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

Natural atmospheric radioactivity

International Nuclear Information System (INIS)

Renoux, A.

1986-01-01

After having summed up the different old or new units, used in radioactivity and radioprotection, the origins of atmospheric radioactivity are reported. Next the authors deal with the air content in radon, thoron and their radioactive descendants, insisting on the variations of the radon air content and on the radioactive balance between radon and its descendants. Then a few notions concerning the natural radioactive aerosol are developed: electric charge state, granulometric distribution. The possible effects of natural atmospheric radioactivity on man are studied with a distinction between inner irradiation and outer irradiation, an average assessment is shown. Finally the important problem of radon in inhabitations is approached [fr

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)

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

Hazard of radioactive releases resulted from coal burning

International Nuclear Information System (INIS)

Gabbard, V.

1995-01-01

Consideration is given to the data, pointing to the fact, that coal-burning power plants release of radioactive substances, contained in gaseous wastes, is not less, than the same one of nuclear power plants. The necessity of regulating emission of these substance in atmosphere by analogy with nuclear power industry is shown. 1 fig

Radioactive releases from a thorium-contaminated site in Wayne, New Jersey

International Nuclear Information System (INIS)

Wang, J.; Yang, J.; Merry-Libby, P.

1985-01-01

Various residues and wastes from the production of thorium and rare earths from monazite ore are buried on a hillside in Wayne, New Jersey. In addition, contaminated materials (primarily soils) from nearby vicinity properties are being consolidated onto the Wayne site. The US Department of Energy plans to stabilize all the contaminated materials on an interim basis (20 years) until funding is available to remove them to another location. In order to evaluate the effectiveness of interim stabilization measures, pre-remedial action radioactive releases are compared to estimated releases under a reference stabilization option (one meter of soil cover). Two potential pathways are examined: (1) airborne radioactive gases (thoron and radon) and particulates, and (2) seepage into the near-surface groundwater. The relative reduction of releases into the air and groundwater for the reference stabilization option is analyzed using mathematical models for radioactive gas fluxes and atmospheric dispersion as well as groundwater transport and dispersion. The consequent health implications for nearby individuals and the general population are also estimated. Health effects due to radioactive releases are estimated to be insignificant

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)

A guide to the use of TIRION. A computer programme for the calculation of the consequences of releasing radioactive material to the atmosphere

International Nuclear Information System (INIS)

Kaiser, G.D.

1976-11-01

A brief description is given of the contents of TIRION, which is a computer program that has been written for use in calculations of the consequences of releasing radioactive material to the atmosphere. This is followed by a section devoted to an account of the control and data cards that make up the input to TIRION. (author)

Sellafield (release of radioactivity)

Energy Technology Data Exchange (ETDEWEB)

Cunningham, J; Goodlad, A; Morris, M

1986-02-06

A government statement is reported, about the release of plutonium nitrate at the Sellafield site of British Nuclear Fuels plc on 5 February 1986. Matters raised included: details of accident; personnel monitoring; whether radioactive material was released from the site; need for public acceptance of BNFL activities; whether plant should be closed; need to reduce level of radioactive effluent; number of incidents at the plant.

Evaluation of food contamination and health risks caused by radioactive fallout released from atmospheric nuclear detonation tests

International Nuclear Information System (INIS)

Shimada, Yoko; Ito, Yoshihiko; Yoneda, Minoru; Morisawa, Shinsuke

2011-01-01

Before Fukushima Daiichi nuclear disaster, radionuclide like 137 Cs released from atmospheric nuclear detonation tests and Chernobyl disaster has been transported worldwide in the environment and finally taken up by humans through various pathways. In this research, dietary intake of 137 Cs and the related health risks to Japanese caused by chronic global radioactive food contamination from 1945 to 2010 were evaluated by using the mathematical model for the evaluation of global distribution of 137 Cs with food ingestion and domestic and international food supply model. The results of this evaluation can show a background situation before Fukushima disaster and give important information for the risk assessment of this disaster. (author)

Massive radioactive releases have a great impact on the accident costs

International Nuclear Information System (INIS)

Pascucci-Cahen, L.; Momal, P.

2013-01-01

This article investigates the costs of the consequences of a nuclear accident. The importance of the costs is very dependant on the amount of radioactivity released in the environment during the accident. 2 severe accidents are considered, each accident involves the fusion of the core but the first is characterized by a limited amount of radioactivity released in the atmosphere while the second involves massive radioactive releases. The list of consequences is as comprehensive as possible: site decontamination and dismantlement, land decontamination, sanitary impacts, population displacement, agricultural and economical losses, impact on tourism, impact on the production of electricity...In the first case the total cost reaches 120 billion euros which is still manageable at the scale of a country whereas in the second case the bill reaches 430 billion euros which is unbearable for a country. The very slight probability of such events does not compensate for their catastrophic potentials. (A.C.)

PAVAN: an atmospheric-dispersion program for evaluating design-basis accidental releases of radioactive materials from nuclear power stations

International Nuclear Information System (INIS)

Bander, T.J.

1982-11-01

This report provides a user's guide for the NRC computer program, PAVAN, which is a program used by the US Nuclear Regulatory Commission to estimate downwind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Such an assessment is required by 10 CFR Part 100 and 10 CFR Part 50. The program implements the guidance provided in Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants. 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 (e.g., through building penetrations and vents) or elevated releases from free-standing stacks. Various options may be selected by the user. They 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. It cannot handle multiple emission sources. A description of the main program and all subroutines is provided. Also included as appendices are a complete listing of the program and two test cases with the required data inputs and the resulting program outputs

Underground Nuclear Explosions and Release of Radioactive Noble Gases

Science.gov (United States)

Dubasov, Yuri V.

2010-05-01

Over a period in 1961-1990 496 underground nuclear tests and explosions of different purpose and in different rocks were conducted in the Soviet Union at Semipalatinsk and anovaya Zemlya Test Sites. A total of 340 underground nuclear tests were conducted at the Semipalatinsk Test Site. One hundred seventy-nine explosions (52.6%) among them were classified as these of complete containment, 145 explosions (42.6%) as explosions with weak release of radioactive noble gases (RNG), 12 explosions (3.5%) as explosions with nonstandard radiation situation, and four excavation explosions with ground ejection (1.1%). Thirty-nine nuclear tests had been conducted at the Novaya Zemlya Test Site; six of them - in shafts. In 14 tests (36%) there were no RNG release. Twenty-three tests have been accompanied by RNG release into the atmosphere without sedimental contamination. Nonstandard radiation situation occurred in two tests. In incomplete containment explosions both early-time RNG release (up to ~1 h) and late-time release from 1 to 28 h after the explosion were observed. Sometimes gas release took place for several days, and it occurred either through tunnel portal or epicentral zone, depending on atmospheric air temperature.

Protection of atmospheric air against radioactive gas and aerosol contaminants

International Nuclear Information System (INIS)

Zykova, A.S.

1984-01-01

Measures for contamination protection of atmospheric air subdivided into active and passive ones, are considered. The active measures envisage: development and application of waste-free flowsheets, use of flowsheets which restrict formation of gaseous-aerosol discharges; application of highly efficient treatment facilities torage. Dispersion of radioactive substances, released with discharges to the atmosphere, using high stacks; development of the corresponding site-selection solutions and arrangement of sanitary protective zones belong to passive measures. Measures for protection of atmospheric air also include waste and air contamination monitoring. The measures described are considered as applied to NPPs

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.

PWR-GALE, Radioactive Gaseous Release and Liquid Release from PWR

International Nuclear Information System (INIS)

Chandrasekaran, T.; Lee, J.Y.; Willis, C.A.

1988-01-01

1 - Description of program or function: The PWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from pressurized water reactors (PWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment. 2 - Method of solution: GALE calculates expected releases based on 1) standardized coolant activities derived from ANS Standards 18.1 Working Group recommendations, 2) release and transport mechanisms that result in the appearance of radioactive material in liquid and gaseous waste streams, 3) plant-specific design features used to reduce the quantities of radioactive materials ultimately released to the environs, and 4) information received on the operation of nuclear power plants. 3 - Restrictions on the complexity of the problem: The liquid release portion of GALE uses subroutines taken from the ORIGEN (CCC-217) to calculate radionuclide buildup and decay during collection, processing, and storage of liquid radwaste. Memory requirements for this part of the program are determined by the large nuclear data base accessed by these subroutines

The estimation of areas of ground that may be contaminated after an accidental release of pollutant to the atmosphere

International Nuclear Information System (INIS)

Corbett, J.O.

1979-01-01

A method is developed for calculating the area of ground contaminated above a prescribed level after an accidental release of radioactivity or any other pollutant to the atmosphere. Numerical calculations are made for a wide range of releases, atmospheric conditions and rates of wet and dry deposition. It is shown that high atmospheric stability and rain both tend to maximize the area of significant contamination for most of the plausible range of releases. However, for very large hypothetical releases, dry conditions with an unstable atmosphere spread significant contamination furthest afield. (author)

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

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

Atmospheric Dispersion Assessment for Potential Accidental Releases at Yonggwang Nuclear Power Plants

International Nuclear Information System (INIS)

Na, Man Gyun; Sim, Young Rok; Jung, Chul Kee; Lee, Goung Jin; Kim, Soong Pyung; Chung, Sung Tai

2000-01-01

XOQ DW code is currently used to assess the atmospheric dispersion for the routine releases of radioactive gaseous effluents at Yonggwang nuclear power plants. This code was developed based on XOQDOQ code and an additional code is required to assess the atmospheric dispersion for potential accidental releases. In order to assess the atmospheric dispersion for the accidental releases, XOQAR code has been developed by using PAVAN code that is based on Reg. Guide 1.145. The terrain data of XOQ DW code inputs and the relative concentrations (X/Q) of XOQ DW code outputs are used as the inputs of the XOQAR code through the interface with XOQ DW code. By using this code, the maximum values of X/Q at exclusion area and low population zone boundaries except for sea areas were assessed as 1.33 x 10 -4 and 7.66 x 10 -6 sec/m 3 , respectively. Through the development of this code, a code system is prepared for assessing the atmospheric dispersion for the accidental releases as well as the routine releases. This developed code can be used for other domestic nuclear power plants by modifying the terrain input data

Parametric study of radioactive release from a breached containment

International Nuclear Information System (INIS)

Kenigsberg, A.; Hasan, D.; Elias, E.

1980-01-01

A hypothetical accident is analyzed, in which an external (out-of-plant) natural or man-made event causes a loss-of-coolant accident after penetrating the containment wall. The computer codes CONTEMPT and RELAP4 have been used to study the containment thermal-hydraulic behavior during the accident. Results are given in the form of graphs showing the thermal-hydraulic response of the containment and the profile of radioactive release to the atmosphere. The physical model and input data are discussed. 13 refs

Static and mobile networks design for atmospheric accidental releases monitoring

International Nuclear Information System (INIS)

Abida, R.

2010-01-01

The global context of my PhD thesis work is the optimization of air pollution monitoring networks, but more specifically it concerns the monitoring of accidental releases of radionuclides in air. The optimization problem of air quality measuring networks has been addresses in the literature. However, it has not been addresses in the context of surveillance of accidental atmospheric releases. The first part of my thesis addresses the optimization of a permanent network of monitoring of radioactive aerosols in the air, covering France. The second part concerns the problem of targeting of observations in case of an accidental release of radionuclides from a nuclear plant. (author)

Releases of radioactivity at the Savannah River Plant, 1954--1985

International Nuclear Information System (INIS)

Zeigler, C.C.; Lawrimore, I.B.

1988-07-01

Radioactive releases from Savannah River Plant (SRP) facilities to air, water and earthen seepage basins have been monitored and tabulated throughout the history of the site. The purpose of this report is to provide a source of data on routine releases of radioactivity to air, water and seepage basins that can be used for analyses of trends, environmental impact, etc. As used in this report, routine radioactive releases means radioactive materials that are released through established effluents from process facilities. This report provides a summary of radioactive releases that inflects the release values contained m records and documents from startup through 1985

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

Site-sensitive hazards of potential airborne radioactive release from sources on the Kola peninsula

International Nuclear Information System (INIS)

Bergman, R.; Thaning, L.; Baklanov, A.

1998-02-01

In this work we focus on cases of airborne releases from some of the sources on the Kola Peninsula - primarily nuclear reactors on submarines and the Kola Nuclear Power Plant (KNPP). The purpose of our study is to illustrate, and discuss some features - dependent on site and release characteristics - of the deposition patterns resulting from assumed unit radioactive releases to the atmosphere from a location at a fjord and from the KNPP in Polyarnye Zori. Using meteorological data for one real weather situation, the analysis is based on simulating the transport in air of assumed radioactive releases and estimating the deposition pattern on local, meso- and regional scales. By allowing unit releases to occur simultaneously from the site at the fjord and from the power plant (and with the same release profile in time) comparisons are made of differences in deposition patterns in and outside the Kola region. In this case study a set of assumed release heights, durations of the release, and particle size distributions are applied to indicate the dependence for the resulting deposition pattern on these parameters

Releases of radioactivity at the Savannah River Plant, 1954-1980

Energy Technology Data Exchange (ETDEWEB)

Ashley, C.; Zeigler, C. C.; Culp, P. A.

1982-01-01

This report contains summaries of releases of radioactivity to onsite seepage basins and to plant effluents for each year since plant startup (1954 through 1980). Releases for the years 1954 through 1959 were reassessed in 1974 and assigned release values for specific long-lived radionuclides. These long-lived radionuclides (half-lives greater than 1 year) are the only radionuclides included for the years 1954 through 1970. Since 1970 all detectable radionuclides have been included. Measured migration o radionuclides from F-, H-, and K-Area seepage basins and desorption of /sup 137/Cs from the Four Mile Creek stream bed are included in Summary B of this report. Summaries of monthly releases for 1979 and 1980 and total SRP releases by radionuclide in three categories: liquid to seepage basins, liquid to streams, and atmospheric are also included. Monthly releases for 1979 are included because the 1979 issue of this report was not published. All 1979 data are included in this report.

Atmospheric natural radioactivity outdoors

International Nuclear Information System (INIS)

Renoux, A.

1985-01-01

Following a short account of natural atmospheric radioactivity, radon concentrations are given as well as their variations with time obtained by means of a original apparatus developped in Brest. The radioactive equilibrium of radon and its daughters is then considered, many experiments demonstrating that equilibrium is seldom reached even for 218 Po (RaA). Finally, some characteristics of natural radioactive aerosols are studied: charge, particle size distribution (demonstrating they are fine aerosols since only 30 per cent are made of particles with radii exceeding 0,1 μm) [fr

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)

Models and methods to evaluate consequences of the release of airborne radioactivity from NNPs

International Nuclear Information System (INIS)

Anh, T.H.

1989-01-01

To examine the radioactive contamination and possible consequences of a nuclear power plant on living organisms during its operation periodes, the computer programmes were elaborated for assessing its fluences on the environment. The authors have resolved the following problems: i) Calculation of fission product inventories in the reactor core; ii) Calculation of the atmospheric dispersion of the released radionuclides under the meteorological conditions as well as the deposition of the radioactive substances on the soil; iii) Calculation of the irradiation doses

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

Methodology for calculating radiation doses from radioactivity released to the environment

International Nuclear Information System (INIS)

Killough, G.G.; McKay, L.R.

1976-03-01

This document represents a compilation of the principal environmental transport and dosimetry models developed, adapted, and implemented by the Radiological Analyses and Applications Group of the Environmental Sciences Division of the Oak Ridge National Laboratory. The transport of released radioactivity through the natural environment is discussed in four sections: atmospheric dispersion, resuspension of material by wind action, terrestrial transport, and movement of material in underground water seepage. The discussion of dose to man and biota is divided into internal and external exposure sections. And finally, a developmental model (CONDOS) which estimates the dose to a population resulting from the manufacture, storage, distribution, use, and disposal of consumer products which contain radioactivity is described. Numerous tables are included

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)

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)

Analysis on the atmospheric dispersion of radioactive materials

International Nuclear Information System (INIS)

Nagai, Haruyasu

2012-01-01

JAEA has been developing a new prediction system of comprehensive movement, SPEEDI-MP (SPEEDI Multi-model Package), which can treat continuously and strictly with the migration behavior of radioactive materials at atmosphere, sea, and land region. JAEA has been further promoting the detail analysis of atmospheric migration of radioactive materials dispersed by an accident. Then, using a part of this system, the atmospheric-diversion prediction system, WSPEEDI-II, the atmospheric diversion mass and the atmospheric diffusion analysis were carried out. This issue reports the summary. (M.H.)

SUBDOSA: a computer program for calculating external doses from accidental atmospheric releases of radionuclides

International Nuclear Information System (INIS)

Strenge, D.L.; Watson, E.C.; Houston, J.R.

1975-06-01

A computer program, SUBDOSA, was developed for calculating external γ and β doses to individuals from the accidental release of radionuclides to the atmosphere. Characteristics of SUBDOSA are: doses from both γ and β radiation are calculated as a function of depth in tissue, summed and reported as skin, eye, gonadal, and total body dose; doses are calculated for releases within each of several release time intervals and nuclide inventories and atmospheric dispersion conditions are considered for each time interval; radioactive decay is considered during the release and/or transit using a chain decay scheme with branching to account for transitions to and from isomeric states; the dose from gamma radiation is calculated using a numerical integration technique to account for the finite size of the plume; and the program computes and lists the normalized air concentrations at ground level as a function of distance from the point of release. (auth)

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

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

A procedure for estimating site specific derived limits for the discharge of radioactive material to the atmosphere

CERN Document Server

Hallam, J; Jones, J A

1983-01-01

Generalised Derived Limits (GDLs) for the discharge of radioactive material to the atmosphere are evaluated using parameter values to ensure that the exposure of the critical group is unlikely to be underestimated significantly. Where the discharge is greater than about 5% of the GDL, a more rigorous estimate of the derived limit may be warranted. This report describes a procedure for estimating site specific derived limits for discharges of radioactivity to the atmosphere taking into account the conditions of the release and the location and habits of the exposed population. A worksheet is provided to assist in carrying out the required calculations.

Models for the evaluation of ingestion doses from the consumption of terrestrial foods following an atmospheric radioactive release

International Nuclear Information System (INIS)

Nair, S.

1984-04-01

Various methods are described which have been incorporated in the FOODWEB module of the CEGB's NECTAR environmental code and are currently being used within CEGB to assess ingestion doses from consumption of terrestrial foods following an atmospheric radioactive release. Four foodchain models which have been developed within CEGB are fully described and results of typical calculations presented. Also given are the results of a validation of the dynamic model against measured 90 Sr and 137 Cs levels in milk in the U.K. resulting from weapons fallout. Methods are also described for calculating individual and population doses from ingestion using the results of the model calculations. The population dose calculations utilise a data base describing the spatial distribution of production of a wide range of agricultural products. The development of such a data base for Great Britain is described, based on the 1972 land use and livestock census, and maps are presented for each agricultural product. (U.K.)

Hazard of radioactive releases resulted from coal burning; Opasnost` vysvobozhdeniya radioaktivnykh produktov pri szhiganii uglya

Energy Technology Data Exchange (ETDEWEB)

Gabbard, V

1995-09-01

Consideration is given to the data, pointing to the fact, that coal-burning power plants release of radioactive substances, contained in gaseous wastes, is not less, than the same one of nuclear power plants. The necessity of regulating emission of these substance in atmosphere by analogy with nuclear power industry is shown. 1 fig.

Portable Filtered Air Suction System for Released Radioactive Gases Prevention under a Severe Accident of NPPs

International Nuclear Information System (INIS)

Gu, Beom W.; Choi, Su Y.; Rim, Chun T.

2013-01-01

In this paper, the portable filtered air suction system (PoFASS) for released radioactive gases prevention under a severe accident of NPP is proposed. This technology can prevent the release of the radioactive gases to the atmosphere and it can be more economical than FVCS because PoFASS can cover many NPPs with its high mobility. The conceptual design of PoFASS, which has the highest cost effectiveness and robustness to the environment condition such as wind velocity and precipitation, is suggested and the related previous research is introduced in this paper. The portable filtered air suction system (PoFASS) for released radioactive gases prevention can play a key role to mitigate the severe accident of NPP with its high cost effectiveness and robustness to the environment conditions. As further works, the detail design of PoFASS to fabricate a prototype for a demonstration will be proceeded. When released radioactive gases from the broken containment building in the severe accident of nuclear power plants (NPPs) such as the Chernobyl and Fukushima accidents occur, there are no ways to prevent the released radioactive gases spreading in the air. In order to solve this problem, several European NPPs have adopted the filtered vented containment system (FVCS), which can avoid the containment failure through a pressure relief capability to protect the containment building against overpressure. However, the installation cost of FVCS for a NPP is more than $10 million and this system has not been widely welcomed by NPP operating companies due to its high cost

GPU-based parallel computing in real-time modeling of atmospheric transport and diffusion of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Santos, Marcelo C. dos; Pereira, Claudio M.N.A.; Schirru, Roberto; Pinheiro, André, E-mail: jovitamarcelo@gmail.com, E-mail: cmnap@ien.gov.br, E-mail: schirru@lmp.ufrj.br, E-mail: apinheiro99@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2017-07-01

Atmospheric radionuclide dispersion systems (ARDS) are essential mechanisms to predict the consequences of unexpected radioactive releases from nuclear power plants. Considering, that during an eventuality of an accident with a radioactive material release, an accurate forecast is vital to guide the evacuation plan of the possible affected areas. However, in order to predict the dispersion of the radioactive material and its impact on the environment, the model must process information about source term (radioactive materials released, activities and location), weather condition (wind, humidity and precipitation) and geographical characteristics (topography). Furthermore, ARDS is basically composed of 4 main modules: Source Term, Wind Field, Plume Dispersion and Doses Calculations. The Wind Field and Plume Dispersion modules are the ones that require a high computational performance to achieve accurate results within an acceptable time. Taking this into account, this work focuses on the development of a GPU-based parallel Plume Dispersion module, focusing on the radionuclide transport and diffusion calculations, which use a given wind field and a released source term as parameters. The program is being developed using the C ++ programming language, allied with CUDA libraries. In comparative case study between a parallel and sequential version of the slower function of the Plume Dispersion module, a speedup of 11.63 times could be observed. (author)

GPU-based parallel computing in real-time modeling of atmospheric transport and diffusion of radioactive material

International Nuclear Information System (INIS)

Santos, Marcelo C. dos; Pereira, Claudio M.N.A.; Schirru, Roberto; Pinheiro, André; Coordenacao de Pos-Graduacao e Pesquisa de Engenharia

2017-01-01

Atmospheric radionuclide dispersion systems (ARDS) are essential mechanisms to predict the consequences of unexpected radioactive releases from nuclear power plants. Considering, that during an eventuality of an accident with a radioactive material release, an accurate forecast is vital to guide the evacuation plan of the possible affected areas. However, in order to predict the dispersion of the radioactive material and its impact on the environment, the model must process information about source term (radioactive materials released, activities and location), weather condition (wind, humidity and precipitation) and geographical characteristics (topography). Furthermore, ARDS is basically composed of 4 main modules: Source Term, Wind Field, Plume Dispersion and Doses Calculations. The Wind Field and Plume Dispersion modules are the ones that require a high computational performance to achieve accurate results within an acceptable time. Taking this into account, this work focuses on the development of a GPU-based parallel Plume Dispersion module, focusing on the radionuclide transport and diffusion calculations, which use a given wind field and a released source term as parameters. The program is being developed using the C ++ programming language, allied with CUDA libraries. In comparative case study between a parallel and sequential version of the slower function of the Plume Dispersion module, a speedup of 11.63 times could be observed. (author)

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

A general advection-diffusion model for radioactive substance dispersion released from nuclear power plants

International Nuclear Information System (INIS)

Buske, D.

2011-01-01

The present contribution focuses on the question of radioactive material dispersion after discharge from a nuclear power plant in the context of micro-meteorology, i.e. an atmospheric dispersion model. The advection-diffusion equation with Fickian closure for the turbulence is solved for the atmospheric boundary layer where the eddy diffusivity coefficients and the wind profile are assumed to be space dependent. The model is solved in closed form using integral transform and spectral theory. Convergence of the solution is discussed in terms of a convergence criterion using a new interpretation of the Cardinal Theorem of Interpolation theory and Parseval's theorem. The solution is compared to other methods and model adequacy is analyzed. Model validation is performed against experimental data from a controlled release of radioactive material at the Itaorna Beach (Angra dos Reis, Rio de Janeiro state, Brazil, 1985). (author)

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

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

Atmospheric dispersion of radioactive materials

International Nuclear Information System (INIS)

Chino, Masamichi

1988-01-01

The report describes currently available techniques for predicting the dispersion of accidentally released radioactive materials and techniques for visualization using computer graphics. A simulation study is also made on the dispersion of radioactive materials released from the Chernobyl plant. The simplest models include the Gauss plume model and the puff model, which cannot serve to analyze the effects of the topography, vertical wind shear, temperature inversion layer, etc. Numerical analysis methods using advection and dispersion equations are widely adopted for detailed evaluation of dispersion in an emergency. An objective analysis model or a hydrodynamical model is often used to calculate the air currents which are required to determine the advection. A small system based on the puff model is widely adopted in Europe, where the topography is considered to have only simple effects. A more sophisticated large-sized system is required in nuclear facilities located in an area with more complex topographic features. An emergency system for dispersion calculation should be equipped with a graphic display to serve for quick understanding of the radioactivity distribution. (Nogami, K.)

10 CFR 61.41 - Protection of the general population from releases of radioactivity.

Science.gov (United States)

2010-01-01

... radioactivity. 61.41 Section 61.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR... from releases of radioactivity. Concentrations of radioactive material which may be released to the... maintain releases of radioactivity in effluents to the general environment as low as is reasonably...

Discussion on the methods for calculation release limits for low-level radioactive waste

International Nuclear Information System (INIS)

Cao Fengbo; Liu Xiaochao

2012-01-01

The release request for low-level radioactive waste are briefly described in this paper. Associating with the conditions of low-level radioactive waste of some radioactive waste processing station, the methods and gist for calculating release limits for low-level radioactive waste with national release limits and annual effective dose limit for the public or the occupation are discussed. Then release limits for the low-level radioactive waste are also proposed. (authors)

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

An update on radioactive release and exposures after the Fukushima Dai-ichi nuclear disaster.

LENUS (Irish Health Repository)

McLaughlin, P D

2012-09-01

On 11 March 2011, the Richter scale 0.9-magnitude Tokohu earthquake and tsunami struck the northeast coast of Japan, resulting in widespread injury and loss of life. Compounding this tragic loss of life, a series of equipment and structural failures at the Fukushima Dai-ichi nuclear power plant (FDNP) resulted in the release of many volatile radioisotopes into the atmosphere. In this update, we detail currently available evidence about the nature of immediate radioactive exposure to FDNP workers and the general population. We contrast the nature of the radioactive exposure at FDNP with that which occurred at the Chernobyl power plant 25 years previously. Prediction of the exact health effects related to the FDNP release is difficult at present and this disaster provides the scientific community with a challenge to help those involved and to continue research that will improve our understanding of the potential complications of radionuclide fallout.

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)

General Atomic's radioactive gas recovery system

International Nuclear Information System (INIS)

Mahn, J.A.; Perry, C.A.

1975-01-01

General Atomic Company has developed a Radioactive Gas Recovery System for the HTGR which separates, for purposes of retention, the radioactive components from the non-radioactive reactor plant waste gases. This provides the capability for reducing to an insignificant level the amount of radioactivity released from the gas waste system to the atmosphere--a most significant improvement in reducing total activity release to the environment. (U.S.)

Impact on the marine environment of radioactive releases resulting from the Fukushima-Daiichi nuclear accident. April 4, 2011

International Nuclear Information System (INIS)

2011-01-01

After having outlined that measurements taken over several days in the sea water in the vicinity of the power station have revealed severe contamination of the marine environment by various radionuclides released as a result of the accident at the Fukushima-Daiichi nuclear power station, this report describes the origins of the contamination of the marine environment (release of liquid effluents directly into the sea in the vicinity of the damaged reactors, atmospheric fallout onto the surface of the sea, conveyance of radioactive pollution by rainout of contaminated ground). Then, while proposing several maps, the authors analyse and comment the dispersion in the sea of radioactive pollutants by addressing the following issues: topography of the sea bed and sea currents off the Japanese coast, immediate or short term dispersion (a few days), mid-term dispersion (weeks and months), long term and large scale future of the radioactive pollutants. Finally, the report briefly discusses the impact of radioactive pollution on living species

Fifty years of atmospheric radioactivity monitoring by the German Meteorological Service

International Nuclear Information System (INIS)

2006-01-01

At a commemorative event at the Langen Training and Congress Center on 8 and 9 June 2005 it was brought to the attention of the audience that the German Meteorological Service has been charged with the sovereign task of monitoring atmospheric radioactivity since 8 August 1955. The purpose of this commission at the time was to measure traces of radioactivity in the atmosphere and precipitation and make forecasts on the movement of radioactive air masses. This was motivated by the above-ground nuclear tests carried out by the USA and the Soviet Union and the resulting measurable increase in atmospheric radioactivity levels. Equipped as it was with the necessary infrastructure the German Meteorological Service offered to take on this monitoring task. The importance of being able to assess the meteorological situation and provide data on radioactivity levels in the atmosphere and precipitation became apparent in 1986 after the reactor disaster of Chernobyl. When the Law on Preventive Radiation Protection was enacted in 1986 it was therefore only logical for the German Meteorological Service's commission to monitor atmospheric radioactivity levels to be renewed

Parameters of atmospheric radioactivity in Bulgaria

International Nuclear Information System (INIS)

Yaneva, B.; Todorov, P.; Georgieva, D.

2006-01-01

Bulgaria is a country which is located on the Balkan Peninsula, at the Eastern part of Europe. There are a lot of polluting sources, which can affect the environmental parameters and human health. One of these parameters is a radioactivity. It can be as a result from natural and anthropological sources. One of the most important sources of radiological influence to the environment and its components is from atmosphere. Anthropological sources of atmospheric pollution are Nuclear power plants, different kinds of industrial plants, and so on. The systematic control on these parameters is made by the Ministry of environment and water in Bulgaria. The atmospheric radioactivity research is based on collecting of many samples and its examine. The collecting of these aerosol samples on different kind of filters is automatic and it is put into practice by fixed stations located in some of the main towns in Bulgaria - Sofia, Varna, Burgas, Vratza and Montana. The required amount of air for each sample is 1000m 3 . These samples are analyzed by gamma-spectrometry analysis for determination of specifies activity of natural and anthropological radionuclides in them. Monitoring data for the atmospheric radioactivity can be characterized by concentrations of Cs-137, Be-7. The results show that concentrations of Cs-137 are 3 and the concentrations for Be-7 vary from 0.7 to 15.7 mBq/m 3 . Other important radionuclides are Sr-90, Uranium and Ra-226

A methodology for the evaluation of collective doses arising from radioactive discharges to the atmosphere

International Nuclear Information System (INIS)

Hallam, J.; Linsley, G.S.

1980-01-01

The ICRP recommend the use of optimisation as a means of ensuring that the total detriment from any practice is appropriately small in relation to the benefit resulting from its introduction. The calculation of total health detriment requires the evaluation of the complete dose distribution throughout the irradiated population from all isotopes via all pathways. This paper describes methods for the evaluation of collective dose, which may be used in the assessment of detriment. The stages in the assessment of collective dose from an atmospheric release can be summarised as follows: (1) An atmospheric dispersion model is used to evaluate the spatial distribution of activity and thereby the dose to an individual from inhalation and external irradiation at any position with respect to the discharge point. (2) The UK population distribution on a 1 x 1 km grid is then used for the evaluation of collective dose from these pathways. (3) Foodchain models are used to estimate the radioactivity per unit mass in a range of different foodstuffs per unit deposition rate or surface deposit. (4) The distribution of agricultural practices in the UK on a 5 x 5 km grid, taken together with the atmospheric dispersion model allows the estimation of the total activity reaching man via food, and hence the collective dose. This combination of models and data arrays allows assessments to be made of the collective dose due to atmospheric releases of radioactive materials at any geographical location in the United Kingdom. (author)

Modeling the atmospheric dispersion of radioactive effluents in a nuclear accident situation

International Nuclear Information System (INIS)

Margeanu, Sorin

2002-01-01

In case of a nuclear accident, which could lead to release of radioactive contaminants, fastest countermeasures are needed related to sheltering, iodine distribution, evacuation and interdiction of food and water consumption. All these decisions should be based either on estimation of inhaled dose and the dose due to external exposure for public, or on the estimation of radioactive concentration in food (which will depend on the radioactive concentration in air and ground deposition). The dispersion model used, was a Gaussian 'puff' model. The vertical dispersion was considered not dependent on the release high. The used meteorological data are specific for the SCN - Pitesti site, collected every hour for one year. The meteorological data file contains: the wind speed (in m/s), wind direction (degrees clockwise from north), atmospheric stability category, precipitation rate (in mm/h) and the high of the mixing layer (in m). A hypothetical major nuclear accident at TRIGA - SSR of INR - Pitesti, due to a serious damage of the reactor core leading, to a large release of radioactive contaminants was examined. The release was considered as a single phase with of one hour duration. The release factors for the considered isotopic mixture are 100% noble gases (of the reactor core inventory), 40% iodine (of the reactor core inventory) and 40% particulate, i.e., 40% of the fission products of core fission products inventory, released as particles. The accuracy of the model could be increased by implementation of the code on a real-time system, where the acquisition of the parameters done is on-line, namely, the data are introduced as soon as the modification of meteorological and dosimetric conditions are produced. In this case, the parameters used in formulas can be adjusted according with the field situation. Unfortunately the real-time systems need more powerful resources: monitoring stations which can measure and send on-line the data and which can cover a large area

Some considerations about the natural atmospheric radioactive aerosol

International Nuclear Information System (INIS)

Renoux, A.; Madelaine, G.

1985-01-01

From experiments made in Brest by the use of a semi-automatic device for direct measurements of atmospheric radon (the double filter method), we obtained daily average values of Radon 222 concentration, and establish that the values obtained are completely different according to the wind direction. We establish that radioactive balance is never realized in the air between radon and its daughters RaA(Po218), RaB(Pb214) and RaC(Bi214); the state of radioactive balance strongly depends on wind direction. We also study the ionic state of the radioactive aerosol accruing from Radon 222. Using an experimental system consisting of absolute filters, diffusion batteries, cascade impactors and ions tubes, we establish the size distribution of natural radioactive aerosol. We thus show 40% of the natural atmospheric radioactivity is located on particles whose radii are inferior to 2 . 10-2 mm. A good agreement is provided between the theory and our experimental points

Natural radioactivity balance in the atmosphere of the southern hemisphere

International Nuclear Information System (INIS)

Lambert, G.; Ardouin, B.; Polian, G.; Sanak, J.

1972-01-01

It is well known that radon-222 is a radioactive rare gas, continuously produced in the soil by the disintegration of radium-226. Radon can diffuse in the soil and is outgassed into the atmosphere from the surface of the continents at the rate of about 0.7 atoms/ (cm 2 -second). Whenever the soil is covered by snow or even an iceshelf, the flux of radon becomes negligible. Surficial sea water also contains radium-226 and the oceans could release into the atmosphere a part of the produced radon. Therefore a small flux of 10 -2 atoms/(cm 2 -second) can be expected from the surface of the oceans. The radon-222 half-life of 3.8 days is long enough so that the measured radon is usually of continental origin even in the middle of any main ocean. However, below 50 0 South, it is difficult to attribute the radon to either a continental or oceanic origin. Data are presented on seasonal and altitudinal variations in radon-220, lead-210, polonium-210, and radon-222 concentrations in air samples from various locations in the Southern Hemisphere. The relation of air mass circulation in the Antartic to radioactivity in air is discussed. (U.S.)

Fate of gaseous tritium and carbon-14 released from buried low-level radioactive waste

International Nuclear Information System (INIS)

Striegl, R.G.

1988-01-01

Microbial decomposition, chemical degradation, and volatilization of buried low-level radioactive waste results in the release of gases containing tritium ( 3 H) and carbon-14 ( 14 C) to the surrounding environment. Water vapor, carbon dioxide, and methane that contain 3 H or 14 C are primary products of microbial decomposition of the waste. Depending on the composition of the waste source, chemical degradation and volatilization of waste also may result in the production of a variety of radioactive gases and organic vapors. Movement of the gases in materials that surround waste trenches is affected by physical, geochemical, and biological mechanisms including sorption, gas-water-mineral reactions, isotopic dilution, microbial consumption, and bioaccumulation. These mechanisms either may transfer 3 H and 14 C to solids and infiltrating water or may result in the accumulation of the radionuclides in plant or animal tissue. Gaseous 3 H or 14 C that is not transferred to other forms is ultimately released to the atmosphere

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

Derived emergency reference levels for the introduction of countermeasures in the early to intermediate phases of emergencies involving the release of radioactive materials to atmosphere

International Nuclear Information System (INIS)

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

1986-03-01

Derived Emergency Reference Levels (DERLs) are practical quantities intended for use in the aftermath of an accident involving the release of radioactive materials to atmosphere and for use in preparing emergency plans for the protection of the public. The results of environmental measurements may be compared with them as a means of assessing the seriousness of the release and in order to form judgements on the need to institute protective countermeasures. DERLs are the practical expression of Emergency Reference Levels, the radiological criteria for planning the introduction of emergency countermeasures. DERLs have been evaluated for a range of radionuclides which could be released in the event of an accident and for a number of different exposure pathways that are relevant in the initial phase of an accident. These pathways are: inhalation of activity both in the plume and resuspended from the ground; skin irradiation by β-emitting noble gases in the cloud; doses from β-emitters deposited on the skin; and external γ irradiation from ground deposits. (author)

Monitoring of released radioactive gaseous and liquid effluent at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Oka, M.; Keta, S.; Nagai, S.; Kano, M.; Ishihara, N.; Moriyama, T.; Ogaki, K.; Noda, K.

2009-01-01

Rokkasho Reprocessing Plant (RRP) Rokkasho Reprocessing Plant started its active tests with spent fuel at the end of March 2006. When spent fuels are sheared and dissolved, radioactive gaseous effluent and radioactive liquid effluent such as krypton-85, tritium, etc. are released into the environment. In order to limit the public dose as low as reasonably achievable in an efficient way, RRP removes radioactive material by evaporation, rinsing, filtering, etc., and then releases it through the main stack and the sea discharge pipeline that allow to make dispersion and dilution very efficiently. Also, concerning the radioactive gaseous and liquid effluent to be released into the environment, the target values of annual release have been defined in the Safety Rule based on the estimated annual release evaluated at the safety review of RRP. By monitoring the radioactive material in gaseous exhaust and liquid effluent RRP controls it not to exceed the target values. RRP reprocessed 430 tUpr of spent fuel during Active Test (March 2006 to October 2008). In this report, we report about: The outline of gaseous and liquid effluent monitoring. The amount of radioactive gaseous and liquid effluent during the active test. The performance of removal of radioactive materials in gaseous and liquid effluents. The impact on the public from radioactive effluents during the active test. (author)

Releases of radioactive substances from Swedish nuclear power plants (RAKU)

Energy Technology Data Exchange (ETDEWEB)

Ingemansson, T.; Bergstroem, C. [ALARA Engineering AB, Skultuna (Sweden)

1997-04-01

Releases of radioactivity to air and water from Swedish nuclear power plants have been studied and compared with those from foreign reactors. Averaged over the years from commissioning of the reactors to the last year data are available, the release of radioactive noble gas from the Swedish BWRs has been about the same as from comparable foreign reactors. The oldest Swedish BWRs, Oskarshamn 1 and 2 (O1 and O2) and Ringhals 1 (R1), have simple off-gas systems with only one delay volume. All BWRs in US, Germany, Japan and Switzerland are equipped with more sophisticated off-gas systems. It can be expected that O1, O2 and R1 therefore will have the highest release of noble gas activity at an international comparison if they do not modernize their off-gas system. BWRs in US, Germany and Japan are today equipped with recombiners and with one exception also charcoal columns. Japanese BWRs report zero releases to air. Releases of radioactivity to water after commissioning was about the same for most of the studied reactors. Some of the newest German plants have had low annual releases already at commissioning. Improvements of the treatment systems at old German, Swiss and US reactors have significantly lowered the releases. For most of the Swedish plants the annual releases to water have remained at the initial level. Forsmark 3 has succeeded in decreasing the release of radionuclides to water by a factor of almost one hundred compared to other Swedish reactors. Also O3 has managed to decrease the liquid effluents. Japanese plants have zero release of radioactivity excluding tritium to water. The release of tritium is about the same for all reactors of the same type in the world. 35 refs, 31 figs, 24 tabs.

Evaluation Of Radioactivity Of Released Air During Postirradiation Examination At The RMI

International Nuclear Information System (INIS)

Prayitno, B.; Eko, Pudjadi

1998-01-01

Radioactivity evaluation of released air during post-irradiation examination at RMI has been done since january 1993 to december 1996. The released air radioactivity has been observed during post-irradiation examinations of irradiated fuels and structure materials in the hot cell. Analysis method employed has been by air sampling and measurement of the alpha and beta activities by using alpha beta aerosol LB 150 D model. Air release from RMI was sucked by using an air pump having 40 m3/hour capacity which is equipped with a 200 mm diameter filter paper. The filter paper is automatically counted by the detector of the instrument. The average of the daily maximum counting result in a month has been used as monthly data. It has been shown that there have been increase in the released air radioactivity caused by the post-irradiation examination activity. The data of the released air activity obtained have been used to calculate the radioactivity concentration and radioactivity on the soil surface based on Gauss Plumes. The calculation result have shown that the alpha and beta radioactivity concentration at stacks and on the soil surface are less then the set maximum permissible concentration (MPC)

Principles for limiting releases of radioactive effluents into the environment

International Nuclear Information System (INIS)

1986-01-01

This publication is concerned with the subject of limiting releases of radioactive effluents during normal, controlled operation of nuclear installations. It does not deal with releases from accidents where it is only possible to limit exposures by intervention. In 1978 the IAEA published guidance on the concepts and principles for use by the competent authorities in setting limits for planned releases of radioactive material into the environment (Safety Series No. 45). This publication is a complete revision of Safety Series No. 45 and its Annex

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

Monitoring of the release of gaseous and aerosol-bound radioactive materials. Pt. 2

International Nuclear Information System (INIS)

1992-01-01

KTA 1503 contains requirements on technical installations and supplementary organizational measures considered necessary in order to monitor the release of gaseous and aerosol-bound radioactive materials. It consists of part 1: Monitoring of the release of radioactive materials together with stack gas during normal operation; part 2: Monitoring of the release of radioactive materials together with stack gas in the event of incidents; part 3: Monitoring of radioactive materials not released together with stack gas. The concept on which this rule is based is to ensure that in the case of incidents during which the result of effluent monitoring remains meaningful, such monitoring can be reliably performed. (orig./HSCH) [de

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

Study of radio-active ions in the atmosphere

International Nuclear Information System (INIS)

Renoux, A.

1965-01-01

A comparative study is made of active, deposits of radon and thoron in suspension in the atmosphere by means of α radiation counting, using ZELENY tubes, scattering equipment, filter papers or membranes. It has been possible to show the existence of small and large ions which are negative and positive, as well as of neutral radio-active nuclei; their properties are studied. A theoretical interpretation of the results is presented. The average content of radon (using the Ra A concentration) and of Th B in the air has been determined. The radioactive equilibrium between radon and its daughter products in atmospheric air are examined. The techniques developed for active radon and thoron deposits are applied to the study of artificial radio-activity, the analyses being carried out by means of γ spectrometry. (author) [fr

Final safety analysis report for the atmospheric protection system

International Nuclear Information System (INIS)

1976-06-01

An Atmospheric Protection System (APS) has been constructed at the Idaho Chemical Processing Plant to minimize the release of radioactive particulate material to the atmosphere from nonroutine occurrences. Existing off-gas cleanup systems remove radioactive particulates to well below allowable limits for controlled areas before release to the plant stack. Previously all ventilation air from process cells was discharged to the stack without treatment. The APS provides continuous filtration of all ventilation air from process cells and backup filtration of all process off gases before they are released to the atmosphere. A safety analysis of the potential hazards associated with the APS has been completed. The review indicates that the system is capable of withstanding design basis natural phenomena including a flood, tornado, and earthquake without releasing unacceptable amounts of radioactive particulate from the filters to the environment. An in-cell explosion, fire, mechanical damage, and other postulated accident situations were investigated. From these, the design basis accident postulated for the facility is complete release of the maximum amount of radioactive particulate collected on the 104 ventilation air HEPA filters to the atmosphere via the 250-foot high stack. Even though the release of all the radioactive particulate contained on the filters is hardly credible, it would not present an unacceptable hazard to personnel on or offsite

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...

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)

Consequences of severe radioactive releases to Nordic Marine environment

DEFF Research Database (Denmark)

Iosjpe, M.; Isaksson, M.; Joensen, H.P.

- or minor – radioactive releases to Nordic marine environment. As a reference, the release amounts from a 3000 MWth reactor size were used. Based on source term analyses, the chosen release fractions in the study were: iodine 20% (of the total core inventory), caesium 10%, tellurium 10%, strontium 0...

Dynamics of radioactive lead isotopes in the global environmental atmosphere

International Nuclear Information System (INIS)

Koike, Yuya; Kosako, Toshiso

2006-01-01

Fundamental information of radioactive lead isotopes, which used as the atmospheric tracer in the global environmental atmosphere, is reviewed. Emanation and exhalation of Rn and Tn, parent nuclide, is stated. Some reports on measurement and application of short-lived lead isotopes are reported. Transfer of radioactive lead isotopes in the atmosphere, vertical profiles of radon, thoron, and short-lived lead isotopes for different turbulent mixing conditions, deposition to aerosol, basic processes of Rn decay product behavior in air defining 'unattached' and 'aerosol-attached' activities, seasonal variation of atmospheric 210 Pb concentration at Beijing and Chengdu, seasonal variation of atmospheric 212 Pb concentration at several observation sites in Japan Islands, and variation in the atmospheric concentration of 212 Pb along with SO 2 are shown. (S.Y.)

Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

Energy Technology Data Exchange (ETDEWEB)

Egarievwe, Stephen U. [Nuclear Engineering and Radiological Science Center, Alabama A and M University, Huntsville, AL (United States); Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States); Coble, Jamie B.; Miller, Laurence F. [Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States)

2015-07-01

The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

International Nuclear Information System (INIS)

Egarievwe, Stephen U.; Coble, Jamie B.; Miller, Laurence F.

2015-01-01

The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

Applied exposure modeling for residual radioactivity and release criteria

International Nuclear Information System (INIS)

Lee, D.W.

1989-01-01

The protection of public health and the environment from the release of materials with residual radioactivity for recycle or disposal as wastes without radioactive contents of concern presents a formidable challenge. Existing regulatory criteria are based on technical judgment concerning detectability and simple modeling. Recently, exposure modeling methodologies have been developed to provide a more consistent level of health protection. Release criteria derived from the application of exposure modeling methodologies share the same basic elements of analysis but are developed to serve a variety of purposes. Models for the support of regulations for all applications rely on conservative interpretations of generalized conditions while models developed to show compliance incorporate specific conditions not likely to be duplicated at other sites. Research models represent yet another type of modeling which strives to simulate the actual behavior of released material. In spite of these differing purposes, exposure modeling permits the application of sound and reasoned principles of radiation protection to the release of materials with residual levels of radioactivity. Examples of the similarities and differences of these models are presented and an application to the disposal of materials with residual levels of uranium contamination is discussed. 5 refs., 2 tabs

Exhaust gas cleaning system for handling radioactive fission and activation gases

International Nuclear Information System (INIS)

Queiser, H.; Schwarz, H.

1975-01-01

An exhaust gas cleaning system utilizing the principle of delaying radioactive gases to permit their radioactive decay to a level acceptable for release to the atmosphere, comprising an adsorbent for adsorbing radioactive gas and a container for containing the adsorbent and for constraining gas to flow through the adsorbent, the adsorbent and the container forming simultaneously an adsorptive delay section and a mechanical delay section, by means of a predetermined ratio of volume of voids in the adsorbent to total volume of the container containing the adsorbent, for delaying radioactive gas to permit its radioactive decay to a level acceptable for release to the atmosphere is described. A method of using an adsorbent for cleaning a radioactive gas containing an isotope which is adsorbed by the adsorbent and containing an isotope whose adsorption by the adsorbent is low as compared to the isotope which is adsorbed and which is short-lived as compared to the isotope which is adsorbed, comprising constraining the gas to flow through the adsorbent with the retention time for the isotope which is adsorbed being at least the minimum for permitting radioactive decay to a level acceptable for release to the atmosphere and with the retention time for the isotope of relatively low adsorption and relatively short life being at least the minimum for permitting radioactive decay to a level acceptable for release to the atmosphere is also described. (U.S.)

Prevention and mitigation of groundwater contamination from radioactive releases

International Nuclear Information System (INIS)

1988-10-01

This document gives basic information on potential pathways and mechanisms, by which radioactive materials from releases can reach man, and on modelling considerations to predict the behaviour of radioactive materials in the ground. The main objective is to present an overview of existing techniques for preventing the offsite releases of contaminants into the groundwater systems and techniques for mitigation of effects of such releases should they occur. The recommended techniques are fully applicable to any hazardous materials, such as organic liquids, and toxic materials or otherwise dangerous materials, the presence of which in the accessible biosphere can represent health risks as well as economic losses to the general public. 11 refs, 2 figs, 8 tabs

Monitoring for radioactive materials releasing to environment in M310 reformatived nuclear power plant

International Nuclear Information System (INIS)

Yin Zhenyu; Yang Guangli; Xu Guang

2012-01-01

Airborne radioactive materials of nuclear power plant (NPP) releases to the environment from the stack of NPP. Radioactive liquid waste releases of the ocean, the fluvial and the lake through the liquid waste letdyke of NPP. Further more, a few radioactive waste may be taken out of the NPP by vehicle or personnel. For the purpose of strict management and control above-mentioned waste, we use detect equipment monitoring radioactive waste of NPP. Management and control for the releasing of radioactive material to the environment in M310 reformatived NPP is strict and safety. (authors)

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

Radioactive materials released from nuclear power plants

International Nuclear Information System (INIS)

Tichler, J.; Norden, K.; Congemi, J.

1991-05-01

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1988 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1988 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs

Released radioactivity reducing device

International Nuclear Information System (INIS)

Miyamoto, Yumi.

1995-01-01

A water scrubber is disposed in a scrubber tank and a stainless steel fiber filter is disposed above the water scrubber. The upper end of the scrubber tank is connected by way of a second bent tube to a capturing vessel incorporating a moisture removing layer and an activated carbon filter. The exit of the capturing vessel is connected to a stack. Upon occurrence of an accident of a BWR-type power plant, gases containing radioactive materials released from a reactor container are discharged into the water scrubber from a first bent tube through a venturi tube nozzle, and water soluble and aerosol-like radioactive materials are captured in the water. Aerosol and splashes of water droplets which can not be captured thoroughly by the water scrubber are captured by the stainless steel fiber filter. Gases passing through the scrubber tank are introduced to a capturing vessel through a second bent tube, and organic iodine is captured by the activated carbon filter. (I.N.)

The cleanup of releases of radioactive materials from commercial low-level radioactive waste disposal sites: Whose jurisdiction?

International Nuclear Information System (INIS)

Hartnett, C.

1994-01-01

There exists an overlap between the Comprehensive Environmental Response, Compensation and Recovery Act (open-quotes CERCLAclose quotes) and the Atomic Energy Act (open-quotes AEAclose quotes) regarding the cleanup of releases of radioactive materials from commercial low-level radioactive waste sites. The Nuclear Regulatory Commission (open-quotes NRCclose quotes) and Agreement States have jurisdiction under the AEA, and the Environmental Protection Agency (open-quotes EPAclose quotes) has jurisdiction pursuant to CERCLA. This overlapping jurisdiction has the effect of imposing CERCLA liability on parties who have complied with AEA regulations. However, CERCLA was not intended to preempt existing legislation. This is evidenced by the federally permitted release exemption, which explicitly exempts releases from CERCLA liability pursuant to an AEA license. With little guidance as to the applicability of this exemption, it is uncertain whether CERCLA's liability is broad enough to supersede the Atomic Energy Act. It is the purpose of this paper to discuss the overlapping jurisdiction for the cleanup of releases of radioactive materials from commercial low-level radioactive waste disposal sites with particular emphasis on the cleanup at the Maxey Flats, West Valley and Sheffield sites

Radioactive materials released from nuclear power plants (1976)

International Nuclear Information System (INIS)

Decker, T.R.

1978-11-01

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1976 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1976 release data are compared with previous year releases in tabular form. Data covering specific radionuclides are summarized

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)

Behavior of radioactive organic iodide in an atmosphere of High Temperature Gas-cooled Reactor

International Nuclear Information System (INIS)

Saeki, Masakatsu; Nakashima, Mikio; Sagawa, Chiaki; Masaki, Nobuyuki; Hirabayashi, Takakuni; Aratono, Yasuyuki

1990-06-01

Formation and decomposition behavior of radioactive organic iodide have been studied in an atmosphere of High Temperature Gas-cooled Reactor (High Temperature Engineering Test Reactor, HTTR). Na 125 I was chosen for radioactive iodine source instead of CsI diffusing from coated fuel particles. Na 125 I adsorbed on graphite was heated in pure He and He containing O 2 or H 2 O atmosphere. The results obtained are as follows. It was proved that organic iodide was formed with organic radicals released from graphite even in He atmosphere. Thus, the interchange rate of inorganic iodide with organic iodide was remarkably decreased with prolonged preheat-treatment period at 1000degC. Organic iodide formed was easily decomposed by its recirculation into hot reaction tube kept at 900degC. When organic iodide was passed through powdered graphite bed, more than 70% was decomposed at 90degC. Oxygen and water vapour intermixed in He suppressed the interchange rate of inorganic iodide with organic iodide. These results suggest that organic iodide rarely exists in the pressure vessel under normal operating condition of HTTR, and, under hypothetical accident condition of HTTR, organic iodide fraction never exceeds the value used for a safety assessment of light water reactor. (author)

Impact on the marine environment of radioactive releases resulting from the Fukushima-Daiichi nuclear accident. May 13, 2011

International Nuclear Information System (INIS)

2011-01-01

This information note updates and supplements the previous note of 4 April on the same subject. It describes the origins of the contamination of the marine environment (Direct releases into the sea close to the damaged reactors, atmospheric fall-out onto the surface of the sea, transport of radioactive pollution by leaching of contaminated soil). Then, while proposing several maps, the authors analyse and comment the dispersion in the sea of radioactive pollutants: ocean currents off the Japanese coasts, charts showing the distribution of caesium 137 in seawater, and results of simulations of dispersion. The report briefly discusses the impact of radioactive pollution on living species: concentrations observed in fish, expected concentrations based on the seawater measurements. Finally, it briefly discusses the presence of radionuclides in sediments

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

Releases of radioactivity at the Savannah River Plant, 1954--1975

International Nuclear Information System (INIS)

Ashley, C.; Zeigler, C.C.

1976-07-01

This report contains summaries of releases of radioactivity to the environs from the Savannah River Plant for each year since plant startup (1954-1975). It also contains monthly summaries of 1975 releases from major emission sources (Separations and Reactor Areas). Releases for the years 1954 through 1959 are reassessed and assigned release values for long-lived specific radionuclides. These long-lived radionuclides (half lives greater than one year) are the only radionuclides included for the years 1954 through 1970. Beginning in 1971 all detectable radionuclides are included. The tabulated data, now compiled by computer, will be updated annually. All measured migration of radioactivity from the F- and H-Area seepage basin systems to Four Mile Creek, and from the K-Area containment basin to Pen Branch is listed in the release summaries and will be updated annually

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

Concept and approaches used in assessing individual and collective doses from releases of radioactive effluents

International Nuclear Information System (INIS)

1988-06-01

To guide on the applications of the principles for limiting radioactive releases contained in Safety Series 77, the Agency is in the process of preparing a number of safety guides. The first one is this present document which deals with the principal aspects of the methods for the assessment of the individual and collective dose. It aims at giving a general guidance to those responsible for establishing programmes for the determination of individual doses as well as collective doses in connection with licensing a site for a nuclear installation. The document is concerned with the principles applied for calculating individual and collective doses from routine releases of radionuclides to the atmosphere and hydrosphere but not releases directly to the geosphere, as in waste management. These areas will be covered by other Agency publications. 75 refs, figs and tabs

Measurement of radioactivity in the atmosphere and pollution nearby an atomic centre

International Nuclear Information System (INIS)

Labeyrie, J.; Weill, J.

1955-01-01

The French Atomic Energy Commission (CEA) is particularly interested in studies on atmospheric radioactivity by reason of the necessity to control the atmosphere nearby nuclear plants as uranium mines, nuclear reactors and hot laboratories or radioactive materials treatment plants. Thus, the CEA developed different apparatus to control and monitor the atmosphere nearby its sites. These air monitors are essentially of two types: the first one, called 'Babar', monitors smokes, fogs and dusts, the second type is an ionization chamber and measures the concentration of radioactive gas in the air. The functioning and sensitivity of these two systems are discussed. (M.P.)

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

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

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

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

An optimisation technology for more precise determination of a source for modelling radioactive releases to the atmosphere

International Nuclear Information System (INIS)

Golubenkov, A.V.; Borodin, R.V.

1993-01-01

This paper deals with refining meteorological parameters and source term characteristics required for models of atmospheric dispersion and deposition of radioactivity in the area adjacent to facilities affected by a nuclear accident. The proposed methodology involves the minimisation of an objective function that is the sum of weighted norms of deviations between measured and model values. The measured values are spatially interpolated and the weights determined by the type of measurement and the precision of interpolation. Consideration is given to a technique of initial approximation based on calculating regression functions for the parameters to be refined using measured radioactivity. Coefficients for these functions are calculated by analysis of a multitude of simulated situations. Also discussed is a heuristic method, using multiple random perturbations on the data, for assessing the validity of the solution. Based on these calculations confidence intervals are determined for the refined model parameters. (author)

Atmospheric diffusion study and its application to nuclear energy

International Nuclear Information System (INIS)

Chino, Masamichi

1990-01-01

The report reviews studies on atmospheric diffusion of radioactive substances released from a smokestack. Smoke containing radioactive substances, or radioactive plume, diffuses into air while being affected by atmospheric turbulent flows in various ways depending on the scale of the plume. The diffusion of a radioactive plume released from a smokestack is discussed first, focusing on the diffusion process in the vicinity of the smokestack, in the atmospheric boundary layer and in the troposphere. Many theoretical studies have been conducted by using the Gaussian plume model, though it is too simple to take into account the topographic effects and unstationary atmospheric conditions. Various numerical calculation models (designed for numerical calculation by a computer) have recently been developed, particularly for the implementation of environmental impact evaluation. Diagnostic and forecast type models are available for atmospheric air flow calculation. Other models available for diffusion analysis include the puff model, segment model, PIC (particle in cell)model, and random walk model. (N.K.)

Restoration of water environment contaminated by radioactive cesium released from Fukushima Daiichi NPP

Energy Technology Data Exchange (ETDEWEB)

Takeshita, K.; Takahashi, H. [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 157-8550 (Japan); Jinbo, Y. [CDM Cosulting Co.Ltd., 1-13-13 Tsukiji Chuo-ku Tokyo 104-0045 (Japan); Ishido, A. [Radwaste and Decommissioning Center, 1-7-6 Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

2013-07-01

In the Fukushima Daiichi NPP Accident, large amounts of volatile radioactive nuclides, such as {sup 131}I, {sup 134}Cs and {sup 137}Cs, were released to the atmosphere and huge areas surrounding the nuclear site were contaminated by the radioactive fallout. In this study, a combined process with a hydrothermal process and a coagulation settling process was proposed for the separation of radioactive Cs from contaminated soil and sewage sludge. The coagulation settling operation uses Prussian Blue (Ferric ferrocyanide) and an inorganic coagulant. The recovery of Cs from sewage sludge sampled at Fukushima city (100.000 Bq/kg) and soil at a nearby village (55.000 Bq/kg), was tested. About 96% of Cs in the sewage sludge was removed successfully by combining simple hydrothermal decomposition and coagulation settling. However, Cs in the soil was not removed sufficiently by the combined process (Cs removal is only 56%). The hydrothermal decomposition with blasting was carried out. The Cs removal from the soil was increased to 85%. When these operations were repeated twice, the Cs recovery was over 90%. The combined process with hydrothermal blasting and coagulation settling is applicable to the removal of Cs from highly contaminated soil.

The terrestrial environmental dynamics of radioactive nuclides released by the Fukushima nuclear accident

International Nuclear Information System (INIS)

Furukawa, Jun

2014-01-01

Research into environmental dynamics of radioactive nuclides released by the Fukushima nuclear accident, especially radiocesium 137 Cs (half-life, 30.1 years), is highly focused especially on diffusion processes of radiocesium into ecosystems, which is high-priority knowledge. Because of relatively sparse knowledge about the reallocation of radiocesium contained in organic matter in terrestrial ecosystems, the effects of diffused rediocesium into ecosystem cannot be accurately estimated. In this article, the terrestrial environmental dynamics of radiocesium mainly in the processes of plant uptake and the possibility of release from plants will be discussed. Plants uptake minerals from soil and these minerals are likewise ingested by animals that feed on plants, including humans. Therefore one of the main gateways of radiocesium into ecosystem is via plants. From the viewpoint of human dietary consumption, rice contamination with radiocesium has been energetically investigated and useful data are accumulating. Processes of radiocesium uptake mechanisms by plants are being researched using legumes, e.g. soybean. Speculation on the possibility of radiocesium release into forest atmosphere via plant activity will be introduced. (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

Modelling of motorway tunnels scenario for utilization of conditionally released radioactive materials

International Nuclear Information System (INIS)

Hrncir, Tomas; Panik, Michal; Necas, Vladimir

2011-01-01

Considerable amount of solid radioactive waste with radioactivity slightly above the limits for unconditional release is generated during the decommissioning of the nuclear installations. Conditional release deals with precisely this type of materials with activity slightly above limits in order to save considerable financial resources, which would be otherwise spend on treatment, conditioning and disposal of these materials at appropriate repository. The basic principles of conditional release as well as possibilities of reusing of the conditionally released materials are described. One of these possibilities of the reusing was chosen and application proposal of conditional release of metal waste - steel reinforcement in the concrete, which could be used for construction of motorway tunnels, was created. The computer code Visiplan 4.0 3D ALARA planning tool software was used for the calculation of effective individual dose for personnel constructing the tunnel and for critical group related to scenario. Particular models for individual scenarios of conditional release have been developed within the scope of this software code. The aim of the paper is to determine a level of the radioactivity of conditional released materials to avoid over exceeding the value of annual individual effective dose 10μSv/year established by international recommendations. (author)

ORNL radioactive waste operations

International Nuclear Information System (INIS)

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards

Chapter 2. Peculiarities of radioactive particle formation and isotope fractionation resulted from underground nuclear explosions

International Nuclear Information System (INIS)

1996-01-01

Radioactive particles, forming terrain fallouts from underground nuclear explosion differ sufficiently from radioactive particles, produced by atmospheric nuclear explosions. Patterns of underground nuclear explosion development, release of radioactivity to the atmosphere, formation of a cloud and base surge, peculiarities of formed radioactive particles, data on isotope fractionation in radioactive particles are presented. Scheme of particle activation, resulted from underground explosions is given

Impact of rainstorm and runoff modeling on predicted consequences of atmospheric releases from nuclear reactor accidents

International Nuclear Information System (INIS)

Ritchie, L.T.; Brown, W.D.; Wayland, J.R.

1980-05-01

A general temperate latitude cyclonic rainstorm model is presented which describes the effects of washout and runoff on consequences of atmospheric releases of radioactive material from potential nuclear reactor accidents. The model treats the temporal and spatial variability of precipitation processes. Predicted air and ground concentrations of radioactive material and resultant health consequences for the new model are compared to those of the original WASH-1400 model under invariant meteorological conditions and for realistic weather events using observed meteorological sequences. For a specific accident under a particular set of meteorological conditions, the new model can give significantly different results from those predicted by the WASH-1400 model, but the aggregate consequences produced for a large number of meteorological conditions are similar

Models for environmental impact assessments of releases of radioactive substances from CERN facilities

CERN Document Server

Vojtyla, P

2005-01-01

The document describes generic models for environmental impact assessments of releases of radioactive substances from CERN facilities. Except for few models developed in the Safety Commission, the models are based on the 1997 Swiss directive HSK-R-41 and on the 2001 IAEA Safety Report No. 19. The writing style is descriptive, facilitating the practical implementation of the models at CERN. There are four scenarios assumed for airborne releases: (1) short-term releases for release limit calculations, (2) actual short-term releases, (3) short-term releases during incidents/accidents, and (4) chronic long-term releases during the normal operation of a facility. For water releases, two scenarios are considered: (1) a release into a river, and (2) a release into a water treatment plant. The document shall be understood as a reference for specific environmental studies involving radioactive releases and as a recommendation of the Safety Commission.

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

Charging and coagulation of radioactive and nonradioactive particles in the atmosphere

International Nuclear Information System (INIS)

Kim, Yong-ha; Yiacoumi, Sotira

2016-01-01

Charging and coagulation influence one another and impact the particle charge and size distributions in the atmosphere. However, few investigations to date have focused on the coagulation kinetics of atmospheric particles accumulating charge. This study presents three approaches to include mutual effects of charging and coagulation on the microphysical evolution of atmospheric particles such as radioactive particles. The first approach employs ion balance, charge balance, and a bivariate population balance model (PBM) to comprehensively calculate both charge accumulation and coagulation rates of particles. The second approach involves a much simpler description of charging, and uses a monovariate PBM and subsequent effects of charge on particle coagulation. The third approach is further simplified assuming that particles instantaneously reach their steady-state charge distributions. It is found that compared to the other two approaches, the first approach can accurately predict time-dependent changes in the size and charge distributions of particles over a wide size range covering from the free molecule to continuum regimes. The other two approaches can reliably predict both charge accumulation and coagulation rates for particles larger than about 0.04 micrometers and atmospherically relevant conditions. These approaches are applied to investigate coagulation kinetics of particles accumulating charge in a radioactive neutralizer, the urban atmosphere, and an atmospheric system containing radioactive particles. Limitations of the approaches are discussed.

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

Environmental system applied to radioactive liquid effluent release

International Nuclear Information System (INIS)

Nisti, Marcelo Bessa

2009-01-01

The current environmental administration considers the productive activity as an environmental system, defined as a group of processes, interactions, parameters and factors involved in the production. This mastering dissertation evaluated the release of the liquid radioactive effluents at Instituto de Pesquisas Energeticas e Nucleares (IPEN), under a systemic environmental study. The study evaluated the source term at IPEN in the period from 2004 to 2008, making use of gamma-ray and alpha spectrometry, instrumental neutron activation analysis, liquid phase scintillation and atomic absorption spectrometry. The employed methodologies were verified using samples from the Intercomparison National Program - PNI/IRD and Reference Materials. The facilities that contributed the most in these releases were the Radiopharmaceutical Center (CR) and the Research Reactor Center (CRPq) with an average of 11,4% and 87,4%, respectively, relative to the present radioactive activity. The sewer system releases were within the radioactive protection regulations, showing the effectiveness of IPEN's Radioactive Effluents Monitoring Program. The concentration of the stable elements Ag, Cd, Cr, Fe, Mn, Ni, Pb and Zn was determined in the liquid effluent in ali the samples from the storage tanks TR1 and CR in the period from 2004 to 2008 and in some of the samples of other IPEN's facilities in the period from 2004 to 2007. Among the analyzed effluents, two samples were higher than the stable elements discharge standards established in the state of Sao Paulo, one sample was higher than the required value of the element cadmium and the other higher than required value of the element zinco The storage tank TR1 discharge flow was estimated in 10,9 ± 0,9 m3 h -1 . The dilution factor at discharge point E1 was estimated using a radiotracers the isotopes 3 H, 137 CS, 60 Co, 54 Mn and 65 Zn, which are commonly released into IPEN's sewer system. The executed radiotracer study was carried out

Consequences of severe radioactive releases to Nordic Marine environment

Energy Technology Data Exchange (ETDEWEB)

Iosjpe, M. [Norwegian Radiation Protection Authority (NRPA) (Norway); Isaksson, M. [Univ. of Gothenburg (Sweden); Joensen, H.P. [Froskaparsetur Foeroya. Faroe Islands, Torshavn (Denmark); Lahtinen, J. [Radiation and Nuclear Safety Authority (Finland); Logemann, K. [Univ. of Iceland (Iceland); Palsson, S.E. [Geislavarnir Rikisins (Iceland); Roos, P. [Technical Univ. of Denmark. Risoe DTU, Roskilde (Denmark); Suolanen, V. [Technical Research Centre of Finland (Finland)

2013-02-15

In the report, consequences of hypothetical severe nuclear accidents releases to Nordic marine environment are preliminary considered. The considered marine area comprises the Baltic Sea (Sweden, Denmark, Finland) and the North Atlantic (Iceland, Faroes, Norway) areas. The hypothetical severe nuclear accidents can be related to nuclear power plants, nuclear powered submarines or ice-breakers. Quite comprehensive survey on radioactive source terms of extremely severe nuclear power and submarine accidents has been done. This enables to estimate more realistically possible radioactive releases of various elements and nuclides to marine environment. One recent reference is of course the Fukushima accident and estimated releases there. The marine flows and dilution circumstances around the Nordic nuclear power plants and in the Baltic Sea area in general, has been studied. Respectively marine flows related to Iceland and Faroes coasts are considered with measured data and with preliminary 3D-model simulations. The substantial depth of sea water in the North Atlantic affect vertical concentration profiles to some extent. At Icelandic or Faroese waters, a potential submarine accident would likely occur in a well defined water mass, and radioactivity from the accident would be detected and spread with the flow regime of the water mass in the world ocean. Based on hypothetical severe accidents scenarios, preliminary consequence calculations has been done. It should be emphasised that the considered severe accident cases, considered in this study, do not directly attach any specific Nordic nuclear power plant or any specific submarine type. The considered radioactive releases will, however, provide specified references for more extensive consideration of environmental consequences of severe - or minor - radioactive releases to Nordic marine environment. As a reference, the release amounts from a 3000 MW{sub th} reactor size were used. Based on source term analyses, the

Consequences of severe radioactive releases to Nordic Marine environment

International Nuclear Information System (INIS)

Iosjpe, M.; Isaksson, M.; Joensen, H.P.; Lahtinen, J.; Logemann, K.; Palsson, S.E.; Roos, P.; Suolanen, V.

2013-02-01

In the report, consequences of hypothetical severe nuclear accidents releases to Nordic marine environment are preliminary considered. The considered marine area comprises the Baltic Sea (Sweden, Denmark, Finland) and the North Atlantic (Iceland, Faroes, Norway) areas. The hypothetical severe nuclear accidents can be related to nuclear power plants, nuclear powered submarines or ice-breakers. Quite comprehensive survey on radioactive source terms of extremely severe nuclear power and submarine accidents has been done. This enables to estimate more realistically possible radioactive releases of various elements and nuclides to marine environment. One recent reference is of course the Fukushima accident and estimated releases there. The marine flows and dilution circumstances around the Nordic nuclear power plants and in the Baltic Sea area in general, has been studied. Respectively marine flows related to Iceland and Faroes coasts are considered with measured data and with preliminary 3D-model simulations. The substantial depth of sea water in the North Atlantic affect vertical concentration profiles to some extent. At Icelandic or Faroese waters, a potential submarine accident would likely occur in a well defined water mass, and radioactivity from the accident would be detected and spread with the flow regime of the water mass in the world ocean. Based on hypothetical severe accidents scenarios, preliminary consequence calculations has been done. It should be emphasised that the considered severe accident cases, considered in this study, do not directly attach any specific Nordic nuclear power plant or any specific submarine type. The considered radioactive releases will, however, provide specified references for more extensive consideration of environmental consequences of severe - or minor - radioactive releases to Nordic marine environment. As a reference, the release amounts from a 3000 MW th reactor size were used. Based on source term analyses, the chosen

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

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

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

Study on radioactive release of gaseous and liquid effluents during normal operation of AP1000

International Nuclear Information System (INIS)

Gong Quan; Zhou Jing; Liu Yu

2014-01-01

The gaseous and liquid radioactive releases of pressurized water reactors plant during normal operation are an important content of environmental impact assessment and play a significant role in the design of nuclear power plant. According to the design characters of AP1OOO radioactive waste management system and the study on the calculation method and the release pathways, the calculation model of the gaseous and liquid radioactive releases during normal operation for AP1OOO are established. Base on the established calculation model and the design parameters of AP1000, the expected value of gaseous and liquid radioactive releases of AP1OOO is calculated. The results of calculation are compared with the limits in GB 6249-2011 and explain the adder that is included tu account for anticipated operational occurrences, providing a reference for environmental impact assessment of pressurized water reactor. (authors)

Release of radioactive materials in simulation test of a postulated solvent fire in a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Nishio, G.; Hashimoto, K.

1989-01-01

This paper reports on small- and large-scale fire tests performed to examine the adequacy of a safety evaluation method for a solvent fire in the extraction process of a nuclear fuel reprocessing plant. The test objectives were to obtain information on the confinement of radioactive materials during a 30% tri-n-butyl phosphate-n-dodecane fire while air ventilation is operating in the cell. The rates of release of cesium, strontium, cerium, ruthenium, and uranium from a burning solvent were determined. The quantities of species released were obtained from the solvent burning rate, smoke generation rate, partition coefficients of species between solvent and water, and coefficients of species entrainment to atmosphere in cell

Release mechanisms from shallow engineered trenches used as repositories for radioactive wastes

International Nuclear Information System (INIS)

Locke, J.; Wood, E.

1987-05-01

This report has been written for the Department of the Environment as part of their radioactive waste management research programme. The aim has been to identify release mechanisms of radioactivity from fully engineered trenches of the LAND 2 type and, to identify the data needed for their assessment. No direct experimental work has been involved. The report starts with a brief background to UK strategy and outlines a basic disposal system. It gives reviews of existing experience of low level radioactive waste disposal from LAND 1 trenches and of UK experience of toxic waste disposal to provide a practical basis for the next section which covers the implications of identified release mechanisms on the design requirements for an engineered trench. From these design requirements and their interaction with potential site conditions (both saturated and unsaturated zone sites are considered) an assessment of radionuclide release mechanism is made. (author)

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

Atmospheric transport, diffusion, and deposition of radioactivity

International Nuclear Information System (INIS)

Crawford, T.V.

1969-01-01

From a meteorological standpoint there are two types of initial sources for atmospheric diffusion from Plowshare applications. One is the continuous point-source plume - a slow, small leak from an underground engineering application. The other is the large cloud produced almost instantaneously from a cratering application. For the purposes of this paper the effluent from neither type has significant fall speed. Both are carried by the prevailing wind, but the statistics of diffusion for each type are different. The use of constant altitude, isobaric and isentropic techniques for predicting the mean path of the effluent is briefly discussed. Limited data are used to assess the accuracy of current trajectory forecast techniques. Diffusion of continuous point-source plumes has been widely studied; only a brief review is given of the technique used and the variability of their results with wind speed and atmospheric stability. A numerical model is presented for computing the diffusion of the 'instantaneously-produced' large clouds. This model accounts for vertical and diurnal changes in atmospheric turbulence, wet and dry deposition, and radioactivity decay. Airborne concentrations, cloud size, and deposition on the ground are calculated. Pre- and post-shot calculations of cloud center, ground level concentration of gross radioactivity, and dry and wet deposition of iodine-131 are compared with measurements on Cabriolet and Buggy. (author)

Atmospheric transport, diffusion, and deposition of radioactivity

Energy Technology Data Exchange (ETDEWEB)

Crawford, T V [Lawrence Radiation Laboratory, Livermore, CA (United States)

1969-07-01

From a meteorological standpoint there are two types of initial sources for atmospheric diffusion from Plowshare applications. One is the continuous point-source plume - a slow, small leak from an underground engineering application. The other is the large cloud produced almost instantaneously from a cratering application. For the purposes of this paper the effluent from neither type has significant fall speed. Both are carried by the prevailing wind, but the statistics of diffusion for each type are different. The use of constant altitude, isobaric and isentropic techniques for predicting the mean path of the effluent is briefly discussed. Limited data are used to assess the accuracy of current trajectory forecast techniques. Diffusion of continuous point-source plumes has been widely studied; only a brief review is given of the technique used and the variability of their results with wind speed and atmospheric stability. A numerical model is presented for computing the diffusion of the 'instantaneously-produced' large clouds. This model accounts for vertical and diurnal changes in atmospheric turbulence, wet and dry deposition, and radioactivity decay. Airborne concentrations, cloud size, and deposition on the ground are calculated. Pre- and post-shot calculations of cloud center, ground level concentration of gross radioactivity, and dry and wet deposition of iodine-131 are compared with measurements on Cabriolet and Buggy. (author)

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.

Risk assessment methodology for evaluating releases of radioactively contaminated materials

International Nuclear Information System (INIS)

Chen, S.Y.

1993-01-01

Extensive decontamination and decommissioning (D ampersand D) activities are expected to be required in the near future in association with license termination of nuclear power facilities and cleanup efforts at the U.S. Department of Energy's (DOE's) weapons production facilities. In advance of these D ampersand D activities, it is becoming increasingly urgent that standards be established for the release of materials with residual radioactive contamination. The only standards for unrestricted release that currently exist address surface contamination. The methods used to justify those standards were developed some 20 yr ago and may not satisfy today's criteria. Furthermore, the basis of setting standards has moved away from the traditional open-quotes instrumentation-basedclose quotes concept toward a open-quotes risk-basedclose quotes approach. Therefore, as new release standards are developed, it will be necessary that risk assessment methodology consistent with modern concepts be incorporated into the process. This paper discusses recent developments in risk methodology and issues and concerns regarding the future development of standards for the release of radioactively contaminated materials

Radioactive materials released from nuclear power plants. Annual report 1977

International Nuclear Information System (INIS)

Decker, T.R.

1978-11-01

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1977 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1977 release data are compared with previous years releases in tabular form. Data covering specific radionuclides are summarized

Conversion factors for estimating release rate of gaseous radioactivity by an aerial survey

International Nuclear Information System (INIS)

Saito, Kimiaki; Moriuchi, Shigeru

1988-02-01

Conversion factors necessary for estimating release rate of gaseous radioactivity by an aerial survey are presented. The conversion factors were determined based on calculation assuming a Gaussian plume model as a function of atmospheric stability, down-wind distance and flight height. First, the conversion factors for plumes emitting mono-energy gamma rays were calculated, then, conversion factors were constructed through convolution for the radionuclides essential in an accident of a nuclear reactor, and for mixtures of these radionuclides considering elapsed time after shutdown. These conversion factors are shown in figures, and also polynomial expressions of the conversion factors as a function of height have been decided with the least-squares method. A user can easily obtain proper conversion factors from data shown here. (author)

Fire simulation in radioactive waste disposal and the radiation risk associated

International Nuclear Information System (INIS)

Domingos, Érica Nascimento

2018-01-01

An atmospheric dispersion of radioactive material is one of the possible consequences of an accident scenario in nuclear installations, radiative and radioactive waste deposit. Taking into account a possibility of this release of radioactive material into the atmosphere this work proposes a modeling of the atmospheric dispersion from a fire scenario in a deposit of radioactive waste of low and middle level of radiation varying the amount of inventory released in the fire. For this simulation was adopted the software of physical codes of medical health, the HotSpot Health Physics Codes which uses the Gaussian model to calculate an atmospheric dispersion based on the Pasquill atmospheric stability classes. This software calculates a total effective dose in relation to distance, such as a compromised dose in a list of specific organs, among them the lung, object of work study for calculating the risk of cancer associated with a low dose of radiation. The radiological risk calculation is held by the BEIR V model, Biological Effects of Ionizing Radiations, one of the models to estimate the relative risk of cancer induced by ionizing radiation. (author)

Influence of plume rise on the consequences of radioactive material releases

International Nuclear Information System (INIS)

Russo, A.J.; Wayland, J.R.; Ritchie, L.T.

1977-01-01

Estimates of health consequences resulting from a postulated nuclear reactor accident can be strongly dependent on the buoyant rise of the plume of released radioactive material. The sensitivity of the consequences of a postulated accident to two different plume rise models has been investigated. The results of these investigations are the subject of this report. One of the models includes the effects of emission angle, momentum, and radioactive heating of the released material. The difference in the consequence estimates from the two models can exceed an order of magnitude under some conditions, but in general the results are similar

The minimization of radioactive releases to the sea from the Tokai Reprocessing Plant

International Nuclear Information System (INIS)

Sugiyama, T.; Yoshikawa, K.; Ishii, T.

1996-01-01

The Tokai Reprocessing Plant (TRP) started hot operation in September 1977. The total amount of about 790 tU of spent fuel, generated in Japan, has been successfully reprocessed as of December 1994. Low-level liquid wastes have been treated safely with the low-level waste treatment process. The design of TRP was based on foreign technology. In the early stage of designing, the radioactivity released to the sea was estimated at approximately 2.6 TBq/day (70 Ci/day) for beta activity (except for tritium). Later, PNC added an evaporator to the process to reduce the level down to 1/100, i.e. 9.6 TBq/year (260 Ci/year) or 2.6 x 10 -2 TBq/day (0.7 Ci/day). In addition, under the supervision of the government, PNC started R and D to further decrease the radioactivity released to the sea in terms of ALARA. Aiming at reducing the activity from 9.6 TBq/year (260 Ci/year) to 1/10 of that value (i.e. 26 Ci/year), the release reduction technology development facility was added. This facility was incorporated into the low-level waste treatment process in 1980, before starting the regular operation of TRP. Since the fuel reprocessing commenced, total radioactivity discharged to the sea has been 1.9 x 10 -2 TBq (0.51 Ci) for beta activity, as of December 1994. Before incorporating the release reduction technology development facility, the yearly level was 3.7 x 10 -3 - 7.4 x 10 -3 TBq (0.1 - 0.2 Ci). After incorporation of the facility, radioactivity released to the sea was greatly decreased to non-detection levels in recent years, in spite of increasing annual reprocessing amounts. Although serious equipment failures have occurred such as the acid recovery evaporator and the dissolvers, there was no influence on radioactivity released to the sea. (author)

Radioactive contamination processes during 14-21 March after the Fukushima accident: What does atmospheric electric field measurements tell us?

Science.gov (United States)

Takeda, M.; Yamauchi, M.; Makino, M.; Owada, T.; Miyagi, I.

2012-04-01

Ionizing radiation from the radioactive material is known to increase atmospheric electric conductivity, and hence to decrease vertical downward atmospheric DC electric field at ground level, or potential gradient (PG). In the past, the drop of PG has been observed after rain-induced radioactive fallout (wet contamination) after nuclear tests or after the Chernobyl disaster. After the nuclear accident Fukushima Dai-ichi nuclear power plant (FNPP) that started 11 March 2011, the PG also at Kakioka, 150 km southwest from the FNPP, also dropped a by one order of magnitude. Unlike the past examples, the PG drop was two-stepped on 14 March and 20 March. Both correspond to two largest southward release of radioactive material according to the data from the radiation dose rate measurement network. We compare the Kakioka's PG data with the radiation dose rate data at different places to examine the fallout processes of both on 14 March and on 20 March. The former turned out to be dry contamination by surface wind, leaving a substantial amount of fallout floating near the ground. The latter turned out to be wet contamination by rain after transport by relatively low-altitude wind, and the majority of the fallout settled to the ground at this time. It is recommended that all nuclear power plant to have a network of PG observation surrounding the plant. Takeda, et al. (2011): Initial effect of the Fukushima accident on atmospheric electricity, Geophys. Res. Lett., 38, L15811, doi:10.1029/2011GL048511. Yamauchi, et al. (2012): Settlement process of radioactive dust to the ground inferred from the atmospheric electric field measurement, Ann. Geophys., 30, 49-56, doi:10.5194/angeo-30-49-2012.

Measurement of radioactive aerosols as an original indicator of atmospheric pollution in urban areas

International Nuclear Information System (INIS)

Le Petit, G.; Millies-Lacroix, J. C.

1998-01-01

The Service Radioanalyses, Chimie et Environnment (Departement Analyses Surveillance de l'Environnement) of the French Atomic Energy Commission, located in suburban Paris, has for many years been conducting atmospheric radioactivity measurements. Since 1994, the laboratory has been using high volume air samplers equipped with filters for the weekly collection of atmospheric aerosols at a mean rate of about 600 m 3 .h -1 . The polypropylene filters, with a collection efficiency in excess of 93%, are compacted after sampling. The atmospheric radioactivity is measured by HP Ge gamma spectrometry after decay of short-lived natural relationship products. A study conducted in 1996 shows good correlation between the evolution with time of some of the indicators routinely used by AIRPARIF, the organization in charge of monitoring the air quality in the Ile-de-France region, to measure atmospheric pollution in the Paris area (SO 2 , NO) and that related to radioactivity of terrestrial ( 210 Pb, 40 K) and anthropogenic ( 137 Cs) origin, as well as the amount of aerosols collected. Further, the distribution in time of the atmospheric radioactivity of cosmogenic origin ( 7 Be) shows a yearly evolution somewhat similar to that observed with ozone

Releases of radioactivity from uranium mills and effluent treatment costs

International Nuclear Information System (INIS)

Witherspoon, J.P.; Sears, M.B.; Blanco, R.E.

1977-01-01

Airborne releases of radioactive materials from uranium milling to the environment consist of ore dust, yellowcake dust, tailings dust, and radon gas while the mill is active. After a mill has ceased operations, tailings may be stabilized to minimize or prevent airborne releases of radioactive particulates. However, radon gas will continue to be released in amounts inversely proportional to the degree of stabilization treatment (and expense). Liquid waste disposal is by evaporation and natural seepage to the ground beneath the tailings impoundment area. The release of radioactive materials (and potential radiation exposures) determines the majority of costs associated with minimizing the environmental impact of uranium milling. Radwaste treatments to reduce estimated radiation doses to individuals to 3 to 5% of those received with current milling practices are equivalent to $0.66 per pounds of U 3 O 8 and 0.032 mill per kWhr of electricity. This cost would cover a high efficiency reverse jet bag filter and high energy venturi scrubbers for dusts, neutralization of liquids, and an asphalt-lined tailings basin with a clay core dam to reduce seepage. In addition, this increased cost would cover stabilization of tailings, after mill closure, with a 1-in. asphalt membrane topped by 2 ft of earth and 0.5 ft of crushed rock to provide protection against future leaching and wind erosion. The cost of reducing the radiological hazards associated with uranium milling to this degree would contribute about 0.4% to the current total cost of nuclear power

Release process for non-real property containing residual radioactive material

International Nuclear Information System (INIS)

Ranek, N.L.; Chen, S.Y.; Kamboj, S.; Hensley, J.; Burns, D.; Fleming, R.; Warren, S.; Wallo, A.

1997-01-01

It is DOE's objective to operate its facilities and to conduct its activities so that radiation exposures to members of the public are maintained within acceptable limits and exposures to residual radioactive materials are controlled. To accomplish this, DOE has adopted Order DOE 5400.51 'Radiation Protection of the Public and the Environment', and will be promulgating IO CR Part 834 to codify and clarify the requirements of DOE 5400.5. Under both DOE 5400.5 and 10 CR Part 834, radioactively contaminated DOE property is prohibited from release unless specific actions have been completed prior to the release. This paper outlines a ten-step process that, if followed, will assist DOE Operations and contractor personnel in ensuring that the required actions established by Order DOE 5400.5 and 10 CR Part 834 have been appropriately completed prior to the release for reuse or recycle of non-real property (e.g., office furniture, computers, hand tools, machinery, vehicles and scrap metal). Following the process will assist in ensuring that radiological doses to the public from the released materials will meet applicable regulatory standards and be as low as reasonably achievable (ALARA)

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

Determination of safe radioactive releases to the atmosphere from the nuclear power site, Dynefontein

International Nuclear Information System (INIS)

Basson, J.K.; Van As, D.

1976-01-01

South Africa's first nuclear power station, Koeberg A, is to be built by Escom at Dynefontein, 28 km north of Cape Town, and the experience gained at the National Nuclear Research Centre, Pelindaba, has been used by the AEB as basis for the pre-operational investigation. The capacity of the environment to accept airborne radioactive effluent safely depends on various local factors such as dispersion conditions, the ecology, the habits of the local population and the accumulation, through critical pathways, of pertinent radionuclides. Long-term average dilution factors at varying distances from a 100m stack have been calculated by ESCOM from mesometeorological data collected by the CSIR. On the basis of available data, permissible release rates are derived for radioisotopes of the noble gases (critical pathway:external cloud exposure), 131 I, 137 Cs, 106 Ru, 125 Sb and 114 Ce and tritium. Although final confirmation of these values can only be obtained after operation, such a pre-operational survey may serve as an example to conventional industry [af

Natural Radioactivity Accumulated in the Arctic from Long-range Atmospheric Transport - Observations in Canadian Monitoring Stations

Energy Technology Data Exchange (ETDEWEB)

Chen, Jing; Zhang, Weihua [Radiation Protection Bureau, Health Canada, 775 Brookfield Road, Ottawa K1A 1C1 (Canada)

2014-07-01

In the environment, the main sources of naturally occurring radionuclides come from radionuclides in the uranium decay series. Activity concentrations of uranium decay series radionuclides may vary considerably from place to place depending on the geological characteristics at the location. Their releases to the atmosphere are mainly through radon ({sup 222}Rn), a radioactive noble gas occurring naturally as an indirect decay product of uranium in soils and rocks. Due to the abundance of uranium, radon continuously emanates from continental land masses. With radon as the main source of naturally occurring radioactivity in the environment, one would think that the Arctic should be an area of low background radiation, because a considerable area of the Arctic is covered by glaciers and permafrost, and radon emanation rate has been reported to be negligible from those glacier and permafrost areas. However, available data have shown the opposite. The elevated level of naturally occurring radioactivity in the Arctic is due to natural sources outside of the Arctic, mainly through long-range atmospheric transport of radon and radon progeny. In some cases, natural radioactivity can accumulate to relatively high levels and become a health concern or a limiting factor of country food consumption. By definition, contaminants are undesirable substances which can cause harm to the environment, the biota, and humans. We can call these naturally accumulating radiological burdens to the Arctic 'natural contaminants' to distinguish them from the traditional meaning of contamination, the 'artificial contaminants' which are attributable to industrial or man-made sources. This paper reviews information available in the literature, analyses long-term atmospheric monitoring data in the Canadian high Arctic, sub-Arctic and mid-latitude sites, and provides discussion on research needed to address questions, such as how heavily the Arctic has been impacted by the

Measurement of radioactive aerosols as an original indicator of atmospheric pollution in urban areas

International Nuclear Information System (INIS)

Le Petit, G.; Millies-Lacroix, J.-C.; Simon, F.

1998-01-01

The Service Radioanalyses, Chimie et Environnement (Departement Analyses Surveillance de l'Environnement) of the French Atomic Energy Commission, located in suburban Paris, has for many years been conducting atmospheric radioactivity measurements. Since 1994, the laboratory has been using high volume air samplers equipped with filters for the weekly collection of atmospheric aerosols at a mean rate of about 600 m 3 .h -1 . The polypropylene filters, with a collection efficiency in excess of 93%, are compacted after sampling. The atmospheric radioactivity is measured by HP Ge gamma spectrometry after decay of short-lived natural relationship products. A study conducted in 1996 shows good correlation between the evolution with time of some of the indicators routinely used by AIRPARIF, the organization in charge of monitoring of the air quality in the Ile-de-France region, to measure atmospheric pollution in the Paris area (SO 2 , NO) and that related to radioactivity of terrestrial ( 210 Pb, 40 K) and anthropogenic ( 137 Cs) origin, as well as the amount of aerosols collected. Further, the distribution in time of the atmospheric radioactivity of cosmogenic origin ( 7 Be) shows a yearly evolution somewhat similar to that observed with ozone. (author). 16 refs., 21 figs., 1 tab

Approach and issues toward development of risk-based release standards for radioactive scrap metal recycle and reuse

International Nuclear Information System (INIS)

Chen, S.Y.; Nieves, L.A.; Nabelssi, B.K.; LePoire, D.J.

1994-01-01

The decontamination and decommissioning of nuclear facilities is expected to generate large amounts of slightly radioactive scrap metal (RSM). It is likely that some of these materials will be suitable for recycling and reuse. The amount of scrap steel from DOE facilities, for instance, is estimated to be more than one million tons (Hertzler 1993). However, under current practice and without the establishment of acceptable recycling standards, the RSM would be disposed of primarily as radioactive low-level waste (LLW). In the United States, no specific standards have been developed for the unrestricted release of bulk contaminated materials. Although standards for unrestricted release of radioactive surface contamination (NRC 1974) have existed for about 20 years, the release of materials is not commonly practiced because of the lack of risk-based justifications. Recent guidance from international bodies (IAEA 1988) has established a basis for deriving risk-based release limits for radioactive materials. It is important, therefore, to evaluate the feasibility of recycling and associated issues necessary for the establishment of risk-based release limits for the radioactive metals

Analysis of the atmospheric 7Be radioactivity by neural network

International Nuclear Information System (INIS)

Moroz, Z.; Myslek-Laurikainen, B.; Matul, M.; Mikolajewski, S.; Preibisz, Z.; Trzaskowaka, H.; Kownacki, C.

2002-01-01

Computational methods of artificial intelligence (neural networks) and modern signal processing (wavelet decomposition were applied for the analysis of atmospheric 7 Be radioactivity data. Measurements were performed each week during 1994-2001 in the sampling station placed at Swider Geophysical Observatory. Raw data as well as those averaged over 4 and 10 weeks were used. Ability of the neural networks for the purpose of representation, interpolation and prediction was tested. The corresponding relative errors are calculated. Next, the time sequences were decomposed using the wavelet method and eight components of different time scales were obtained. Neural networks were applied separately to each of those components. Application of such analysis and their possible extensions useful for the construction of phenomeno-logical models of atmospheric radioactivity are discussed. (author)

Survey of radioactive effluent releases from byproduct material facilities. Technical report

International Nuclear Information System (INIS)

Cook, J.R.

1981-08-01

A survey of over 3,000 NRC byproduct material licensees was conducted in late 1980 to collect data on annual effluent releases of radioactivity. The survey was conducted through a questionnaire, which was sent to NRC licensees who handle radioactive material in unsealed form, i.e., research, medical, and industrial institutions. Principal findings from the survey analysis are as follows: More than 98% of the reported annual releases to air (484 to 490) yield calculated average concentrations at the boundary of the unrestricted area that were at 1% or less than the maximum permissible concentration (MPC) of Appendix B, Table II, Column 1 of 10 CFR 20. The largest reported annual release was estimated to yield a concentration that was approximately 12% of MPC, the 5 other releases ranged from 1 to 10% of MPC. All reported annual releases of liquid waste were within the limits specified by NRC with most facilities reporting annual releases of only a fraction of a curie. Based on the data provided by licensees and analyzed in this report, it appears that in general the environmental impacts from research, medical and industrial institutions and organizations licensed by the NRC to possess and use byproduct materials are minimal and correspond to a small fraction of that from natural background

Aerosols radioactivity in the Bratislava atmosphere

International Nuclear Information System (INIS)

Sykora, I.; Chudy, M.; Durana, L.; Holy, K.; Meresova, J.

2001-01-01

In our laboratory we measured temporal variation of 7 Be concentration in the atmosphere in period 1977 -1994 years. The aerosols were collected through every month at Hydrometeorological Institute in Bratislava-Koliba, latitude 48 grad 10' and altitude 286 m above sea level. Since end of year 2000 we have started to continue monitoring radioactivity of atmosphere aerosols in new locality in Bratislava-Mlynska dolina. Beside 7 Be we measured also 210 Pb radionuclide aerosols concentration. For measured values 7 Be concentrations are considered corrections for decay radionuclide during the time of filters collection, time between end of collection and measurement and decay during the time of measurement. Obtained results for 7 Be concentrations in aerosols shows seasonal summer maximum, but for 210 Pb concentration in aerosols the seasonal variations are not evident. The temporal variations of this radionuclide which is originated in ground-level atmosphere are more sensitive on meteorological factors and can be also influenced by the industrial activity. For better understanding is needed long term monitoring. (authors)

Release procedures and disposal of radioactive residual substances at the Medical University Hanover (MHH)

International Nuclear Information System (INIS)

Scheller, F.; Behrendt, R.; Harke, H.

2005-01-01

The disposal of all radioactive residual packages of the MHH is regulated by the German radiation protection ordinance from 26 th July 2001; shown in appendix III, table 1, column 5: unrestricted release of solid materials and liquids. All radioactive waste packages are collected and handled by the central MHH department for radiation protection. They are sorted for type, nuclide and specific radioactivity. A few packages can directly be released as conventional waste after performing incoming measurements showing very low activity concentrations. Longer living radionuclides with specific activities above the release limits have to be delivered to the national waste disposal. For direct measurements of gamma-emitting radionuclides we use two in-situ-measuring units (ISOCS, Canberra) and a special release unit with 9 plastic scintillators in a fixed geometry (FR-9 PVT, MED Medizintechnik). Fluid beta-emitting radionuclides are measured by taking a fraction and using liquid scintillation counting (LSC). Solid beta-emitting radionuclides activity are calculated. (orig.)

Abnormal radioactivity of the atmosphere. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1952-01-01

Further measurements on the radioactivity of the atmosphere near Puy de Dome are tabulated. The activity in April 1952 with a mean life of 25 hrs was ascribed to the complex particles A. In June 1952 an activity with a mean life of 100 to 400 hrs was attributed to the previously observed A'' particles. The activity associated with the A'' particles was also observed in the soil and air.

Radioactive materials released from nuclear power plants: Annual report, 1984

Energy Technology Data Exchange (ETDEWEB)

Tichler, J.; Norden, K.; Congemi, J.

1987-08-01

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1984 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1984 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Incident involving radioactive material at IAEA Safeguards Laboratory - No radioactivity released to environment

International Nuclear Information System (INIS)

2008-01-01

Full text: Pressure build-up in a small sealed sample bottle in a storage safe resulted in plutonium contamination of a storage room at about 02:30 today at the IAEA's Safeguards Analytical Laboratory in Seibersdorf. All indications are that there was no release of radioactivity to the environment. Further monitoring around the laboratory will be undertaken. No one was working in the laboratory at the time. The Laboratory's safety system detected plutonium contamination in the storage room where the safe was located and in two other rooms - subsequently confirmed by a team of IAEA radiation protection experts. The Laboratory is equipped with multiple safety systems, including an air-filtering system to prevent the release of radioactivity to the environment. There will be restricted access to the affected rooms until they are decontaminated. A full investigation of the incident will be conducted. The IAEA has informed the Austrian regulatory authority. The IAEA's Laboratory in Seibersdorf is located within the complex of the Austrian Research Centers Seibersdorf (ARC), about 35 km southeast of Vienna. The laboratory routinely analyses small samples of nuclear material (uranium or plutonium) as part of the IAEA's safeguards verification work. (IAEA)

Evaluation of radiological releases from the Tomsk-7 accident

Energy Technology Data Exchange (ETDEWEB)

Lussie, W.G.

1995-10-01

On April 6, 1993, there was an uncontrolled release of radioactive material from the fuel reprocessing plant at the Siberian Chemical Combine in Tomsk. The release resulted from the rupture of an over-pressurized feed adjustment tank and subsequent explosion that destroyed the walls and roof of the operating gallery. Radioactive material was released through a 150 meter stack, as well as through the destroyed walls and roof. Relatively stable atmospheric conditions prevailed and a light snow was falling. The radiation release was not excessive, but the spread of radioactive material was compounded by the explosion. Radiation was detected about 26 km from the source. This paper summarizes the information available in the US regarding the release and, using reasonable assumptions, compares the calculated ground activity and radiation levels with the reported measured values.

Evaluation of radiological releases from the Tomsk-7 accident

International Nuclear Information System (INIS)

Lussie, W.G.

1995-01-01

On April 6, 1993, there was an uncontrolled release of radioactive material from the fuel reprocessing plant at the Siberian Chemical Combine in Tomsk. The release resulted from the rupture of an over-pressurized feed adjustment tank and subsequent explosion that destroyed the walls and roof of the operating gallery. Radioactive material was released through a 150 meter stack, as well as through the destroyed walls and roof. Relatively stable atmospheric conditions prevailed and a light snow was falling. The radiation release was not excessive, but the spread of radioactive material was compounded by the explosion. Radiation was detected about 26 km from the source. This paper summarizes the information available in the US regarding the release and, using reasonable assumptions, compares the calculated ground activity and radiation levels with the reported measured values

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

Mesoscale modelling of radioactive contamination formation in Ukraine caused by the Chernobyl accident

International Nuclear Information System (INIS)

Talerko, Nikolai

2005-01-01

This work is devoted to the reconstruction of time-dependent radioactive contamination fields in the territory of Ukraine in the initial period of the Chernobyl accident using the model of atmospheric transport LEDI (Lagrangian-Eulerian DIffusion model). The modelling results were compared with available 137 Cs air and ground contamination measurement data. The 137 Cs atmospheric transport over the territory of Ukraine was simulated during the first 12 days after the accident (from 26 April to 7 May 1986) using real aerological information and rain measurement network data. The detailed scenario of the release from the accidental unit of the Chernobyl nuclear plant has been built (including time-dependent radioactivity release intensity and time-varied height of the release). The calculations have enabled to explain the main features of spatial and temporal variations of radioactive contamination fields over the territory of Ukraine on the regional scale, including the formation of the major large-scale spots of radioactive contamination caused by dry and wet deposition

Size distributions of various radioactive aerosols in the ground-level atmosphere

Energy Technology Data Exchange (ETDEWEB)

Schumann, G.; Baust, E.

1963-11-15

To know the size spectra of radioactive aerosols is important for many reasons. Among others, the efficiency of measuring devices or biological processes, as for instance, retention in the lungs, depend on particle size.The work described deals mainly with two different components of radioactive aerosols in the atmosphere: the natural radon daughters and the fission products originating from nuclear test explosions.

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

Studies for improvement of regulatory control on the radioactive effluent released from nuclear facilities

International Nuclear Information System (INIS)

Cheong, Jae Hak; Park, H. M.; Song, M. C.; Lee, K. H.; Jang, J. K.; Chun, J. K.; Jeong, K. H.

2005-05-01

This report contains the second-year results of the research project titled 'Studies for Improvement of Regulatory Control on the Radioactive Effluent Released from Nuclear Facilities' and mainly provides technical and strategic approaches to improve performance of regulatory control on the gaseous effluent released from domestic nuclear facilities. The main result contained here includes overview and technical bases of radioactive gaseous effluent control (Chapter 1), reconsideration of the sensitivity requirements for measurement of radioactivity in gaseous effluent sample (Chapter 2), uncertainty analysis of the calculated radioactivity in gaseous effluent (Chapter 3), and improvement of quantification method of noble gas releases (Chapter 4). In addition, analysis of the impact due to combined sampling of particulate from multiple release points (Chapter 5), comparison of domestic nuclear reactors gaseous effluent data to foreign PWRs (Chapter 6), standardized sampling technique for collection of gaseous tritium (Chapter 7), and application of Xe-133 equivalent concept to gaseous effluent control (Chapter 8) are also provided. As a whole, this report provides a generic approach to improve the performance of regulatory control on the gaseous effluent. Therefore, actual enforcement of the recommendations should be preceded by establishment of a series of action plans reflecting on the site- and facility-specific design and operational features

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

Radioactivity release vs probability for a steam generator tube rupture accident

International Nuclear Information System (INIS)

Buslik, A.J.; Hall, R.E.

1978-01-01

A calculation of the probability of obtaining various radioactivity releases from a steam generator tube rupture (SGTR) is presented. The only radioactive isotopes considered are Iodine-131 and Xe-133. The particular accident path considered consists of a double-ended guillotine SGTR followed by loss of offsite power (LOSP). If there is no loss of offsite power, and no system fault other than the SGTR, it is judged that the consequences will be minimal, since the amount of iodine released through the condenser air ejector is expected to be quite small; this is a consequence of the fact that the concentration of iodine in the vapor released from the condenser air ejector is very small compared to that dissolved in the condensate water. In addition, in some plants the condenser air ejector flow is automatically diverted to containment or a high-activity alarm. The analysis presented here is for a typical Westinghouse PWR such as described in RESAR-3S

Nuclear risk from atmospheric dispersion in Northern Europe - Summary Report

DEFF Research Database (Denmark)

Lauritzen, Bent

The objective of the NordRisk II project has been to derive practical means for assessing the risks from long-range atmospheric dispersion of radioac-tive materials. An atlas over different atmospheric dispersion and deposi-tion scenarios has been developed using historical numerical weather pre......-diction (NWP) model data. The NWP model data covers three years span-ning the climate variability associated with the North Atlantic Oscillation, and the atlas considers radioactive releases from 16 release sites in and near the Nordic countries. A statistical analysis of the long-range disper......-sion and deposition patterns is undertaken to quantify the mean dispersion and deposition as well as the variability. Preliminary analyses show that the large-scale atmospheric dispersion and deposition is near-isotropic, irrespective of the release site and detailed climatology, and allows for a simple...

Offsite doses from SRP radioactive releases - 1985

International Nuclear Information System (INIS)

Marter, W.L.

1986-01-01

This memorandum summarizes the offsite doses from releases of radioactive materials to the environment from SRP operations in 1985. These doses were calculated for inclusion in the environmental report for 1985 to be issued by the Health Protection Department (DPSPU-86-30-1). The environmental report is prepared annually for distribution to state environmental agencies, the news media, and interested members of the public. More detailed data on offsite exposures by radionuclide and exposure pathway will be included in the environmental report

Sensitivity Analysis of Dousing Spray Trip on Radioactive Release in Pressure Tube Rupture Accident with Both End Fitting Failures

Energy Technology Data Exchange (ETDEWEB)

Jang, M. S.; Kang, H. S; Kim, S. R. [NESS, Daejeon (Korea, Republic of)

2015-10-15

We analyzed the sensitivity analysis of dousing spray trip conditions on radioactive release. In terms of conservativeness, the set 1 trip would be more appropriate in RR analysis than set 2 trip, which is the general condition of RR analysis. Radioactive releases from the containment building is related to containment air pressure, which increases by the coolant discharge from loss of coolant accident and the actuation conditions of dousing spray and so on. In LOCA analysis, the dousing spray trip conditions are set for the analysis objectives; for peak pressure (PP), for pressure signal (PS), for radioactive release (RR) and etc. In RR analysis, we would determine the dousing spray trip condition to increase radioactive release to the public for conservatism. Therefore, we carried out the sensitivity analysis of dousing spray trip condition on radioactive release from containment building using GOTHIC and SMART program for CANDU.

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

Radioactive waste gas processing systems

International Nuclear Information System (INIS)

Kita, Kaoru; Minemoto, Masaki; Takezawa, Kazuaki.

1981-01-01

Purpose: To effectively separate and remove only hydrogen from hydrogen gas-containing radioactive waste gases produced from nuclear power plants without using large scaled facilities. Constitution: From hydrogen gas-enriched waste gases which contain radioactive rare gases (Kr, Xe) sent from the volume control tank of a chemical volume control system, only the hydrogen is separated in a hydrogen separator using palladium alloy membrane and rare gases are concentrated, volume-decreased and then stored. In this case, an activated carbon adsorption device is connected at its inlet to the radioactive gas outlet of the hydrogen separator and opened at its outlet to external atmosphere. In this system, while only the hydrogen gas permeates through the palladium alloy membrane, other gases are introduced, without permeation, into the activated carbon adsorption device. Then, the radioactive rare gases are decayed by the adsorption on the activated carbon and then released to the external atmosphere. (Furukawa, Y.)

Radioactive release data from Canadian nuclear generating stations 1872-1987

International Nuclear Information System (INIS)

1989-03-01

All nuclear generating stations emit small quantities of radioactive effluent both into the atmosphere and in the form of liquid effluent, into the adjoining water body, be it river, lake or sea. The purpose of this document is to report on the magnitude of these emissions for each nuclear generating station in Canada and to indicate how these emissions compare with the relevant limitations imposed by the Atomic Energy Control Board as part of its regulatory and licensing program. This report incorporates histograms indicating the annual releases of tritium in air, noble gases, iodine-131, airborne particulates, tritium in water and waterborne gross beta activity for each nuclear generating station. In addition, for Pickering NGS 'A', annual released of carbon-14 are depicted for the years 1986 and 1987. In each case the emission data are compared to the Derived Emission Limit (DEL) in order that the data may be placed in perspective. At present, only Pickering NGS 'A' is required to monitor and report carbon-14 emissions. Environmental monitoring for C-14 is conducted around the Bruce site to determine the environmental impact of its emission and whether effluent monitoring will be necessary in future years. Three nuclear generating stations have been permanently taken out of service during the last few years (Gentilly NGS-1, Douglas Point NGS and NPD NGS). Some small emissions from these sites do still occur, however, due to decontamination and decommissioning operations. (11 tabs., 26 figs.)

Solidification method of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Baba, Tsutomu; Chino, Koichi; Sasahira, Akira; Ikeda, Takashi

1992-07-24

Metal solidification material can completely seal radioactive wastes and it has high sealing effect even if a trace amount of evaporation should be caused. In addition, the solidification operation can be conducted safely by using a metal having a melting point of lower than that of the decomposition temperature of the radioactive wastes. Further, the radioactive wastes having a possibility of evaporation and scattering along with oxidation can be solidified in a stable form by putting the solidification system under an inert gas atmosphere. Then in the present invention, a metal is selected as a solidification material for radioactive wastes, and a metal, for example, lead or tin having a melting point of lower than that of the decomposition temperature of the wastes is used in order to prevent the release of the wastes during the solidification operation. Radioactive wastes which are unstable in air and scatter easily, for example, Ru or the like can be converted into a stable solidification product by conducting the solidification processing under an inert gas atmosphere. (T.M.).

Enviromental radioactivity of 1987 in Romania

International Nuclear Information System (INIS)

Galeriu, D.; Oncescu, M.

1988-02-01

The radioactivity of atmosphere. hydrosphere, lithosphere and biosphere from 1987 is compared with that one from preceeding years, after 1963. Estimations of the effective dose equivalent (EDE) for the natural, additional (due to man-made releases), medical and occupational exposure are given. (authors)

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

Methods for determining the release of radioactive material into the environment

International Nuclear Information System (INIS)

Farges, L.; Daw, H.T.

1976-01-01

The current policy on the discharge of radioactive effluents calls for the containment of radioactive wastes in most instances. The resulting doses to individuals and populations have been shown by many surveys to be very small (UNSCEAR Report, 1972). Nevertheless, small amounts of radioactive releases are made to the environment during normal operation of nuclear facilities. Whenever discharge of radioactive effluents to the environment is permitted, careful consideration is made of all the relevant factors which might lead to exposure of man. However, with the expansion of nuclear power programmes, more sophistication is required in setting discharge limits to the environment, taking into consideration future sources as well as present sources. The IAEA's recommendations conform to the dose limitation system set out by the International Commission on Radiological Protection (ICRP). The system implies that the individual dose limits should never be exceeded. Furthermore, the ICRP guidelines require that doses be kept as low as reasonably possible, taking social and economic considerations into account. This second objective, usually called optimization, implies the use of differential cost-benefit analysis. At present, decisions are still made by other procedures, for example, by applying safety factors to release limits derived only from the dose limits. However, the ICRP system of dose limitation, including optimization, appears to be a more rational approach to the establishment of release limits. Thus, it is necessary to provide basic material on concepts which are intended for use and decision making by national authorities, and the Agency plans to publish a series of complementary documents on the application of these concepts to various specific cases. (author)

Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

International Nuclear Information System (INIS)

Brits, R.J.N; Prinsloo, L.; De Jesus, A.S.M.

1981-07-01

The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1980. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartbeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 0 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborn activity from nuclear-bomb tests are reported. Due to the absence of fresh fallout, the levels for most fission products have fallen below the limit of detection. No environmental radioactivity resulting from NNRC releases could be detected above the natural background or accumulated fallout levels [af

Recent results on atmospheric radioactivity at Ibadan, Nigeria

International Nuclear Information System (INIS)

Adeniyi, M.O.; Oladiran, E.O.

2006-01-01

Measurements of alpha and beta radiations carried out in Ibadan (Nigeria) are presented. Activity of alpha radiation in the air is much lower than that of beta. The mean daily activity (Bq) ranged from 0.013 to 0.075 for alpha and from 1.475 to 76.136 for beta throughout the periods of investigation which include wet, dry and harmattan periods. The highest activity occurred during harmattan followed by wet period and the least was during the dry period. The harmattan dust originating from the Sahara desert is found to be radioactive. During wet period the aerosols and the condensation nuclei present in the atmosphere were also found to be radioactive to some extent. Background beta (β) and alpha (α) activities were found to have increased greatly over those earlier reported in the period between 1986/1987-2001/2002. Beta activity has two peaks at 19 and 6hLT while the peak time of alpha activity varies randomly throughout the periods of observation. The minima activities of alpha and beta occur throughout the day. The results showed that ambient α and β activities were highly correlated to atmospheric potential gradient

Determination of the potential radiation exposure of the population close to the Asse II mine caused by deduction of radioactive substances with the discharge air in the normal operation using the ''Atmospheric Radionuclide-Transport-Model'' (ARTM)

International Nuclear Information System (INIS)

Esch, D.; Wittwer, C.

2014-01-01

Between 1967 and 1978 125.787 packages filled with low-level and intermediate-level radioactive waste were emplaced in the mining plant Asse II. Volatile radioactive substances like H-3, C-14 and Rn-222 are released from the emplaced waste. These substances reach the ventilated parts of the mine and are released with the discharge air. The potential radiation exposure of the population caused by deduction of radioactive substances with the discharge air in the normal operation is determined by the ''Atmospheric Radionuclide-Transport-Model'' (ARTM). As result the maximal deductions of volatile radioactive substances with the discharge air in the normal operation of the Asse II mine lead to radiation exposure of the population, which is considerably lower than the permissible values of application rate.

Use of OND-86 recommendations for calculation of the Shelter radioactive release

International Nuclear Information System (INIS)

Bogatov, S.A.

2000-01-01

A model of radioactive release from the Shelter has been considered under current operation conditions. Integral assessment of current dust release has been done on the base of natural ventilation rate. Model predictions are consistent (20% accuracy) with experimental results of air contamination measurements at the earth surface. 12 refs., 1 tab., 6 figs

Geographical distribution of radioactive nuclides released from the Fukushima Daiichi Nuclear Power Station accident in eastern Japan

International Nuclear Information System (INIS)

Ishida, Masanobu; Umetsu, Kohei; Sugimoto, Miyabi; Yamaguchi, Yuta; Yamazaki, Hideo; Nakagawa, Ryota

2013-01-01

The geographical distribution of radioactive nuclides released from the Fukushima Daiichi Nuclear Power Station accident in metropolitan areas located in eastern Japan was investigated. The radioactive contamination of environmental samples, including soil and biological materials, was analyzed. The concentrations of 131 I, 134 Cs, and 137 Cs in the soil samples collected from Fukushima City were 122000, 11500 and 14000 Bq/kg on 19th March 2011 and 129000, 11000 and 13700 Bq/kg on 26th March 2011, for the three nuclides respectively. The concentrations of 131 I, 134 Cs and 137 Cs in the soil samples collected from March-June 2011 from study sites ranged from 240 to 101000, 28 to 26200, and 14 to 33700 Bq/kg, respectively. In Higashiosaka City, it began to detect those radioactive nuclides in the atmospheric airborne dust from 25th March. Radioactive fission products 95 Zr- 95 Nb were detected on 18th April 2011. Biological samples collected from Tokyo Bay were studied. The maximum concentrations of 134 Cs and 137 Cs detected in the biological samples were 12.2 and 19.2 Bq/kg, which were measured in goby. 131 I was not detected in the biological samples however, trace amounts of the short half-life nuclide 110m Ag were found in the shellfish samples. (author)

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

Real Time Radioactivity Monitoring and its Interface with predictive atmospheric transport modelling

International Nuclear Information System (INIS)

Raes, F.

1990-01-01

After the Chernobyl accident, a programme was initiated at the Joint Research Centre of the Commission of the European Communities named 'Radioactivity Environmental Monitoring' (REM). The main aspects considered in REM are: data handling, atmospheric modelling and data quality control related to radioactivity in the environment. The first REM workshop was held in December 1987: 'Aerosol Measurements and Nuclear Accidents: A Reconsideration'. (CEC EUR 11755 EN). These are the proceedings of the second REM workshop, held in December 1989, dealing with real-time radioactivity monitoring and its interface with predictive atmospheric models. Atmospheric transport models, in applications extending over time scales of the order of a day or more become progressively less reliable to the extent that an interface with real-time radiological field data becomes highly desirable. Through international arrangements for early exchange of information in the event of a nuclear accident (European Community, IAEA) such data might become available on a quasi real-time basis. The question is how best to use such information to improve our predictive capabilities. During the workshop the present status of on-line monitoring networks for airborne radioactivity in the EC Member States has been reviewed. Possibilities were discussed to use data from such networks as soon as they become available, in order to update predictions made with long range transport models. This publication gives the full text of 13 presentations and a report of the Round Table Discussion held afterwards

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

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)

Study of the behaviour of artificial radioactive aerosols. Applications to some problems of atmospheric circulation (1963)

International Nuclear Information System (INIS)

Lambert, G.

1963-11-01

The aim of this work, consists in the examination of the behaviour of radioactive aerosols produced in the atmosphere by nuclear explosions, in order to deduce the most general laws governing atmospheric circulation and diffusion. After having given a general table of the radioactive aerosols present the authors consider the validity and the precision of the measurement methods and the concentration of the aerosols at ground level and in the upper atmosphere, as well as their deposition on the ground. The existence is thus demonstrated of a tropospheric equatorial barrier and of discontinuous and seasonal aspects of stratosphere-troposphere transfers. The role is shown of precipitations and dry auto-filtration in the lower atmosphere cleaning processes. This work makes it possible to describe the general behaviour of dust from the stratosphere, and to improve the total radioactive contamination of the globe. (author) [fr

Retention and subsequent release of radioactivity from the incineration of wastes containing microspheres

International Nuclear Information System (INIS)

Emery, R.J.; Watson, J.E. Jr.

1990-01-01

Incineration is the preferred method for disposing of animal carcasses containing radioactive microspheres at the authors University. Routine surveys of ash from successive nonradioactive burns revealed significant contamination from previously incinerated microspheres. Past studies on microsphere incineration quantified the amount of activity retained in ash, but did not address any subsequent releases. This topic was not considered in earlier studies because, in most cases, the carcasses were placed in some type of container to facilitate recovery of ash, preventing contamination of the incinerator refractory. In this study, five sets of controlled burns were performed to quantify the subsequent releases of the microsphere radioisotopes 141 Ce, 113 Sn, 102 Ru, 95 Nb, and 46 Sc. Each set consisted of three successive burns. The first burn of each set incinerated a non-radioactive carcass, the second burn, a radioactive carcass, and the third, a non-radioactive carcass. In all of the burns, the carcasses were placed directly on the incinerator refractory floor, which is the standard procedure during normal operations

Virtual cascade impactors for the collection of radioactive atmospheric aerosols

International Nuclear Information System (INIS)

Berner, A.

1988-01-01

Starting from impaction theory, the properties of virtual impaction stages are discussed and compared to classical impactors. Virtual impaction stages offer the benefit of sampling coarse particles without bouncing and reentrainment, but turbulent mixing affects the performance of virtual stages. Future research should concentrate on special configurations for reducing the effects of turbulent mixing. Virtual impaction stages for sampling radioactive aerosols are to be designed in regard of the analytical requirements, the purpose of the measurements, and the aerosol. Therefore, the aerosol components expected in radioactive aerosols are discussed on the background of the multimodal model, which relates the size distribution to the genesis and the history of the aerosol. Reference is made to recent data of the radioactive atmospheric aerosol

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

Some discussions on micrometeorology and atmospheric diffusion of classic and radioactive industrial pollutions. 3

International Nuclear Information System (INIS)

Veverka, O.; Valenta, V.; Vlachovsky, K.

1977-01-01

The vertical motion of an industrial plume, either conventional or radioactive is discussed and the respective formulas are given. The solution is given for the vertical rise of the plume and for the bent-over semi-horizontal plume under neutral, stable, and unstable atmospheric conditions. A theoretical model is described for the continuous rise of the radioactive plume under stable atmospheric conditions. The effective height is defined of the plume with regard to the shape of terrain and wind velocity. (J.P.)

Implementation of a model of atmospheric dispersion and dose calculation in the release of radioactive effluents in the Nuclear Centre

International Nuclear Information System (INIS)

Cruz L, C. A.

2015-01-01

In the present thesis, the software DERA (Dispersion of Radioactive Effluents into the Atmosphere) was developed in order to calculate the equivalent dose, external and internal, associated with the release of radioactive effluents into the atmosphere from a nuclear facility. The software describes such emissions in normal operation, and not considering the exceptional situations such as accidents. Several tools were integrated for describing the dispersion of radioactive effluents using site meteorological information (average speed and wind direction and the stability profile). Starting with the calculation of the concentration of the effluent as a function of position, DERA estimates equivalent doses using a set of EPA s and ICRP s coefficients. The software contains a module that integrates a database with these coefficients for a set of 825 different radioisotopes and uses the Gaussian method to calculate the effluents dispersion. This work analyzes how adequate is the Gaussian model to describe emissions type -puff-. Chapter 4 concludes, on the basis of a comparison of the recommended correlations of emissions type -puff-, that under certain conditions (in particular with intermittent emissions) it is possible to perform an adequate description using the Gaussian model. The dispersion coefficients (σ y and σ z ), that using the Gaussian model, were obtained from different correlations given in the literature. Also in Chapter 5 is presented the construction of a particular correlation using Lagrange polynomials, which takes information from the Pasquill-Gifford-Turner curves (PGT). This work also contains a state of the art about the coefficients that relate the concentration with the equivalent dose. This topic is discussed in Chapter 6, including a brief description of the biological-compartmental models developed by the ICRP. The software s development was performed using the programming language Python 2.7, for the Windows operating system (the XP

Forum on impact of radioactive materials on the atmospheric pollutant inventory and on the radioactivity uptake by plants

International Nuclear Information System (INIS)

1987-01-01

This report contains 6 separately documented lectures about the following topics of the meeting: 1) Radiation exposure of plants caused by the reactor accident of Chernobyl; 2) Tritium and radiocarbon concentrations in trees; 3) Energetics of the atmospheric trace materials cycle; 4) Phenomenology of formation and decomposition of ozone in the lower atmosphere, and 5) Comparison of radioactivity levels and trace materials in the air. (PW)

Nuclear refugees after large radioactive releases

International Nuclear Information System (INIS)

Pascucci-Cahen, Ludivine; Groell, Jérôme

2016-01-01

However improbable, large radioactive releases from a nuclear power plant would entail major consequences for the surrounding population. In Fukushima, 80,000 people had to evacuate the most contaminated areas around the NPP for a prolonged period of time. These people have been called “nuclear refugees”. The paper first argues that the number of nuclear refugees is a better measure of the severity of radiological consequences than the number of fatalities, although the latter is widely used to assess other catastrophic events such as earthquakes or tsunami. It is a valuable partial indicator in the context of comprehensive studies of overall consequences. Section 2 makes a clear distinction between long-term relocation and emergency evacuation and proposes a method to estimate the number of refugees. Section 3 examines the distribution of nuclear refugees with respect to weather and release site. The distribution is asymmetric and fat-tailed: unfavorable weather can lead to the contamination of large areas of land; large cities have in turn a higher probability of being contaminated. - Highlights: • Number of refugees is a good indicator of the severity of radiological consequences. • It is a better measure of the long-term consequences than the number of fatalities. • A representative meteorological sample should be sufficiently large. • The number of refugees highly depends on the release site in a country like France.

Indoor-atmospheric radon-related radioactivity affected by a change of ventilation strategy

International Nuclear Information System (INIS)

Kobayashi, Tuneo

2006-01-01

The present author has kept observation for concentrations of atmospheric radon, radon progeny and thoron progeny for several years at the campus of Fukushima Medical University. Accidentally, in the midst of an observation term, i.e., February 2005, the facility management group of the university changed a strategy for the manner of ventilation, probably because of a recession: tidy everyday ventilation of 7:30-24:00 into shortened weekday ventilation of 8:00-21:00 with weekend halts. This change of ventilation manner brought a clear alteration for the concentrations of radon-related natural radioactivity in indoor air. The present paper concerns an investigation of the effect of the ventilation strategy on the indoor-atmospheric radon-related radioactivity. (author)

Freedom: a transient fission-product release model for radioactive and stable species

International Nuclear Information System (INIS)

Macdonald, L.D.; Lewis, B.J.; Iglesias, F.C.

1989-05-01

A microstructure-dependent fission-gas release and swelling model (FREEDOM) has been developed for UO 2 fuel. The model describes the transient release behaviour for both the radioactive and stable fission-product species. The model can be applied over the full range of operating conditions, as well as for accident conditions that result in high fuel temperatures. The model accounts for lattice diffusion and grain-boundary sweeping of fusion products to the grain boundaries, where the fission gases accumulate in grain-face bubbles as a result of vacancy diffusion. Release of fission-gas to the free void of the fuel element occurs through the interlinkage of bubbles and cracks on the grain boundaries. This treatment also accounts for radioactive chain decay and neutron-induced transmutation effects. These phenomena are described by mass balance equations which are numerically solved using a moving-boundary, finite-element method with mesh refinement. The effects of grain-face bubbles on fuel swelling and fuel thermal conductivity are included in the ELESIM fuel performance code. FREEDOM has an accuracy of better than 1% when assessed against an analytic solution for diffusional release. The code is being evaluated against a fuel performance database for stable gas release, and against sweep-gas and in-cell fission-product release experiments at Chalk River for active species

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

On the use of the HOTSPOT code for evaluating accidents involving radioactive materials

International Nuclear Information System (INIS)

Sattinger, D.; Sarussi, R.; Tzarfati, Y.; Levinson, S.; Tshuva, A.

2004-01-01

The HOTSPOT Health Physics code was created by LLNL in order to provide Health Physics personnel with a fast, field portable calculation tool for evaluating accidents involving radioactive materials. The HOTSPOT code is a first order approximation of the radiation effects associated with the atmospheric release of radioactive materials. HOTSPOT programs are reasonably accurate for a timely initial assessment. More importantly, HOTSPOT code produce a consistent output for the same input assumptions, and minimize the probability of errors associated with reading a graph incorrectly. Four general programs, Plume, Explosion, Fire, and Resuspension, calculate a downwind assessment following the release of radioactive material resulting from a continuous or puff release, explosive release, fuel or fire, or an area contamination event. Additional programs estimate the dose commitment from inhalation of any one of the radionuclides listed in the database of radionuclides, calibrate a radiation survey instrument for ground survey measurements, and screening of alpha emitters in the Lung. We believe that the HOTSPOT code is extremely valuable in providing reasonable and reliable guidance for a diversity of application. For example, we demonstrate the release of 241 Am(20Ci) to the atmosphere

Regularities in the behavior of radioactive aerosols in the near-earth atmosphere

Energy Technology Data Exchange (ETDEWEB)

Makhonko, K.P.; Avramenko, A.S.; Martynenko, V.P.; Volokitin, A.A.; Rabotnova, F.A.

1979-10-01

The relationship is considered between the power of nuclear explosions and mean annual magnitudes of surface concentrations and atmospheric fallout of long-lived isotopes which are products of these explosions. The role of Chinese nuclear explosions in pollution of the atmosphere over the territory of the USSR is demonstrated. Regularities are discussed about the annual course of concentrations of products of atmospheric nuclear explosions, features in concentration distribution over the territory of the USSR as well as the impact of the amount and type of atmospheric precipitation upon the formation of radioactive fallout.

Cask for radioactive material and method for preventing release of neutrons from radioactive material

International Nuclear Information System (INIS)

Gaffney, M.F.; Shaffer, P.T.

1981-01-01

A cask for radioactive material, such as nuclear reactor fuel or spent nuclear reactor fuel, includes a plurality of associated walled internal compartments for containing such radioactive material, with neutron absorbing material present to absorb neutrons emitted by the radioactive material, and a plurality of thermally conductive members, such as longitudinal copper or aluminum castings, about the compartment and in thermal contact with the compartment walls and with other such thermally conductive members and having thermal contact surfaces between such members extending, preferably radially, from the compartment walls to external surfaces of the thermally conductive members, which surfaces are preferably in the form of a cylinder. The ends of the shipping cask also preferably include a neutron absorber and a conductive metal covering to dissipate heat released by decay of the radioactive material. A preferred neutron absorber utilized is boron carbide, preferably as plasma sprayed with metal powder or as particles in a matrix of phenolic polymer, and the compartment walls are preferably of stainless steel, copper or other corrosion resistant and heat conductive metal or alloy. The invention also relates to shipping casks, storage casks and other containers for radioactive materials in which a plurality of internal compartments for such material, e.g., nuclear reactor fuel rods, are joined together, preferably in modular construction with surrounding heat conductive metal members, and the modules are joined together to form a major part of a finished shipping cask, which is preferably of cylindrical shape. Also within the invention are methods of safely storing radioactive materials which emit neutrons, while dissipating the heat thereof, and of manufacturing the present shipping casks

International comparison on radioactive releases of PWR between 1975 and 1988

International Nuclear Information System (INIS)

Benedittini, M.; Tabare, M.

1990-02-01

This report presents the main results of a comparison on radioactive releases from 135 PWRs in the following countries: Belgium, Federal Republic of Germany, Finland, France, Japan, Sweden, Switzerland and the United States. For liquid releases, distinctions have been undertaken between tritium and no tritium activities and for gaseous releases between noble gases and halogens-aerosols. Data has been collected from literature published or by contacting utilities administrative staff or authorities in order to constitute a data base. As regards this comparison however, reactors, the commercial operation of which started prior to July 1974, have been excluded [fr

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.

Study of radio-active ions in the atmosphere; Etude des ions radioactifs de l'atmosphere

Energy Technology Data Exchange (ETDEWEB)

Renoux, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1965-01-01

A comparative study is made of active, deposits of radon and thoron in suspension in the atmosphere by means of {alpha} radiation counting, using ZELENY tubes, scattering equipment, filter papers or membranes. It has been possible to show the existence of small and large ions which are negative and positive, as well as of neutral radio-active nuclei; their properties are studied. A theoretical interpretation of the results is presented. The average content of radon (using the Ra A concentration) and of Th B in the air has been determined. The radioactive equilibrium between radon and its daughter products in atmospheric air are examined. The techniques developed for active radon and thoron deposits are applied to the study of artificial radio-activity, the analyses being carried out by means of {gamma} spectrometry. (author) [French] On effectue une etude comparative entre les depots actifs du radon et du thoron en suspension dont l'atmosphere a l'aide de comptages de rayonnement {alpha}, en utilisant des tubes de ZELENY, une batterie de diffusion, des papiers filtres ou des membranes. On met ainsi en evidence la presence de petits et gros ions negatifs et positifs, ainsi que celle de noyaux neutres radioactifs, et on etudie leurs proprietes. Une Interpretation theorique des resultats obtenus est developpee. On determine la teneur moyenne de l'air en radon (a partir de la concentration en Ra A) et en Th B. L'equilibre radioactif entre le radon et ses descendants, dans l'air atmospherique, est examine. Les Techniques mises au point pour les depots actifs du radon et du thoron sont appliquees a l'etude de la radioactivite artificielle, les depouillements s'effectuant par spectrometrie {gamma}. (auteur)

Radioactive iodine releases from nuclear power plant, (1)

International Nuclear Information System (INIS)

Hashimoto, Tatsuya

1974-01-01

Concerning the release of radioactive iodine from nuclear power plants, the guidelines and data both in Japan and abroad are briefed, including those in the United States, Tsuruga nuclear power station and working Group of the Environmental Radiation Study Committee. In case of the Tsuruga nuclear power station, the radiation dose and other data for a few years are presented. Parameters and factors proposed by the working group cover such as the dose through food intake and respiration, concentration factor, etc. (Mori, K.)

Analysis of a Radioactive Release in a Nuclear Waste Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Poppiti, James [Dept. of Energy, Washington, DC (United States); Nelson, Roger [Dept. of Energy, Carlsbad, NM (United States); MacMillan, Walter J. [Nuclear Waste Partners, Carlsbad, NM (United States); Cunningham, Scott

2017-07-01

The Waste Isolation Pilot Plant (WIPP) is a 655-meter deep mine near Carlsbad, New Mexico, used to dispose the nation’s defense transuranic waste. Limited airborne radioactivity was released from a container of radioactive waste in WIPP on 14 February, 2014. As designed, a mine ventilation filtration system prevented the large scale release of contamination from the underground. However, isolation dampers leaked, which allowed the release of low levels of contaminants after the event until they were sealed. None of the exposed individuals received any recordable dose. While surface contamination was limited, contamination in the ventilation system and portions of the underground was substantial. High efficiency particulate air (HEPA) filters in the operating ventilation system ensure continued containment during recovery and resumption of disposal operations. However, ventilation flow is restricted since the incident, with all exhaust air directed through the filters. Decontamination and natural fixation by the hygroscopic nature of the salt host rock has reduced the likelihood of further contamination spread. Contamination control and ventilation system operability are crucial for resumption of operations. This article provides an operational assessment and evaluation of these two key areas.

Analysis of a Radioactive Release in a Nuclear Waste Disposal Facility

International Nuclear Information System (INIS)

Poppiti, James; Nelson, Roger; MacMillan, Walter J.; Cunningham, Scott

2017-01-01

The Waste Isolation Pilot Plant (WIPP) is a 655-meter deep mine near Carlsbad, New Mexico, used to dispose the nation's defense transuranic waste. Limited airborne radioactivity was released from a container of radioactive waste in WIPP on 14 February, 2014. As designed, a mine ventilation filtration system prevented the large scale release of contamination from the underground. However, isolation dampers leaked, which allowed the release of low levels of contaminants after the event until they were sealed. None of the exposed individuals received any recordable dose. While surface contamination was limited, contamination in the ventilation system and portions of the underground was substantial. High efficiency particulate air (HEPA) filters in the operating ventilation system ensure continued containment during recovery and resumption of disposal operations. However, ventilation flow is restricted since the incident, with all exhaust air directed through the filters. Decontamination and natural fixation by the hygroscopic nature of the salt host rock has reduced the likelihood of further contamination spread. Contamination control and ventilation system operability are crucial for resumption of operations. This article provides an operational assessment and evaluation of these two key areas.

Calculation of releases of radioactive materials in gaseous effluents from nuclear-powered merchant ships (NMS-GEFF code)

International Nuclear Information System (INIS)

Cardile, F.P.; Bangart, R.L.; Collins, J.T.

1978-06-01

The Intergovernmental Maritime Consultative Organization IMCO) is currently preparing guidelines concerning the safety of nuclear-powered merchant ships. An important aspect of these guidelines is the determination of the releases of radioactive material in effluents from these ships and the control exercised by the ships over these releases. To provide a method for the determination of these releases, the NRC staff has developed a computerized model, the NMS-GEFF Code, which is described in the following chapters. The NMS-GEFF Code calculates releases of radioactive material in gaseous effluents for nuclear-powered merchant ships using pressurized water reactors

Conditioning the radioactive oils released from the Cernavoda NPP operation

International Nuclear Information System (INIS)

Popescu, I.; Deneanu, N.; Dulama, M.; Baboiescu, E.

2001-01-01

The radioactive oils released during the Cernavoda NPP operation are lubricating oils used in the primary circuit pumps, hydraulic oils used in the reactor charging machine, as well as, waste turbine oils. The primary cooling circuit is the main way of contamination. This waste contain variable amounts of tritium of activities up to 10 8 Bq/l and relatively small amounts of β/γ emitting radionuclides. The radioactive oils resulting of the heat transport system may contain as much as 1.8 TBq/l of tritium. At INR Pitesti, Department of Radioactive Waste Processing, studies were done concerning the radioactive oils conditioning in concrete. It was found that the minimal compression level required for disposal, of 50 MPa, was exceeded. As consequence, the conditioned waste fulfils the conditions of acceptance provided by the Radioactive Waste National Repository at Baita-Bihor. The main stages of the process are: - dosing the radioactive oil, water and NOFOX9 and NOFOX4 emulsion additives for the 220 l or 80 l barrel; - mixing these ingredients up to reaching the emulsion state; - dosing the cement and lime; - adding the enhancing silicate and shaking the mixture to get a homogeneous matrix; - closing the barrel; - conditioning the 80 l barrel within the 220 l container. The production capacity is of 5 to 8 barrels/shift

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.

Air modelling as an alternative to sampling for low-level radioactive airborne releases

International Nuclear Information System (INIS)

Morgenstern, M.Y.; Hueske, K.

1995-01-01

This paper describes our efforts to assess the effect of airborne releases at one DOE laboratory using air modelling based on historical data. Among the facilities affected by these developments is Los Alamos National Laboratory (LANL) in New Mexico. RCRA, as amended by the Hazardous and Solid Waste Amendments (HSWA) in 1984, requires all facilities which involve the treatment, storage, and disposal of hazardous waste obtain a RCRA/HSWA waste facility permit. LANL complied with CEARP by initiating a process of identifying potential release sites associated with LANL operations prior to filing a RCRA/HSWA permit application. In the process of preparing the RCRA/HSWA waste facility permit application to the U.S. Environmental Protection Agency (EPA), a total of 603 Solid Waste Management Units (SWMUs) were identified as part of the requirements of the HSWA Module VIH permit requirements. The HSWA Module VIII permit requires LANL to determine whether there have been any releases of hazardous waste or hazardous constituents from SWMUs at the facility dating from the 1940's by performing a RCRA Facility Investigation to address known or suspected releases from specified SWMUs to affected media (i.e. soil, groundwater, surface water, and air). Among the most troublesome of the potential releases sites are those associated with airborne radioactive releases. In order to assess health risks associated with radioactive contaminants in a manner consistent with exposure standards currently in place, the DOE and LANL have established Screening Action Levels (SALs) for radioactive soil contamination. The SALs for each radionuclide in soil are derived from calculations based on a residential scenario in which individuals are exposed to contaminated soil via inhalation and ingestion as well as external exposure to gamma emitters in the soil. The applicable SALs are shown

Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

International Nuclear Information System (INIS)

Brits, R.J.N.; Van der Westhuizen, G.S.H.; Annandale, J.

1983-06-01

The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1982. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartebeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 90 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborne activity from nuclear-bomb tests are reported. Due to absence of fresh fallout material the levels for most fission products have fallen below the limit of detection. No environmental radioactivity due to releases from the Pelindaba site could be detected above the natural background or accumulated fallout levels. Unplanned releases of UF 6 occur sometimes. Accordingly, some of the environmental samples were also analysed for uranium. The results obtained so far do not indicate an increase in uranium levels in the environment

Radioactive materials released from nuclear power plants. Annual report, 1982. Volume 3

International Nuclear Information System (INIS)

Tichler, J.; Norden, K.

1986-02-01

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1982 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1982 release data are summarized in tabular form. Data covering specific radionuclides are summarized

The MAFF dry cloth collector programme for monitoring airborne radioactivity

International Nuclear Information System (INIS)

McHugh, J.O.; Smith, B.D.; Hunt, G.J.; Thomas, R.E.G.

1986-01-01

The history of the MAFF airborne radioactivity monitoring programme and its current operation using dry cloth collectors are described. The detection system has become well established as a sensitive indicator of airborne radioactivity. Details of collector materials, deployment around the major UK nuclear establishments and procedures for radiometric analysis of cloths are given. Typical results for the period 1980-82 show that at most sites only nuclear weapons fallout was detected. The systems's usefulness is exemplified by its response to the release of I-131 from Sellafield in 1981; this release was of negligible radiological significance but was easily detected. The response of dry cloths to various sources of atmospheric radioactivity and factors affecting collection efficiency are discussed. (author)

Influence of radioactivity on surface charging and aggregation kinetics of particles in the atmosphere.

Science.gov (United States)

Kim, Yong-Ha; Yiacoumi, Sotira; Lee, Ida; McFarlane, Joanna; Tsouris, Costas

2014-01-01

Radioactivity can influence surface interactions, but its effects on particle aggregation kinetics have not been included in transport modeling of radioactive particles. In this research, experimental and theoretical studies have been performed to investigate the influence of radioactivity on surface charging and aggregation kinetics of radioactive particles in the atmosphere. Radioactivity-induced charging mechanisms have been investigated at the microscopic level, and heterogeneous surface potential caused by radioactivity is reported. The radioactivity-induced surface charging is highly influenced by several parameters, such as rate and type of radioactive decay. A population balance model, including interparticle forces, has been employed to study the effects of radioactivity on particle aggregation kinetics in air. It has been found that radioactivity can hinder aggregation of particles because of similar surface charging caused by the decay process. Experimental and theoretical studies provide useful insights into the understanding of transport characteristics of radioactive particles emitted from severe nuclear events, such as the recent accident of Fukushima or deliberate explosions of radiological devices.

Control of synthesis and release of radioactive acetylcholine in brain slices from the rat. Effects of neurotropic drugs

Science.gov (United States)

Grewaal, D. S.; Quastel, J. H.

1973-01-01

1. Studies of the synthesis and release of radioactive acetylcholine in rat brain-cortex slices incubated in Locke–bicarbonate–[U-14C]glucose media, containing paraoxon as cholinesterase inhibitor, revealed the following phenomena: (a) dependence of K+-or protoveratrine-stimulated acetylcholine synthesis and release on the presence of Na+ and Ca2+ in the incubation medium, (b) enhanced release of radioactive acetylcholine by substances that promote depolarization at the nerve cell membrane (e.g. high K+, ouabain, protoveratrine, sodium l-glutamate, high concentration of acetylcholine), (c) failure of acetylcholine synthesis to keep pace with acetylcholine release under certain conditions (e.g. the presence of ouabain or lack of Na+). 2. Stimulation by K+ of radioactive acetylcholine synthesis was directly proportional to the external concentration of Na+, but some synthesis and release of radioactive acetylcholine occurred in the absence of Na+ as well as in the absence of Ca2+. 3. The Na+ dependence of K+-stimulated acetylcholine synthesis was partly due to suppression of choline transport, as addition of small concentrations of choline partly neutralized the effect of Na+ lack, and partly due to the suppression of the activity of the Na+ pump. 4. Protoveratrine caused a greatly increased release of radioactive acetylcholine without stimulating total radioactive acetylcholine synthesis. Protoveratrine was ineffective in the absence of Ca2+ from the incubation medium. It completely blocked K+ stimulation of acetylcholine synthesis and release. 5. Tetrodotoxin abolished the effects of protoveratrine on acetylcholine release. It had blocking effects (partial or complete) on the action of high K+, sodium l-glutamate and lack of Ca2+ on acetylcholine synthesis and release. 6. Unlabelled exogenous acetylcholine did not diminish the content of labelled tissue acetylcholine, derived from labelled glucose, suggesting that no exchange with vesicular acetylcholine took

Release of radioactive fission products from BN-600 reactor untight fuel elements

International Nuclear Information System (INIS)

Osipov, S.L.; Tsikunov, A.G.; Lisitsin, E.C.

1996-01-01

The experimental data on the release of radioactive fission products from BN-600 reactor untight fuel elements are given in the report. Various groups of radionuclides: inert gases Xe, Kr, volatile Cs, J, non-volatile Nb, and La are considered. The results of calculation-experimental study of transfer and distribution of radionuclides in the reactor primary circuit, gas system and sodium coolant are considered. It is shown that some complex radioactivity transfer processes can be described by simple mathematical models. (author)

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

Atmospheric transport of radioactive debris to Norway in case of a hypothetical accident related to the recovery of the Russian submarine K-27

International Nuclear Information System (INIS)

Bartnicki, Jerzy; Amundsen, Ingar; Brown, Justin; Hosseini, Ali; Hov, Øystein; Haakenstad, Hilde; Klein, Heiko; Lind, Ole Christian; Salbu, Brit; Szacinski Wendel, Cato C.; Ytre-Eide, Martin Album

2016-01-01

The Russian nuclear submarine K-27 suffered a loss of coolant accident in 1968 and with nuclear fuel in both reactors it was scuttled in 1981 in the outer part of Stepovogo Bay located on the eastern coast of Novaya Zemlya. The inventory of spent nuclear fuel on board the submarine is of concern because it represents a potential source of radioactive contamination of the Kara Sea and a criticality accident with potential for long-range atmospheric transport of radioactive particles cannot be ruled out. To address these concerns and to provide a better basis for evaluating possible radiological impacts of potential releases in case a salvage operation is initiated, we assessed the atmospheric transport of radionuclides and deposition in Norway from a hypothetical criticality accident on board the K-27. To achieve this, a long term (33 years) meteorological database has been prepared and used for selection of the worst case meteorological scenarios for each of three selected locations of the potential accident. Next, the dispersion model SNAP was run with the source term for the worst-case accident scenario and selected meteorological scenarios. The results showed predictions to be very sensitive to the estimation of the source term for the worst-case accident and especially to the sizes and densities of released radioactive particles. The results indicated that a large area of Norway could be affected, but that the deposition in Northern Norway would be considerably higher than in other areas of the country. The simulations showed that deposition from the worst-case scenario of a hypothetical K-27 accident would be at least two orders of magnitude lower than the deposition observed in Norway following the Chernobyl accident. - Highlights: • Long-term meteorological database has been developed for atmospheric dispersion. • Using this database, the worst case meteorological scenarios have been selected. • Mainly northern parts of Norwegian territory will be

Deposition of radionuclides and their subsequent relocation in the environment following an accidental release to the atmosphere

International Nuclear Information System (INIS)

Underwood, B.Y.; Roed, J.; Paretzke, H.G.

1993-01-01

The objective of the project is to improve, as necessary, the models and parameterizations used in estimating the intensity and spatial distribution of deposited activity, and the total health/economic impact of such deposits in assessments of the consequences of accidental releases of radioactivity. The study comprises the influence of various weather conditions on deposition; the resuspension of deposited 137 Cs activity; the weathering of deposits in urban and rural environments; the ultimate fate and dosimetric impact of radionuclides carried by urban run-off water; the impact of the atmosphere's dispersion capabilities. Objectives and results of the four contributions to the project for the reporting period are presented. (R.P.) 5 refs., 4 figs., 1 tab

Application of two-barrier model of radioactive agent transport in sea water for analyzing artificial radionuclide release from containers with radioactive waste dumped in Kara Sea

Energy Technology Data Exchange (ETDEWEB)

Grishin, Denis S.; Laykin, Andrey I.; Kuchin, Nickolay L.; Platovskikh, Yuri A. [Krylov State Research Center, Saint Petersburg, 44 Moskovskoe shosse, 196158 (Russian Federation)

2014-07-01

Modeling of artificial radionuclide transport in sea water is crucial for prognosis of radioecological situation in regions where dumping of radioactive waste had been made and/or accidents with nuclear submarines had taken place. Distribution of artificial radionuclides in bottom sediments can be a detector of radionuclide release from dumped or sunk objects to marine environment. Proper model can determine the dependence between radionuclide distribution in sediments and radionuclide release. Following report describes two-barrier model of radioactive agent transport in sea water. It was tested on data from 1994 - 2013 expeditions to Novaya Zemlya bays, where regular dumping of solid radioactive waste was practiced by the former USSR from the early 1960's until 1990. Two-barrier model agrees with experimental data and allows more accurate determination of time and intensity of artificial radionuclide release from dumped containers. (authors)

Studies on the radioactivity of the atmosphere. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1951-01-01

The existence in the atmosphere of a radioactive substance, labeled A, of several hours half life has been confirmed in flights at 3300 m, and at a ground station at 1460 m. Concentrations of Rn, Tn, A, and A' observed from March 15 to August 14, 1951, are tabulated. The concentration of substance A, of 20- to 30- hr half life, is related to atomic explosions and precipitation.

The regulation of radioactive effluent release in France (mainly from large nuclear installations)

International Nuclear Information System (INIS)

Hebert, Jean.

1978-01-01

In parallel with the licensing system for construction and operation of classified or so-called large nuclear installations (INB) there are in France regulations for the release of radioactive effuents from such installations. The regulations applicable to installations other than INBs are not specifically of a nuclear nature, while those covering INBs, which are analysed in this study, in particular, cover effluent release in liquid or gaseous form. The licensing and control procedures for such release are analysed in detail. (NEA) [fr

Measurement of radioactivity in the atmosphere and pollution nearby an atomic centre; Mesure de la radioactivite de l'atmosphere et de la pollution au voisinage d'un centre atomique

Energy Technology Data Exchange (ETDEWEB)

Labeyrie, J; Weill, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

The French Atomic Energy Commission (CEA) is particularly interested in studies on atmospheric radioactivity by reason of the necessity to control the atmosphere nearby nuclear plants as uranium mines, nuclear reactors and hot laboratories or radioactive materials treatment plants. Thus, the CEA developed different apparatus to control and monitor the atmosphere nearby its sites. These air monitors are essentially of two types: the first one, called 'Babar', monitors smokes, fogs and dusts, the second type is an ionization chamber and measures the concentration of radioactive gas in the air. The functioning and sensitivity of these two systems are discussed. (M.P.)

A Bayesian Analysis of the Radioactive Releases of Fukushima

DEFF Research Database (Denmark)

Tomioka, Ryota; Mørup, Morten

2012-01-01

the types of nuclides and their levels of concentration from the recorded mixture of radiations to take necessary measures. We presently formulate a Bayesian generative model for the data available on radioactive releases from the Fukushima Daiichi disaster across Japan. From the sparsely sampled...... the Fukushima Daiichi plant we establish that the model is able to account for the data. We further demonstrate how the model extends to include all the available measurements recorded throughout Japan. The model can be considered a first attempt to apply Bayesian learning unsupervised in order to give a more......The Fukushima Daiichi disaster 11 March, 2011 is considered the largest nuclear accident since the 1986 Chernobyl disaster and has been rated at level 7 on the International Nuclear Event Scale. As different radioactive materials have different effects to human body, it is important to know...

Implementation of meso-scale radioactive dispersion model for GPU

Energy Technology Data Exchange (ETDEWEB)

Sunarko [National Nuclear Energy Agency of Indonesia (BATAN), Jakarta (Indonesia). Nuclear Energy Assessment Center; Suud, Zaki [Bandung Institute of Technology (ITB), Bandung (Indonesia). Physics Dept.

2017-05-15

Lagrangian Particle Dispersion Method (LPDM) is applied to model atmospheric dispersion of radioactive material in a meso-scale of a few tens of kilometers for site study purpose. Empirical relationships are used to determine the dispersion coefficient for various atmospheric stabilities. Diagnostic 3-D wind-field is solved based on data from one meteorological station using mass-conservation principle. Particles representing radioactive pollutant are dispersed in the wind-field as a point source. Time-integrated air concentration is calculated using kernel density estimator (KDE) in the lowest layer of the atmosphere. Parallel code is developed for GTX-660Ti GPU with a total of 1 344 scalar processors using CUDA. A test of 1-hour release discovers that linear speedup is achieved starting at 28 800 particles-per-hour (pph) up to about 20 x at 14 4000 pph. Another test simulating 6-hour release with 36 000 pph resulted in a speedup of about 60 x. Statistical analysis reveals that resulting grid doses are nearly identical in both CPU and GPU versions of the code.

Caesium releases under the form of silicon micro-balls during the Fukushima-Daiichi accident. Information note

International Nuclear Information System (INIS)

2016-01-01

After having outlined that the most part (89 per cent) of radioactive cesium released in the atmosphere during the Fukushima accident was made under the form of silicon micro-balls which were more irradiating than other aerosols marked by cesium radioactive isotopes, this note first discusses whether these silicon micro-balls containing radioactive cesium were resulting from a specific phase of atmospheric release. It discusses the nature of these micro-balls, and discusses whether it is possible to quantitatively assess the contribution of these micro-balls to global releases and deposits. It discusses how these micro-balls could have formed, whether their formation can be associated with a specific phase of reactor degradation or with the degradation of a specific reactor. It discusses whether a specific behaviour of these micro-balls can be expected in the environment, and their possible impacts on radiological consequences

Situation 2002: release monitoring and surveillance of environment of Cea centers

International Nuclear Information System (INIS)

2003-07-01

This publication renders an account of the situation of the releases of liquid and gaseous radioactive effluents, for the year 2002, as well as the radioactivity levels measured in the vicinity of Cea centers through the systematic surveillance of atmosphere, waters, vegetation and milk. An analysis on five years allows to follow their evolution. (N.C.)

A high-performance liquid chromatography method for the serotonin release assay is equivalent to the radioactive method.

Science.gov (United States)

Sono-Koree, N K; Crist, R A; Frank, E L; Rodgers, G M; Smock, K J

2016-02-01

The serotonin release assay (SRA) is considered the gold standard laboratory test for heparin-induced thrombocytopenia (HIT). The historic SRA method uses platelets loaded with radiolabeled serotonin to evaluate platelet activation by HIT immune complexes. However, a nonradioactive method is desirable. We report the performance characteristics of a high-performance liquid chromatography (HPLC) SRA method. We validated the performance characteristics of an HPLC-SRA method, including correlation with a reference laboratory using the radioactive method. Serotonin released from reagent platelets was quantified by HPLC using fluorescent detection. Results were expressed as % release and classified as positive, negative, or indeterminate based on previously published cutoffs. Serum samples from 250 subjects with suspected HIT were tested in the HPLC-SRA and with the radioactive method. Concordant classifications were observed in 230 samples (92%). Sera from 41 healthy individuals tested negative. Between-run imprecision studies showed standard deviation of performance characteristics, equivalent to the historic radioactive method, but avoids the complexities of working with radioactivity. © 2015 John Wiley & Sons Ltd.

Monitoring water for radioactive releases in the United States

International Nuclear Information System (INIS)

Porter, C.R.; Broadway, J.A.; Kahn, B.

1990-01-01

The major radiological environmental monitoring programs for water in the United States are described. The applications of these programs for monitoring radioactive fallout, routine discharges from nuclear facilities, and releases due to accidents at such facilities are discussed, and some examples of measurements are presented. The programs monitor rainfall, surface water, and water supplies. Samples are usually collected and analyzed on a monthly or quarterly schedule, but the frequency is increased in response to emergencies. (author)

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)

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.

New approaches to deriving limits of the release of radioactive material into the environment

International Nuclear Information System (INIS)

Lindell, B.

1977-01-01

During the last few years, new principles have been developed for the limitation of the release of radioactive material into the environment. It is no longer considered appropriate to base the limitation on limits for the concentrations of the various radionuclides in air and water effluents. Such limits would not prevent large amounts of radioactive material from reaching the environment should effluent rates be high. A common practice has been to identify critical radionuclides and critical pathways and to base the limitation on authorized dose limits for local ''critical groups''. If this were the only limitation, however, larger releases could be permitted after installing either higher stacks or equipment to retain the more short-lived radionuclides for decay before release. Continued release at such limits would then lead to considerably higher exposure at a distance than if no such installation had been made. Accordingly there would be no immediate control of overlapping exposures from several sources, nor would the system guarantee control of the future situation. The new principles described in this paper take the future into account by limiting the annual dose commitments rather than the annual doses. They also offer means of controlling the global situation by limiting not only doses in critical groups but also global collective doses. Their objective is not only to ensure that individual dose limits will always be respected but also to meet the requirement that ''all doses be kept as low as reasonably achievable''. The new approach is based on the most recent recommendations by the ICRP and has been described in a report by an IAEA panel (Procedures for establishing limits for the release of radioactive material into the environment). It has been applied in the development of new Swedish release regulations, which illustrate some of the problems which arise in the practical application

New approaches to deriving limits of the release of radioactive material into the environment

International Nuclear Information System (INIS)

Lindell, B.

1977-01-01

During the last few years, new principles have been developed for the limitation of the release of radioactive material into the environment. It is no longer considered appropriate to base the limitation on limits for the concentrations of the various radionuclides in air and water effluents. Such limits would not prevent large amounts of radioactive material from reaching the environment should effluent rates be high. A common practice has been to identify critical radionuclides and critical pathways and to base the limitation on authorized dose limits for local ''critical groups''. If this were the only limitation, however, larger releases could be permitted after installing either higher stacks or equipment to retain the more shortlived radionuclides for decay before release. Continued release at such limits would then lead to considerably higher exposure at a distance than if no such installation had been made. Accordingly there would be no immediate control of overlapping exposures from several sources, nor would the system guarantee control of the future situation. The new principles described in this paper take the future into account by limiting the annual dose commitments rather than the annual doses. They also offer means of controlling the global situation by limiting not only doses in critical groups but also global collective doses. Their objective is not only to ensure that individual dose limits will always be respected but also to meet the requirement that ''all doses be kept as low as reasonably achievable''. The new approach is based on the most recent recommendations by the ICRP and has been described in a report by an IAEA panel (Procedures for Establishing Limits for the Release of Radioactive Material into the Environment). It has been applied in the development of new Swedish release regulations, which illustrate some of the problems which arise in the practical application. (author)

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.

Environmental radioactivity. Global transport, distribution and its long-term variation

International Nuclear Information System (INIS)

Hirose, Katsumi

2015-01-01

Fukushima Dai-ichi Nuclear Power Plant (F1NPP) accident, which occurred as a result of huge earthquake and resulting tsunami, had a severe impact on world communities as did Japanese, because of cause of serious radioactivity contamination in the environment. Long-term effects of radioactivity contamination from F1NPP are concerned. To assess the long-term environmental effects of the F1NPP accident, it is important to review the history of global radioactivity contamination, which started from Hiroshima and Nagasaki nuclear explosions in Aug. 1945. Radionuclides released in the environment as a result of atmospheric nuclear explosions, nuclear reactor accident and others are migrated between atmosphere, hydrosphere, biosphere and lithosphere according to natural processes. We describe long-term environmental behaviors of anthropogenic radionuclides derived from the atmospheric nuclear explosions and others, which is useful to predict the behaviors and fate of the F1NPP-derived radionuclides. (author)

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)

Study to build up method for determining radioactivity of H-3 in atmosphere

International Nuclear Information System (INIS)

Vuong Thu Bac; Nguyen Thi Thu Ha; Vo Thi Anh; Ha Thi Lan Anh; Cao Duc Viet; Duong Van Thang; Dinh Thi Bich Lieu

2015-01-01

Tritium is the radioactive isotope of the hydrogen element (denoted as T or H-3). Main chemical forms of Tritium in the atmosphere are Tritium vapor (HTO) and gaseous Tritium (HT). HTO and HT were collected simultaneously by the MARC-7000 Tritium sampler. The sampler has been specifically designed for capturing Tritium most efficiently using a series of four sample bottles, a cooling system and a system of Palladium-Alumina catalytic oven. Air Tritium samples were collected at a flow rate of 30 L/h continuously for duration up to 15 days depending on atmospheric humidity. Average efficiency of H-3 collection in the atmosphere was 74.82 %. The collected samples were enriched by electrolytic method. The electrolysed samples were purified afterward by distillation with PbCl_2 for alkali precipitation. Finally the samples were mixed with Packard Ultima Gold LLT cocktail in proportion of 1:1 and measured by the TRI CARB 3170 TR/SL Liquid scintillation counting system in a total period of 1000 min. Minimum detectable activity (MDA) was about of 4 mBq/m"3. Relative error was less than 11%. 24 air samples in Hanoi for one year from 11/2013 to 10/2014 were collected and analyzed. Monthly average radioactivity of H-3 was 22.39 mBq/m"3 and its standard deviation was 4.84 mBq/m"3. This value was 5.6 times higher than MDA value and equivalent to H-3 background level in several countries. The obtained technical procedure is applicable to determine Tritium radioactivity in the atmosphere. (author)

Radioactive aerosol detection station for near real-time atmospheric monitoring

International Nuclear Information System (INIS)

Mason, L.R.; Bohner, John D.

1997-01-01

A radionuclide aerosol detection station has been developed to measure radioactivity in the environment. The objective is to monitor the atmosphere for anthropogenic radioactivity that could be indicative of nuclear weapons tests to verify the Comprehensive Nuclear Test Ban Treaty. Eighty stations will form the backbone of the International Monitoring System in which stations are linked to a central analysis facility called the International Data Centre. Data are transmitted to this centre in near real-time to facilitate rapid detection. Principal process of the field measurement are collection, separation, and assay. Collection of airborne radioactivity is achieved through high-volume air sampling. Aerosols separation is accomplished by high-efficiency particulate filtration. Radionuclides assay is achieved by in-situ high resolution gamma spectrometry. These modules are integrated into a unit that provides power, control, and communication support subsystems. Station operation is semi-automatic requiring only minimal human interaction. (author). 6 refs., 3 figs., 3 tabs

Measurement of artificial radioactivity in the atmosphere at Ottawa, Canada

Energy Technology Data Exchange (ETDEWEB)

Terentiuk, F

1958-01-01

In recent years there has been considerable interest in the artificial radioactivity in the atmosphere originating from atomic and thermonuclear explosions. For the past year daily measurements of radioactivity have been made at Ottawa. The sampling times corresponded to air volumes of 425 cubic metric and 2000 cubic meters, respectively. Filters were kept for a period of 3 days before measurements were made in order to permit natural activity resulting from daughter products of radon and thoron to decay to a negligible value. Measurements of the gross beta activity from the filters were made directly with end-window Geiger tubes. Filters showing considerable initial radioactivity were measured at intervals of a few days in order to obtain the rate of decay of the activity. It was hoped that the data obtained would make it possible to fix the date of the explosion responsible for the filter activity but the fixing of dates was very uncertain.

Regulatory analysis on criteria for the release of patients administered radioactive material

International Nuclear Information System (INIS)

Schneider, S.; McGuire, S.A.

1994-05-01

The Nuclear Regulatory Commission (NRC) has received two petitions to amend its regulations in 10 CFR Parts 20 and 35 as they apply to doses received by members of the public exposed to patients released from a hospital after they have been administered radioactive material. While the two petitions are not identical they both request that the NRC establish a dose limit of 5 millisieverts (0.5 rem) per year for individuals exposed to patients who have been administered radioactive materials. This Regulatory Analysis evaluates three alternatives. Alternative 1 is for the NRC to amend its patient release criteria in 10 CFR 35.75 to use the more stringent dose limit of 1 millisievert per year in 10 CFR 20.1301(a) for its patient release criteria. Alternative 2 is for the NRC to continue using the existing patient release criteria in 10 CFR 35.75 of 1,110 megabecquerels of activity or a dose rate at one meter from the patient of 0.05 millisievert per hour. Alternative 3 is for the NRC to amend the patient release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts for patient release. The evaluation indicates that Alternative 1 would cause a prohibitively large increase in the national health care cost from retaining patients in a hospital longer and would cause significant personal and psychological costs to patients and their families. The choice of Alternatives 2 or 3 would affect only thyroid cancer patients treated with iodine-131. For those patients, Alternative 3 would result in less hospitalization than Alternative 2. Alternative 3 has a potential decrease in national health care cost of $30,000,000 per year but would increase the potential collective dose from released therapy patients by about 2,700 person-rem per year, mainly to family members

Regulatory analysis on criteria for the release of patients administered radioactive material

Energy Technology Data Exchange (ETDEWEB)

Schneider, S.; McGuire, S.A. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications; Behling, U.H.; Behling, K.; Goldin, D. [Cohen (S.) and Associates, Inc., McLean, VA (United States)

1994-05-01

The Nuclear Regulatory Commission (NRC) has received two petitions to amend its regulations in 10 CFR Parts 20 and 35 as they apply to doses received by members of the public exposed to patients released from a hospital after they have been administered radioactive material. While the two petitions are not identical they both request that the NRC establish a dose limit of 5 millisieverts (0.5 rem) per year for individuals exposed to patients who have been administered radioactive materials. This Regulatory Analysis evaluates three alternatives. Alternative 1 is for the NRC to amend its patient release criteria in 10 CFR 35.75 to use the more stringent dose limit of 1 millisievert per year in 10 CFR 20.1301(a) for its patient release criteria. Alternative 2 is for the NRC to continue using the existing patient release criteria in 10 CFR 35.75 of 1,110 megabecquerels of activity or a dose rate at one meter from the patient of 0.05 millisievert per hour. Alternative 3 is for the NRC to amend the patient release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts for patient release. The evaluation indicates that Alternative 1 would cause a prohibitively large increase in the national health care cost from retaining patients in a hospital longer and would cause significant personal and psychological costs to patients and their families. The choice of Alternatives 2 or 3 would affect only thyroid cancer patients treated with iodine-131. For those patients, Alternative 3 would result in less hospitalization than Alternative 2. Alternative 3 has a potential decrease in national health care cost of $30,000,000 per year but would increase the potential collective dose from released therapy patients by about 2,700 person-rem per year, mainly to family members.

Method for solidification of radioactive iodine-containing solid wastes

International Nuclear Information System (INIS)

Ozawa, Yoshihiro; Funabashi, Kiyomi; Uetake, Naoto.

1987-01-01

Purpose: To process radioactive iodine containing solid wastes as non-leaching solidified wastes with no risk of iodine release. Method: It has been known for the thermal stability of CuI, PbI 2 or adsorbents containing the same that they do not release iodine in an inert gas atmosphere or in a reducing atmosphere at a temperature lower than 480 deg C. In view of the above, adsorbents containing iodine in the chemical form of CuI or PbI 2 , or CuI or powdery PbI 2 per se are sealed and solidified into low melting glass at a temperature of lower than 480 deg C at which no iodine release occurs in a non-oxidative atmosphere. Since the products are vitrified wastes, they scarcely show leaching property and are excellent in durability and stability. (Takahashi, M.)

A review of ''The potential effects of release of krypton-85''

International Nuclear Information System (INIS)

Saunders, C.P.R.

1993-06-01

A Report into the potential effects of the release of Krypton-85 from the Thermal Oxide Reprocessing Plant (THORP) at Sellafield, was commissioned by British Nuclear Fuels Ltd. The report dealt with the atmospheric impact of the release of Krypton-85 and considered specifically the areas of atmospheric electricity, ionisation, aerosols and conductivity, in terms of the releases of Krypton-85 from THORP. This present review has three objectives: to consider the atmospheric effects of the proposed discharges from THORP, to comment upon the magnitude of the postulated effects from Krypton-85 discharges compared with those from other sources of radioactivity in the atmosphere, and, to comment on the conclusions drawn by the authors of the report. This review was conducted under the aegis of the United Kingdom Inspectorate of Pollution. (author)

Modelling of radioactive fallout in the vicinity of Chernobyl nuclear power plant accident

International Nuclear Information System (INIS)

Israel, Y.A.; Petrov, V.N.; Severov, D.A.

1988-03-01

Deposition of radioactive products escaping into the atmosphere for a long time from the Chernobylsk-4 reactor resulting in residual radioactive contamination of the region at a distance of up to 100 km from the nuclear power plant is considered. The suggested model may be used for estimation of the possible scope of nuclear danger in the regions of nuclear power plants and creation of conditions ensuring safety of the population at possible accidents. The following topics are developed: height of elevation and conditions of radionuclide transfer in the atmosphere; dynamics of release and dispersive composition of radioactive products; calculations of radiation levels at a close trace [fr

Estimation of the time-dependent radioactive source-term from the Fukushima nuclear power plant accident using atmospheric transport modelling

Science.gov (United States)

Schoeppner, M.; Plastino, W.; Budano, A.; De Vincenzi, M.; Ruggieri, F.

2012-04-01

Several nuclear reactors at the Fukushima Dai-ichi power plant have been severely damaged from the Tōhoku earthquake and the subsequent tsunami in March 2011. Due to the extremely difficult on-site situation it has been not been possible to directly determine the emissions of radioactive material. However, during the following days and weeks radionuclides of 137-Caesium and 131-Iodine (amongst others) were detected at monitoring stations throughout the world. Atmospheric transport models are able to simulate the worldwide dispersion of particles accordant to location, time and meteorological conditions following the release. The Lagrangian atmospheric transport model Flexpart is used by many authorities and has been proven to make valid predictions in this regard. The Flexpart software has first has been ported to a local cluster computer at the Grid Lab of INFN and Department of Physics of University of Roma Tre (Rome, Italy) and subsequently also to the European Mediterranean Grid (EUMEDGRID). Due to this computing power being available it has been possible to simulate the transport of particles originating from the Fukushima Dai-ichi plant site. Using the time series of the sampled concentration data and the assumption that the Fukushima accident was the only source of these radionuclides, it has been possible to estimate the time-dependent source-term for fourteen days following the accident using the atmospheric transport model. A reasonable agreement has been obtained between the modelling results and the estimated radionuclide release rates from the Fukushima accident.

Box model of radionuclide dispersion and radiation risk estimation for population in case of radioactivity release from nuclear submarine number-sign 601 dumped in the Kara Sea

International Nuclear Information System (INIS)

Yefimov, E.I.; Pankratov, D.V.; Ignatiev, S.V.

1997-01-01

When ships with nuclear reactors or nuclear materials aboard suffer shipwreck or in the case of burial or dumping of radioactive wastes, atmospheric fallout, etc., radionuclides may be released and spread in the sea, contaminating the sea water and the sea bottom. When a nuclear submarine (NS) is dumped this spread of activity may occur due to gradual core destruction by corrosion over many years. The objective of this paper is to develop a mathematical model of radionuclide dispersion and to assess the population dose and radiation risk for radionuclide release from the NS No. 601, with Pb-Bi coolant that was dumped in the Kara Sea

Conceptual Design of Portable Filtered Air Suction Systems For Prevention of Released Radioactive Gas under Severe Accidents of NPP

Energy Technology Data Exchange (ETDEWEB)

Gu, Beom W.; Choi, Su Y.; Yim, Man S.; Rim, Chun T. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2014-05-15

It becomes evident that severe accidents may occur by unexpected disasters such as tsunami, heavy flood, or terror. Once radioactive material is released from NPP through severe accidents, there are no ways to prevent the released radioactive gas spreading in the air. As a remedy for this problem, the idea on the portable filtered air suction system (PoFASS) for the prevention of released radioactive gas under severe accidents was proposed. In this paper, the conceptual design of a PoFASS focusing on the number of robot fingers and robot arm rods are proposed. In order to design a flexible robot suction nozzle, mathematical models for the gaps which represent the lifted heights of extensible covers for given convex shapes of pipes and for the covered areas are developed. In addition, the system requirements for the design of the robot arms of PoFASS are proposed, which determine the accessible range of leakage points of released radioactive gas. In this paper, the conceptual designs of the flexible robot suction nozzle and robot arm have been conducted. As a result, the minimum number of robot fingers and robot arm rods are defined to be four and three, respectively. For further works, extensible cover designs on the flexible robot suction nozzle and the application of the PoFASS to the inside of NPP should be studied because the radioactive gas may be released from connection pipes between the containment building and auxiliary buildings.

Assessment of Radioactive Liquid Effluents Release at IPEN-CNEN/SP

International Nuclear Information System (INIS)

Bessa Nisti, Marcelo; Godoy dos Santos, Adir Janete

2008-01-01

A continuous effluent monitoring program has been established at IPEN's plant in order to allow an environmental impact assessment due to radioactive liquid effluent discharge to sanitary system. Representative samples of radioactive liquid effluents are analyzed by using high resolution gamma spectroscopy and instrumental neutron activation analysis, facing to Brazilian radioprotection regulatory rules. The results are consolidating yearly in the Institute source-term. In this paper, results of the source-term are presented, concerning to years 2004, 2005 and 2006. The total activity discharged was 8.5xl0 8 Bq, 5.7x10 8 Bq and 2.7xl0 8 Bq, respectively. As the release is strongly dependent on the total amount of the effluent and on the dilution factor, special attention is needed in order to obtain the correct value of that last one. The estimated inside plant dilution factor, considering the recent facilities and the reshaping of the sewerage system was 80, 180 and 130, for period of 2004, 2005 and 2006 discharged liquid radioactive effluent

Estimation of radionuclide releases in atmosphere from Cernavoda NPP based on continuous gaseous effluent monitoring

International Nuclear Information System (INIS)

Bobric, E.; Murgoci, S.; Popescu, I.; Ibadula, R.

2001-01-01

Monitoring of gaseous effluents from Cernavoda NPP is performed to assess the environmental impact of the plant operation. The results of the monitoring program are used to evaluate the population doses in order to ensure that the emissions of radionuclides in air are below regulatory limits and radiation doses are maintained ALARA. It complements, but is independent from the Operational Environmental Monitoring Program for Cernavoda NPP. Gaseous effluent monitors provide continuous indication of the radioactivity content in atmospheric emissions. Except for noble gases, these monitors also collect samples for later detailed analysis in the station Health Physics Laboratory. This paper presents the main equipment and the results of the gaseous effluents monitoring program in order to assess the impact of Cernavoda NPP operation and to predict the future releases as function of radionuclides concentrations in CANDU systems, based on the identified trends.(author)

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...

Reduction of releases of radioactive effluents from light-water-power-reactors in Japan

International Nuclear Information System (INIS)

Yoshida, Y.; Itakura, T.; Kanai, T.

1977-01-01

Japan Atomic Energy Commission established the dose objectives to the population around the light-water-reactors in May, 1975, based on the ''ALAP'' concept. These values are respectively, 5 mrems per year for total body and 15 mrems per year for thyroid of an individual in the critical group in the environs, due to both gaseous and liquid effluents from LWRs in one site. The present paper describes the implications of the dose objective values, control measures which have been adopted to reduce releases of radioactive materials and related technical developments in Japan. The main control measures for reduction of radioactive gaseous effluents are an installation of a charcoal gas holdup system for decay of noble gases and a supply of clean steam for the gland seal of a turbine in BWR, and a storage tank system allowing decay of noble gases in PWR. For liquid effluents are taken measures to re-use them as the primary coolant. Consequently, the amounts of radioactivity released to the environment from any LWR during normal operation have been maintained under the level to meet the above dose objective values. For research reactors, reduction of release of effluents has also been carried out in a similar way to LWRs. In order to establish the techniques applicable for further reduction, studies are being made on the control measures to reduce leakage of radioiodine, an apparatus for removal of krypton, the treatment of laundry waste and measures to remove the crud in the primary coolant. Presentation is also made on the energy-integrated gas monitor for gaseous effluent and systems of measuring γ dose from radioactive cloud descriminating from natural background, which have been developed for effective monitoring thus reduced environmental dose

Leaching behavior of a simulated bituminized radioactive waste form under deep geological conditions

International Nuclear Information System (INIS)

Nakayama, Shinichi; Iida, Yoshihisa; Nagano, Tetsushi; Akimoto, Toshiyuki

2003-01-01

The leaching behavior of a simulated bituminized waste form was studied to acquire data for the performance assessment of the geologic disposal of bituminized radioactive waste. Laboratory-scale leaching tests were performed for radioactive and non-radioactive waste specimens simulating bituminized waste of a French reprocessing company, COGEMA. The simulated waste was contacted with deionized water, an alkaline solution (0.03-mol/l KOH), and a saline solution (0.5-mol/l KCl) under atmospheric and anoxic conditions. The concentrations of Na, Ba, Cs, Sr, Np, Pu, NO 3 , SO 4 and I in the leachates were determined. Swelling of the bituminized waste progressed in deionized water and KOH. The release of the soluble components, Na and Cs, was enhanced by the swelling, and considered to be diffusion-controlled in the swelled layers of the specimens. The release of sparingly soluble components such as Ba and Np was solubility-limited in addition to the progression of leaching. Neptunium, a redox-sensitive element, showed a distinct difference in release between anoxic and atmospheric conditions. The elemental release from the bituminized waste specimens leached in the KCl was very low, which is likely due to the suppression of swelling of the specimens at high ionic strength. (author)

A study on the safety of spent fuel management. Radioactive source term modelling

Energy Technology Data Exchange (ETDEWEB)

Chun, Kwan Sik; Lee, Hoo Keun; Park, Keun Il; Hwoang, Jung Ki; Chung, Choong Hwan [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

1992-02-01

The types and probabilities of events which may occur during the process of reception, transfer and storage of spent fuels in an away-from-reactor (AFR) spent fuel storage facility were analyzed in order to calculate the amount of radioactive material released to operation area and atmosphere, and the basic model for predicting the radioactive source-term under normal and abnormal operations were developed. Also, oxidation and dissolution of U0{sub 2} pellet was investigated to estimate the amount of radioactive materials released from spent fuel and the release characteristics of radionuclides from defected spent fuel rods was analyzed. Basic information using FIRAC code to analyze the ventilation system during fire accident was prepared and FIRIN was detached from FIRAC modified to simulate the compartment fire by personal computer. (Author).

UNIDOSE - a computer program for the calculation of individual and collective doses from airborne radioactive pollutants

International Nuclear Information System (INIS)

Karlberg, O.; Schwartz, H.; Forssen, B.-H.; Marklund, J.-E.

1979-01-01

UNIDOSE is a program system for calculating the consequences of a radioactive release to the atmosphere. The program is applicable for computation of dispersion in a rnage of 0 - 50 km from the release point. The Gaussion plume model is used for calculating the external dose from activity in the atmosphere, on the ground and the internal dose via inhalation. Radioactive decay, as well as growth and decay of daughter products are accounted for. The influence of dry deposition and wash-out are also considered. It is possible to treat time-dependent release-rates of 1 - 24 hours duration and constant release-rates for up to one year. The program system also contains routines for the calculation of collective dose and health effects. The system operates in a statistical manner. Many weather-situations, based on measured data, can be analysed and statistical properties, such as cumulative frequences, can be calculated. (author)

Discharges of radioactive materials to the environment in Argentina

International Nuclear Information System (INIS)

Curti, Adriana R.

2003-01-01

The International Atomic Energy Agency (IAEA) is creating a database of information on radioactive discharges to atmospheric and aquatic environments from nuclear and radioactive installations, and from facilities using radionuclides in medicine, industry and research. The database is expected to facilitate the analysis of worldwide trends in discharge levels and provide a basis for assessing the impact of the discharges on humans and on the environment. In November 2002 took place the first meeting of national contact points and the Nuclear Regulatory Authority (ARN in Spanish) was present as the counterpart for the provision of discharge data from Argentina. This paper, presented in the above mentioned meeting, is a general overview of the radioactive discharges control in Argentina including the legal infrastructure, the population dose assessment methodology and the main characteristics of the facilities in the country with authorized radioactive discharges to the environment. It is mentioned their location, release mode, surface water body type, main radionuclides and typical annual release activities. (author)

CRRIS, Health Risk Assessment from Atmospheric Releases of Radionuclides

International Nuclear Information System (INIS)

1999-01-01

1 - Description of program or function: CRRIS consists 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 be used alone for various assessment applications. Because of its modular structure, CRRIS allows assessments to be tailored to the user's needs. Radionuclides are handled by CRRIS either in terms of the released radionuclides or the exposure radionuclides which consist of both the released nuclides and decay products that build up during environmental transport. Atmospheric dispersion calculations are performed by the ANEMOS computer code for distances less than 100 km and the RETADD-II computer code regional-scale distances. Both codes estimate annual-average air concentrations and ground deposition rates by location. SUMIT will translate and scale multiple ANEMOS runs onto a master grid. TERRA reads radionuclide air concentrations and deposition rates to estimate concentrations of radionuclides in food and surface soil. Radiologic decay and ingrowth, soil leaching, and transport through the food chain are included in the calculations. MLSOIL computes an effective radionuclide ground-surface concentration to be used in computing external health effects. The five-layer model of radionuclide transport through soil in MLSOIL provides an alternative to the single-layer model used in TERRA. DFSOIL computes dose factors used in MLSOIL to compute doses from the five soil layers and from the ground surface. ANDROS reads environmental concentrations of radionuclides computed by the other CRRIS codes and produces tables of doses and risks to individuals or populations from atmospheric releases of radionuclides. 2 - Method of solution: SUMIT performs geometric interpolation. TERRA and MLSOIL are terrestrial transport compartment models. DFSOIL computes soil-layer-specific dose factors based on the point-kernel method

Method of processing radioactive wastes

International Nuclear Information System (INIS)

Matagi, Yoshihiko; Takahara, Akira; Ootsuka, Katsuyuki.

1984-01-01

Purpose: To avoid the reduction in the atmospheric insulation by preventing the generation of CO 2 , H 2 O, etc. upon irradiation of microwave heat. Method: Radioactive wastes are charged into a hopper, supplied on a conveyor, fed each by a predetermined amount to a microwave furnace and heated by microwaves applied from a microwave guide. Simultaneously, inert gases are supplied from a supply line. The Radioactive wastes to be treated are shielded by the inert gases to prevent the combustion of decomposed gases produced from the wastes upon irradiation of microwave heat to thereby prevent the generation of CO 2 , H 2 , etc., as well as the generated decomposed gases are diluted with the inert gases to decrease the dissociation of the decomposed gases to prevent the reduction in the atmospheric insulation. Since the spent inert gases can be recovered for reuse, the amount of gaseous wastes released to the atmosphere can be decreased and the working life of the high performance air filters can be extended. (Sekiya, K.)

Release of Radioactive Scrap Metal/Scrap Metal (RSM/SM) at Nevada Test Site (NTS)

International Nuclear Information System (INIS)

1993-01-01

Reynolds Electrical and Engineering Company, Inc. (REECo) is the prime contractor to the US Department of Energy (DOE) in providing service and support for NTS operations. Mercury Base Camp is the main control point for the many forward areas at NTS, which covers 1,350 square miles. The forward areas are where above-ground and underground nuclear tests have been performed over the last 41 years. No metal (or other material) is returned to Mercury without first being tested for radioactivity. No radioactive metals are allowed to reenter Mercury from the forward areas, other than testing equipment. RAMATROL is the monitor check point. They check material in various ways, including swipe tests, and have a large assortment of equipment for testing. Scrap metal is also checked to address Resource Conservation and Recovery Act concerns. After addressing these issues, the scrap metals are categorized. Federal Property Management Regulations (FPMR) are followed by REECo. The nonradioactive scrap material is sold through the GSA on a scheduled basis. Radioactive scrap metal are presently held in forward areas where they were used. REECo has gained approval of their Nevada Test Site Defense Waste Acceptance Criteria, Certification, and Transfer Requirements, NVO-325 application, which will allow disposal on site, when RSM is declared a waste. The guideline that REECo uses for release limits is DOE Order 5480.11, Radiation Protection for Occupational Works, Attachment 2, Surface Radioactivity Guides, of this order, give release limits for radioactive materials. However, the removal of radioactive materials from NTS require approval by DOE Nevada Operations Office (DOE/NV) on a case-by-case basis. Requirements to consider before removal are found in DOE Order 5820.2A, Radioactive Waste Management

Radioactivity of French coast of the Channel due to the release of technectium 99 and iodine 129: modelisation and measurements

International Nuclear Information System (INIS)

Robeau, D.; Patti, F.; Charmasson, S.

1988-01-01

Radioactive releases of Iodine 129 are controlled by measurements of the radioactivity in the liquid effluents before it is released in to the sea from the outlet of the reprocessing plant of La Hague. The effects on the marine environment are examined by a radioactive survey of Technecium 99 and Iodine 129 in Fucus (common seaweed). This radioactivity is measured along the north coast of France from Roscoff in the west of Brittany to Wimereux close to the Belgian frontier. The theoretical study of dispersion of radionuclides in the Channel has permitted a simulation model of the transfer of pollutants and particularly Technecium 99 and Iodine 129 to be formulated. (author)

Assessment of the Potential Release of Radioactivity from Installations at AERE, Harwell. Implications for Emergency Planning

Energy Technology Data Exchange (ETDEWEB)

Flew, Elizabeth M.; Lister, B. A.J. [Atomic Energy Research Establishment, Harwell, Didcot, Berks. (United Kingdom)

1969-10-15

As part of a review of the site emergency organization at AERE, a realistic reappraisal has been made of the potential hazard to the establishment and district of all the buildings containing significant amounts of radioactive materials. To assess the amount of radioactive material which might be released under specified accident conditions, four factors have been applied to the total building stock: (a) the fraction of the stock involved, (b) the percentage conversion to an aerosol form, (c) release from primary containment and (d) release from the building. These potential release figures have been compared with ''site hazardous release'' figures for relevant radionuclides i.e., amounts which could give rise to exposure above defined reference levels. Those buildings with more than one tenth of the potential for causing; a site or district hazard have been designated ''risk buildings''. Such a quantitative assessment, although necessarily very approximate, has been of considerable value in determining the type and complexity of the central emergency organization required and in producing the right emphasis on exercises, training, liaison with outside bodies, etc. (author)

Effective equivalent dose in the critical group due to release of radioactive effluents

International Nuclear Information System (INIS)

Santos, John W.A. dos; Varandas, Luciana R.; Souza, Denise N.; Souza, Cristiano B.F.; Lima, Sandro Leonardo N.; Mattos, Marcos Fernando M.; Moraes, Jose Adenildo T.

2005-01-01

To ensure that the emissions of radioactive material by liquid and gaseous pathways are below applicable limits it is necessary to evaluate the effective equivalent dose in the critical group, which is a magnitude that takes into consideration the modeling used and the terms radioactive activity source. The calculation of this dose considers each radionuclide released by the activity of Nuclear plant, liquid and gaseous by, and the sum of the values obtained is controlled so that this dose does not exceed the goals of the regulatory body, the CNEN and the goals established by the Nuclear power plant. To hit these targets various controls are used such as: controls for effluent monitors instrumentation, environmental monitoring programs, effluent release controls and dose calculation in the environment. According to the findings, it is concluded that during the period of operation of the plants, this dose is below of the required limits

ARRRG/FOOD, Doses from Radioactive Release to Food Chain

International Nuclear Information System (INIS)

Napier, B.A.; Roswell, R.L.; Kennedy, W.E. Jr.; Strenge, D.L.

1984-01-01

1 - Description of problem or function: ARRRG calculates radiation doses to humans for radionuclides released to bodies of water from which people might obtain fish, other aquatic foods, or drinking water, and in which they might fish, swim, or boat. FOOD calculates radiation doses to humans from deposition on farm or garden soil and crops during either an atmospheric or water release of radionuclides. Deposition may be either directly from the air or from irrigation water. With both programs, doses may be calculated for either a maximum- exposed individual or for a population group. Doses calculated are a one-year dose and a committed dose from one year of exposure. The exposure is usually considered as chronic; however, equations are included to calculate dose and dose commitment from acute, one-time, exposure. 2 - Method of solution: The radiation doses from external exposure to contaminated farm fields or shorelines are calculated assuming an 'infinite' flat plane source of radionuclides. A factor of two is included for surface roughness, and a modifying factor is used to compensate for finite extent in the shoreline calculations. The radionuclide concentrations in aquatic and irrigated food products are based on the radionuclide concentration in the contaminated water, which is based on the release rate of radioactive contamination and the characteristics of the receiving water body. Concentration of radionuclides in plants depends on the concentrations in the soil, air, and water. Concentration of radionuclides in farm animal products, such as milk, meat, or eggs, depends on the animal's consumption of feed, forage, and water containing radionuclides. For persons swimming in contaminated water, the dose is calculated assuming that the body of water is an infinite medium relative to the range of emitted radiations. Persons boating on the water are assumed to be exposed to a dose rate half that of swimmers. Internal doses are calculated as a function of

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

NKS-B NordRisk II: Nuclear risk from atmospheric dispersion in Northern Europe - Summary report

International Nuclear Information System (INIS)

Lauritzen, B.

2011-05-01

The objective of the NordRisk II project has been to derive practical means for assessing the risks from long-range atmospheric dispersion of radioactive materials. An atlas over different atmospheric dispersion and deposition scenarios has been developed using historical numerical weather prediction (NWP) model data. The NWP model data covers three years spanning the climate variability associated with the North Atlantic Oscillation, and the atlas considers radioactive releases from 16 release sites in and near the Nordic countries. A statistical analysis of the long-range dispersion and deposition patterns is undertaken to quantify the mean dispersion and deposition as well as the variability. Preliminary analyses show that the large-scale atmospheric dispersion and deposition is near-isotropic, irrespective of the release site and detailed climatology, and allows for a simple parameterization of the global dispersion and deposition patterns. The atlas and the underlying data are made available in a format compatible with the ARGOS decision support system, and have been implemented in ARGOS. (Author)

NKS-B NordRisk II: Nuclear risk from atmospheric dispersion in Northern Europe - Summary report

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

2011-05-15

The objective of the NordRisk II project has been to derive practical means for assessing the risks from long-range atmospheric dispersion of radioactive materials. An atlas over different atmospheric dispersion and deposition scenarios has been developed using historical numerical weather prediction (NWP) model data. The NWP model data covers three years spanning the climate variability associated with the North Atlantic Oscillation, and the atlas considers radioactive releases from 16 release sites in and near the Nordic countries. A statistical analysis of the long-range dispersion and deposition patterns is undertaken to quantify the mean dispersion and deposition as well as the variability. Preliminary analyses show that the large-scale atmospheric dispersion and deposition is near-isotropic, irrespective of the release site and detailed climatology, and allows for a simple parameterization of the global dispersion and deposition patterns. The atlas and the underlying data are made available in a format compatible with the ARGOS decision support system, and have been implemented in ARGOS. (Author)

Kalman filtration of radiation monitoring data from atmospheric dispersion of radioactive materials

DEFF Research Database (Denmark)

Drews, M.; Lauritzen, B.; Madsen, H.

2004-01-01

A Kalman filter method using off-site radiation monitoring data is proposed as a tool for on-line estimation of the source term for short-range atmospheric dispersion of radioactive materials. The method is based on the Gaussian plume model, in which the plume parameters including the source term...

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

Ranking system for mixed radioactive and hazardous waste sites

International Nuclear Information System (INIS)

Hawley, K.A.; Napier, B.A.

1985-01-01

The Environmental Protection Agency's Hazard Ranking System (HRS) is a simplified management decision tool that provides a common basis for evaluating a multitude of hazardous waste sites. A deficiency in the HRS for application to Department of Energy mixed radioactive and hazardous waste sites is its inability to explicitly handle radioactive material. A modification to the basic HRS to add the capability to consider radioactivity is described. The HRS considers the exposure routes of direct contact, fire/explosion, atmospheric release, surface-water release, and ground-water release. Each exposure route is further divided into release, route, containment, waste, and target characteristics. To maintain the basic HRS structure, only the waste characteristics section of each exposure route was modified. A ranking system was developed, using radiation dose pathway analysis, to group radionuclides by dose factors. For mixed waste sites, the ranking factor derived for radionuclides is compared with the ranking factor obtained for hazardous chemicals and the most restrictive is used in the overall ranking. The modified HRS has the advantages of being compatible with the original HRS, has reasonable information requirements, and provides scientifically defensible conclusions. 17 references, 2 figures, 6 tables

Safety apparatus for serious radioactive accidents (1962)

International Nuclear Information System (INIS)

Estournel, R.; Rodier, J.

1962-01-01

In the case of a serious radioactive accident, radioactive dust and gases may be released into the atmosphere. It is therefore necessary to be able to evaluate rapidly the importance of the risk to the surrounding population, and to be able to ensure, even in the event of an evacuation of the Centre, the continuation of the radioactivity analyses and the decontamination of the personnel. For this, the Anti-radiation Protection Service at Marcoule has organised mobile detection teams and designed a mobile laboratory and a mobile shower-unit. After describing the duty of the mobile teams, the report gives a description of the apparatus which would be used at the Marcoule Centre in the case of a serious radioactive accident. The method of using this apparatus is given. (authors) [fr

Risk assessment based on current release standards for radioactive surface contamination

International Nuclear Information System (INIS)

Chen, S.Y.

1993-09-01

Standards for uncontrolled releases of radioactive surface contamination have been in existence in the United States for about two decades. Such standards have been issued by various agencies, including the US Department of Energy. This paper reviews the technical basis of published standards, identifies areas in need of revision, provides risk interpretations based on current technical knowledge and the regulatory environment, and offers suggestions for improvements

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

Emissions of the corrosion radionuclides in an atmosphere

International Nuclear Information System (INIS)

Vardanyan, M.

2010-01-01

In area of Armenian nuclear power plant location, in atmospheric air in majority of cases log two technogenic radionuclides: l 37 C s and 9 0 S r. Presence of these radionuclides basically is caused by global fall out (consequences of tests of the nuclear weapon and Chernobyl NPP accident), whose contribution to the contents of these radionuclides in atmosphere is incomparably greater, than emissions from the NPP. However there are some cases when in an atmosphere are registered the technogenic radionuclides, caused by emissions from NPP. In the present work such case is considered. Gas-aerosol releases of NPP in the atmosphere are carefully purified by means of various high-efficiency filters and gas-cleaning systems. Nevertheless, one should forecast and measure, the possible impact of these releases on the environment in the regions surrounding the NPP. Radioactive releases of the Armenian NPP (ANPP) contain the set of radionuclides characteristic for NPPs of this type. They may be divided into three groups: 1 31 I , 1 37 C s, 1 34 C s, 9 0 S r and 8 9 S r fission fragments, isotopes of noble gases krypton and xenon and other radionuclides; corrosion originated radionuclides: 6 0 C o, 1 10m A g, 5 4 M n, 5 l C r and others; activation products of the heat-transfer agent itself. It should be noted that the amount of radioactive materials released in the environment by the ANPP during the whole period of its operation was much lower than the admissible quantities specified in the corresponding legal documents (RSN, NPPSP) acting in Armenia, which are practically identical to the internationally accepted norms. The amounts of releases and their radionuclides composition for the ANPP are given

Comment on 'On the long-range detection of radioactivity using electromagnetic radiation'

International Nuclear Information System (INIS)

Fuks, I.M.; Martynenko, S.I.

2004-01-01

The fact that the mesosphere is an electrically active element in the global atmospheric electric circuit provides a possible mechanism for troposphere-mesosphere-ionosphere coupling during releases of radioactive materials at the ground level, and this is discussed in this comment

Maxdose-SR and popdose-SR routine release atmospheric dose models used at SRS

Energy Technology Data Exchange (ETDEWEB)

Jannik, G. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Trimor, P. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-07-28

MAXDOSE-SR and POPDOSE-SR are used to calculate dose to the offsite Reference Person and to the surrounding Savannah River Site (SRS) population respectively following routine releases of atmospheric radioactivity. These models are currently accessed through the Dose Model Version 2014 graphical user interface (GUI). MAXDOSE-SR and POPDOSE-SR are personal computer (PC) versions of MAXIGASP and POPGASP, which both resided on the SRS IBM Mainframe. These two codes follow U.S. Nuclear Regulatory Commission (USNRC) Regulatory Guides 1.109 and 1.111 (1977a, 1977b). The basis for MAXDOSE-SR and POPDOSE-SR are USNRC developed codes XOQDOQ (Sagendorf et. al 1982) and GASPAR (Eckerman et. al 1980). Both of these codes have previously been verified for use at SRS (Simpkins 1999 and 2000). The revisions incorporated into MAXDOSE-SR and POPDOSE-SR Version 2014 (hereafter referred to as MAXDOSE-SR and POPDOSE-SR unless otherwise noted) were made per Computer Program Modification Tracker (CPMT) number Q-CMT-A-00016 (Appendix D). Version 2014 was verified for use at SRS in Dixon (2014).

Experimentation of nuclear weapons, releases and storages of radioactive wastes in the Kara sea and in New Zemble

International Nuclear Information System (INIS)

Charmasson, S.

1996-01-01

132 nuclear weapons were tested from 1955 to 1990 in New Zemble. From 1959 to 1993, low level liquid radioactive wastes, low and medium level solid radioactive wastes, reactor core and fuel of submarine and nuclear propelled ships were released in the Kara and the Barentz seas. For these two seas, a recapitulation of the different radioactive sources and the found level of radioactivity of the marine environment are presented. (A.B.). 22 refs. 4 figs., 6 tabs

Simulation Studies of Diffusion-Release and Effusive-Flow of Short-Lived Radioactive Isotopes

CERN Document Server

Zhang, Yan; Kawai, Yoko

2005-01-01

Delay times associated with diffusion release from targets and effusive-flow transport of radioactive isotopes to ion sources are principal intensity limiters at ISOL-based radioactive ion beam facilities, and simulation studies with computer models are cost effective methods for designing targets and vapor transport systems with minimum delay times to avoid excessive decay losses of short lived ion species. A finite difference code, Diffuse II, was recently developed at the Oak Ridge National Laboratory to study diffusion-release of short-lived species from three principal target geometries. Simulation results are in close agreement with analytical solutions to Fick’s second equation. Complementary to the development of Diffuse II, the Monte-Carlo code, Effusion, was developed to address issues related to the design of fast vapor transport systems. Results, derived by using Effusion, are also found to closely agree with experimental measurements. In this presentation, the codes will be used in conc...

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

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)

Digital processing method for monitoring the radioactivity of stack releases

International Nuclear Information System (INIS)

Vialettes, H.; Leblanc, P.; Perotin, J.P.; Lazou, J.P.

1978-01-01

The digital processing method proposed is adapted for data supplied by a fixed-filter detector normally used for analogue processing (integrator system). On the basis of the raw data (pulses) from the detector, the technique makes it possible to determine the rate of activity released whereas analogue processing gives only the released activity. Furthermore, the method can be used to develop alarm systems on the basis of a possible exposure rate at the point of fall-out, and by including in the program a coefficient which allows for atmospheric diffusion conditions at any given time one can improve the accuracy of the results. In order to test the digital processing method and demonstrate its advantages over analogue processing, various atmospheric contamination situations were simulated in a glove-box and analysed simultaneously, using both systems, from the pulses transmitted by the same sampling and fixed-filter detection unit. The experimental results confirm the advantages foreseen in the theoretical research. (author)

Simplified analytical model to simulate radionuclide release from radioactive waste trenches

International Nuclear Information System (INIS)

Sa, Bernardete Lemes Vieira de

2001-01-01

In order to evaluate postclosure off-site doses from low-level radioactive waste disposal facilities, a computer code was developed to simulate the radionuclide released from waste form, transport through vadose zone and transport in the saturated zone. This paper describes the methodology used to model these process. The radionuclide released from the waste is calculated using a model based on first order kinetics and the transport through porous media was determined using semi-analytical solution of the mass transport equation, considering the limiting case of unidirectional convective transport with three-dimensional dispersion in an isotropic medium. The results obtained in this work were compared with other codes, showing good agreement. (author)

The national scheme for monitoring radioactive fallout in milk

International Nuclear Information System (INIS)

Green, B.M.R.

1979-01-01

The National Radiological Protection Board, Harwell, assumed responsibility for the national milk monitoring scheme on Jan. 1, 1979. Milk contamination provides a good guide to radioactivity in the British diet. Brief reference is made to U.K. surveys of radioactive fallout in human food prior to January 1979, and current arrangements for the sampling of milk in the U.K. are explained. The milk is analysed for 90 Sr, 137 Cs and stable calcium. Additional samples are collected to check for 131 I or other short-lived isotopes in the event of atmospheric nuclear tests or accidents involving possible releases of radioactivity. (U.K.)

Radioactive release from VVER-1000 reactors after a terror attack

International Nuclear Information System (INIS)

Sdouz, G.

2005-01-01

Full text: One of the terror scenarios for nuclear power plants is a severe damage of the reactor containment caused by a plane crash or a missile. Due to the loss of electric power the cooling of the core is not maintained leading to a core melt accident. Normally in the course of severe accidents an intact containment has the ability to retain a large part of the radioactive inventory. The goal of this work is the investigation of the behavior of the radioactive release from a VVER-1000-type reactor during a severe accident with a large containment leak from the beginning of the accident. The results are compared with the release in a severe accident via a very small leakage due to the untightness of the containment. This work supplements a series of studies investigating the behavior of a VVER-1000-type reactor during severe accidents under different accident management strategies. The focus in this study is on the 'station blackout'-sequence (or TMLB' in the WASH-1400 nomenclature). The calculations were performed using the Source Term Code Package (STCP), hydrogen explosions are not considered. Up to the melt-through of the cavity bottom the thermal-hydraulics phenomena are almost identical to the TMLB'-case with an intact containment from the beginning. The phenomena occur slightly delayed due to the large containment leak. When the core-concrete-interaction begins the resulting gases leave the containment through the large leak and do not cause a pressure increase. The containment pressure remains at ambient pressure. Due to the different behavior and to the different release times of the nuclides the deviations to the scenario with an intact containment show a great variety. From this comparison it can be shown that the intact containment retains the nuclides up to a factor of 6000. (author)

Order of 4 august 1989 on licensing the release of gaseous radioactive effluents by the Cattenom nuclear production centre (units 3 and 4)

International Nuclear Information System (INIS)

1989-08-01

This Order fixes the conditions and limits of authorised releases of gaseous radioactive effluents from Units 3 and 4 of the Cattenom nuclear power plant. It specifies these are maximum limits, below which the radioactive releases should be as low as possible [fr

Proposal of the concept of selection of accidents that release large amounts of radioactive substances in the high temperature engineering test reactor

International Nuclear Information System (INIS)

Ono, Masato; Honda, Yuki; Takada, Shoji; Sawa, Kazuhiro

2015-01-01

In Position, construction and equipment of testing and research reactor to be subjected to the use standards for rules Article 53 (prevention of expansion of the accident to release a large amount of radioactive material) generation the frequency is a lower accident than design basis accident, when what is likely to release a large amount of radioactive material or radiation from the facility has occurred, and take the necessary measures in order to prevent the spread of the accident. There is provided a lower accident than frequency design basis accidents, for those that may release a large amount of radioactive material or radiation. (author)

Source term estimation and the isotopic ratio of radioactive material released from the WIPP repository in New Mexico, USA

International Nuclear Information System (INIS)

Thakur, P.

2016-01-01

After almost 15 years of operations, the Waste Isolation Pilot Plant (WIPP) had one of its waste drums breach underground as a result of a runaway chemical reaction in the waste it contained. This incident occurred on February 14, 2014. Moderate levels of radioactivity were released into the underground air. A small portion of the contaminated underground air also escaped to the surface through the ventilation system and was detected approximately 1 km away from the facility. According to the source term estimation, the actual amount of radioactivity released from the WIPP site was less than 1.5 mCi. The highest activity detected on the surface was 115.2 μBq/m 3 for 241 Am and 10.2 μBq/m 3 for 239+240 Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m 3 of 241 Am and 5.8 μBq/m 3 of 239+240 Pu at a monitoring station located approximately 1 km northwest of the WIPP facility. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment. In this paper, the early stage monitoring data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and an oversight monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP) LLC were utilized to estimate the actual amount of radioactivity released from the WIPP underground. The Am and Pu isotope ratios were measured and used to support the hypothesis that the release came from one drum identified as having breached that represents a specific waste stream with this radionuclide ratio in its inventory. This failed drum underwent a heat and gas producing reaction that overpowered its vent and

Innovative concept for a major breakthrough in atmospheric radioactive xenon detection for nuclear explosion monitoring

International Nuclear Information System (INIS)

Le Petit, G.; Cagniant, A.; Gross, P.; Achim, P.; Douysset, G.; Taffary, T.; Moulin, C.; Morelle, M.

2013-01-01

The verification regime of the comprehensive test ban treaty (CTBT) is based on a network of three different waveform technologies together with global monitoring of aerosols and noble gas in order to detect, locate and identify a nuclear weapon explosion down to 1 kt TNT equivalent. In case of a low intensity underground or underwater nuclear explosion, it appears that only radioactive gases, especially the noble gas which are difficult to contain, will allow identification of weak yield nuclear tests. Four radioactive xenon isotopes, 131m Xe, 133m Xe, 133 Xe and 135 Xe, are sufficiently produced in fission reactions and exhibit suitable half-lives and radiation emissions to be detected in atmosphere at low level far away from the release site. Four different monitoring CTBT systems, ARIX, ARSA, SAUNA, and SPALAX TM have been developed in order to sample and to measure them with high sensitivity. The latest developed by the French Atomic Energy Commission (CEA) is likely to be drastically improved in detection sensitivity (especially for the metastable isotopes) through a higher sampling rate, when equipped with a new conversion electron (CE)/X-ray coincidence spectrometer. This new spectrometer is based on two combined detectors, both exhibiting very low radioactive background: a well-type NaI(Tl) detector for photon detection surrounding a gas cell equipped with two large passivated implanted planar silicon chips for electron detection. It is characterized by a low electron energy threshold and a much better energy resolution for the CE than those usually measured with the existing CTBT equipments. Furthermore, the compact geometry of the spectrometer provides high efficiency for X-ray and for CE associated to the decay modes of the four relevant radioxenons. The paper focus on the design of this new spectrometer and presents spectroscopic performances of a prototype based on recent results achieved from both radioactive xenon standards and air sample

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

Global atmospheric dispersion modelling after the Fukushima accident

Energy Technology Data Exchange (ETDEWEB)

Suh, K.S.; Youm, M.K.; Lee, B.G.; Min, B.I. [Korea Atomic Energy Research Institute (Korea, Republic of); Raul, P. [Universidad de Sevilla (Spain)

2014-07-01

A large amount of radioactive material was released to the atmosphere due to the Fukushima nuclear accident in March 2011. The radioactive materials released into the atmosphere were mostly transported to the Pacific Ocean, but some of them were fallen on the surface due to dry and wet depositions in the northwest area from the Fukushima nuclear site. Therefore, northwest part of the nuclear site was seriously contaminated and it was designated with the restricted zone within a radius of 20 ∼ 30 km around the Fukushima nuclear site. In the early phase of the accident from 11 March to 30 March, the radioactive materials were dispersed to an area of the inland and offshore of the nuclear site by the variations of the wind. After the Fukushima accident, the radionuclides were detected through the air monitoring in the many places over the world. The radioactive plume was transported to the east part off the site by the westerly jet stream. It had detected in the North America during March 17-21, in European countries during March 23-24, and in Asia during from March 24 to April 6, 2011. The radioactive materials were overall detected across the northern hemisphere passed by 15 ∼ 20 days after the accident. Three dimensional numerical model was applied to evaluate the dispersion characteristics of the radionuclides released into the air. Simulated results were compared with measurements in many places over the world. Comparative results had good agreements in some places, but they had a little differences in some locations. The difference between the calculations and measurements are due to the meteorological data and relatively coarse resolutions in the model. Some radioactive materials were measured in Philippines, Taiwan, Hon Kong and South Korea during from March 23-28. It inferred that it was directly transported from the Fukushima by the northeastern monsoon winds. This event was well represented in the numerical model. Generally, the simulations had a good

Technical subsidies for the operation of IRD/CNEN emergency vehicles in the case of a nuclear accident at the Angra Nuclear Power Plant with associated radioactive releases to the atmosphere

International Nuclear Information System (INIS)

Leao, J.L.B.

1982-03-01

Technical support is provided for the operation of an emergency vehicle of Instituto de Radioprotecao e Dosimetria/Comissao Nacional de Energia Nuclear, Rio de Janeiro, Brazil, in the event of uncontrolled release of radioactivity from the Angra Nuclear Power Plant (NPP) to the atmosphere. It is based on internationally adopted emergency decision process philosophy, the concept of 'Protective Action Guide' (PAG), the exposure pathways relevant to nuclear accidents, the measuring systems to be used in obtaining the exposure rate in the effluent 'plume', the methods utilized to predict dose to the population, radioiodine suppression measures, the monitoring instrumentation available to the emergency group, some post-accident considerations and finally, the monitoring that may be carried out from an aircraft. Information is given about the NPP operator's responsabilities with respect to the prediction of the consequences of an accident, as well as methods for thyroid and whole body dose estimation based on exposure to the radioiodine and noble gases present in the effluent plume. The example of the Three Mile Island's incident is used to formulate some observations regarding collective dose to the public estimates derived from measurements made from a helicopter. (Author) [pt

Size distribution of natural aerosols and radioactive particles issued from radon, in marine and hardly polluted urban atmospheres

International Nuclear Information System (INIS)

Tymen, Georges.

1979-03-01

With a view to studying the natural radioactive particles produced by atttachment of 222 Rn daughters on environmental aerosol particles, the behaviours of CASELLA MK2 and ANDERSEN cascade impactors were first investigated. Their characteristic stage diameters were determined and size distributions of airborne particles were obtained in various situations. Moreover, an experimental and automatic equipment for measuring radon was devised and a method was developed in order to evaluate RaA, RaB, RaC concentrations in the free atmosphere. A degree of radioactive desequilibrium between 222 Rn and its daughters, more important than that in other locations was thus demonstrated. Furthermore, by means of various aerosol collection systems (ion tubes, diffusion batteries, cascade impactors, filters), the cumulative size distribution of natural radioactivity was established in the air, at ground level. Finally, from a theory of attachment of small radioactive ions on atmospheric particles, a tentative explanation of experimental results was made [fr

Regulatory review of releases from HIFAR of radioactive airborne effluent

International Nuclear Information System (INIS)

Westall, D.J.; Macnab, D.I.

1996-01-01

Full text: The Nuclear Safety Bureau (NSB) was set up by legislation in 1992 as an independent Commonwealth corporate body reporting to the Minister for Health and Family Services. Its functions include monitoring and reviewing the safety of nuclear plant owned or operated by the Australian Nuclear Science and Technology Organisation (ANSTO). The NSB sets requirements for authorisation of the operation of the HIFAR research reactor, and may impose restrictions and conditions on its operation. The authorisation for the operation of HIFAR includes a requirement for arrangements for the treatment, safe storage and disposal of solid, liquid and gaseous radioactive wastes from the reactor. The objective is to establish conditions which would ensure that radiation exposure to plant personnel and the public from radioactive wastes are within acceptable limits and that releases are maintained as low as reasonably achievable. The NSB has developed expectations based on international best practice, against which to review HIFAR's arrangements for satisfying the requirement and achieving the objective. Arrangements for the release of airborne radioactive effluent from HIFAR were reviewed by the NSB as part of an overall review of the upgrade of safety documentation for HIFAR. The NSB's expectations for the review were drawn from the International Atomic Energy Agency (IAEA) Basic Safety Standards (Safety Series No 115-I) and the National Health and Medical Research Council (NHMRC) Recommendations for Limiting Exposure to Ionizing Radiation (1995). These expectations included a hierarchy of primary dose limits, stack discharge limits and reference levels for HIFAR aimed at ensuring that radiation doses to the public due to airborne effluent are less than the national dose limits and ANSTO's dose constraints, and are as low as reasonably achievable. An approach favoured by the operator is to work directly to a primary dose limit using an airborne dispersion computer program to

Surveillance of radioactivity in the atmosphere by the Deutscher Wetterdienst (DWD) in the framework of nuclear emergency response programmes

International Nuclear Information System (INIS)

Steinkopff, T.; Dalheimer, A.; Dyck, W.; Fay, B.; Glaab, H.; Jacobsen, I.

2000-01-01

The Deutscher Wetterdienst (DWD), German Meteorological Service, is charged with the surveillance of radioactivity in the atmosphere as a part of the emergency information network of the 'Integrated Measurement and Information System' (IMIS) in Germany. The results of measurements of radioactivity and the meteorological products are transferred regularly to this network. The DWD is also integrated into the Environmental Emergency Response Programme (EER) of the World Meteorological Organization (WMO) as a communication hub. The computer infrastructure, the operational experience in data management as well as the national and international communication systems in operation are significant arguments to run the early alert system on the surveillance of atmospheric radioactivity at the national meteorological service. (author)

A preliminary assessment of selected atmospheric dispersion, food-chain transport, and dose-to-man computer codes for use by the DOE Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Riggle, K.J.; Roddy, J.W.

1989-02-01

This work is part of the ongoing Systems Modeling Program at Oak Ridge National Laboratory, which is assisting the DOE Office of Civilian Radioactive Waste Management in selecting appropriate computer codes for the process of licensing a high-level radioactive waste repository or a monitored retrievable storage facility. A preliminary study of codes for predicting dose to man following airborne releases of radionuclides is described. These codes use models for estimating atmospheric dispersion of activity and deposition onto the ground surface, exposures via external irradiation, inhalation of airborne activity, and ingestion following transport through terrestrial food chains, and the dose per unit exposure for each exposure mode. A set of criteria is given for use in choosing codes for further examination. From a list of over 150 computer codes, five were selected for review

Comparison of the accident process, radioactivity release and ground contamination between Chernobyl and Fukushima-1

International Nuclear Information System (INIS)

Imanaka, Tetsuji; Hayashi, Gohei; Endo, Satoru

2015-01-01

In this report, we have reviewed the basic features of the accident processes and radioactivity releases that occurred in the Chernobyl accident (1986) and in the Fukushima-1 accident (2011). The Chernobyl accident was a power-surge accident that was caused by a failure of control of a fission chain reaction, which instantaneously destroyed the reactor and building, whereas the Fukushima-1 accident was a loss-of-coolant accident in which the reactor cores of three units were melted by decay heat after losing the electricity supply. Although the quantity of radioactive noble gases released from Fukushima-1 exceeded the amount released from Chernobyl, the size of land area severely contaminated by 137 Cesium ( 137 Cs) was 10 times smaller around Fukushima-1 compared with around Chernobyl. The differences in the accident process are reflected in the composition of the discharged radioactivity as well as in the composition of the ground contamination. Volatile radionuclides (such as 132 Te- 132 I, 131 I, 134 Cs and 137 Cs) contributed to the gamma-ray exposure from the ground contamination around Fukishima-1, whereas a greater variety of radionuclides contributed significantly around Chernobyl. When radioactivity deposition occurred, the radiation exposure rate near Chernobyl is estimated to have been 770 μGy h −1 per initial 137 Cs deposition of 1000 kBq m −2 , whereas it was 100 μGy h −1 around Fukushima-1. Estimates of the cumulative exposure for 30 years are 970 and 570 mGy per initial deposition of 1000 kBq m −2 for Chernobyl and Fukusima-1, respectively. Of these exposures, 49 and 98% were contributed by radiocesiums ( 134 Cs + 137 Cs) around Chernobyl and Fukushima-1, respectively

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

Comment on 'On the long-range detection of radioactivity using electromagnetic radiation'

Energy Technology Data Exchange (ETDEWEB)

Fuks, I.M. E-mail: iosif.fuks@noaa.gov; Martynenko, S.I. E-mail: sergey.i.martynenko@univer.kharkov.ua

2004-05-01

The fact that the mesosphere is an electrically active element in the global atmospheric electric circuit provides a possible mechanism for troposphere-mesosphere-ionosphere coupling during releases of radioactive materials at the ground level, and this is discussed in this comment.

Surveillance of the environmental radioactivity

International Nuclear Information System (INIS)

Schneider, Th.; Gitzinger, C.; Jaunet, P.; Eberbach, F.; Clavel, B.; Hemidy, P.Y.; Perrier, G.; Kiper, Ch.; Peres, J.M.; Josset, M.; Calvez, M.; Leclerc, M.; Leclerc, E.; Aubert, C.; Levelut, M.N.; Debayle, Ch.; Mayer, St.; Renaud, Ph.; Leprieur, F.; Petitfrere, M.; Catelinois, O.; Monfort, M.; Baron, Y.; Target, A.

2008-01-01

The objective of these days was to present the organisation of the surveillance of the environmental radioactivity and to allow an experience sharing and a dialog on this subject between the different actors of the radiation protection in france. The different presentations were as follow: evolution and stakes of the surveillance of radioactivity in environment; the part of the European commission, regulatory aspects; the implementation of the surveillance: the case of Germany; Strategy and logic of environmental surveillance around the EDF national centers of energy production; environmental surveillance: F.B.F.C. site of Romans on Isere; steps of the implementation 'analysis for release decree at the F.B.F.C./C.E.R.C.A. laboratory of Romans; I.R.S.N. and the environmental surveillance: situation and perspectives; the part of a non institutional actor, the citizenship surveillance done by A.C.R.O.; harmonization of sampling methods: the results of inter operators G.T. sampling; sustainable observatory of environment: data traceability and samples conservation; inter laboratories tests of radioactivity measurements; national network of environmental radioactivity measurement: laboratories agreements; the networks of environmental radioactivity telemetry: modernization positioning; programme of observation and surveillance of surface environment and installations of the H.A.-M.A.V.L. project (high activity and long life medium activity); Evolution of radionuclides concentration in environment and adaptation of measurements techniques to the surveillance needs; the national network of radioactivity measurement in environment; modes of data restoration of surveillance: the results of the Loire environment pilot action; method of sanitary impacts estimation in the area of ionizing radiations; the radiological impact of atmospheric nuclear tests in French Polynesia; validation of models by the measure; network of measurement and alert management of the atmospheric

Accumulation of radioactive cesium released from Fukushima Daiichi Nuclear Power Plant in terrestrial cyanobacteria Nostoc commune.

Science.gov (United States)

Sasaki, Hideaki; Shirato, Susumu; Tahara, Tomoya; Sato, Kenji; Takenaka, Hiroyuki

2013-01-01

The Fukushima Daiichi Nuclear Power Plant accident released large amounts of radioactive substances into the environment and contaminated the soil of Tohoku and Kanto districts in Japan. Removal of radioactive material from the environment is an urgent problem, and soil purification using plants is being considered. In this study, we investigated the ability of 12 seed plant species and a cyanobacterium to accumulate radioactive material. The plants did not accumulate radioactive material at high levels, but high accumulation was observed in the terrestrial cyanobacterium Nostoc commune. In Nihonmatsu City, Fukushima Prefecture, N. commune accumulated 415,000 Bq/kg dry weight (134)Cs and 607,000 Bq kg(-1) dry weight (137)Cs. The concentration of cesium in N. commune tended to be high in areas where soil radioactivity was high. A cultivation experiment confirmed that N. commune absorbed radioactive cesium from polluted soil. These data demonstrated that radiological absorption using N. commune might be suitable for decontaminating polluted soil.

Release of the radioactive patient following radiation therapy

International Nuclear Information System (INIS)

Powers, J.; Cancer Board, A.

2004-01-01

Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

Release of the radioactive patient following radiation therapy

Energy Technology Data Exchange (ETDEWEB)

Powers, J.; Cancer Board, A.

2004-07-01

Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

Development of DOE complexwide authorized release protocols for radioactive scrap metals

International Nuclear Information System (INIS)

Chen, S. Y.

1998-01-01

Within the next few decades, several hundred thousand tons of metal are expected to be removed from nuclear facilities across the U.S. Department of Energy (DOE) complex as a result of decontamination and decommissioning (D and D) activities. These materials, together with large quantities of tools, equipment, and other items that are commonly recovered from site cleanup or D and D activities, constitute non-real properties that warrant consideration for reuse or recycle, as permitted and practiced under the current DOE policy. The provisions for supporting this policy are contained in the Draft Handbook for Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material published by DOE in 1997 and distributed to DOE field offices for interim use and implementation. The authorized release of such property is intended to permit its beneficial use across the entire DOE complex. The objective of this study is to develop readily usable computer-based release protocols to facilitate implementation of the Handbook in evaluating the scrap metals for reuse and recycle. The protocols provide DOE with an effective oversight tool for managing release activities

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

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

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.

Malicious release of radioactive materials in urban area. Exposure of the public and emergency staff, protective measures

International Nuclear Information System (INIS)

Koch, Wolfgang; Lange, Florentin

2016-01-01

The preparedness for hypothetical radiological scenarios is part of the tasks for governmental authorities, safety and emergency organizations and the staff in case of the incident. The EURATOM guideline for radiation protection has to be implemented into national laws. According to the guidelines it is required that emergency planning has to be prepared for hypothetical radiological scenarios including terroristic or other maliciously motivated attacks using radioactive materials. The study includes assumptions on the released respirable radioactivity, restriction of the hazardous area, wind induced re-suspension of radioactive dusts and inhalation exposure, and mitigation measures.

Initial effect of the Fukushima accident on atmospheric electricity

Science.gov (United States)

Takeda, M.; Yamauchi, M.; Makino, M.; Owada, T.

2011-08-01

Vertical atmospheric DC electric field at ground level, or potential gradient (PG), suddenly dropped by one order of magnitude at Kakioka, 150 km southwest from the Fukushima Dai-ichi nuclear power plant (FNPP) right after the plant released a massive amount of radioactive material southward on 14 March, 2011. The PG stayed at this level for days with very small daily variations. Such a long-lasting near-steady low PG has never been observed at Kakioka. The sudden drop of PG with one-hour time scale is similar to those associated with rain-induced radioactive fallout after nuclear tests and the Chernobyl disaster. A comparison with the PG data with the radiation dose rate data at different places revealed that arrival of the radioactive dust by low-altitude wind caused the PG drop without rain. Furthermore, the PG might have reflected a minor release several hours before this release at the distance of 150 km. It is recommended that all nuclear power plant to have a network of PG observation surrounding the plant.

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.

Preliminary results of the TMI-2 radioactive iodine mass balance study

International Nuclear Information System (INIS)

Pelletier, C.A.; Cox, T.E.; Reeder, D.L.; Vollique, P.G.; Thomas, C.D.

1982-01-01

Analysis of samples taken from the Three Mile Island Unit 2 (TMI-2) reactor building following the 1979 accident indicates the fraction of the radioactive iodine (radioiodine) inventory in the core released to the uilding atmosphere is smaller tan assumed in Regulatory Guide 1.4. This summary presents analytical results supporting this conclusion

Krypton-85 and other airborne radioactivity measurements throughout Ireland

International Nuclear Information System (INIS)

Smith, K.J.; Murray, M.; Wong, J.; Sequeira, S.; Long, S.C.; Rafferty, B.

2004-01-01

In compliance with articles 35 and 36 of the EURATOM Treaty, the Radiological Protection Institute of Ireland (RPII) undertakes a comprehensive programme of radioactivity monitoring in the Irish terrestrial environment. Radioactivity is present in the terrestrial environment due to natural processes, the testing of nuclear weapons in the atmosphere, accidents such as the Chernobyl accident and the routine discharge of radionuclides from nuclear installations. The RPII monitors airborne radioactivity concentrations at ten stations throughout Ireland, of which, nine are equipped with low volume particulate samplers and one, in Dublin, with a high volume particulate sampler. The low volume particulate samples are assessed for total beta activity and high volume samples for gamma emitting radionuclides such as caesium-137 and beryllium-7. In addition, air sampled at the RPII laboratory in Dublin, is monitored for krypton-85, a radioactive noble gas, released into the environment primarily as a result of the reprocessing of nuclear fuel at installations such as Sellafield in the UK and La Hague in France. Since the inception of the krypton measurements in 1993 a trend of increasing atmospheric concentrations has been observed. The results of the krypton-85 monitoring, as well as the airborne radioactivity concentration measurements, will be presented and discussed in this paper. (author)

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

Some discussions on micrometeorology and atmospheric diffusion of classic and radioactive industrial pollutions. 5

International Nuclear Information System (INIS)

Veverka, O.; Valenta, V.; Vlachovsky, K.

1976-01-01

The formulae are given expressing the atmospheric dispersion of industrial emissions released from the stacks of industrial plants and power plants. Gaussian distribution of the emissions is assumed. The behaviour of the plume is discussed and the concepts of lofting and fumigation are explained. Generalized relations are derived for the calculation of the atmospheric dispersion of gaseous wastes applicable to both high and short stack disposal and to the leakage from buildings, assuming that the source of emissions is of a point type and emissions are released continuously. (L.O.)

Study about the integrated treatment of chemical and radioactive effluents, introducing the zero release concept

International Nuclear Information System (INIS)

Mierzwa, Jose Carlos

1996-01-01

An Integrated System to the treatment of Chemical and Radioactive Effluents to the Centro Experimental Aramar is proposed and evaluated, introducing the Effluent Zero Release concept, where factors related to the environmental regulation in vigor in the country, as well as the availability of hydrological resources in the place where CEA have been implanted, are considered. Through a literature analysis of the main effluents treatment techniques available nowadays and after a case of study selection, take into account two industrial installations that will be implanted at CEA, it was defined an arrangement to compose the Integrated System to the Treatment of Chemicals and Radioactive Effluents, focusing the Zero Release concept consolidation. A defined arrangement uses a combination among three treatment processes, it means chemical precipitation, reverse osmosis and evaporation, that were experimentally evaluated. The proposed arrangement was evaluated using synthetic effluents, that were prepared based on data from literature and conception documents of the installation considered in this work. Three kinds of effluents were simulated, one arising from a nuclear reactor laundry, one arising from the water refrigeration system and demineralized water production to the nuclear reactor and the other one arising from a nuclear material production laboratory. Each effluent were individually submitted to the selected treatment processes, to get the best operational conditions for each treatment process. The results got during the laboratory assays show that the proposed Integrated System to the Treatment of Chemicals and Radioactive Effluents is feasible, consolidating the Effluent Zero Release concept, which is the proposition of this work. (author)

Limitation of releases and filtration by sand

International Nuclear Information System (INIS)

Schektman, N.

1986-01-01

In the highly hypothetic case of a severe reactor accident, it may lead to an increase of pressure within the containment and up to a value above the calculated pressure. A procedure is necessary in this case to maintain the integrity of the containment to prevent a release of radioactive products to the environment, while controlling in the best way releases. So, EDF and the CEA have developed a device of decompression-filtration of the containment atmosphere, using a free penetration of the containment and a sand box; the device and its operation constitute the U5 procedure [fr

Source terms for airborne radioactivity arising from uranium mill wastes

International Nuclear Information System (INIS)

O'Riordan, M.C.; Downing, A.L.

1978-01-01

One of the problems in assessing the radiological impact of uranium milling is to determine the rates of release to the air of material from the various sources of radioactivity. Such source terms are required for modelling the transport of radioactive material in the atmosphere. Activity arises from various point and area sources in the mill itself and from the mill tailings. The state of the tailings changes in time from slurry to solid. A layer of water may be maintained over the solids during the life of the mine, and the tailings may be covered with inert material on abandonment. Releases may be both gaseous and particulate. This paper indicates ways in which radon emanation and the suspension of long-lived particulate activity might be quantified, and areas requiring further exploration are identified

Feasibility study of cocos, condensation of containment atmosphere on structures

International Nuclear Information System (INIS)

Rij, H.M. van; Vonka, V.

1989-12-01

The aim of this report is to assess the state of the art of the knowledge of the thermo-hydraulic conditions within a LWR containment in order to determine both the radioactive and the non-radioactive aerosol deposition rates during a severe reactor accident. The radioactive aerosol in the containment atmosphere is, together with the noble gases, responsible for the radioactive source term into the biosphere when a containment failure occurs. The dominant aerosol removal mechanisms depend strongly upon the thermal-hydraulic state of the containment atmosphere. It is demonstrated that the thermohydraulic state, determined by heat sources and the sensible heat transport, is predominantly super-heated when fission products are released into the containment. Hence the thermohydraulic conditions are not favorable for an intensive bulk condensation onto aerosol particles during an essential period of time. A station black-out scenario, in which the primary system of the considered 500 MWe PWR with a dry cavity is depressurized prior to vessel failure, is used as an example to demonstrate this effect. The results, obtained with the CONTAIN code, show the relevance of the sensible heat transport in the period of time (c.a. 30 minutes) between the end of the injection of the steam and fission products into the containment, and the molten core concrete interaction. All considered variation of the station black-out scenario, in which the decay heat dissipated in the containment atmosphere has been 10% of the total decay heat, indicate that the atmosphere becomes super-heated within the 30 minutes. Reducing the fraction of the decay heat in the containment from the 10% to 5% increases the time period with saturated conditions. The amount of the decay heat released into the containment atmosphere forms the major factor determining the thermohydraulic state. It influences the duration of the bulk condensation period, which in turn has an influence on the aerosol deposition

Adsorption of radioactive I2 gas onto atmospheric aerosol

International Nuclear Information System (INIS)

Noguchi, Hiroshi; Murata, Mikio; Suzuki, Katsumi.

1990-01-01

Laboratory scale experiments on the adsorption of radioactive elemental iodine (I 2 ) gas onto atmospheric aerosol showed that the adsorption reached an equilibrium state in about twelve minutes at high initial I 2 concentrations. The proportion of iodine which was adsorbed on the aerosol gradually decreased with increading initial I 2 concentration ranging over 10 -13 to 10 -9 g/cm 3 at a reaction time of 31 min but was almost constant at a reaction time of 2 min. A fraction of iodine desorbed from particulate iodine as mainly I 2 gas. An adsorption isotherm of atmospheric aerosol for I 2 gas was estimated from the experimental data of long reaction time and high I 2 concentrations. Using this adsorption isotherm, a theoretical equation, which was similar to our previous equation, was derived to explain the experimental results. A geometric mean and standard deviation of sticking probability in the equation were estimated to be 1.2 x 10 -2 and 2.7, respectively. Almost all experimental data were within ranges of calculated results considering the geometric standard deviation of sticking probability. (author)

Intercomparison of numerical simulations on oceanic dispersion of the radioactive cesium released because of the Fukushima disaster

Energy Technology Data Exchange (ETDEWEB)

Kawamura, H.; Kobayshi, T.; Furuno, A. [Japan Atomic Energy Agency, Ibaraki (Japan); Usui, N.; Kamachi, M. [Japan Meteorological Agency, Meteorological Research Inst., Ibaraki (Japan); Nishikawa, S.; Ishikawa, Y. [Japan Agency for Marine-Earth Science and Tech., Kanagawa (Japan)

2014-07-01

We conducted numerical simulations on oceanic dispersion of the radioactive cesium released because of the Fukushima disaster in the North Pacific. Two independent oceanic reanalysis data were used in the simulations. Both simulations suggested that the {sup 137}Cs concentration had been reduced to the pre-Fukushima level around 2.5 years after the disaster. The intercomparison revealed that meso-scale eddies accompanied by the Kuroshio Extension may have efficiently diluted the radioactive cesium at the sea surface. The meso-scale eddies also played an important role in transporting the surface radioactive cesium into the intermediate layer. (author)

Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

International Nuclear Information System (INIS)

Chen Xiaoqiu

2009-01-01

Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

Limitation of releases of radioactive effluents for nuclear power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Tolksdorf, P.; Buehling, A.

1981-01-01

Empirical values relating to the effluents of nuclear power plants in the Federal Republic of Germany are now available. These values cover a period of several years of operation. The measured emissions of radioactive substances are often very much below the maximum permissible values, based on the dose limits for the environment stipulated in the legal regulations. Extensive technical and administrative measures contribute to the reduction of radioactive effluents. Furthermore, additional possibilities for improvement are mentioned which may lead to a further reduction of radioactive effluents. These are derived from investigations into the release of radioactive substances in nuclear power plants. The licensing procedure in the Federal Republic of Germany in fixing discharge limits is outlined. Proposals are made concerning licence values which may be determined for the radioactive effluents in modern standardized nuclear power plants with light-water reactors. The resulting radiation exposures are quoted for a typical nuclear power plant site. (author)

Estimation of maximum credible atmospheric radioactivity concentrations and dose rates from nuclear tests

International Nuclear Information System (INIS)

Telegadas, K.

1979-01-01

A simple technique is presented for estimating maximum credible gross beta air concentrations from nuclear detonations in the atmosphere, based on aircraft sampling of radioactivity following each Chinese nuclear test from 1964 to 1976. The calculated concentration is a function of the total yield and fission yield, initial vertical radioactivity distribution, time after detonation, and rate of horizontal spread of the debris with time. calculated maximum credible concentrations are compared with the highest concentrations measured during aircraft sampling. The technique provides a reasonable estimate of maximum air concentrations from 1 to 10 days after a detonation. An estimate of the whole-body external gamma dose rate corresponding to the maximum credible gross beta concentration is also given. (author)

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

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

Full text: The paper presents the method of dispersion calculation, witch can be applied for the DLE calculation. This is necessary to ensure a secure performance of the Experimental Pilot Plant for Tritium and Deuterium Separation (using the technology for detritiation based upon isotope catalytic exchange between tritiated heavy water and deuterium followed by cryogenic distillation of the hydrogen isotopes). For the calculation of the dispersion of radioactivity effluents in the atmosphere, at a given distance between source and receiver, the Gaussian mathematical model was used. This model is currently applied for estimating the long-term results of dispersion in case of continuous or intermittent emissions as basic information for long-term radioprotection measures for areas of the order of kilometres from the source. We have considered intermittent or continuous emissions of intensity lower than 1% per day relative to the annual emission. It is supposed that the radioactive material released into environment presents a gaussian dispersion both in horizontal and vertical plan. The local dispersion parameters could be determined directly with turbulence measurements or indirectly by determination of atmospheric stability. Weather parameters for characterizing the atmospheric dispersion include: - direction of wind relative to the source; - the speed of the wind at the height of emission; - parameters of dispersion to different distances, depending on the atmospheric turbulence which characterizes the mixing of radioactive materials in the atmosphere; - atmospheric stability range; - the height of mixture stratum; - the type and intensity of precipitations. The choice of the most adequate version of Gaussian model depends on the relation among the height where effluent emission is in progress, H (m), and the height at which the buildings influence the air motion, HB (m). There were defined three zones of distinct dispersion. This zones can have variable lengths

Mathematical modeling of radionuclide release through a borehole in a radioactive waste repository

International Nuclear Information System (INIS)

Choi, Heui Joo

1996-02-01

The effects of inadvertent human intrusion as a form of direct drilling into a radioactive waste repository are discussed in this thesis. It has been mentioned that the inadvertent direct drilling into the repository could provide a release pathway for radionuclides even with its low occurrence probability. The following analyses are carried out regarding the problem. The maximum concentration in a water-filled borehole penetrating a repository is computed with a simple geometry. The modeling is based upon the assumption of the diffusive mass transfer in the waste forms and the complete mixing in the borehole. It is shown that the maximum concentrations of six radionuclides in the borehole could exceed the Maximum Permissible Concentration. Also, the diffusive mass transport in a water-filled borehole is investigated with a solubility-limited boundary condition. An analytic solution is derived for this case. Results show that the diffusive mass transport is fast enough to justify the assumption of the complete mixing compared with the considered time span. The axial diffusive mass transport along a water-filled borehole is modeled to compute the release rate taking account of the rock matrix diffusion. The results show that the release of short-lived radionuclides are negligible due to the low concentration gradient in early time and the rock matrix diffusion. The release rates of four long-lived radionuclides are computed. It is also shown that the model developed could be applied to a borehole at a non-cylindrically shaped repository and the off-center drilling of a cylindrical repository. The release rates of long-lived nuclides through a porous material-filled borehole are computed. The results show that the release of all the long-lived nuclides is negligible up to half million years in the case that the borehole is filled with the porous material. The radiological effects of the nuclides released through the borehole penetrating the repository are computed

Regulatory analysis on criteria for the release of patients administered radioactive material. Final report

Energy Technology Data Exchange (ETDEWEB)

Schneider, S.; McGuire, S.A.

1997-02-01

This regulatory analysis was developed to respond to three petitions for rulemaking to amend 10 CFR parts 20 and 35 regarding release of patients administered radioactive material. The petitions requested revision of these regulations to remove the ambiguity that existed between the 1-millisievert (0.1-rem) total effective dose equivalent (TEDE) public dose limit in Part 20, adopted in 1991, and the activity-based release limit in 10 CFR 35.75 that, in some instances, would permit release of individuals in excess of the current public dose limit. Three alternatives for resolution of the petitions were evaluated. Under Alternative 1, NRC would amend its patient release criteria in 10 CFR 35.75 to match the annual public dose limit in Part 20 of 1 millisievert (0.1 rem) TEDE. Alternative 2 would maintain the status quo of using the activity-based release criteria currently found in 10 CFR 35.75. Under Alternative 3, the NRC would revise the release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts (0.5 rem) TEDE.

Regulatory analysis on criteria for the release of patients administered radioactive material. Final report

International Nuclear Information System (INIS)

Schneider, S.; McGuire, S.A.

1997-02-01

This regulatory analysis was developed to respond to three petitions for rulemaking to amend 10 CFR parts 20 and 35 regarding release of patients administered radioactive material. The petitions requested revision of these regulations to remove the ambiguity that existed between the 1-millisievert (0.1-rem) total effective dose equivalent (TEDE) public dose limit in Part 20, adopted in 1991, and the activity-based release limit in 10 CFR 35.75 that, in some instances, would permit release of individuals in excess of the current public dose limit. Three alternatives for resolution of the petitions were evaluated. Under Alternative 1, NRC would amend its patient release criteria in 10 CFR 35.75 to match the annual public dose limit in Part 20 of 1 millisievert (0.1 rem) TEDE. Alternative 2 would maintain the status quo of using the activity-based release criteria currently found in 10 CFR 35.75. Under Alternative 3, the NRC would revise the release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts (0.5 rem) TEDE

30 years of the Goiania Accident: a comparative study with other radioactivity dispersion events

International Nuclear Information System (INIS)

Smith, Ricardo Bastos; Vicente, Roberto

2017-01-01

The year 2017 marks 30 years since the radioactive accident that occurred in the city of Goiania, capital of the state of Goias. It was the largest radiological accident in Brazil, and one of the largest in the world occurring outside nuclear facilities. Regarding the accidents at nuclear power plants, two of the biggest were Chernobyl in Ukraine, a year and a half before Goiania, and the Fukushima accident in Japan, in 2011. Different amounts of radioactive material were dispersed in the environment in each of these events. However, each one’s main pathway of dispersion was different: the accident of Goiania was terrestrial, Chernobyl was at the atmosphere, and Fukushima was mainly in the ocean. This work aims to study these different amounts, comparing such activities. In addition, it proposes to compare the sea dispersion of Fukushima with the amount of radioactive waste dumped in the oceans, when the release of radioactive waste at sea was permitted. It also proposes to compare the Chernobyl aerial dispersion with the radioactive material dissipated in the atmosphere, resulting from the more than 500 atmospheric nuclear tests conducted between 1945 and 1962 by the United States, the former Soviet Union, England, France and China. (author)

30 years of the Goiania Accident: a comparative study with other radioactivity dispersion events

Energy Technology Data Exchange (ETDEWEB)

Smith, Ricardo Bastos; Vicente, Roberto, E-mail: rbsmith@ipen.br, E-mail: rvicente@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

The year 2017 marks 30 years since the radioactive accident that occurred in the city of Goiania, capital of the state of Goias. It was the largest radiological accident in Brazil, and one of the largest in the world occurring outside nuclear facilities. Regarding the accidents at nuclear power plants, two of the biggest were Chernobyl in Ukraine, a year and a half before Goiania, and the Fukushima accident in Japan, in 2011. Different amounts of radioactive material were dispersed in the environment in each of these events. However, each one’s main pathway of dispersion was different: the accident of Goiania was terrestrial, Chernobyl was at the atmosphere, and Fukushima was mainly in the ocean. This work aims to study these different amounts, comparing such activities. In addition, it proposes to compare the sea dispersion of Fukushima with the amount of radioactive waste dumped in the oceans, when the release of radioactive waste at sea was permitted. It also proposes to compare the Chernobyl aerial dispersion with the radioactive material dissipated in the atmosphere, resulting from the more than 500 atmospheric nuclear tests conducted between 1945 and 1962 by the United States, the former Soviet Union, England, France and China. (author)

Examination of a measuring method for fallout radioactivity released by the accident of the Fukushima Dai-ichi NPS. Surface contamination measurement

International Nuclear Information System (INIS)

Yoshii, Taiki; Kawasaki, Satoru

2013-08-01

Radioactive nuclides were released in the atmosphere by the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station in March, 2011, and they are detected on the materials that had no artificial radioactive nuclides before the accident. Confronted with this situation, NISA issued a guideline titled 'A guideline regarding treatment of materials in nuclear facilities considering the influence of fallout released from the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station' on March 30, 2012. Nuclear Regulatory Authority refers to applying the existing bylaw until the time to make decision of the updated bylaw. The guideline shows that after judging whether there is the influence of fallout or not, the conventional clearance and NR systems can be used when there is no influence of fallout. On the other hand, the special treatment is required when it is judged that there is the influence. This report describes a specific example of measuring method to evaluate the influence of fallout, in case of surface contamination. This report focused surface contamination of flat object as target. Preliminary investigation shows that the distribution of surface contamination due to fallout is near to lognormal distribution. Therefore, the sampling measurement can be adopted. The average surface contamination of target is decided from sampling data by using 90% upper confidence limit of Chebyshev inequality. Also, the minimum sampling number is decided. The evaluation of the influence of fallout is judged from the result of surface contamination measurement, weight of target and surface area of target. (author)

Calculation of releases of radioactive materials in gaseous and liquid effluents from boiling water reactors (BWR-GALE Code)

International Nuclear Information System (INIS)

Bangart, R.L.; Bell, L.G.; Boegli, J.S.; Burke, W.C.; Lee, J.Y.; Minns, J.L.; Stoddart, P.G.; Weller, R.A.; Collins, J.T.

1978-12-01

The calculational procedures described in the report reflect current NRC staff practice. The methods described will be used in the evaluation of applications for construction permits and operating licenses docketed after January 1, 1979, until this NUREG is revised as a result of additional staff review. The BWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment

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.)

Fire simulation in radioactive waste disposal and the radiation risk associated; Simulação de incêndio em depósito de rejeitos radioativos e o risco associado a esse cenário

Energy Technology Data Exchange (ETDEWEB)

Domingos, Érica Nascimento

2018-05-01

An atmospheric dispersion of radioactive material is one of the possible consequences of an accident scenario in nuclear installations, radiative and radioactive waste deposit. Taking into account a possibility of this release of radioactive material into the atmosphere this work proposes a modeling of the atmospheric dispersion from a fire scenario in a deposit of radioactive waste of low and middle level of radiation varying the amount of inventory released in the fire. For this simulation was adopted the software of physical codes of medical health, the HotSpot Health Physics Codes which uses the Gaussian model to calculate an atmospheric dispersion based on the Pasquill atmospheric stability classes. This software calculates a total effective dose in relation to distance, such as a compromised dose in a list of specific organs, among them the lung, object of work study for calculating the risk of cancer associated with a low dose of radiation. The radiological risk calculation is held by the BEIR V model, Biological Effects of Ionizing Radiations, one of the models to estimate the relative risk of cancer induced by ionizing radiation. (author)

Graphic displays on PCs of gaseous diffusion models of radionuclide releases to the atmosphere

International Nuclear Information System (INIS)

Campo Ortega, E. del

1993-01-01

The well-known MESOI program has been modified and improved to adapt it to a PC/AT with VGA colour monitor. Far from losing any of its powerful characteristics to calculate the transport, diffusion, deposition and decay of gaseous radioactive effluents discharged to the atmosphere, it has been enhanced to allow graphic viewing of concentrations, wind speed and direction and puff locations in colour, all on a background map of the site. The background covers a 75 x 75 km square and has a graphic grid density of 421 x 421 pixels. This means that effluent concentration is represented approximately every 170 metres in the 'clouded-area'. Among the modifications and enhancements made, the following are of particular interest: 1. A new subroutine called NUBE has been added, which calculates the distribution of effluent concentration of activity in a grid of 421 x 421 pixels. 2. Several subroutines have been added to obtain graphic displays and printouts of the cloud, wind field and puff locations. 3. Graphic display of the geographic plane of the area surrounding the effluent release point. 4. Off-line preparation of meteorological and topographical data files necessary for program execution. (author)

Complete release from regulatory control via the density of radioactive contamination of soil of the Chornobyl exclusion zone

International Nuclear Information System (INIS)

Bondarenko, Oleg; Fadeev, Mykhaylo; Kireev, Serhiy; Proskura, Mykola

2008-01-01

Full text: In this work a general procedure of establishment the criterion of complete release from regulatory control via the density of radioactive contamination of soil of alone areas of the Chornobyl exclusion zone is represented by the following three stages, namely: 1) Justification of the dose criterion of complete release by applying the fundamental approaches of regulating the prolonged exposure of the public on a basement of ICRP Publication No. 82; 2) Justification of a procedure for establishment of dose constraint through evaluation of the statistical distribution of a controlled radiation value through determination of the high boundary of the confidence interval; 3) Generalization of conversion coefficients (via the density of radioactive contamination of soil) and coverage coefficients for the dose forming factors of the public (inhalation intake of transuranium radionuclides both at natural and technogenic dust resuspension, peroral intake of 137 Cs and 90 Sr via food stuff, external exposure from 137 Cs); on a basis of these coefficients average doses and dose constraint of a critical group of the public are calculated. As it is shown in the work, the generalized criterion of complete release from regulatory control via the density of radioactive contamination of soil of the Chornobyl exclusion zone can be defined by dividing the recommended ICRP dose clearance level for situation of the post-accidental prolonged exposure of a critical group of the public, namely, 0.3 mSv·year -1 to the dose conversion coefficient (i.e. transfer from the superficial soil contamination of radioactivity to the dose constraint for the Chornobyl exclusion zone), namely, 12.9 μSv·year -1 /((kBq·M -2 ). Thus, a level of the density of radioactive contamination of soil, that provides the complete release from regulatory control makes 23.3 kBq·M -2 . For completion of the work on justification of the criterion of complete territory release in the conditions of

Applicability of Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) to releases of radioactive substances

International Nuclear Information System (INIS)

Miller, S.R.

1987-01-01

The Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), commonly called Superfund, provided a $1.6 billion fund (financed by a tax on petrochemical feedstocks and crude oil and by general revenues) for the cleanup of releases of hazardous substances, including source, special nuclear or byproduct material, and other radioactive substances, from mostly inactive facilities. The US Environmental Protection Agency (EPA) is authorized to require private responsible parties to clean up releases of hazardous substances, or EPA, at its option, may undertake the cleanup with monies from the Fund and recover the monies through civil actions brought against responsible parties. CERCLA imposes criminal penalties for noncompliance with its reporting requirements. This paper will overview the key provisions of CERCLA which apply to the cleanup of radioactive materials

Transboundary radioactive and chemical pollution simulation using an atmospheric/marine predicting system

International Nuclear Information System (INIS)

Telenta, B.; Antic, D.

2001-01-01

The atmospheric models can be used to simulate the transport of contaminants in typical accidental cases and for realistic meteorological conditions. Some numerical models for weather forecast can be used for near to real simulations of propagation of radioactive nuclides or classical chemical pollutants to the atmosphere. The various meteorological parameters are taken into account and various meteorological conditions, even complex ones, can be analyzed. The models can be used for very well assessment of the airborne pollution from energy sources and industrial installations, for comparative studies and for safety analysis. This report describes an proposal for a project of the transboundary pollution simulation, that can be used for the East Mediterranean Region. The project is based on the numerical models developed in the in simulating of the Chernobyl accident and similar hypothetical cases. The study is based on an atmospheric models developed in Euro-Mediterranean Centre on Insular Coastal Dynamics (ICoD), Foundation for International Studies, Valeta, Malta

Principles for establishing limits for the release of radioactive materials into the environment

International Nuclear Information System (INIS)

1978-01-01

The document provides a basic consideration of concepts and principles for use by national authorities in setting limits for planned releases of radioactive material. The following topics are discussed general concepts, assessment of dose to the critical group, assessment of collective dose commitments, application of optimization techniques to the determination of discharge limits, explanation and application of the concept of collective dose commitment, discharge limitations based on concentration indices

Radiation protection requirements in the limitation of the release of radioactive effluents

International Nuclear Information System (INIS)

Beninson, D.

1978-01-01

The paper summarizes the requirements of radiation protection, as presented in the new ICRP recommendation, in relation to the limitation of the release of radioactive effluents. The concepts of effective dose equivalent and collective dose equivalent are used in the presentation of the optimization procedures and the dose limitation to individuals. The dose commitment is used for the procedures applied to control future exposures. An appendix describes the basic concepts and quantities used in assessments of human exposures and risks. (author)

The influence of season of the year on the predicted agricultural consequences of accidental releases of radionuclides to atmosphere

International Nuclear Information System (INIS)

Simmonds, J.R.

1985-02-01

In Europe, because of the seasonal nature of agricultural practices, the consequences for agriculture of an accidental release of radioactive materials to atmosphere are likely to vary depending upon the time of year when the release occurs. The quantification of this variation is complicated by the need to take into account the introduction of countermeasures to restrict the radiation exposure from ingestion of contaminated foods, and by the presence in accidental releases of radionuclides which persist over several seasons. In this study, the effect on agricultural consequences of accidental releases occurring at different times of the year is examined. The consequences are expressed in terms of the amount of produce affected by restrictions on food supplies and the collective radiation dose from ingestion of food. The investigation has been carried out for three hypothetical releases representing a range of releases postulated for pressurised water reactors (PWRs). The effect of season of the year was determined for accidental releases occurring both in a single, defined set of meteorological conditions and for a range of possible meteorological conditions. For the main part of the study, consideration was limited to agricultural production in the UK only, but the effect of extending the analysis beyond the UK boundary was also considered. The results of the study show that considerable variation can occur in agricultural consequences following an accidental release at different times of the year. For the larger releases considered, this variation is reduced due to the effect of the introduction of countermeasures, particularly when consideration is limited to the UK only. Seasonal variation tends to be greater for the results of a deterministic analysis, which uses a single set of constant meteorological conditions, than for the results of a full probabilistic assessment. From the results presented here it is also seen that for many applications of

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)

Discharges of radioactive materials to the environment in Argentina

CERN Document Server

Curti, A R

2003-01-01

The International Atomic Energy Agency (IAEA) is creating a database of information on radioactive discharges to atmospheric and aquatic environments from nuclear and radioactive installations, and from facilities using radionuclides in medicine, industry and research. The database is expected to facilitate the analysis of worldwide trends in discharge levels and provide a basis for assessing the impact of the discharges on humans and on the environment. In November 2002 took place the first meeting of national contact points and the Nuclear Regulatory Authority (ARN in Spanish) was present as the counterpart for the provision of discharge data from Argentina. This paper, presented in the above mentioned meeting, is a general overview of the radioactive discharges control in Argentina including the legal infrastructure, the population dose assessment methodology and the main characteristics of the facilities in the country with radioactive discharges to the environment. It is mentioned their location, release...

The annual averaged atmospheric dispersion factor and deposition factor according to methods of atmospheric stability classification

Energy Technology Data Exchange (ETDEWEB)

Jeong, Hae Sun; Jeong, Hyo Joon; Kim, Eun Han; Han, Moon Hee; Hwang, Won Tae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-09-15

This study analyzes the differences in the annual averaged atmospheric dispersion factor and ground deposition factor produced using two classification methods of atmospheric stability, which are based on a vertical temperature difference and the standard deviation of horizontal wind direction fluctuation. Daedeok and Wolsong nuclear sites were chosen for an assessment, and the meteorological data at 10 m were applied to the evaluation of atmospheric stability. The XOQDOQ software program was used to calculate atmospheric dispersion factors and ground deposition factors. The calculated distances were chosen at 400 m, 800 m, 1,200 m, 1,600 m, 2,400 m, and 3,200 m away from the radioactive material release points. All of the atmospheric dispersion factors generated using the atmospheric stability based on the vertical temperature difference were shown to be higher than those from the standard deviation of horizontal wind direction fluctuation. On the other hand, the ground deposition factors were shown to be same regardless of the classification method, as they were based on the graph obtained from empirical data presented in the Nuclear Regulatory Commission's Regulatory Guide 1.111, which is unrelated to the atmospheric stability for the ground level release. These results are based on the meteorological data collected over the course of one year at the specified sites; however, the classification method of atmospheric stability using the vertical temperature difference is expected to be more conservative.

Research on atmospheric radioactivity. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1954-01-01

In flight at 2800 m, traces of radioactive particles were gathered, by means of a corona effect similar to that of Sella, and of long period, on April 24, 1954. At Puy-de-Dome (1465 m) after a fall of rain and snow on May 3 to 4, 1954, samples of the fallen residue showed very feeble radioactivity of period 10 days or more. This radioactivity of the airborne particles was independent of their probable natural electrical charge and mobility and was indicative of an atomic cloud.

The variation of health effects based on the scenarios considering release parameters and meteorological data

International Nuclear Information System (INIS)

Jeong, Jong Tae; Ha, Jae Joo

2000-01-01

The variation of health effects resulting from the severe accidents of the YGN 3 and 4 nuclear power plants was examined based on scenarios considering the release parameters and meteorological data. The release parameters and meteorological data considered in making basic scenarios are release height, heat content, release time, warning time, wind speed, rainfall rate, and atmospheric stability class. The seasonal scenarios were also made in order to estimate the seasonal variation of health effects by considering seasonal characteristics of Korea. According to the results, there are large differences in consequence analysis from scenario to although an equal amount of radioactive materials is released to the atmosphere. Also, there are large differences in health effects from season to season due to distinct seasonal characteristics of Korea. Therefore, it is necessary to consider seasonal characteristics in developing optimum emergency response strategies

The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: the influence of the meteorological conditions

International Nuclear Information System (INIS)

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

1980-04-01

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 previous study by the National Radiological Protection Board. In the present study the sensitivity of the predicted consequences to the meteorological conditions was investigated. The influence of the wind direction, and hence the distribution of the exposed population, and of atmospheric stability at the time of the release are considered separately. Conclusions are reached on the precision required in specifying atmospheric stability conditions to estimate reliably the distribution of possible consequences following a given release of activity. The probability distributions of consequences for selected releases from two locations are evaluated taking account of the frequency distribution of wind direction and atmospheric stability at each location. The variation is large and demonstrates the importance of taking account of the whole range of meteorological conditions when assessing the risk presented by an accidental release of activity. (author)

Updated synthesis of knowledge related to the impact of radioactive releases from the damaged nuclear site of Fukushima Dai-Ichi on the marine environment - 13 July 2012

International Nuclear Information System (INIS)

2012-01-01

Illustrated by tables, figures and graphs, this report first comments the evolution of the radioactive pollution of sea water: main radionuclides notices in sea water since the 21 March 2011 (with two main origins: atmospheric fallouts, liquid releases from the site), evolution of sea water contamination along the coast at the vicinity of the power station, simulation of caesium 137 dispersion in sea water off Japan. Then, it comments the evolution of the presence of radionuclides in sediments and in marine species (species with contamination level exceeding the admissible level for consumption, concentrations noticed by sea animals, expected evolution for marine species, other published data)

Krypton-85 pollution and atmospheric electricity

International Nuclear Information System (INIS)

Harrison, R.G.; ApSimon, H.M.

1994-01-01

Krypton-86 is a chemically inert radioactive gas present in the atmosphere, concentrations of which have been greatly increased by nuclear reprocessing and weapons testing since 1945. The long half-life (10.7 yr), allows the gas to mix thoroughly in the atmosphere. Ionization caused by krypton-85 increases the electrical conductivity of atmospheric air. Further increases in krypton-85 emissions seem inevitable. The increase in air conductivity due to release of krypton-85 will vary with height, and be larger over the oceans than over the land. Increases in conductivity will produce uncertain effects on atmospheric phenomena, so changes are compared in magnitude with other factors perturbing the conductivity, such as combustion aerosol burdens, volcanic eruptions and nuclear weapons testing. Conductivity changes are expected to have the greatest significance for meteorological phenomena close to the source. (Author)

Results of concentration measurements of artificial radioactive aerosols in the lower atmosphere; Resultats des mesures de concentration, dans la basse atmosphere, des aerosols radioactifs artificiels

Energy Technology Data Exchange (ETDEWEB)

Ardouin, B; Jehanno, C; Labeyrie, J; Lambert, G; Tanaevsky, O; Vassy, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1963-07-01

This report gives the results of the measurements of artificial gross-{beta}-radioactivity in aerosols in the lower atmosphere; these measurements have been made by the Electronic Physics Service of the Electronic Department, and by the Atmospheric Physics Laboratory of the Paris Science Faculty. The measurements were begun in September 1956 and were continued in an increasing number of stations both in France and in the rest of the world. The present report deals with the period up to the end of august 1961, that is up to the end of the nuclear moratorium. After recalling the constitution and the properties of radioactive aerosols present in the atmosphere, the authors describe the measurement methods, estimate their accuracy and discuss various aspects of the results. (authors) [French] Ce rapport contient les resultats des mesures de radioactivite {beta} globale d'origine artificielle des aerosols dans la basse atmosphere, effectuees conjointement par le Service d'Electronique Physique du Departement d'Electronique et le Laboratoire de Physique de l'Atmosphere de la Faculte des Sciences de Paris. Les mesures ont commence en septembre 1956 et ont ete poursuivies dans un nombre croissant de stations, tant en France que dans le reste du monde. Le present rapport s'arrete a la fin aout 1961, c'est-a-dire au moment de la reprise des essais nucleaires. Apres avoir rappele la constitution et les proprietes des aerosols radioactifs presents dans l'atmosphere, les auteurs indiquent les methodes de mesure utilisees, evaluent leur precision et discutent les differents aspects des resultats de leurs mesures. (auteurs)

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.

Methodology for assessing the radiological consequences of radioactive releases from the BPX Facility at PPPL

International Nuclear Information System (INIS)

McKenzie-Carter, M.A.; Lyon, R.E.; Rope, S.K.

1991-04-01

This report contains information to support the Environmental Assessment for the Burning Plasma Experiment (BPX) Project proposed for the Princeton Plasma Physics Laboratory (PPPL). The assumptions and methodology used to assess the impact to members of the public from operational and accidental releases of radioactive material from the proposed BPX during the operational period of the project are described. A description of the tracer release tests conducted at PPPL by NOAA is included; dispersion values from these tests are used in the dose calculations. Radiological releases, doses, and resulting health risks are calculated and summarized. The computer code AIRDOS- EPA, which is part of the computer code system CAP-88, is used to calculate the individual and population doses for routine releases; FUSCRAC3 is used to calculate doses resulting from off-normal releases where direct application of the NOAA tracer test data is not practical. Where applicable, doses are compared to regulatory limits and guideline values. 48 refs., 16 tabs

A model for radiological consequences of nuclear power plant operational atmospheric releases

International Nuclear Information System (INIS)

Kocar, Cemil; Soekmen, Cemal Niyazi

2009-01-01

A dynamic dose and risk assessment model is developed to estimate radiological consequences of atmospheric emissions from nuclear power plants. Internal exposure via inhalation and ingestion, external exposure from clouds and radioactivity deposited on the ground are included in the model. The model allows to simulate interregional moves of people and multi-location food supply in the computational domain. Any long-range atmospheric dispersion model which yields radionuclide concentrations in air and on the ground at predetermined time intervals can easily be integrated into the model. The software developed is validated against radionuclide concentrations measured in different environmental media and dose values estimated after the Chernobyl accident. Results obtained using the model compare well with dose estimates and activities measured in foodstuffs and feedstuffs

Radiation exposure in an urban dwelling following an accidental release of radioactivity

International Nuclear Information System (INIS)

Cannell, Robert J.

1988-01-01

The intent of this work is the improved knowledge of how much protection would be afforded to the occupants of a dwelling in the event of a release of radioactivity into the environment. Fundamental to this is the question of how radioactive aerosols and dusts outside of a dwelling affect the inhabitants, what proportion of and by what routes radioactive materials penetrate the structural fabric of the dwelling, and again, how these materials affect the occupants once inside the dwelling. Whilst related research has already provided some answers to this question, experimental work on the tracking of radioactive materials or their analogues was, and still is, required. The major effort of this research has been in the development of an image gathering and processing system which provides a measurement of the mass and spatial distribution of a fluorescent tracer deposited on a surface. Although capable of further refinement, the technique is usable experimentally and its initial use in studying the transport of tracer analogues of radioactive materials is described. One of the main determinants of the behaviour of aerosols is their deposition rate and measurements of this rate for several aerosol-bound radionuclides were made in a test house. The results of these measurements and the dust transport experiments are collated and together with current values from the literature provide the input data for a computer house model. This simple house model has been developed with the primary purpose of indicating which parameters, specifically related to the characteristics of a dwelling, are most influential in determining what degree of protection the occupants will gain. The estimates of protection resulting from the model are summarised, and its sensitivity to the input parameters is used to indicate where further experimental work needs to be undertaken. (author)

Verification of computer system PROLOG - software tool for rapid assessments of consequences of short-term radioactive releases to the atmosphere

Energy Technology Data Exchange (ETDEWEB)

Kiselev, Alexey A.; Krylov, Alexey L.; Bogatov, Sergey A. [Nuclear Safety Institute (IBRAE), Bolshaya Tulskaya st. 52, 115191, Moscow (Russian Federation)

2014-07-01

In case of nuclear and radiation accidents emergency response authorities require a tool for rapid assessments of possible consequences. One of the most significant problems is lack of data on initial state of an accident. The lack can be especially critical in case the accident occurred in a location that was not thoroughly studied beforehand (during transportation of radioactive materials for example). One of possible solutions is the hybrid method when a model that enables rapid assessments with the use of reasonable minimum of input data is used conjointly with an observed data that can be collected shortly after accidents. The model is used to estimate parameters of the source and uncertain meteorological parameters on the base of some observed data. For example, field of fallout density can be observed and measured within hours after an accident. After that the same model with the use of estimated parameters is used to assess doses and necessity of recommended and mandatory countermeasures. The computer system PROLOG was designed to solve the problem. It is based on the widely used Gaussian model. The standard Gaussian model is supplemented with several sub-models that allow to take into account: polydisperse aerosols, aerodynamic shade from buildings in the vicinity of the place of accident, terrain orography, initial size of the radioactive cloud, effective height of the release, influence of countermeasures on the doses of radioactive exposure of humans. It uses modern GIS technologies and can use web map services. To verify ability of PROLOG to solve the problem it is necessary to test its ability to assess necessary parameters of real accidents in the past. Verification of the computer system on the data of Chazhma Bay accident (Russian Far East, 1985) was published previously. In this work verification was implemented on the base of observed contamination from the Kyshtym disaster (PA Mayak, 1957) and the Tomsk accident (1993). Observations of Sr-90

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

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

The sources and fate of radionuclides emitted to the atmosphere

International Nuclear Information System (INIS)

Sandalls, J.

2001-01-01

The thesis represents an account of the sources and fate of radionuclides entering the atmosphere, and indicates where the candidate, through his own work, has contributed to the overall picture. The sources of the natural and man-made radionuclides found in the atmosphere are identified. New data on emissions from UK coal-fired power stations and UK steel works are reported. Radionuclides produced in nuclear fission and released to the atmosphere in the detonation of nuclear weapons, in nuclear accidents, and through routine discharges from nuclear sites have added to the atmospheric burden of radioactive materials; both acute and chronic low-level emissions are discussed. The various natural processes which remove radionuclides from the atmosphere are described. Soon after release, many radioactive materials become attached to the atmospheric aerosol, but others undergo gas-phase reactions. Some gases are sufficiently long-lived in the troposphere as to find their way into the stratosphere where their fate may be determined by the short-wave radiation from the sun. The nature of the particles of fuel emitted to the atmosphere in the explosion and fire at the Chernobyl nuclear power plant in 1986 are discussed, together with the associated environmental problems. The ground is the major sink for radionuclides leaving the atmosphere, and the behaviour of the more radiologically important radionuclides following deposition is described with special reference to: (i) fallout in both the urban and living environments; (ii) the pathways which may lead to contamination of the food chain; (iii) how the fuel particle fallout from Chernobyl was unique in nuclear accidents; (iv) soil-to-plant transfer of radioelements and (v) how radiation exposure of man can be mitigated in both the contaminated urban and rural environments. (author)

Decree No 74-1181 of 31 December 1974 concerning liquid radioactive effluent releases from nuclear installations

International Nuclear Information System (INIS)

1975-01-01

This Decree prescribes the licensing procedure for the release of liquid wastes from nuclear installations as well as the technical supervision of such operations. It does not apply to the transport of radioactive effluents which is governed by the regulations on the transport of dangerous goods. (NEA) [fr

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.

Study of atmospheric stagnation, recirculation, and ventilation potential at Narora Atomic Power Station site

International Nuclear Information System (INIS)

Kumar, Deepak; Kumar, Avinash; Kumar, Vimal; Rao, K.S.; Kumar, Jaivender; Ravi, P.M.

2011-01-01

Atmosphere is an important pathway to be considered in assessment of the environmental impact of radioactivity releases from nuclear facilities. Estimation of concentration of released effluents in air and possible ground contamination needs an understanding of relevant atmospheric dispersion. This article describes the meteorological characteristics of Narora Atomic Power Station (NAPS) site by using the integral parameters developed by Allwine and Whiteman. Meteorological data measured during the period 2006-2010 were analyzed. The integral quantities related to the occurrence of stagnation, recirculation, and ventilation characteristics were studied for NAPS site to assess the dilution potential of the atmosphere. Wind run and recirculation factors were calculated for a 24-h transport time using 5 years of hourly surface measurements of wind speed and direction. The occurrence of stagnation, recirculation, and ventilation characteristics during 2006-2010 at NAPS site is observed to be 33.8% of the time, 19.5% of the time, and 34.7% of the time, respectively. The presence of strong winds with predominant wind direction NW and WNW during winter and summer seasons leads to higher ventilation (48.1% and 44.3%) and recirculation (32.6% of the summer season). The presence of light winds and more dispersed winds during prewinter season with predominant wind directions W and WNW results in more stagnation (59.7% of the prewinter season). Thus, this study will serve as an essential meteorological tool to understand the transport mechanism of atmospheric radioactive effluent releases from any nuclear industry. (author)

Health and environmental impacts of a fertilizer plant - Part I: Assessment of radioactive pollution

Energy Technology Data Exchange (ETDEWEB)

Righi, Serena [Interdepartment Centre for Research in Environmental Science, University of Bologna, via dell' Agricoltura 5, 48100 Ravenna (Italy)]. E-mail: serena.righi2@unibo.it; Lucialli, Patrizia [ARPA, Emilia-Romagna Regional Agency for Prevention and Environment, Department of Ravenna, via Alberoni 17/19, 48100 Ravenna (Italy); Bruzzi, Luigi [Interdepartment Centre for Research in Environmental Science, University of Bologna, via dell' Agricoltura 5, 48100 Ravenna (Italy)

2005-07-01

The aim of the first part of this investigation is to assess the radioactive pollution caused by a production plant of complex fertilizers (that is to say containing nitrogen, phosphorus and, in some cases, potassium). Firstly, the authors determine the concentrations of natural radioactivity present in raw materials, end products and wastes of the industrial plant. Then, they carry out an assessment of radioactive releases into the atmosphere, hydrosphere and lithosphere as well as of their significance from the environmental point of view. The second part of the investigation will be aimed at assessing the annual effective doses to plant workers and to members of the population surrounding the industrial site.

Health and environmental impacts of a fertilizer plant - Part I: Assessment of radioactive pollution

International Nuclear Information System (INIS)

Righi, Serena; Lucialli, Patrizia; Bruzzi, Luigi

2005-01-01

The aim of the first part of this investigation is to assess the radioactive pollution caused by a production plant of complex fertilizers (that is to say containing nitrogen, phosphorus and, in some cases, potassium). Firstly, the authors determine the concentrations of natural radioactivity present in raw materials, end products and wastes of the industrial plant. Then, they carry out an assessment of radioactive releases into the atmosphere, hydrosphere and lithosphere as well as of their significance from the environmental point of view. The second part of the investigation will be aimed at assessing the annual effective doses to plant workers and to members of the population surrounding the industrial site

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

Review of IAEA recommendations on the principles and methodologies for limiting releases of radioactive effluents to the environment

International Nuclear Information System (INIS)

Ahmed, J.U.

1988-01-01

The limitation of radioactive releases is governed by the basic principles of radiation protection as presented in the ICRP Publication No. 26 and IAEA Safety Series No. 9. Unter its current programme on release limitation the IAEA issued Safety Series No. 77 on principles for release limitation and Safety Series No. 67 on protection against transboundary radiation exposures. A Safety Guide on global upper bounds is now nearly ready for publication, and to guide on the application of Safety Series No. 77, four documents are in various stages of completion

Effect of the foodchain in radioactivities released from thermal power plants

International Nuclear Information System (INIS)

Okamoto, K.

1980-01-01

Food chains involving 210 Pb and 210 Po have been investigated in Japan, with special reference to the vegetable and sea food chain. Although much smaller than the natural background, the collective dose of coal burning including this food chain was 100 to 1000 times larger than that excluding it, the Suess effect being too small to cancel it. The dose due to coal burning was comparable to or even greater than that of nuclear energy. The need for further investigation of radioactive release due to the oil and natural gas industries is also emphasised, with particular reference to radon and its daughters 210 Pb and 210 Po. (U.K.)

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

Radiological consequences of atmospheric releases from coal-fired power plants

International Nuclear Information System (INIS)

Tveten, U.

1985-06-01

The report deals with the individual and collective doses resulting from radioactive materials contained in the stack releases of coal-fired power plants. A critical analysis of relevant calculations in literature is given. The different reports analyzed show a very wide range in calculated doses. To a great extent these differences may be explained by the wide range in the assumptions adopted. There is also disagreement on what exposure pathways are the most important, and what nuclides contribute most to calculated doses. A most probable value of 0.5 mrem/year for the maximum individual effective dose equivalent commitment, is indicated in the report

The releases control and the environment survey of the Cea Centers

International Nuclear Information System (INIS)

2002-01-01

The Cea sets the environment protection in the heart of its security policy, which is based on the mastership of risks resulting from the researches activities and installations development. This policy aims to reduce as small as possible compared with the technical and economical necessities, the impact of its activities on the human and the environment. This document, takes stock for the year 2002, of the liquid and gas radioactive effluents releases as also of the radioactivity level around the Cea Centers, by a systematic monitoring of the atmosphere, the waters, the vegetation and the milk. (A.L.B.)

Current and perspective on the radioactive waste management at territory of the Kola Peninsula

International Nuclear Information System (INIS)

Amazova, Ludmila

1999-01-01

According to this presentation, 25 thousand cubic metres of solid radioactive waste of one million Ci activity has accumulated in the Murmansk Region because of previous civilian and military activities and more will come as a result of the coming decommissioning of nuclear submarines and nuclear power plants. Only a part of the solid radioactive waste is reprocessed at the Kola nuclear power plant and at the repairing and technological enterprise Atomflot. Compaction and incineration are used to decrease the volume of waste. An incineration facility at Atomflot fails to satisfy new requirements and even releases more radioactivity to the atmosphere than what used to come from the Kola nuclear power plant operation. Solid radioactive waste is stored non-reprocessed Spetscombinat special plant Radon. This plant collects and stores radioactive waste produced by the civil industry and at the bases of the Northern Fleet. It is emphasised, however, that during the observation period there were no cases of dangerous increase in radioactivity in the atmosphere. Soil and vegetation contamination by long-lived radionuclides was at the background level. The establishment of a common reprocessing and regional storage facility for long-term storage has been proposed by the Ministry for Atomic Energy

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

The characteristics of local atmospheric circulation around the Wolsung NPP in Korea

International Nuclear Information System (INIS)

Lee, G.B.; Lee, M.C.; Song, Y.I.

1998-01-01

The transport of air pollutants in coastal regions has been known to be strongly affected by the mesoscale atmospheric circulations such as sea-land breezes. These mesoscale atmospheric circulations depend on synoptic weather conditions. In this study, a three-dimensional sea-land breeze model was developed to evaluate the effects of the sea and land breezes on the atmospheric dispersion of radioactive materials released from nuclear power plants in Korea. In the model, the hydrostatic primitive equations in the terrain-following coordinate system were used. The mesoscale atmospheric circulation simulation were carried out under various synoptic weather conditions for all seasons around the Wolsung nuclear power plant site

Illustrative assessment of human health issues arising from the potential release of chemotoxic substances from a generic geological disposal facility for radioactive waste.

Science.gov (United States)

Wilson, James C; Thorne, Michael C; Towler, George; Norris, Simon

2011-12-01

Many countries have a programme for developing an underground geological disposal facility for radioactive waste. A case study is provided herein on the illustrative assessment of human health issues arising from the potential release of chemotoxic and radioactive substances from a generic geological disposal facility (GDF) for radioactive waste. The illustrative assessment uses a source-pathway-receptor methodology and considers a number of human exposure pathways. Estimated exposures are compared with authoritative toxicological assessment criteria. The possibility of additive and synergistic effects resulting from exposures to mixtures of chemical contaminants or a combination of radiotoxic and chemotoxic substances is considered. The case study provides an illustration of how to assess human health issues arising from chemotoxic species released from a GDF for radioactive waste and highlights potential difficulties associated with a lack of data being available with which to assess synergistic effects. It also highlights how such difficulties can be addressed.

Illustrative assessment of human health issues arising from the potential release of chemotoxic substances from a generic geological disposal facility for radioactive waste

International Nuclear Information System (INIS)

Wilson, James C; Towler, George; Thorne, Michael C; Norris, Simon

2011-01-01

Many countries have a programme for developing an underground geological disposal facility for radioactive waste. A case study is provided herein on the illustrative assessment of human health issues arising from the potential release of chemotoxic and radioactive substances from a generic geological disposal facility (GDF) for radioactive waste. The illustrative assessment uses a source–pathway–receptor methodology and considers a number of human exposure pathways. Estimated exposures are compared with authoritative toxicological assessment criteria. The possibility of additive and synergistic effects resulting from exposures to mixtures of chemical contaminants or a combination of radiotoxic and chemotoxic substances is considered. The case study provides an illustration of how to assess human health issues arising from chemotoxic species released from a GDF for radioactive waste and highlights potential difficulties associated with a lack of data being available with which to assess synergistic effects. It also highlights how such difficulties can be addressed.

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)

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)

Settlement process of radioactive dust to the ground inferred from the atmospheric electric field measurement

Science.gov (United States)

Yamauchi, M.; Takeda, M.; Makino, M.; Owada, T.; Miyagi, I.

2012-01-01

Radioactive materials from the accident at Fukushima Dai-ichi nuclear power plant (FNPP) in March 2011 spread over a large area, increasing the atmospheric electric conductivity by their ionizing effect, and reducing the vertical (downward) component of the DC electric field near the ground, or potential gradient (PG). PG data at Kakioka, 150 km away from the FNPP, showed independent changes compared to the radiation dose rate, and a comparison of these data revealed the local dynamics of the radioactive dust. (1) The initial drop of the PG to almost zero during 14-15 March is most likely due to radioactive dust suspended in the air near the ground during cloudy weather. (2) An episode of PG increase to more than 50 V m-1 on 16 March is most likely due to the re-suspension of the radioactive dust from the surface and subsequent removal from Kakioka by the strong wind from the non-contaminated area. (3) Low but finite values of the PG during 16-20 March most likely reflect a reduced amount of radioactive material near the ground after the above wind transported away the majority of the suspended radioactive dust. (4) Very low values of the PG after substantial rain on 20-22 March most likely reflect settlement of the radioactive material by rain-induced fallout. (5) Temporal recovery of daily variations from the end of March to the middle of April with low nighttime fair-weather baseline PG most likely reflects re-suspension of the radioactive dust into the air from the ground and trees, and subsequent transport to the other region or fallout to the ground until late April. (6) Weakening of the daily variation and gradual recovery of the nighttime fair-weather baseline after mid-April suggests a complete settlement of the radioactive material to the ground with partial migration to the subsurface.

Radioactive waste disposal: Regulations and Application

International Nuclear Information System (INIS)

Hebert, Jean.

1977-01-01

The regulation of radioactive discharges, i.e. solid radioactive waste resulting from operation of nuclear installations and liquid and gazeous effluents released by them may be dealt with from two angles: the receiving environment and the polluting agent. French law covers both. Law on atmospheric pollution is based mainly on the Act of 2 August 1961 while the Act of 16 December 1964 governs water pollution. Both Acts have been the subject of a great number of implementing decrees, certain of which contain standards specific to radioactive pollution. Regulations on the polluting agent, namely its activity, comply with the generally established distinction between large nuclear installations and others. There again, there are many applicable texts, in particular, the Act of 19 July 1976 for classified installations, and the Decree of 11 December 1963, supplemented by the Decrees of 6 November 1974 and 31 December 1974 for large nuclear installations. This detailed analysis of national regulations is followed by a presentation of the applicable provisions in the Communities law and in international public law. (N.E.A.) [fr

Historical releases of radioactivity to the environment from ORNL

International Nuclear Information System (INIS)

Ohnesorge, W.F.

1986-05-01

This report gives a brief history and assessment of ORNL radionuclide releases to the environment. A short history and an inventory of radioactivity disposed of by shallow land burial and hydrofracture techniques are given along with a brief discussion of the potential environmental impact of these disposed materials. The data available for this report varied greatly in quality. Data on contaminated liquid waste and liquids discharged to the environment are much more reliable than early data on contaminated air discharges and contaminated solid waste. Data for more recent years are more complete and reliable than data obtained from records dating back to the early history of the laboratory. The data presented here do not include materials retrievably stored (with the exception of uranium solid waste data) or inventories of materials stored in operating or surplus facilities since these materials presently have no contact with or loss to the environment

Atmospheric radionuclides from Fukushima Dai-ichi nuclear accident detected in Lanzhou, China

Institute of Scientific and Technical Information of China (English)

邬家龙王赟; 孙卫; 罗伟立; 王延俊; 张飙

2015-01-01

After the Fukushima Dai-ichi nuclear power plant accident on March 11, 2011, the radioactivity released from the accident was transported around the globe by atmospheric processes. The radioactivity monitoring program on atmospheric particulate in Lanzhou, China was activated by GSCDC to detect the input radionu-clides through atmospheric transport. Several artificial radionuclides were detected and measured in aerosol samples from March 26 to May 2, 2011. The peaked activity concentrations (in mBq/m3) were: 1.194 (131I), 0.231 (137Cs), 0.173 (134Cs) and 0.008 (136Cs), detected on April 6, 2011. The average activity ratio of 131I/137Cs and 134Cs/137Cs in air were 13.5 and 0.78. The significant increase of 137Cs activity concentration, one order of magnitude higher than pre-Fukushima accident levels, in ground level aerosol was observed in 2013, as its re-suspension from soil. The back-trajectory analysis simulated by NOAA-ARL HYSPLIT shows a direct transfer of the air masses released from Fukushima to Lanzhou across the Pacific Ocean, North America and Europe at the height close to 9000 m AGL. The value of effective dose for inhalation is close to one millionth of the annual limit for the general public.

The development of the American national standard, ''control of radioactive surface contamination on materials, equipment and facilities to be released for uncontrolled use''

International Nuclear Information System (INIS)

Shapiro, J.

1980-01-01

The American National Standard, Control of Radioactive Surface Contamination on Materials, Equipment and Facilities to be Released for Uncontrolled Use, was developed under the procedures of ANSI for ANSI Main Committee N13 (Radiation Protection) by a working group of the Health Physics Society Standards Committee. This standard provides criteria for the control of materials, equipment and facilities contaminated with radioactivity proposed to be released for uncontrolled use. Permissible contamination limits are specified as well as methods assessing the levels of contamination. This paper reviews the proceedings of the Subcommittee on Radioactive Surface Contamination, the comments received by reviewers of the standard, the resolution of the committee, and the bases for reaching the final limits, recommendations, and measurement procedures. (H.K.)

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

Method and apparatus for removing radioactive gases from a nuclear reactor

International Nuclear Information System (INIS)

Frumerman, R.; Brown, W.W.

1975-01-01

A description is given of a method for removing radioactive gases from a nuclear reactor including the steps of draining coolant from a nuclear reactor to a level just below the coolant inlet and outlet nozzles to form a vapor space and then charging the space with an inert gas, circulating coolant through the reactor to assist the release of radioactive gases from the coolant into the vapor space, withdrawing the radioactive gases from the vapor space by a vacuum pump which then condenses and separates water from gases carried forward by the vacuum pump, discharging the water to a storage tank and supplying the separated gases to a gas compressor which pumps the gases to gas decay tanks. After the gases in the decay tanks lose their radioactive characteristics, the gases may be discharged to the atmosphere or returned to the reactor for further use

The discovery and history of knowledge of natural atmospheric radioactivity

International Nuclear Information System (INIS)

Renoux, A.

1996-01-01

Everybody knows that the radioactivity was discovered, 100 years ago, by the Frenchman Henri Becquerel at Paris, in Feb. 1896, stemmed from the discovery of X-rays by Roentgen in the preceding year. In 1899, Rutherford was able to show the existence of α and β rays, and in 1900 Villard showed the presence of a third class of rays, the γ rays. The discovery of the rare radioactive gas radon is attributed to P. and M. Curie in 1898 and F. Dorn in 1900. Thoron ( 220 Rn) was discovered by Rutherford and Owens in 1899-1900 and Actinon ( 219 Rn) by Debierne and Geisel about the same time. The radon's radiotoxicity was studied in France since 1904 by Bouchard and Balthazard and in 1924 it was formulated the hypothesis that the great mortality observed in the uranium miners of Schneeberg in Germany and Joachimsthal in Czechoslovakia was maybe due to the radon. But, in fact, Elster and Geitel were the first to see that the radioactivity is present in the atmosphere in about 1901. After this date, many investigations were made (M. Curie, for example), but it is during the fifties and, of course, until today that the most numerous works were developed. In this paper, we speak about the researches of the after second war pioneers: Evans, Wilkening, Kawano, Israel, Junge, Schuman, Bricard... Renoux, Madelaine, Blanc, Fontan, Siksna, Chamberlain, Dyson, Nolan, etc. and the works developed later. Finally, we reach to the nineties, period where the works are particularly directed in the aim of radon and radon progeny indoor, with in particular, many works effectuated in France. (author). 78 refs., 17 figs., 2 tabs

Radiation safety for incineration of radioactive waste contaminated by cesium

International Nuclear Information System (INIS)

Veryuzhs'kij, Yu.V.; Gryin'ko, O.M.; Tokarevs'kij, V.V.

2016-01-01

Problems in the treatment of radioactive waste contaminated by cesium nuclides are considered in the paper. Chornobyl experience in the management of contaminated soil and contaminated forests is analyzed in relation to the accident at Fukushima-1. The minimization of release of cesium aerosols into atmosphere is very important. Radiation influence of inhaling atmosphere aerosols polluted by cesium has damage effect for humans. The research focuses on the treatment of forests contaminated by big volumes of cesium. One of the most important technologies is a pyro-gasification incineration with chemical reactions of cesium paying attention to gas purification problems. Requirements for process, physical and chemical properties of treatment of radioactive waste based on the dry pyro-gasification incineration facilities are considered in the paper together with the discussion of details related to incineration facilities. General similarities and discrepancies in the environmental pollution caused by the accidents at Chornobyl NPP and Fukushima-1 NPP in Japan are analyzed

Screening calculations for radioactive waste releases from non-nuclear facilities

International Nuclear Information System (INIS)

Xu, Shulan; Soederman, Ann-Louis

2009-02-01

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 μSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 μSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment plant

Screening calculations for radioactive waste releases from non-nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Shulan Xu; Soederman, Ann-Louis

2009-02-15

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 muSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 muSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment

Operational control of material release and discharges from nuclear power plant

International Nuclear Information System (INIS)

Szabo, I. C.; Ranga, T.; Daroczi, L.; Deme, S.; Kerekes, A.

2003-01-01

The operational control of radioactive materials during atmospheric release and aquatic discharge from nuclear power plant is a licensing criterion for NPPs. Originally at the Paks NPP the release control was based on activity limits for four groups of elements. These groups were noble gases, long living radio-aerosols, radioiodine and radiostrontium for atmospheric release and specified activity limit for beta emitters, strontium and tritium for aquatic discharge into Danube. These groups were controlled with proper sampling and/or measuring instrumentation. The limit for atmospheric release was given as a 30-day moving average, for liquid discharges the annual limit was stipulated. The new release and discharge limitation system is based on the environmental dose limitation. The dose constraint for Paks NPP is 90 Sv/year of the critical group for all release pathways and the investigation dose limit is equal to 27 Sv/year. The regulation did not subdivide the dose limit for atmospheric and liquid components but for operational control subdivision of dose limits for atmospheric release and aquatic discharge and shorter time period (one day-one month) seems to be useful. The subdivision can be based on past release data and/or previous activity limits. To satisfy dose below the investigation dose limit there should be a proper operation control level for each separately measured component and pathway belonging to reasonable time interval significantly shorter than one year. The main task of the NPP staff is elaboration of reasonable control levels and reference time intervals for different radionuclide and element groups to be used in operational control. Operational control levels are based on measured daily or monthly release rates. In case of noble gases, aerosols and iodine the daily release rates have several sharp peaks per year. Operational control levels give opportunity to detect these peaks for internal investigation purposes. Investigation release limits

Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

International Nuclear Information System (INIS)

1996-01-01

The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour

Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour.

Environmental assessments for the existing radioactive materials in the Weldon Spring raffinate pits

International Nuclear Information System (INIS)

Yang, J.Y.; Wang, J.

1985-01-01

Various radioactive residues (raffinates) and wastes from the processing of uranium and thorium between 1957 and 1966 are stored in four pits at Weldon Spring, Missouri. The US Department of Energy (DOE) plans to stabilize all the contaminated materials on a long-term (more than 1000-year) basis. The effectiveness of stabilization measures are evaluated by estimating radioactive releases under two options: (1) no action, and (2) improved containment using the existing raffinate pits. Two major pathways of radiation exposure are examined: (1) airborne radioactive gases and particulates, and (2) seepage into near-surface groundwater. The relative reductions of releases into the air and groundwater for a reference stabilization option (improved containment) are analyzed using mathematical models for radioactive and particulate gas fluxes and atmospheric dispersion, as well as groundwaterr transport and dispersion. The consequent health risks for nearby individuals and the general public are also evaluated. This study focuses on the migration of radionuclides under existing conditions and evaluates the effectiveness of proposed stabilization measures at the pits. Results indicate that the potential effects to the general public would be insignificant. 22 refs., 2 figs., 6 tabs

First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations.

Science.gov (United States)

Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

2014-10-22

No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric (137)Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12-23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric (137)Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models.

First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations

Science.gov (United States)

Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

2014-01-01

No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric 137Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12–23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric 137Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models. PMID:25335435

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.

Situation 2002: release monitoring and surveillance of environment of Cea centers; Bilan 2002: controle des rejets et surveillance de l'environnement des centres CEA

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

This publication renders an account of the situation of the releases of liquid and gaseous radioactive effluents, for the year 2002, as well as the radioactivity levels measured in the vicinity of Cea centers through the systematic surveillance of atmosphere, waters, vegetation and milk. An analysis on five years allows to follow their evolution. (N.C.)

Evaluation of the atmospheric stability and it influence in the radiological environmental impact of the treatment plant and radioactive waste storage (PTDR)

International Nuclear Information System (INIS)

Ramos V, E.O.; Cornejo D, N.

2006-01-01

It is well-known that the meteorological variables as the atmospheric stability, influence in the atmospheric dispersion of radioactive pollutants, for that as regards radiological safety, it constitutes a demand the evaluation of their impact in the process before mentioned. The present work exposes the results of the study of the radiological impact of our PTDR that it allowed to know the influence of this meteorological parameter in the atmospheric dispersion of radioactive pollutants in its location. To such effects they were processed by means of the methodology of Pasquill - Gifford, data of time zone observations of this meteorological variable obtained in the proximities of the installation, being modeled the worst conditions in atmospheric liberation of their radionuclides inventory, valuing stops the 2 critical considered population groups the doses received by inhalation of polluted air and ingestion of water and polluted products, as well as, for external irradiation from the radioactive cloud and the floor. The obtained annual effective doses due to the modeling situation reach until a mSv, except for the Ra-226 that are lightly superior, implying a risk radiological acceptable chord to the international standard. To the above-mentioned a reduced probability of occurrence of events initiators of the evaluated accidental sequence is added. (Author)

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)