence avoiding these accidents is a most important matter. The accident index in the various industries shows a rate of increase that is larger than should be the case in proportion to the development of the industries concerned, and the larger number of employees. The fact that these indexes are smaller in many countries, however, shows that these accidents can be considerably reduced if suitable measures are taken to avoid them. In chapter 2 of our magazine, issue no. 178, a variety of reasons were discussed that may originate accidents, although these causes are not directly linked to the accident itself. In this article mention is made of some of the measures that can be taken in the handling of cutting and welding equipment, and also of inflammable liquids, to prevent possible accidents.El peso de los accidentes de trabajo sobre la economía supone cantidades muy grandes que, independientemente del inestimable valor de una vida humana, realzan la importancia de la prevención de accidentes. Los índices de accidentes muestran en diferentes industrias un crecimiento mayor de lo que debería corresponder proporcionalmente, habida cuenta del crecimiento laboral. El hecho de que en distintos países los índices sean inferiores, demuestra que se pueden conseguir buenos frutos si se concede primordial importancia a que los trabajos se realicen con las debidas medidas de seguridad. En el Capítulo 2, número 178 de esta Revista, se detallaron diversas causas que pueden originar un accidente sin estar ligadas en forma directa con una tarea determinada. En el presente trabajo se indican algunas de las medidas que deben observarse en el manejo de los equipos de soldadura y corte, así como en el transvase de líquidos inflamables.

Behavior of radioactive products in the containment. Behavior of iodine in accidental situation

International Nuclear Information System (INIS)

Lucas, M.; Fermandjian, J.

1984-12-01

The aim of studies on iodine is to demonstrate that in the case of failure in the containment occuring after more than one day, the total quantity of iodine released would be lower or equal to 1% of the inventory of the core at the moment of the begining of the accident. The first part describes the behavior of iodine in the containment of a PWR, in the case of an important accident. The second part deals with a synthesis of the knowledge about iodine. The third part presents the inventory of the main problems not resolved concerning the chemistry of iodine and the radiolysis of iodine. Finally, the program of studies on iodine is briefly presented; its aim is to develop the knowledge about iodine in accidental situations [fr

Model to estimate radiation dose commitments to the world population from the atmospheric release of radionuclides (LWBR development program)

International Nuclear Information System (INIS)

Rider, J.L.; Beal, S.K.

1978-02-01

The equations developed for use in the LWBR environmental statement to estimate the dose commitment over a given time interval to a given organ of the population in the entire region affected by the atmospheric releases of a radionuclide are presented and may be used for any assessment of dose commitments in these regions. These equations define the dose commitments to the world resulting from a released radionuclide and each of its daughters and the sum of these dose commitments provides the total dose commitment accrued from the release of a given radionuclide. If more than one radionuclide is released from a facility, then the sum of the dose commitments from each released nuclide and from each daughter of each released nuclide is the total dose commitment to the world from that facility. Furthermore, if more than one facility is considered as part of an industry, then the sum of the dose commitments from the individual facilities represents the total world dose commitment associated with that industry. The actual solutions to these equations are carried out by the AIRWAY computer program. The writing of this computer program entailed defining in detail the specific representations of the various parameters such as scavenging coefficients, resuspension factors, deposition velocities, dose commitment conversion factors, and food uptake factors, in addition to providing specific numerical values for these types of parameters. The program permits the examination of more than one released nuclide at a time and performs the necessary summing to obtain the total dose commitment to the world accrued from the specified releases

Response of atmospheric CO2 to changes in land use

International Nuclear Information System (INIS)

King, A.W.; Emanuel, W.R.; Post, W.M.

1991-01-01

This chapter examines how different histories of CO 2 release from past changes in land use influence the simulation of past and future changes in atmospheric CO 2 . The authors first simulate past change in atmospheric CO 2 using reconstructed histories of land-use CO 2 release from a historical-ecological model of land-use change and CO 2 release. They examine the impact of each history on the coincidence between simulated and observed atmospheric CO 2 . They then compare these CO 2 release histories, and their contribution to coincidence or noncoincidence of simulation and observation, with histories reconstructed by deconvolution of the atmospheric CO 2 record. They conclude by exploring the implications of these deconvolved reconstructions for the simulation of future changes in atmospheric CO 2

Flavour from accidental symmetries

International Nuclear Information System (INIS)

Ferretti, Luca; King, Stephen F.; Romanino, Andrea

2006-01-01

We consider a new approach to fermion masses and mixings in which no special 'horizontal' dynamics is invoked to account for the hierarchical pattern of charged fermion masses and for the peculiar features of neutrino masses. The hierarchy follows from the vertical, family-independent structure of the model, in particular from the breaking pattern of the Pati-Salam group. The lightness of the first two fermion families can be related to two family symmetries emerging in this context as accidental symmetries

Accidental childhood poisoning in Calabar at the turn of the 20 th ...

African Journals Online (AJOL)

Background: Accidental poisoning is a preventable cause of childhood morbidity and mortality. Therefore, knowledge of the common causative agents is necessary in order to create awareness among caregivers towards its prevention. Objectives: To document the pattern of accidental childhood poisoning in Calabar from ...

First estimates of the contribution of CaCO3 precipitation to the release of CO2 to the atmosphere during young sea ice growth

Science.gov (United States)

Geilfus, N.-X.; Carnat, G.; Dieckmann, G. S.; Halden, N.; Nehrke, G.; Papakyriakou, T.; Tison, J.-L.; Delille, B.

2013-01-01

report measurements of pH, total alkalinity, air-ice CO2 fluxes (chamber method), and CaCO3 content of frost flowers (FF) and thin landfast sea ice. As the temperature decreases, concentration of solutes in the brine skim increases. Along this gradual concentration process, some salts reach their solubility threshold and start precipitating. The precipitation of ikaite (CaCO3.6H2O) was confirmed in the FF and throughout the ice by Raman spectroscopy and X-ray analysis. The amount of ikaite precipitated was estimated to be 25 µmol kg-1 melted FF, in the FF and is shown to decrease from 19 to 15 µmol kg-1 melted ice in the upper part and at the bottom of the ice, respectively. CO2 release due to precipitation of CaCO3 is estimated to be 50 µmol kg-1 melted samples. The dissolved inorganic carbon (DIC) normalized to a salinity of 10 exhibits significant depletion in the upper layer of the ice and in the FF. This DIC loss is estimated to be 2069 µmol kg-1 melted sample and corresponds to a CO2 release from the ice to the atmosphere ranging from 20 to 40 mmol m-2 d-1. This estimate is consistent with flux measurements of air-ice CO2 exchange. Our measurements confirm previous laboratory findings that growing young sea ice acts as a source of CO2 to the atmosphere. CaCO3 precipitation during early ice growth appears to promote the release of CO2 to the atmosphere; however, its contribution to the overall release by newly formed ice is most likely minor.

The role of the LLNL Atmospheric Release Advisory Capability in a FRMAC response to a nuclear power plant incident

International Nuclear Information System (INIS)

Baskett, R.L.; Sullivan, T.J.; Ellis, J.S.; Foster, C.S.

1994-01-01

The Federal Radiological Emergency Response Plan (FRERP) can provide several emergency response resources in response to a nuclear power plant (NPP) accident if requested by a state or local agency. The primary FRERP technical resources come from the US Department of Energy's (DOE) Federal Radiological Monitoring and Assessment Center (FRMAC). Most of the FRMAC assets are located at the DOE Remote Sensing Laboratory (RSL) at Nellis Air Force Base, Las Vegas, Nevada. In addition, the primary atmospheric dispersion modeling and dose assessment asset, the Atmospheric Release Advisory Capability (ARAC) is located at Lawrence Livermore National Laboratory (LLNL) in Livermore, California. In the early stages of a response, ARAC relies on its automatic worldwide meteorological data acquisition via the Air Force Global Weather Center (AFGWC). The regional airport data are supplemented with data from on-site towers and sodars and the National Oceanographic ampersand Atmospheric Administration's (NOAA) field-deployable real-time rawinsonde system. ARAC is prepared with three-dimensional regional-scale diagnostic dispersion model to simulate the complex mixed fission product release from a reactor accident. The program has been operational for 18 years and is presently developing its third generation system. The current modernization includes faster central computers, a new site workstation system. The current modernization includes faster central computers, a new site workstation system, improvements in its diagnostic dispersion models, addition of a new hybrid-particle source term, and implementation of a mesoscale prognostic model. AS these new capabilities evolve, they will be integrated into the FRMAC's field-deployable assets

A study of the atmospheric dispersion of a high release of krypton-85 above a complex coastal terrain, comparison with the predictions of Gaussian models (Briggs, Doury, ADMS4).

Science.gov (United States)

Leroy, C; Maro, D; Hébert, D; Solier, L; Rozet, M; Le Cavelier, S; Connan, O

2010-11-01

Atmospheric releases of krypton-85, from the nuclear fuel reprocessing plant at the AREVA NC facility at La Hague (France), were used to test Gaussian models of dispersion. In 2001-2002, the French Institute for Radiological Protection and Nuclear Safety (IRSN) studied the atmospheric dispersion of 15 releases, using krypton-85 as a tracer for plumes emitted from two 100-m-high stacks. Krypton-85 is a chemically inert radionuclide. Krypton-85 air concentration measurements were performed on the ground in the downwind direction, at distances between 0.36 and 3.3 km from the release, by neutral or slightly unstable atmospheric conditions. The standard deviation for the horizontal dispersion of the plume and the Atmospheric Transfer Coefficient (ATC) were determined from these measurements. The experimental results were compared with calculations using first generation (Doury, Briggs) and second generation (ADMS 4.0) Gaussian models. The ADMS 4.0 model was used in two configurations; one takes account of the effect of the built-up area, and the other the effect of the roughness of the surface on the plume dispersion. Only the Briggs model correctly reproduced the measured values for the width of the plume, whereas the ADMS 4.0 model overestimated it and the Doury model underestimated it. The agreement of the models with measured values of the ATC varied according to distance from the release point. For distances less than 2 km from the release point, the ADMS 4.0 model achieved the best agreement between model and measurement; beyond this distance, the best agreement was achieved by the Briggs and Doury models.

Impact of Released Fual Moisture on Atmospheric Dynamics

Science.gov (United States)

Brian E. Potter

2003-01-01

A common component of fire incident reports and prescribed burn preparations is an estimate of the energy that was or will be released by the fire. Typically, this is based on the energy released by combustion of the fuel load, reduced to account for the energy that is required to evaporate moisture in the fuel materials. (e.g., Byram 1959, Anderson 1968, Simard et al...

Dental pain as a risk factor for accidental acetaminophen overdose: a case-control study.

Science.gov (United States)

Vogel, Jody; Heard, Kennon J; Carlson, Catherine; Lange, Chad; Mitchell, Garrett

2011-11-01

Patients frequent take acetaminophen to treat dental pain. One previous study found a high rate of overuse of nonprescription analgesics in an emergency dental clinic. The purpose of this study is to determine if patients with dental pain are more likely to be treated for accidental acetaminophen poisoning than patients with other types of pain. We conducted a case-control study at 2 urban hospitals. Cases were identified by chart review of patients who required treatment for accidental acetaminophen poisoning. Controls were self-reported acetaminophen users taking therapeutic doses identified during a survey of emergency department patients. For our primary analysis, the reason for taking acetaminophen was categorized as dental pain or not dental pain. Our primary outcome was the odds ratio of accidental overdose to therapeutic users after adjustment for age, sex, alcoholism, and use of combination products using logistic regression. We identified 73 cases of accidental acetaminophen poisoning and 201 therapeutic users. Fourteen accidental overdose patients and 4 therapeutic users reported using acetaminophen for dental pain. The adjusted odds ratio for accidental overdose due to dental pain compared with other reasons for use was 12.8 (95% confidence interval, 4.2-47.6). We found that patients with dental pain are at increased risk to accidentally overdose on acetaminophen compared with patients taking acetaminophen for other reasons. Emergency physicians should carefully question patients with dental pain about overuse of analgesics. Copyright © 2011 Elsevier Inc. All rights reserved.

Investigación de accidentes y análisis de fallas de barreras preventivas; Accident’s Investigation and Preventive Barriers flaws analysis

Directory of Open Access Journals (Sweden)

Jacinto B Hernández Lavín

2011-02-01

Full Text Available En Cuba, como en el resto del mundo,  la existencia de leyes y regulaciones estatales, obligan a que lasempresas productivas y de servicios cuenten con un sistema de prevención de accidentes y enfermedadesprofesionales que, a partir del control de los riesgos existentes en cada puesto de trabajo, permita laboraren un ambiente seguro. En este artículo se explican las técnicas y procedimientos establecidos en la UNEpara la investigación de accidentes laborales. In Cuba, like in the rest of the world, the existence of Laws and state Regulations, they force to productivecompanies and services, they have a prevention system to avoid the accidents and professional illnessesthat, starting from the control of the existent risks in each work position, allow working in a sure atmosphere.In this article the techniques and procedures are explained, applied in the Electric Union (UNE, for thelabor accident investigation.

Accidentes de trabajo en un hospital de agudos

Directory of Open Access Journals (Sweden)

Pérez Bermúdez B.

1998-01-01

Full Text Available FUNDAMENTO: El mejor conocimiento de los determinantes y circunstancias de producción de los accidentes laborales, favorecerá la implantación de medidas correctoras. El objetivo de este trabajo es describir la evolución temporal de los accidentes de trabajo (AT y determinar los factores de riesgo de baja médica en el Hospital Dr. Peset de Valencia. MÉTODOS: Descripción y análisis retrospectivo de los accidentes de trabajo producidos en el Hospital Dr. Peset de Valencia durante los años 1992 a 1995. Se estimó por métodos deterministas la tendencia y estacionalidad de las series (índices estacionales, IE. Se aplicó un modelo de regresión logística para identificar los factores pronósticos de baja médica y determinar su probabilidad de ocurrencia . RESULTADOS: Las tasas más elevadas de AT se produjeron entre los trabajadores de cocina y lavandería (10,00 AT por 100 trabajadores-año. Los AT con baja médica mantienen una tendencia cercana a cero siendo febrero el mes con I.E más elevado (IE=139,8. Los que cursan sin baja médica tienen una tendencia positiva (r²=0,23, p<0,0001, siendo mayo el mes de mayor siniestralidad (IE=134,2. La probabilidad de que el accidente curse con baja médica aumenta significativamente con la edad, cuando se produce por la tarde, si ha tenido lugar en cocina/lavandería, y si se trata de un esguince o tendinitis. CONCLUSIONES: la actuación sobre la siniestralidad en los AT que cursen con IT, debería centrarse sobre los trabajos menos cualificados y en las áreas de cocina y lavandería.

Report on international round table conference 'Accidental radiation contamination of food of animal origin'. Vol. I

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-07-01

The World Association of Veterinary Food Hygienists (WAVFH) held an international round table conference in Stockholm, Sweden, January 26-29, 1987. The topic of the conference was 'Accidental Radiation Contamination of Food of Animal Origin'. The agenda was divided into three major topic areas: 1. Ecological Science; 2. Veterinary Science - Live Animals; and 3. Veterinary Science - Food of Animal Origin. Experts and delegates from member countries presented papers, participated in discussions and workshops and produced a multidisciplinary report covering the topic areas. The recent accidental release of radioactive substances into the environment from the Chernobyl accident, demonstrated the need for veterinary, ecological, physical and medical sciences to be prepared to respond to an incident in order to protect the environment, food chain, other agricultural assets and humans from the adverse effects of radionuclides. Several presentations suggested that even with the best technologies, national and regional commitment, and relatively unrestricted resource levels, nuclear incidents can cross international boundaries and can contaminate the environment to the extent that the integrity of various food and water supplies can be at risk. Speakers and subsequent discussers tended to concentrate on the issues associated with lessening future environmental impacts if similar types of incidents should occur again.

Report on international round table conference 'Accidental radiation contamination of food of animal origin'. Vol. I

International Nuclear Information System (INIS)

1986-01-01

The World Association of Veterinary Food Hygienists (WAVFH) held an international round table conference in Stockholm, Sweden, January 26-29, 1987. The topic of the conference was 'Accidental Radiation Contamination of Food of Animal Origin'. The agenda was divided into three major topic areas: 1. Ecological Science; 2. Veterinary Science - Live Animals; and 3. Veterinary Science - Food of Animal Origin. Experts and delegates from member countries presented papers, participated in discussions and workshops and produced a multidisciplinary report covering the topic areas. The recent accidental release of radioactive substances into the environment from the Chernobyl accident, demonstrated the need for veterinary, ecological, physical and medical sciences to be prepared to respond to an incident in order to protect the environment, food chain, other agricultural assets and humans from the adverse effects of radionuclides. Several presentations suggested that even with the best technologies, national and regional commitment, and relatively unrestricted resource levels, nuclear incidents can cross international boundaries and can contaminate the environment to the extent that the integrity of various food and water supplies can be at risk. Speakers and subsequent discussers tended to concentrate on the issues associated with lessening future environmental impacts if similar types of incidents should occur again

Night work, long work weeks, and risk of accidental injuries. A register-based study

DEFF Research Database (Denmark)

Larsen, Ann D; Hannerz, Harald; Møller, Simone V

2017-01-01

of the European Labour Force Survey from 1999-2013. The current study was based on 150 438 participants (53% men and 47% women). Data on accidental injuries were obtained at individual level from national health registers. We included all 20-59-year-old employees working ≥32 hours a week at the time...... of the interview. We used Poisson regression to estimate the relative rates (RR) of accidental injuries as a function of night work or long work weeks (>40 hours per week) adjusted for year of interview, sex, age, socioeconomic status (SES), industry, and weekly working hours or night work. Age, sex and SES were....... No associations were found between long work weeks (>40 hours) and accidental injuries. Conclusion: We found a modest increased risk of accidental injuries when reporting night work. No associations between long work weeks and risk of accidental injuries were observed. Age, sex and SES showed no trends when...

Review of calculational models and computer codes for environmental dose assessment of radioactive releases

International Nuclear Information System (INIS)

Strenge, D.L.; Watson, E.C.; Droppo, J.G.

1976-06-01

The development of technological bases for siting nuclear fuel cycle facilities requires calculational models and computer codes for the evaluation of risks and the assessment of environmental impact of radioactive effluents. A literature search and review of available computer programs revealed that no one program was capable of performing all of the great variety of calculations (i.e., external dose, internal dose, population dose, chronic release, accidental release, etc.). Available literature on existing computer programs has been reviewed and a description of each program reviewed is given

Review of calculational models and computer codes for environmental dose assessment of radioactive releases

Energy Technology Data Exchange (ETDEWEB)

Strenge, D.L.; Watson, E.C.; Droppo, J.G.

1976-06-01

The development of technological bases for siting nuclear fuel cycle facilities requires calculational models and computer codes for the evaluation of risks and the assessment of environmental impact of radioactive effluents. A literature search and review of available computer programs revealed that no one program was capable of performing all of the great variety of calculations (i.e., external dose, internal dose, population dose, chronic release, accidental release, etc.). Available literature on existing computer programs has been reviewed and a description of each program reviewed is given.

Application of physiologically based pharmacokinetic modeling in setting acute exposure guideline levels for methylene chloride.

NARCIS (Netherlands)

Bos, Peter Martinus Jozef; Zeilmaker, Marco Jacob; Eijkeren, Jan Cornelis Henri van

2006-01-01

Acute exposure guideline levels (AEGLs) are derived to protect the human population from adverse health effects in case of single exposure due to an accidental release of chemicals into the atmosphere. AEGLs are set at three different levels of increasing toxicity for exposure durations ranging from

Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of atmospheric dispersion model with improved deposition scheme and oceanic dispersion model

Science.gov (United States)

Katata, G.; Chino, M.; Kobayashi, T.; Terada, H.; Ota, M.; Nagai, H.; Kajino, M.; Draxler, R.; Hort, M. C.; Malo, A.; Torii, T.; Sanada, Y.

2014-06-01

Temporal variations in the amount of radionuclides released into the atmosphere during the Fukushima Dai-ichi Nuclear Power Station (FNPS1) accident and their atmospheric and marine dispersion are essential to evaluate the environmental impacts and resultant radiological doses to the public. In this paper, we estimate a detailed time trend of atmospheric releases during the accident by combining environmental monitoring data with atmospheric model simulations from WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information), and simulations from the oceanic dispersion model SEA-GEARN-FDM, both developed by the authors. A sophisticated deposition scheme, which deals with dry and fogwater depositions, cloud condensation nuclei (CCN) activation and subsequent wet scavenging due to mixed-phase cloud microphysics (in-cloud scavenging) for radioactive iodine gas (I2 and CH3I) and other particles (CsI, Cs, and Te), was incorporated into WSPEEDI-II to improve the surface deposition calculations. The fallout to the ocean surface calculated by WSPEEDI-II was used as input data for the SEA-GEARN-FDM calculations. Reverse and inverse source-term estimation methods based on coupling the simulations from both models was adopted using air dose rates and concentrations, and sea surface concentrations. The results revealed that the major releases of radionuclides due to FNPS1 accident occurred in the following periods during March 2011: the afternoon of 12 March due to the wet venting and hydrogen explosion at Unit 1, the morning of 13 March after the venting event at Unit 3, midnight of 14 March when the SRV (Safely Relief Valve) at Unit 2 was opened three times, the morning and night of 15 March, and the morning of 16 March. According to the simulation results, the highest radioactive contamination areas around FNPS1 were created from 15 to 16 March by complicated interactions among rainfall, plume movements, and the temporal variation of

Compact fluorescent lamp phosphors in accidental radiation monitoring

International Nuclear Information System (INIS)

Murthy, K. V. R.; Pallavi, S. P.; Ghildiyal, R.; Parmar, M. C.; Patel, Y. S.; Ravi Kumar, V.; Sai Prasad, A. S.; Natarajan, V.; Page, A. G.

2006-01-01

The application of lamp phosphors for accidental dosimetry is a new concept. Since the materials used in fluorescent lamps are good photo luminescent materials, if one can either use the inherent defects present in the phosphor or add suitable modifiers to induce thermoluminescence (TL) in these phosphors, then the device (fluorescent lamp) can be used as an accidental dosemeter. In continuation of our search for a suitable phosphor material, which can serve both as an efficient lamp phosphor and as a good radiation monitoring device, detailed examination has been carried out on cerium and terbium-doped lanthanum phosphate material. A 90 Sr beta source with 50 mCi strength (1.85 GBq) was used as the irradiation source for TL studies. The TL response as a function of dose received was examined for all phosphors used and it was observed that the intensity of the TL peak vs. dose received was a linear function in the dose range 0.1-200 Gy in each case. Incidentally LaPO 4 :Ce,Tb is a component of the compact fluorescent lamp marketed recently as an energy bright light source. Besides having very good luminescence efficiency, good dosimetric properties of these phosphors render them useful for their use in accidental dosimetry also. (authors)

Modelling short term individual exposure from airborne hazardous releases in urban environments

International Nuclear Information System (INIS)

Bartzis, J.G.; Efthimiou, G.C.; Andronopoulos, S.

2015-01-01

Highlights: • The statistical behavior of the variability of individual exposure is described with a beta function. • The extreme value in the beta function is properly addressed by [5] correlation. • Two different datasets gave clear support to the proposed novel theory and its hypotheses. - Abstract: A key issue, in order to be able to cope with deliberate or accidental atmospheric releases of hazardous substances, is the ability to reliably predict the individual exposure downstream the source. In many situations, the release time and/or the health relevant exposure time is short compared to mean concentration time scales. In such a case, a significant scatter of exposure levels is expected due to the stochastic nature of turbulence. The problem becomes even more complex when dispersion occurs over urban environments. The present work is the first attempt to approximate on generic terms, the statistical behavior of the abovementioned variability with a beta distribution probability density function (beta-pdf) which has proved to be quite successful. The important issue of the extreme concentration value in beta-pdf seems to be properly addressed by the [5] correlation in which global values of its associated constants are proposed. Two substantially different datasets, the wind tunnel Michelstadt experiment and the field Mock Urban Setting Trial (MUST) experiment gave clear support to the proposed novel theory and its hypotheses. In addition, the present work can be considered as basis for further investigation and model refinements.

Modelling short term individual exposure from airborne hazardous releases in urban environments

Energy Technology Data Exchange (ETDEWEB)

Bartzis, J.G., E-mail: bartzis@uowm.gr [University of Western Macedonia, Dept. of Mechanical Engineering, Sialvera & Bakola Str., 50100, Kozani (Greece); Efthimiou, G.C.; Andronopoulos, S. [Environmental Research Laboratory, INRASTES, NCSR Demokritos, Patriarchou Grigoriou & Neapoleos Str., 15310, Aghia Paraskevi (Greece)

2015-12-30

Highlights: • The statistical behavior of the variability of individual exposure is described with a beta function. • The extreme value in the beta function is properly addressed by [5] correlation. • Two different datasets gave clear support to the proposed novel theory and its hypotheses. - Abstract: A key issue, in order to be able to cope with deliberate or accidental atmospheric releases of hazardous substances, is the ability to reliably predict the individual exposure downstream the source. In many situations, the release time and/or the health relevant exposure time is short compared to mean concentration time scales. In such a case, a significant scatter of exposure levels is expected due to the stochastic nature of turbulence. The problem becomes even more complex when dispersion occurs over urban environments. The present work is the first attempt to approximate on generic terms, the statistical behavior of the abovementioned variability with a beta distribution probability density function (beta-pdf) which has proved to be quite successful. The important issue of the extreme concentration value in beta-pdf seems to be properly addressed by the [5] correlation in which global values of its associated constants are proposed. Two substantially different datasets, the wind tunnel Michelstadt experiment and the field Mock Urban Setting Trial (MUST) experiment gave clear support to the proposed novel theory and its hypotheses. In addition, the present work can be considered as basis for further investigation and model refinements.

The significance of ground contamination following an accidental release of radioactivity

International Nuclear Information System (INIS)

Corbett, J.O.

1977-07-01

The reasons for extending the analysis of hypothetical accidents to include ground contamination as a route to radiation dosage in man are discussed. Models and data available for such an assessment of ground contamination are examined with reference to the deposition of radionuclides from the atmosphere and dosage by direct γ-irradiation, ingestion of radionuclides in milk and inhalation of a resuspended aerosol. Dosage through these routes is then compared with that which arises directly from the plume emitted in a hypothetical accident. The assessment methods are subject to uncertainty, so that in some cases only an upper limit to dose or an estimate within an order of magnitude can be obtained. Areas where further research could lead to a reduction of this uncertainty are identified. (author)

Detecting spatiotemporal clusters of accidental poisoning mortality among Texas counties, U.S., 1980 – 2001

Directory of Open Access Journals (Sweden)

Harris Ann

2004-10-01

Full Text Available Abstract Background Accidental poisoning is one of the leading causes of injury in the United States, second only to motor vehicle accidents. According to the Centers for Disease Control and Prevention, the rates of accidental poisoning mortality have been increasing in the past fourteen years nationally. In Texas, mortality rates from accidental poisoning have mirrored national trends, increasing linearly from 1981 to 2001. The purpose of this study was to determine if there are spatiotemporal clusters of accidental poisoning mortality among Texas counties, and if so, whether there are variations in clustering and risk according to gender and race/ethnicity. The Spatial Scan Statistic in combination with GIS software was used to identify potential clusters between 1980 and 2001 among Texas counties, and Poisson regression was used to evaluate risk differences. Results Several significant (p Conclusion The findings of the present study provide evidence for the existence of accidental poisoning mortality clusters in Texas, demonstrate the persistence of these clusters into the present decade, and show the spatiotemporal variations in risk and clustering of accidental poisoning deaths by gender and race/ethnicity. By quantifying disparities in accidental poisoning mortality by place, time and person, this study demonstrates the utility of the spatial scan statistic combined with GIS and regression methods in identifying priority areas for public health planning and resource allocation.

Involving Parents in Indicated Early Intervention for Childhood PTSD Following Accidental Injury

Science.gov (United States)

Cobham, Vanessa E.; March, Sonja; De Young, Alexandra; Leeson, Fiona; Nixon, Reginald; McDermott, Brett; Kenardy, Justin

2012-01-01

Accidental injuries represent the most common type of traumatic event to which a youth is likely to be exposed. While the majority of youth who experience an accidental injury will recover spontaneously, a significant proportion will go on to develop Post-Traumatic Stress Disorder (PTSD). And yet, there is little published treatment outcome…

Development, description and validation of a Tritium Environmental Release Model (TERM).

Science.gov (United States)

Jeffers, Rebecca S; Parker, Geoffrey T

2014-01-01

Tritium is a radioisotope of hydrogen that exists naturally in the environment and may also be released through anthropogenic activities. It bonds readily with hydrogen and oxygen atoms to form tritiated water, which then cycles through the hydrosphere. This paper seeks to model the migration of tritiated species throughout the environment - including atmospheric, river and coastal systems - more comprehensively and more consistently across release scenarios than is currently in the literature. A review of the features and underlying conceptual models of some existing tritium release models was conducted, and an underlying aggregated conceptual process model defined, which is presented. The new model, dubbed 'Tritium Environmental Release Model' (TERM), was then tested against multiple validation sets from literature, including experimental data and reference tests for tritium models. TERM has been shown to be capable of providing reasonable results which are broadly comparable with atmospheric HTO release models from the literature, spanning both continuous and discrete release conditions. TERM also performed well when compared with atmospheric data. TERM is believed to be a useful tool for examining discrete and continuous atmospheric releases or combinations thereof. TERM also includes further capabilities (e.g. river and coastal release scenarios) that may be applicable to certain scenarios that atmospheric models alone may not handle well. Copyright © 2013 Elsevier Ltd. All rights reserved.

Design of a monitoring network over France in case of a radiological accidental release

Science.gov (United States)

Abida, Rachid; Bocquet, Marc; Vercauteren, Nikki; Isnard, Olivier

The Institute of Radiation Protection and Nuclear Safety (France) is planning the set-up of an automatic nuclear aerosol monitoring network over the French territory. Each of the stations will be able to automatically sample the air aerosol content and provide activity concentration measurements on several radionuclides. This should help monitor the French and neighbouring countries nuclear power plants set. It would help evaluate the impact of a radiological incident occurring at one of these nuclear facilities. This paper is devoted to the spatial design of such a network. Here, any potential network is judged on its ability to extrapolate activity concentrations measured on the network stations over the whole domain. The performance of a network is quantitatively assessed through a cost function that measures the discrepancy between the extrapolation and the true concentration fields. These true fields are obtained through the computation of a database of dispersion accidents over one year of meteorology and originating from 20 French nuclear sites. A close to optimal network is then looked for using a simulated annealing optimisation. The results emphasise the importance of the cost function in the design of a network aimed at monitoring an accidental dispersion. Several choices of norm used in the cost function are studied and give way to different designs. The influence of the number of stations is discussed. A comparison with a purely geometric approach which does not involve simulations with a chemistry-transport model is performed.

New tracers identify hydraulic fracturing fluids and accidental releases from oil and gas operations.

Science.gov (United States)

Warner, N R; Darrah, T H; Jackson, R B; Millot, R; Kloppmann, W; Vengosh, A

2014-11-04

Identifying the geochemical fingerprints of fluids that return to the surface after high volume hydraulic fracturing of unconventional oil and gas reservoirs has important applications for assessing hydrocarbon resource recovery, environmental impacts, and wastewater treatment and disposal. Here, we report for the first time, novel diagnostic elemental and isotopic signatures (B/Cl, Li/Cl, δ11B, and δ7Li) useful for characterizing hydraulic fracturing flowback fluids (HFFF) and distinguishing sources of HFFF in the environment. Data from 39 HFFFs and produced water samples show that B/Cl (>0.001), Li/Cl (>0.002), δ11B (25-31‰) and δ7Li (6-10‰) compositions of HFFF from the Marcellus and Fayetteville black shale formations were distinct in most cases from produced waters sampled from conventional oil and gas wells. We posit that boron isotope geochemistry can be used to quantify small fractions (∼0.1%) of HFFF in contaminated fresh water and likely be applied universally to trace HFFF in other basins. The novel environmental application of this diagnostic isotopic tool is validated by examining the composition of effluent discharge from an oil and gas brine treatment facility in Pennsylvania and an accidental spill site in West Virginia. We hypothesize that the boron and lithium are mobilized from exchangeable sites on clay minerals in the shale formations during the hydraulic fracturing process, resulting in the relative enrichment of boron and lithium in HFFF.

La prevención de accidentes

Directory of Open Access Journals (Sweden)

Chinchilla, M.

1966-02-01

Full Text Available Working accidents have a high moral and material impact, and are often easy to avoid, at least in about half the cases. Hence it is most important that campaigns for the reduction of these accidents should be correctly planned, so that such campaigns should not merely result in additional expense, and in a lowering of staff morale, when workers find themselves operating in an unpleasant and dangerous activity. In addition to special requirements, which may be studied in a later paper, and which must necessarily cover a very wide number of alternative cases, there are circumstances of a general nature, such as financial and moral consequences, and psychological repercussions, which influence the prevention of accidents and are the subject of this article.La notable repercusión moral y material que tienen los accidentes de trabajo y la fácil evitación de los mismos, por lo menos en la mitad de los casos, hacen sumamente importante que las campañas de prevención de accidentes estén bien orientadas y proyectadas, para evitar que se traduzcan, únicamente, en un gasto más y en una disminución de la moral del personal, al ver, éste, que está situado en medio de un ambiente desagradable y peligroso. Además de las normas particulares, que pueden ser objeto de otro trabajo posterior, y que han de ser forzosamente amplias, debido a la multiplicidad de factores que intervienen, hay, sin embargo, unas consideraciones de carácter general, tales como repercusiones económicas y morales y factores psicológicos que influyen en la prevención de accidentes y que son objeto del presente artículo.

Taking in account of contextual parameters in post accidental radioecology

International Nuclear Information System (INIS)

Renaud, Ph.; Maubert, H.; Bernie, J.C.

1997-01-01

The consequences on agricultural or breeding products of a radioactive accidental release are strongly linked to the context in which radioactive deposits occur: for example conditions of deposition in relation with agricultural and feeding schedules. These contextual parameters lead to a variation of results given by models greater than transfer factors uncertainties. For example, cow milk contamination stretches on several decades during the months following deposit as a function of feeding practices. In the same way, if a wheat plant receives the deposit during grain development, harvested grains will have a contamination level 10 3 to 10 4 times higher that if deposition occurs before the growing stage. To create a decision support system like the ASTRAL software, the need to realize a modelling of these contextual parameters has been encountered. Moreover, to help experts for evaluations, default informations relative to agricultural and breeding practices for France are given through databases. However, in case of a real accident, it would be important to re-initialize these contextual parameters which change from year to year, in order to obtain more precise assessments. (authors)

A structure for models of hazardous materials with complex behavior

International Nuclear Information System (INIS)

Rodean, H.C.

1991-01-01

Most atmospheric dispersion models used to assess the environmental consequences of accidental releases of hazardous chemicals do not have the capability to simulate the pertinent chemical and physical processes associated with the release of the material and its mixing with the atmosphere. The purpose of this paper is to present a materials sub-model with the flexibility to simulate the chemical and physical behaviour of a variety of materials released into the atmosphere. The model, which is based on thermodynamic equilibrium, incorporates the ideal gas law, temperature-dependent vapor pressure equations, temperature-dependent dissociation reactions, and reactions with atmospheric water vapor. The model equations, written in terms of pressure ratios and dimensionless parameters, are used to construct equilibrium diagrams with temperature and the mass fraction of the material in the mixture as coordinates. The model's versatility is demonstrated by its application to the release of UF 6 and N 2 O 4 , two materials with very different physical and chemical properties. (author)

Medical management of accidentally exposed individuals

International Nuclear Information System (INIS)

Nenot, J.C.

1998-01-01

Bone marrow aplasia is one of the main syndromes following a high dose accidental radiation exposure. Whilst transfusion and bone marrow transplantation have been used with some success starting with the first treatments of accident victims, other therapeutic strategies are needed. With the development of experimental and clinical haematology, promising new approaches to the treatment of aplasia have appeared. New trends for the treatment of haemopoietic injury based on bone marrow transplantation rely on new sources of compatible donor cells, such as cord blood, on the selection of immature haemopoietic cells and on new transplant regimens. Haemopoietic growth factors stimulate the proliferation and/or differentiation of haemopoietic progenitors and, possibly, stem cells. Furthermore, they act on the functions of mature cells. Currently, they have specific uses in haematology related to their role in the regulation of growth and in the differentiation of haemopoietic progenitor cells. Growth factors have already been used for the treatment of accidental radiation induced aplasia and lessons have been learned from their medical management and followup. (author)

Medical management of accidentally exposed individuals

Energy Technology Data Exchange (ETDEWEB)

Nenot, Jean-Claude [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

1997-12-31

Bone marrow aplasia is one of the main syndromes following a high dose accidental radiation exposure. Although both transfusion and bone marrow transplantation have been used with some success since the first treatments of patients, other therapeutic strategies are needed. New promising approaches of the treatment of aplasia have appeared with the development of experimental and clinical hematology. Some new trends for the treatment of the hematopoietic injury based on bone marrow transplantation rely on new sources of compatible donor cells, such as cord blood, on the selection of immature haemopoietic cells and on new transplant regimens. The hematopoietic growth factors stimulate proliferation and/or differentiation of hematopoietic progenitors and possibly stem cells. Furthermore, they act on the functions of mature cells. They have now specific uses in hematology, related to their role in the regulation of growth and differentiation of hematopoietic progenitor cells. Some growth factors have already been used for the treatment of accidental radiation-induced aplasia and lessons have been learned from their medical management and follow-up. (author) 30 refs.

Organically bound tritium (OBT) for various plants in the vicinity of a continuous atmospheric tritium release

International Nuclear Information System (INIS)

Vichot, L.; Boyer, C.; Boissieux, T.; Losset, Y.; Pierrat, D.

2008-01-01

In order to quantify tritium impact on the environmental, we studied vegetation continuously exposed to a tritiated atmosphere. We chose lichens as bio-indicators, trees for determination of past tritium releases of the Valduc Centre, and lettuce as edible vegetables for dose calculation regarding neighbourhood. The Pasquill and Doury models from the literature were tested to estimate tritium concentration in the air around vegetable for distance from the release point less than 500 m. The results in tree rings show that organically bound tritium (OBT) concentration was strongly correlated with tritium releases. Using the GASCON model, the modelled variation of OBT concentration with distance was correlated with the measurements. Although lichens are recognized as bio-indicators, our experiments show that they were not convenient for environmental surveys because their age is not definitive. Thus, tritium integration time cannot be precisely determined. Furthermore, their biological metabolism is not well known and tritium concentration appears to be largely dependent on species. An average conversion rate of HTO to OBT was determined for lettuce of about 0.20-0.24% h -1 . Nevertheless, even if it is equivalent to values already published in the literature for other vegetation, we have shown that this conversion rate, established by weekly samples, varies by a factor of 10 during the different stages of lettuce development, and that its variation is linked to the biomass derivative

Organically bound tritium (OBT) for various plants in the vicinity of a continuous atmospheric tritium release

Energy Technology Data Exchange (ETDEWEB)

Vichot, L. [Commissariat a l' Energie Atomique, CVA/DSTA/SPR/LMSE, 21120 Is-sur-Tille (France)], E-mail: laurent.vichot@cea.fr; Boyer, C.; Boissieux, T.; Losset, Y.; Pierrat, D. [Commissariat a l' Energie Atomique, CVA/DSTA/SPR/LMSE, 21120 Is-sur-Tille (France)

2008-10-15

In order to quantify tritium impact on the environmental, we studied vegetation continuously exposed to a tritiated atmosphere. We chose lichens as bio-indicators, trees for determination of past tritium releases of the Valduc Centre, and lettuce as edible vegetables for dose calculation regarding neighbourhood. The Pasquill and Doury models from the literature were tested to estimate tritium concentration in the air around vegetable for distance from the release point less than 500 m. The results in tree rings show that organically bound tritium (OBT) concentration was strongly correlated with tritium releases. Using the GASCON model, the modelled variation of OBT concentration with distance was correlated with the measurements. Although lichens are recognized as bio-indicators, our experiments show that they were not convenient for environmental surveys because their age is not definitive. Thus, tritium integration time cannot be precisely determined. Furthermore, their biological metabolism is not well known and tritium concentration appears to be largely dependent on species. An average conversion rate of HTO to OBT was determined for lettuce of about 0.20-0.24% h{sup -1}. Nevertheless, even if it is equivalent to values already published in the literature for other vegetation, we have shown that this conversion rate, established by weekly samples, varies by a factor of 10 during the different stages of lettuce development, and that its variation is linked to the biomass derivative.

Organically bound tritium (OBT) for various plants in the vicinity of a continuous atmospheric tritium release.

Science.gov (United States)

Vichot, L; Boyer, C; Boissieux, T; Losset, Y; Pierrat, D

2008-10-01

In order to quantify tritium impact on the environmental, we studied vegetation continuously exposed to a tritiated atmosphere. We chose lichens as bio-indicators, trees for determination of past tritium releases of the Valduc Centre, and lettuce as edible vegetables for dose calculation regarding neighbourhood. The Pasquill and Doury models from the literature were tested to estimate tritium concentration in the air around vegetable for distance from the release point less than 500 m. The results in tree rings show that organically bound tritium (OBT) concentration was strongly correlated with tritium releases. Using the GASCON model, the modelled variation of OBT concentration with distance was correlated with the measurements. Although lichens are recognized as bio-indicators, our experiments show that they were not convenient for environmental surveys because their age is not definitive. Thus, tritium integration time cannot be precisely determined. Furthermore, their biological metabolism is not well known and tritium concentration appears to be largely dependent on species. An average conversion rate of HTO to OBT was determined for lettuce of about 0.20-0.24% h(-1). Nevertheless, even if it is equivalent to values already published in the literature for other vegetation, we have shown that this conversion rate, established by weekly samples, varies by a factor of 10 during the different stages of lettuce development, and that its variation is linked to the biomass derivative.

Deuterium release from Li-D films exposed to atmospheric gases

Energy Technology Data Exchange (ETDEWEB)

Gasparyan, Yu. M., E-mail: YMGasparyan@mephi.ru [National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe highway 31, Moscow (Russian Federation); Popkov, A.S.; Krat, S.A.; Pisarev, A.A.; Vasina, Ya. A. [National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe highway 31, Moscow (Russian Federation); Lyublinski, I.E. [National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe highway 31, Moscow (Russian Federation); JSC “Red Star”, Electrolitniy proezd 1a, Moscow (Russian Federation); Vertkov, A.V. [JSC “Red Star”, Electrolitniy proezd 1a, Moscow (Russian Federation)

2017-04-15

Highlights: • The major part of deuterium desorbs from Li-D films in a very sharp peak at 670–710 K. • Exposure on air leads to intensive deuterium release from the Li-D film at room temperature. • Interaction with water vapor plays a major role in deuterium release from lithium films in the air. - Abstract: Deuterium release from Li-D films co-deposited on a Mo substrate at room temperature in magnetron discharge was investigated by means of thermal desorption spectroscopy. The deuterium concentration in the films was estimated to be D/Li = (14 ± 4)%. TDS from Li-D films just after co-deposition had a sharp peak at 670–710 K. Exposure of deposited Li-D films in the air at room temperature led to deuterium release. Comparison of release in air, water vapor, nitrogen, and oxygen demonstrated that water plays a major role in deuterium release in the air at low temperatures.

Probabilistic approach to external cloud dose calculations using onsite meteorological data

International Nuclear Information System (INIS)

Strenge, D.L.; Watson, E.C.; Bander, T.J.; Kennedy, W.E.

1976-01-01

A method is described for calculation of external total body and skin doses from accidental atmospheric releases of radionuclides based on hourly onsite meteorological data. The method involves calculation of dose values from a finite size cloud for each hourly observation for a given radionuclide inventory. These values are then used to determine the probability of occurrence of dose levels for specified release times ranging from one hour to 30 days

Aerosol release from a hot sodium pool and behaviour in inert gas atmosphere

International Nuclear Information System (INIS)

Sauter, H.; Schuetz, W.

1986-01-01

In the KfK-NALA program, experiments were carried out on the subject of aerosol release from a contaminated sodium pool into inert gas atmosphere under various conditions. Besides the determination of retention factors for fuel and fission products, the sodium aerosol system was investigated and characterized, concerning aerosol generation (evaporation rate), particle size, mass concentration, and deposition behaviour. Pool temperatures were varied between 700 and 1000 K at different geometrical and convective conditions. Technical scale experiments with a 531-cm 2 pool surface area were performed at natural convection in a 2.2-m 3 heated vessel, as well as additional small scale experiments at forced convection and 38.5-cm 2 pool surface area. A best-fit formula is given for the specific evaporation rate into a 400 K argon atmosphere. Approximately, the very convenient relation (dm/dt) (kg/m 2 /h) = 0.1 p (mm Hg) was found. The sodium aerosol diameter lay between 0.6 μm, less than 1 sec after production, and 2.5 μm at maximum concentration. The deposition behaviour was characterized by very small quantities ( 80%) on the bottom cover of the vessel. In the model theoretic studies with the PARDISEKO code, calculations were performed of the mass concentration, particle diameter and deposition behaviour. Agreement with the experimental values could not be achieved until a modulus was introduced to allow for turbulent deposition. (author)

Modelling accidental releases of dangerous gases into the lower troposphere from mobile sources

Czech Academy of Sciences Publication Activity Database

Bernatík, A.; Zimmermann, W.; Pitt, M.; Střižík, M.; Nevrlý, J.; Zelinger, Zdeněk

2008-01-01

Roč. 86, B3 (2008), s. 198-207 ISSN 0957-5820 R&D Projects: GA MŠk OC 111 Grant - others:GA MŠk OC 186 Institutional research plan: CEZ:AV0Z40400503 Keywords : major accidents * transportation of dangerous * substances modelling of release and dispersion Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 0.400, year: 2008

Accidental injuries and cutaneous contaminations during general ...

African Journals Online (AJOL)

Conclusion: This study has demonstrated that cutaneous, percutaneous, and mucous membrane exposure to patients blood and body fluids are common events during general surgical operations. Most accidental injuries were due to solid suture needle-sticks, mostly injured personnel were the primary operating surgeons, ...

On the accuracy, uniqueness and implication of dimensionless accidental relations between fundamental constants

International Nuclear Information System (INIS)

Bahran, M.; Univ. of Oklahoma, Norman-OK,

2002-01-01

Ibrahim et al(1) found an accidental formula relating the gravitational coupling constant, the electromagnetic fine structure constant and the proton to electron mass ratio. This work comments on such relation, in particular it studies the accuracy, uniqueness and unification implication of such accidental relation.(author)

Iodine release from sodium pool combustion

International Nuclear Information System (INIS)

Sagawa, N.; Fukushima, Y.; Yokota, N.; Akagane, K.; Mochizuki, K.

1979-01-01

Iodine release associated with sodium pool combustion was determined by heating 20 gr sodium containing sodium iodide, which was labelled with 131 I and dissolved in the sodium in concentration of 1∼1,000 ppm, to burn on a nickel crucible in conditioned atmosphere in a closed vessel of 0.4 m 3 . Oxygen concentration was changed in 5∼21% and humidity in 0∼89% by mixing nitrogen gas and air. Combustion products were trapped by a Maypack filter composed of particle filters, copper screens and activated charcoal beds and by a glass beads pack cooled by liquid argon. Iodine collected on these filter elements was determined by radio-gas chromatography. When the sodium sample burned in the atmosphere of air at room temperature, the release fractions observed were 6∼33% for sodium and 1∼20% for iodine added in the sodium. The release iodine was present in aerosol at a ratio of 98%, and the remainder in the gas form. The release fraction of iodine trended to decrease as oxygen concentration and humidity in the atmosphere increased. No organic iodide was detected in the combustion products. (author)

Accidental sulphuric acid poisoning in a newborn | Abdulkadir ...

African Journals Online (AJOL)

Accidental sulphuric acid poisoning in a newborn. I Abdulkadir, L Hassan, F Abdullahi, FD Akeredolu, S Purdue, M Okpe, AM Sobowale, OA Adewumi, U Abdullahi, MA Onadiran, TT Sholadoye, S Baba, WN Ogala ...

An accidental death due to electric grinder: Dupatta as a strangulation hazard

OpenAIRE

Deepak Herald D′Souza; Vina R Vaswani; Kishor Kumar Badiadka; Venkat Krishna Shenoy; Boban Babu

2013-01-01

Accidents could occur at home in any age group. Accidental ligature strangulation in adults could be prevented. We are reporting a case of a woman who died in her kitchen due to accidental strangulation by her dupatta while working with the electric grinder. This case highlights the need to educate the people about the safety and potential hazards of these machines.

POPFOOD - a computer code for calculating ingestion collective doses from continuous atmospheric releases

International Nuclear Information System (INIS)

Hotson, J.; Stacey, A.; Nair, S.

1980-07-01

The basic methodology incorporated in the POPFOOD computer code is described, which may be used to calculate equilibrium collective dose rates associated with continuous atmospheric releases and arising from consumption of a broad range of food products. The standard data libraries associated with the code are also described. These include a data library, based on the 1972 agricultural census, describing the spatial distribution of production, in England, Wales and Scotland, of the following food products: milk; beef and veal; pork bacon and ham; poultrymeat; eggs; mutton and lamb; root vegetables; green vegetables; fruit; cereals. Illustrative collective dose calculations were made for the case of 1 Ci per year emissions of 131 I, tritium and 14 C from a typical rural UK site. The calculations indicate that the ingestion pathway results in a greater collective dose than that via inhalation, with the contributions from consumption of root and green vegetables, and cereals being of comparable significance to that from liquid milk consumption, in all three cases. (author)

Radionuclides in an arctic terrestrial ecosystem affected by atmospheric release from the Kraton-3 accidental underground nuclear explosion. 2001-2002

International Nuclear Information System (INIS)

Ramzaev, V.; Golikov, V.; Mishine, A.; Kaduka, M.; Burtcev, I.; Gedeonov, A.; Bulatenkov, Y.U.; Strand, P.; Brown, J.

2004-01-01

Current distributions of artificial radionuclides (ARN) were studied in the main compartments of a larch-tree forest lethally affected by a radioactive release from the Kraton-3 peaceful underground nuclear explosion (65.9 deg N, 112.3 deg E; Yakutia, Russia; 1978). Samples of soil, fungi, lichens, mosses, grasses, shrubs and trees were obtained at points belonging to four zones categorised by the severity of the ecosystem damage. Sampling was supplemented by dose rate measurements in air and mapping. The area of forest characterised by 100% lethality to adult larches (Larix gmelinii) and with partial, visually-detectable damage of other more radio-resistance species (e.g. lichens, mosses) covers a territory of approximately 1.2 km 2 . Elevated levels of long-lived ARN were found at all sampling sites. Maximum registered levels of the ground contamination with radionuclides of Cs, Sr and Pu were three orders of magnitude higher than those expected from global fallout. The ratios of 137 Cs to some other significant radionuclides in the ground contamination were as follows [mean (range)]: 90 Sr - 0.57(0.02-0.93); 239,240 Pu 44(25-72); 60 Co 470(220-760). Twenty-three years after a discrete contamination event, 90-95% of the total deposited radiocesium and plutonium has still remained in the lichen-moss on-ground cover and in the top 5 cm organic soil layer. At the same time, vertical and horizontal migrations of 90 Sr in soil were more pronounced. Strong surface contamination with 137 Cs, 90 Sr and plutonium was detected at the twigs and bark of the dead larches. The young larches that grew at the contaminated area following the initial destruction of the forest demonstrated a substantial ability to accumulate 137 Cs, 90 Sr and plutonium via roots, while the bushes selectively accumulated mainly radiostrontium. In contrast, some fungi concentrated mostly radiocesium. The levels of gamma dose rate in air and the environmental contamination with 137 Cs were found to

Dose assessments for Greifswald and Cadarache with updated source terms from ITER NSSR-2

International Nuclear Information System (INIS)

Raskob, W.; Hasemann, I.

1998-08-01

The International Thermonuclear Experimental Reactor ITER is in its late engineering phase. One of the most important safety aspects - in particular for achieving public acceptance - is to assure that the releases of harzardous material are minimal during normal operation and for accidental events, even if very unlikely. To this purpose probabilistic dose assessments for accidental atmospheric releases of various ITER source terms which contain tritium and/or activation products were performed for the sites of Greifswald, Germany, and Cadarache, France. In addition, routine releases into the atmosphere and hydrosphere have been evaluated. No country specific rules were applied and the input parameters were adapted as far as possible to those used within former studies to achieve a better comparability with site independent dose assessments performed in the frame of ITER. The calculations were based on source terms which, for the first time, contain a combination of tritium and activation products. This allowed a better judgment of the contribution to the total dose of the individual fusion relevant materials. The results were compared to site independent dose limits defined in the frame of ITER. Annual doses from routine releases (CAT-I) are below 0.1 μSv for the aquatic scenarios and are close to 1 μSv for the atmospheric source terms. Source terms for two different categories of accidental releases, representing 'extremely unlikely events' (CAT-IV) and 'hypothetical sequences' (CAT-V), were investigated. In none of these cases, the release scenarios of category CAT-IV exceed the ITER limits. In addition, relevant characteristic quantities of the early dose distribution from the hypothetical scenarios of type CAT-V are still below 50 mSv or 100 mSv, values which are commonly used as lower reference values for evacuation in many potential home countries of ITER. These site specific assessments confirmed that the proposed release limits and thus the derived dose

The challenge of emergency response dispersion models on the meso-gamma urban scale: A case study of the July 26, 1993 oleum tank car spill in Richmond, California

International Nuclear Information System (INIS)

Baskett, R.L.; Vogt, P.J.; Schalk, W.W. III; Pobanz, B.M.; Foster, C.S.; Ellis, J.S.

1995-01-01

Atmospheric modeling of accidental toxic chemical releases requires accurate simulation of wind flows on the 1 to 25 km (meso-γ) scale. Complex meteorological fields have been a challenge to real-time emergency response models for decades especially when,wind observations are sparse. 'ne Gaussian model is a reasonable tool for the first few kilometers if the terrain is relatively flat, the wind flow is simple (no vertical structure), and meteorological data are available at the source. Most other situations demand three-dimensional models. Three-dimensional diagnostic wind field models depend on available meteorological observations which are subsequently adjusted by mass conservation to create a wind field over the terrain. Even in urban areas with multiple meteorological stations, 3-D diagnostic models may suffer from a lack of sufficient real-time observations. Deterministic models are stressed even more during variable low wind speed or stable atmospheric conditions, especially if the release is denser-than-air. Furthermore, typical wind direction measurement errors of 5 to 10 degrees extrapolated 10 or 20 km cause significant dislocations of downwind concentrations. This paper presents a recent case study that illustrates the difficulty of modeling accidental toxic releases in urban areas

Release enhancement of tritium from graphite by addition of hydrogen

International Nuclear Information System (INIS)

Saeki, Masakatsu; Masaki, N.M.

1989-01-01

The release behavior of tritium from graphite was studied in pure He and He + H 2 atmosphere. The release from powdered graphite was significantly enhanced in hydrogen environment. Apparent diffusion coefficients of tritium in graphite also became much higher in an atmosphere containing hydrogen than values obtained in pure helium atmosphere. A careful investigation of the release processes resulted in the conclusion that the most important process of tritium behaviour in graphite was diffusion, but the desorption process of tritium from the surface played a significant role. The enhancement of the desorption process was controlled by atomic hydrogen. (orig.)

Cytogenetic biological dosimetry. Dose estimative in accidental exposure

International Nuclear Information System (INIS)

Santos, O.R. dos; Campos, I.M.A. de.

1988-01-01

The methodology of cytogenetic biological dosimetry is studied. The application in estimation of dose in five cases of accidental exposure is reported. An hematological study and culture of lymphocytes is presented. (M.A.C.) [pt

A study of wet deposition of atmospheric tritium releases at the Ontario Power Generation, Pickering Nuclear Generating Station

International Nuclear Information System (INIS)

Crooks, G.; DeWilde, J.; Yu, L.

2001-01-01

The Ontario Power Generation,Pickering Nuclear Generating Station (PNGS) has been investigating deposition of atmospheric releases of tritium on their site. This study has included numerical dispersion modelling studies conducted over the past three years, as well as an ongoing field monitoring study. The following paper will present results of the field monitoring study and make comparisons to the numerical modelling. The results of this study could be of potential use to nuclear stations in quantifying tritium deposition in near field regions where building wake effects dominate pollutant dispersion

AXAIR: A Computer Code for SAR Assessment of Plume-Exposure Doses from Potential Process-Accident Releases to Atmosphere

Energy Technology Data Exchange (ETDEWEB)

Pillinger, W.L.

2001-05-17

This report describes the AXAIR computer code which is available to terminal users for evaluating the doses to man from exposure to the atmospheric plume from postulated stack or building-vent releases at the Savannah River Plant. The emphasis herein is on documentation of the methodology only. The total-body doses evaluated are those that would be exceeded only 0.5 percent of the time based on worst-sector, worst-case meteorological probability analysis. The associated doses to other body organs are given in the dose breakdowns by radionuclide, body organ and pathway.

Preliminary analysis of public dose from CFETR gaseous tritium release

Energy Technology Data Exchange (ETDEWEB)

Nie, Baojie [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China); University of Science and Technology of China, Hefei, Anhui 230027 (China); Ni, Muyi, E-mail: muyi.ni@fds.org.cn [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China); Lian, Chao; Jiang, Jieqiong [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China)

2015-02-15

Highlights: • Present the amounts and limit dose of tritium release to the environment for CFETR. • Perform a preliminary simulation of radiation dose for gaseous tritium release. • Key parameters about soil types, wind speed, stability class, effective release height and age were sensitivity analyzed. • Tritium release amount is recalculated consistently with dose limit in Chinese regulation for CFETR. - Abstract: To demonstrate tritium self-sufficiency and other engineering issues, the scientific conception of Chinese Fusion Engineering Test Reactor (CFETR) has been proposed in China parallel with ITER and before DEMO reactor. Tritium environmental safety for CFETR is an important issue and must be evaluated because of the huge amounts of tritium cycling in reactor. In this work, different tritium release scenarios of CFETR and dose limit regulations in China are introduced. And the public dose is preliminarily analyzed under normal and accidental events. Furthermore, after finishing the sensitivity analysis of key input parameters, the public dose is reevaluated based on extreme parameters. Finally, tritium release amount is recalculated consistently with the dose limit in Chinese regulation for CFETR, which would provide a reference for tritium system design of CFETR.

Measuring the visual salience of alignments by their non-accidentalness.

Science.gov (United States)

Blusseau, S; Carboni, A; Maiche, A; Morel, J M; Grompone von Gioi, R

2016-09-01

Quantitative approaches are part of the understanding of contour integration and the Gestalt law of good continuation. The present study introduces a new quantitative approach based on the a contrario theory, which formalizes the non-accidentalness principle for good continuation. This model yields an ideal observer algorithm, able to detect non-accidental alignments in Gabor patterns. More precisely, this parameterless algorithm associates with each candidate percept a measure, the Number of False Alarms (NFA), quantifying its degree of masking. To evaluate the approach, we compared this ideal observer with the human attentive performance on three experiments of straight contours detection in arrays of Gabor patches. The experiments showed a strong correlation between the detectability of the target stimuli and their degree of non-accidentalness, as measured by our model. What is more, the algorithm's detection curves were very similar to the ones of human subjects. This fact seems to validate our proposed measurement method as a convenient way to predict the visibility of alignments. This framework could be generalized to other Gestalts. Copyright © 2015 Elsevier Ltd. All rights reserved.

Development of three-dimensional trajectory model for detecting source region of the radioactive materials released into the atmosphere

Energy Technology Data Exchange (ETDEWEB)

Suh, Kyung Suk; Park, Ki Hyun; Min, Byung Il; Kim, Sora; Yang, Byung Mo [Nuclear Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-05-15

It is necessary to consider the overall countermeasure for analysis of nuclear activities according to the increase of the nuclear facilities like nuclear power and reprocessing plants in the neighboring countries including China, Taiwan, North Korea, Japan and South Korea. South Korea and comprehensive nuclear-test-ban treaty organization (CTBTO) are now operating the monitoring instruments to detect radionuclides released into the air. It is important to estimate the origin of radionuclides measured using the detection technology as well as the monitoring analysis in aspects of investigation and security of the nuclear activities in neighboring countries. A three-dimensional forward/backward trajectory model has been developed to estimate the origin of radionuclides for a covert nuclear activity. The developed trajectory model was composed of forward and backward modules to track the particle positions using finite difference method. A three-dimensional trajectory model was validated using the measured data at Chernobyl accident. The calculated results showed a good agreement by using the high concentration measurements and the locations where was near a release point. The three-dimensional trajectory model had some uncertainty according to the release time, release height and time interval of the trajectory at each release points. An atmospheric dispersion model called long-range accident dose assessment system (LADAS), based on the fields of regards (FOR) technique, was applied to reduce the uncertainties of the trajectory model and to improve the detective technology for estimating the radioisotopes emission area. The detective technology developed in this study can evaluate in release area and origin for covert nuclear activities based on measured radioisotopes at monitoring stations, and it might play critical tool to improve the ability of the nuclear safety field.

Joint research and development on toxic-material emergency response between ENEA and LLNL. 1982 progress report

International Nuclear Information System (INIS)

Gudiksen, P.; Lange, R.; Dickerson, M.; Sullivan, T.; Rosen, L.; Walker, H.; Boeri, G.B.; Caracciolo, R.; Fiorenza, R.

1982-11-01

A summary is presented of current and future cooperative studies between ENEA and LLNL researchers designed to develop improved real-time emergency response capabilities for assessing the environmental consequences resulting from an accidental release of toxic materials into the atmosphere. These studies include development and evaluation of atmospheric transport and dispersion models, interfacing of data processing and communications systems, supporting meteorological field experiments, and integration of radiological measurements and model results into real-time assessments

Personal protective clothing against accidental immersion

Energy Technology Data Exchange (ETDEWEB)

Elliott, David; Tipton, Michael [Surrey Univ., Robens Inst. of Health and Safety, Guildford (United Kingdom)

1997-12-31

The requirements for protective clothing against accidental immersion are discussed and the advantages and limitations of the main types of immersion protection available are analysed. The variety of designs available reflects the various circumstances under which they may be used. In broad terms in the offshore industry these include the following activities: normal work without risk of immersion but with a possible need to abandon the rig or ship; work in areas where there is risk of accidentally falling into the sea; flying over the sea in a helicopter. The first response to sudden immersion in sea water, which must usually be considered to be cold, is a sudden gasp often followed by an immediate phase of uncontrolled breathing. Since control of ones breathing between and under the breaking waves is essential to staying alive, this is a critical time. After surviving this initial ``cold shock`` phase, the effects of body heat loss become hazardous. Protection against hypothermia has been the priority for those providing survival suits and protective clothing while the hazard of the immediate response to cold immersion has been unrecognised to a large extent. (UK)

An accidental death due to electric grinder: Dupatta as a strangulation hazard

Directory of Open Access Journals (Sweden)

Deepak Herald D′Souza

2013-01-01

Full Text Available Accidents could occur at home in any age group. Accidental ligature strangulation in adults could be prevented. We are reporting a case of a woman who died in her kitchen due to accidental strangulation by her dupatta while working with the electric grinder. This case highlights the need to educate the people about the safety and potential hazards of these machines.

Risk assessment for stonecutting enterprises Accidental risks in the course of petroleum production and stone extraction

Science.gov (United States)

Aleksandrova, A. J.; Timofeeva, S. S.

2018-01-01

The paper is devoted to the assessment of accidental risks occurring at the works engaged in stone extracting and petroleum production. Two basic kinds of accidents common for stone extracting and petroleum production have been chosen to be discussed in the part under consideration. The most dangerous accidental situation characteristic for a stone milling line is an unsanctioned explosion, UE, of blasting agents used for the development of stone deposits. The analysis of a risk occurrence in certain accidental situations is to be carried out. With reference to petroleum extraction, a combustibles and lubricants (C & L) explosion is the most dangerous of characteristic accidental situations. To reveal the most probable causes of accidental situations to be realized, a graph of cause and effect relations has been constructed for each of the accidental situations most probable causes to real situation of an accident. Disasters of a natural origin are the most probable causes of unsanctioned explosions at the deposits of stone raw materials. Technology related natural disasters are the most probable causes of unsanctioned explosions to be realized at multiple well platforms engaged in petroleum production.

Accidental poisoning with detomidine and butorphanol.

Science.gov (United States)

Hannah, N

2010-09-01

This is a case report concerning a veterinarian who spilled detomidine and butorphanol on dermatitic hands while sedating a horse. This resulted in acute poisoning from which the patient spontaneously recovered with supportive management. Veterinarians often suffer from occupational dermatitis and handle strong sedatives with no gloves while working around unpredictable animals. Thus, this group is at risk of accidental self-poisoning from this method.

accidental injuries in children (physical child abuse)

African Journals Online (AJOL)

2016-12-06

Dec 6, 2016 ... are often due to minor accidental injuries. However ... In dark-skinned children, bruises may be confused with café-au-lait spots. .... A bruise should not be examined in isolation if reason- ... dren with intellectual disability, such as autism and hy- ... opmental stage, social and environmental factors includ-.

21 CFR 1002.20 - Reporting of accidental radiation occurrences.

Science.gov (United States)

2010-04-01

...: Accidental Radiation Occurrence Reports (HFZ-240), Office of Communication, Education, and Radiation Programs, 9200 Corporate Blvd., Rockville, MD 20850, and the reports and their envelopes shall be distinctly...

Methods For Calculating Thyroid Doses to The Residents Of Ozersk Due to 131I Releases From The Stacks of The Mayak Production Association

Energy Technology Data Exchange (ETDEWEB)